s~'km palo nuclear unit ii arizona publi palo unit byname palo … · 2018. 7. 31. ·...

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REGULATOR'i %FORMATION DISTRIBUTION S~'KM (RIDS) ACCESSION NBR:8012220319 DOC ~ DATE: 80/1?/09 NOTARIZED: YES FACIL:STN"50-528 Palo Verde Nuclear Stationr Unit ii Arizona Publi STN-50-5?9 Palo Ver de Nucl ear Stationi Unit 2p At izona Publ i STN-50-530 Palo Verde Nuclear Stations Unit 3i Arizona Publi AUTH BYNAME AUTHOR AFFILIATION VAN BRUNT,E.E. Arizona Public Ser vice Co, RECIP ~ NAME RECIPIENT AFFILIATION DENTONrH ~ RE office of Nuclear Reactor Regulationi Director 05000528 0 05000530 SUBJECT: Forwards util L Rechtel Power Corp 801113 L 05 responses to open items re Class IE ac power sys review L as continuation of review record, Final resolution to be submit.ted upon < resolution. DISTRIBUTI N CODE: 8001S COPIES RECEIVED:LTR ENCL ~ SIZE ~ 0 TITLE; PSAR/FSAR AMDTS and Related Correspondence NOTES:Standardized Plant, Standardized Plant. Standardized Plant. '05000528 05000529 05000530 RECIPIENT ID CODE/NAME ACTION: A/D LI CKNSNG LEEpJ ~ INTERNAL: ACCID EVAL BR26 CHEM ENG BR 06 CORE PERF BR 10 EMERG PREP 22 GEOSCIENCES 10 HYD/GKO BR 15 ILE 06 LIC QUAL BR MECH ENG BR 16 NRC PDR 02 OP LIC BR PROC/TST REV 20 RA S BR22 NEG FI 01 ENG BR25 COPIES LTtR ENCL 0 1 0 1 1 1 1 1 0 1 1 2 3 3 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME MIRAGLI A i F ~ KERRIGAN e J ~ 04 AUX SYS BR 07 CONT SYS BR 09 EFF TR SYS BR12 EQUIP QUAL BR13 HUM FACT ENG BR ISC SYS BR 16 LIC GUID BR MATL ENG BR 17 MPA OELD POWER SYS BR 19 QA BR 21 REAC SYS BR 23 SIT ANAL BR 20 SYS INTERAC BR COPIES LTTR ENCL 1 0 1 1 1 1 1 1 3 3 1 1 1 1 1 1 1 1 1 0 1 0 1 1 1 1 1 1 1 1 1 1 ~iP EXTERNAL: ACRS NSIC 27 05 16 16 1 1 LPDR 03 1 1 DEtl 2 g tggo TOTAL NUMBER OF COPIES REQUIRED: LTTR 57 ENCL 51

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Page 1: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

REGULATOR'i %FORMATION DISTRIBUTION S~'KM (RIDS)

ACCESSION NBR:8012220319 DOC ~ DATE: 80/1?/09 NOTARIZED: YESFACIL:STN"50-528 Palo Verde Nuclear Stationr Unit ii Arizona Publi

STN-50-5?9 Palo Ver de Nucl ear Stationi Unit 2p At izona Publ iSTN-50-530 Palo Verde Nuclear Stations Unit 3i Arizona Publi

AUTH

BYNAME

AUTHOR AFFILIATIONVAN BRUNT,E.E. Arizona Public Ser vice Co,

RECIP ~ NAME RECIPIENT AFFILIATIONDENTONrH ~ RE office of Nuclear Reactor Regulationi Director

05000528005000530

SUBJECT: Forwards util L Rechtel Power Corp 801113 L 05 responses toopen items re Class IE ac power sys review L as continuationof review record, Final resolution to be submit.ted upon <resolution.

DISTRIBUTI N CODE: 8001S COPIES RECEIVED:LTR ENCL ~ SIZE ~0TITLE; PSAR/FSAR AMDTS and Related Correspondence

NOTES:Standardized Plant,Standardized Plant.Standardized Plant.

'050005280500052905000530

RECIPIENTID CODE/NAME

ACTION: A/D LICKNSNGLEEpJ ~

INTERNAL: ACCID EVAL BR26CHEM ENG BR 06CORE PERF BR 10EMERG PREP 22GEOSCIENCES 10HYD/GKO BR 15ILE 06LIC QUAL BRMECH ENG BR 16NRC PDR 02OP LIC BRPROC/TST REV 20RA S BR22NEG FI 01

ENG BR25

COPIESLTtR ENCL

01 0

1

1

1 1

1 0

1 1

23 31 1

1 1

1 1

1 1

1

1 1

1 1

1

RECIPIENTID CODE/NAME

MIRAGLIA i F ~

KERRIGAN e J ~ 04

AUX SYS BR 07CONT SYS BR 09EFF TR SYS BR12EQUIP QUAL BR13HUM FACT ENG BRISC SYS BR 16LIC GUID BRMATL ENG BR 17MPAOELDPOWER SYS BR 19QA BR 21REAC SYS BR 23SIT ANAL BR 20SYS INTERAC BR

COPIESLTTR ENCL

1 01 1

1

1 1

1

3 31 1

1 1

1 1

1 1

1 0

1 01 1

1 1

1 1

1 1

1 1

~iP

EXTERNAL: ACRSNSIC

2705

16 161 1

LPDR 03 1 1

DEtl 2 g tggo

TOTAL NUMBER OF COPIES REQUIRED: LTTR 57 ENCL 51

Page 2: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 3: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

a p PKJEHM(Q IKSWMeI CIOIKnsKlrP. O BOX 2I666 PHOENIXs ARIZONA 85036

December 9, 1980ANPP-16868 - JMA/WFQ

Dr. H. R. Denton, DirectorNuclear Reactor RegulationU.S. Nuclear Regulatory CommissionWashington, D.C. 20555

Subject: Palo Verde Nuclear Generating StationPVNGS Units 1, 2 and 3Docket Nos. STN-50-528/529/530

Dear Dr. Denton:

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The responses of Bechtel Power Corporation and Arizona Public ServiceCompany to the open items of the Class IE AC Power System Review forPVNGS are enclosed for your use, and as a continuation of the AC SystemReview record.

These responses have been distributed to each member of the PVNGS PowerSystems Review Board for their review. The Review Board is to assurethat these responses sufficiently address the concerns noted in theoriginal presentation. Final'esolution of the open items by the ReviewBoard will be submitted to you when completed.

Respectfully submitted,

ARIZONA PUBLIC SERVICE C H NY

cc: J. KerriganF. Rosa

By: Q '' ' ~LCE win E. Van Brunt, Jr.APS Vice President,

Nuclear ProjectsANPP Project Director

On its own behalf and as agentfor all other joint applicants.State of Arizona )

ss.".,~ -, C,ou'nty of Maricopa)

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Subscjibed and sworn to before me this /0 day of g86-Age&

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~'"~>q 'iIey,'.commission expires: DRAT p 5 /'PEPesse> > q six

1980.

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Page 4: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 5: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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"'-" '0'"'- " 'echtel Power CorporationEngineers —Constructors

12400 East Imperial Highway'orwalk, Catitornia 90650

MAILAOORESSP.o. BOX 60660 ~ TERMINALANNEX. LOS ANGELES. CAUFOANIA60060TELEPHONE. (2I3) 664.60 I I

B/ANPP-E-66051MOC 130362November 13','980

Arizona Nuclear Po~er ProspectP. 0. Box 21666 - Mail Station 3003Phoenix, Arizona 85036

Attention: Mr. Edwin E. Van Brunt, Jr.APS Vice President, ANPP Project Director

Subject: Arizona Nuclear Power ProspectBechtel Job 10407Resolutions of Open Items fromA.C. Power System Review BoardPile: N.28-.02

Reference: Transcript of System Review Board, July 9, 1980

Dear Mr. Van Brunt:

Enclosed are resolutions of the open items addressed at the System ReviewBoard meeting for the Class IE AC Power System held on July 9, 1980.

Very truly yours,

BECHTEL POWER CORPORATION

GPK: pb

W. ~ Wilson~r WProject nagerLos geles Power Division

Enclosure: (1) Resolutions of Open Items Addressed atSystem Review Board Meeting (28 pages, 4 copies)

cc: F. W. Hartley N. HoefertD. B. Fasnacht C. RogersJ. Allen R. KramerW. +inn C. Perguson (CE)J. Barrow M Barnoski (CE)

All w/enclosure

Page 6: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 7: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

RESOLUTIONS OF OPEN ITEMS ADDRESSED AT

SYSTEM REVIEW BOARD MEETING FOR CLASS IE AC POWER SYSTEM

ACTION 81

Was a spare ESF transformer purchased? (page 27)

RESPONSE

Yes. The equipment tag number is A-E-NBN-X03S ~ This transformer will bestored outside with other spare transformers in the startup transformer yard .

ACTION !32

What is the degree of separation between electrical and mechanical systemson the same or different trains? (page 31)

RESPONSE

This action was closed in the meeting as noted on pages 188-189 of thetranscript."

ACTION 83

Is there a door on the double walls on the top of Figure 1-4? If so, arethere, security annunciations on the door? Is either door a fire barrier?(page 44)

RESPONSE

There is one door at each wall. Both doors have security annunciation andmeet the requirements of 10CFR73.55. .Each door has-a l-l/2 hour fire barrierrating. Thus, total door barrier delay time is 3 hours'igure 1-4 has beenrevised to show these doors and is provided as Attachment 3.

ACTION 84

Are there any operational problems that may develop due to sequencing oneload group if the second load group is still operating in the normal mode?(pages 65-69)

RESPONSE

A loss of offsite power to only one ESF bus is sensed by the undervoltagerelays on that bus which initiate load shedding of loads on that bus,starting of the respective diesel generator, and respective undervoltage,loss of offsite power, and load shed alarming. On closing of the dieselgenerator breaker, the forced shutdown loads assigned to the affected ESF

bus are sequentially started by the respective ESF load sequencer. No

Page 8: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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actions are initiated on the other ESF bus, which is unaffected and stillenergized by, offsite power ~

These actions will not cause a plant condition requiring protective action,'rdisturb reactor operations. Any normally running equipment that will be

load shed on detection of undervoltage will be restarted by the ESF loadsequencer, or available for manual restart under administrative controlsAdditional forced shutdown equipment started by the ESF load sequencer willnot cause any undesirable system initiation since the ESF load sequencer 'onlyactuates pumps and fans, and does not position any valves. An undervoltagecondition on the train A ESF bus does realign the normally running nuclearcooling ~ater system and the normal chilled water system for forced shutdown,but the realignment does not interrupt normal operations.

The respective undervoltage and loss of offsite power/load shed alarms pro-vide sufficient indication to the control room operator to enable assessmentof the loss of offsite power to a single ESF bus ~ Alignment of any forcedshutdown initiated systems to a normal operating status could be accomplishedusing the various component status indications and actuation switches.

ACTION //5

Where does the power source originate which would supply power to the pumpsthat are to supply suction to the two diesel generator storage tanks? Also,can these tanks be cross connected and, if so, how is power supply suppliedto the pump in a cross connect mode? (pages 75-77)

RESPONSE

The diesel fuel oil transfer pumps DFA-POl and DFB-P01 are powered from theirrespective train A and train B IE buses. The pump discharges are connectedsuch that. manual operation of normally LOCKED CLOSED valves will allow thefuel oil day tank of a diesel engine to be supplied from the storage tank ofthe other diesel engine. The transfer pumps have manual start capabilitiesfor use during this fueling operation.

The failure of a diesel engine could leave one transfer pump unpowered. Theother pump and engine provide all necessary power for safe shutdown. Failureof pump "A" requires the use of pump "B", powered by operating diesel gener-ator "B", to provide fuel to diesel, engine "A".

ACTION 86

,Bechtel provide diesel generator loading profile curves, voltage andfrequency recovery characteristics curves and response time of excitationsystem to load variations. (pages 90-91)

RESPONSE

Prototype diesel generator voltage and frequency/loading profile curves areprovided in Attachment 1 ~ As noted in the transcript (page 190), the NRC

interpretation of the SRP page 8.3.1-11 requirement is that the excitation, system response characteristics are considered acceptable by NRC if the

Page 10: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 11: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

0voltage and frequency response of generator is in accord with specification'requirements ~ The specification requirements are provided in Attachment 2.Comparison of Attachments 1 and 2 shows that the NRC acceptance criteria aremet. '

ACTION Pr7

Provide results of Bechtel's review of NUREG CR-0660, "Enhancement of DieselGenerator Rel'iability." (pages 96-97)

RESPONSE

The results of Bechtel's review of NUREG CR-0660 are as follows:

The report was reviewed to evaluate the design of the PVNGS diesel generatorsin regard to the findings of the report-

This evaluation did not include evaluation of the report in regard to therecommendations for maintenance and inspection practices, personnel trainingor other personnel practices which may affect the reliability of the dieselgenerators.

SUMMARY

Evaluation of the design of the PVNGS diesel generators with respect to thespecific design recommendation of the report shows that the PVNGS designincorporates all the recommendation or meets the intent of the recommen-dation.

EVALUATION OF DESIGN

PVNGS Diesel Generator Desi n Summar

The following is a brief description of the PVNGS diesel generators:

The 7760 HP, 20 cyl1nder vee type engine, with an exhaust gas driventurbocharger, drives a 5500 KW generator. The engine 1s started bycompressed air admitted to the cyl1nders by a timed distributor forcranking. Fuel is supplied from an elevated fuel oil day tank to aneng1ne driven booster pump. Warm lubricating oil is continuouslycirculated through the engine during standby. Jacket water is inter-mittently heated and circulated through the engine during standby.During operat1on, both the lubricating oil and )acket cooling water arecooled in heat exchangers by essential spray pond water. Thermostaticbypass valves are provided for the lubricating oil and )acket waterheat exchangers ~ Combustion air is provided through an air intakeplenum approx1mately 40 ft above grade, at the side of the bu1lding-Engine and building exhaust are discharged approximately 95 ft and90 ft, respectively, above grade. The engine exhaust is directedvertically upward. The control panels are located in separate con-trol rooms with air filtration and cooling.

Page 12: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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REPORT RECOMMENDATION

The specific design recommendations in the report are as follows:

A. Most Significant Corrective'ction

1- Air driers should be used in compressed air starting systems,preferably refrigerated air driers.

2. Electrical contacts and relays should have dustproof contacts.Control cabinets should be dustproof- Diesel generating roomventilating air should be taken at least 20 feet above

graders

3. The turbocharger should have a heavy duty gear drive.

B- Significant Corrective Actions

1 ~ Prelubrication of 3 to 5 minutes before all starts exceptemergency.

2. Prelubrication initiated by emergency start signal.

. C. Additional Corrective Action

1. Engine combustion air should be taken directly from outside the'uilding at least 20 ft above grade and properly filtered.

2. Engine room ventilation air should be filtered and taken at feast20 feet above grade. Ventilation air should be separate fromcombustion air.

3. Engine room ventilation air and engine exhaust gas should not bepermitted to recirculate or enter any other plant building.

4. Bulk fuel oil tanks should have a means to remove water.

5. Fuel pumps should be engine driven, with the supply by an assuredgravity feed or powered by a Class IE battery.

6. Generator insulation should withstand a 105 C temperature rise0

over 40 C ambient ~0

7. Engine cooling water temperature control should be by a 3-waythermostat for directing the engine water to the cooler orbypass, and be of the "Arnot" brand or equal.

8. Concrete floors should be painted to prevent concrete dust fromentering electrical cabinets.

9. Instruments, controls, monitoring or indicating elements shouldbe supported in or on a freestanding, directly floor-mountedpanel to the extent functionally practical except for necessarysensors such as those in piping.

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, Comparison of PVNGS Desi n to the Re ort Recommendations

A. Most Significant Corrective Actions

1. Air Driers

PVNGS uses refrigerated air driers to a dew point of -35F. PVNGS

also provides filters gust upstream of the starting air distribu-tor ~

2. Dustproof Electrical Contacts

PVHGS uses dustproof enclosures on all engine and auxiliary skidcontacts. The control panels are installed in a separate controlroom with a filtered air supply- In addition, the cabinet ventshave filters. The engine room air is taken approximately 40 feetabove grade but is

unfiltered'.

The PVNGS diesel turbocharger is directly exhaust gas driven.There is no gear drive.

B- Significant Corrective Action

1 and 2 Pre-lubrication:

PVNGS continuously circulates warm oil until a start signal isreceived and the engine begins cranking.

C- Additional Corrective Action

1. Combustion Air

PVHGS design takes combustion air directly from the outsideapproximately 40 feet above grade. The air is drawn throughan oil bath filter and piped directly to the engines

2. Engine Room Air

PVHGS does not filter the engine room air. However, the reportmakes this recommendation because most installations have theelectrical control panels in the engine room. Therefore, therecommendation is aimed at reducing the possibility of dust-induced failures. PVNGS uses a separate enclosed control room,and electrical gear in the engine room is dustproof. The doorto the control room is normally closed. Therefore, PVNGS meetsthe intent of this recommendation.

3. Recirculation of Ventilation Air

PVHGS design precludes recirculation by separation of the intakeand exhaust points, and direction of the engine exhaustvertically upward

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4- Water Removal from Fuel Oil Storage

PVNGS provides a low point for water collectiori in the buriedfuel oil storage tanks, and a pipe for use in water removal ~

5- Fuel Pumps and Supply

PVNGS uses an engine-driven fuel oil pump, with assured gravityfeed, of approximately 30 feet of head from the fuel oil day.tank.

6. Generator Insulation

PVNGS uses Class F insulation, rated at 100 C rise over 40 Cambient'ormal operation under design ambient of 60 C (140F)is a 75 C rise.0

7 ~ Engine Cooling Water Control

PVNGS uses an "Arnot" thermostat to direct engine water to thejacket water heat exchanger or to bypass. The same design isalso provided on the engine lubricating oil.

8. Painted Concrete Floors

PVNGS will have the diesel generator control room floors paintedwith an epoxy type concrete surfacer and finish coat (MobilChemical Co ~ 46-X-2900 surfacer and Mobil,76 epoxy finish coat)to preclude concrete dust from entering the cabinets. The engineroom is not dust controlled and will not have painted floors.,

9. Instrument and Control Monitoring

PVNGS design mounts only those instruments and controls on theengine which cannot be mounted elsewhere. The engine sits uponits own foundation; thereby reducing vibration to the buildingsIn addition, the PVNGS diesel operates at a relatively slow600 rpm, and this also reduces engine vibrations.

Desi n Conclusions

The above comparison shows the PVNGS design, both from an engine designand a building design viewpoint, meets, or exceeds, the design

recommen-.'ationsof the reports

ACTION 88

Verify insulation class and temperature rise for the diesel generator.(page 104)

RESPONSE

Generator insulation is class F, 75 C temperature rise over 60 C ambient'0

Page 18: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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ACTION 89

Does Regulatory Guide 1.63 allow thermal fusing of field cables?(pages 141-142)

RESPONSE

Our interpretation of Regulatory Guide 1.63 is that fusing of penetrationcables is not allowable'owever, the present design allows for fusingof field cables external to the penetration. In our opinion there is noviolation of Regulatory Guide 1.63. However, based on NRC s position inthe AC System presentation, even field cable fusing will not be acceptable.Therefore, we are studying the application of double protection in MCC

circuits, including two breakers in series or a fuse in series with theMCC breaker.

ACTION 5'10

Provide the results of Bechtel's review of NRC IE Bulletin '79-27 relating tothe design of PVNGS. Has Bechtel looked at conditions brought about by thefailure of a non-Class IE bus? (pages 165-175)

RESPONSE

IE Bulletin 79-27 addressed three review areas. These were:

1. Review the Class 1-E and non-Class 1-E buses supplying power tosafety and non-safety related instrumentation and control systemswhich could affect the ability to achieve a cold shutdown conditionusing existing procedures or procedures developed under item 2

below. For each bus:

a) identify and review the alarm and/or indication provided in thecontrol room to alert the operator to the loss of power to thebusy

b) identify the instrument and control system loads connected to thebus and evaluate the effects of loss of power to these loadsincluding the ability to achieve a cold shutdown condition;

c) describe any proposed design modifications resulting from thesereviews and evaluations, and your proposed schedule forimplementing those modifications.

2. Prepare emergency procedures or review existing ones that will beused by control room operators, including procedures required toachieve a cold shutdown condition', upon loss of power to each Class1-E and non-Class 1-E bus supplying power to safety and non-safetyrelated instrument and control systems. The emergency proceduresshould include:

8

a) the diagnostics/alarms/indicators/symptom resulting from thereview and evaluation conducted per item 1 above;

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0b) the use of alternate indication and/or control circuits which may

be powered from other non-Class 1-E or Class 1-E instrumentatonand control buses;

c) methods for restoring power to the bus.

Describe any proposed design modifications or administrative controlsto be'mplemented resulting from these procedures, and your proposedschedule for implementing the changes.

3 Re-review IE Circular No. 79-02, Failure of 120 Volt Vital AC PowerSupplies., dated January 11, 1979, to include both Class 1-E and non-Class 1-E safety related power supply inverters ~ Based on a reviewof 'operating experience and your re-review of IE Circular No. 79-02,describe any proposed design modifications or administrative controlsto be implemented as a result of the re-review.

EVALUATION OF DESIGN

In general, our review has determined that the PVNGS design consists of twoungrounded non-Class XE 120 Vac instrument distribution panels E-NNN-Dll andE-NVN-D12 and four ungrounded vital (Class IE) 120 Vac instrument distri-bution panels E-PNA-D25, E-PNB-D26, E-PND-D27, and E-PND-D28.

Each ungrounded non-Class IE Vac instrument distribution panel is normallysupplied from a 480 Vac non-Class IE motor control center through a voltageregulator-transformer to a transfer switch. A back-up source is providedfrom a 480 Vac Class IE motor control center through a Class IE voltageregulator-transformer as an isolation device to the transfer switch. Thetransfer switch automatically transfers, upon loss of power on the normalsource, to the back-up sources Manual transfer is required to return tothe normal source. The distribution panel is fed from the transfer switchth'rough a panel feeder breaker. Distribution to the instrument cabinets isthrough branch circuit breakers .

Each ungrounded vital (Class IE) 120 Vac instrument distribution panel isnormally supplied from a 125 Vdc Class IE control center through an inverterto a manual transfer switch. A back-up source is provided from a 480 Vac non-Class IE motor control center through a voltage regulatortransformer to themanual transfer switch- The distribution panel is fed from the transferswitch through a panel feeder breaker.

Our specific response to item l.a is that an alarm for each non-Class IE'nstrumentdistribution panel is provided to the operator in the control

room. Annunciation will occur on the following:

o Normal source undervoltage

o'ack-up source undervoltage

o Ground detection

o Overload tripping of the panel feeder breaker

o Overload tripping of any branch circuit breaker

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An alarm is provided for each Class IE instrument distribution panel and analarm for each Class IE inverter and transfer switch. Annunciation willoccur on the following:,

o Inverter output or input breaker tripped

o Overload o Inverter output voltage low or high

o Input dc voltage low

o Loss of synchronize

o Transfer switch not on normal source

o Inverter fan failure

o Distribution panel undervoltage

o Ground detection

o Overload tripping of the panel feeder breaker

For item 1.b, the instrument and control system loads connected to eachinstrument distribution panel are provided as noted on Table 1.

Those specific instrument parameters and controls detailed in CESSAR7-4.1.1.10-7 as being required to achieve cold shutdown are listed below.Instrument loop displays and controls available to the control room operatorand the instrument distribution panel supply are identified'

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TABLE 1

120 VAC UNCROUNDED INSTRUMENT DISTRIBUTION PANEL INSTRUMENT um CtanROL SYSTEM LOADS

E-PIIA-D25

ESPAS hux, Relay oCab, J-Shh<01Process Protec- otive Instr.Csb. A»lJ-SBA-C02ASupplenentary oProtect. Sys.J-SBA-C04Radiation Monitors 0J-SQA-RU-Z9, 31& 33Rcaote Shutdcwn oPanelBOP Analog Instr, oCsb. J-ZJA&02A6 B 0hux. Prot. Cab.

'J-SAA-C03" oPlant Prot.- Sys.(PPS) J-SBA-C01 oProcess Prot ~

Instr. Ceb. h-2J-SBA-C02B 0BOP ESFAS & LoadSequencerJ-SAA-C02A 0MOV PositionIndicators 0ContsinmcntHydrogenAnalyzerJ-HPA-E01 0Chlorine DetectorJ-NJA-E01

E-PNB-D26

ESFAS.Aux. RelayCsb. J-Shh-C01Process Protec-tive Instr.Cab. 5-2J"SBB&025-SupplcnentaryProtec. Sys.J-SBB&04Radiation MonitorsJ-SQB-RU-l~ 30» 32,& 34Remote ShutdovnPanelBOP Analog

Instr'ab

J-ZJ5~2Ahux. Prot Ceb,J-5ABC03Plant Prot. Sys.(PPS) J-SBB-C01Process Protec-tive Instr. Cab.B-1 J-SBB-C02ABOP ESFAS & LoadSequencerJ-SAB-C025MOY PositionIndicatorsContsinnentHydrogenhnslyaerJ-HPB-502Chlorine DetectorJ-HJB-EOl

E-PNC-D27

o ESFAS Aux. RelayCsb. J-SAB-C01

o SupplementaryProtect. Sys.J SBC-C04

o CEDHCS Aux. Ceb.C5 J-SFC-C01

o hux. Prot. Cab.J-SAC-C03

o Plant Prot. Sys.(PPS) J-SBC-Col

o Process ProtectiveInstr. Cab. CJ-SBC-COZA

o MOV PositionIndicators

E-PND D28

o ESFAS hux. RelayCeb. J-SAB-C01

o SupplcnentaryProtect+ Sys ~

J-SBD-C04o CEDMCS Aux. Cab.

C6 J-SFD-C01o Aux. Prot. Csb.

J-SAD-C03o Plant Prot. Sya.

(PPS) J-SBD-C010 Process Protective

Instr. Csb. DJ-SBD«C02A

o MOV Position.Indicators

E-NNH-Dl1

o RCS-2 & CVCS-2 oProcess Instr,J-ZJN-C01B&D

o SIS/RCP-1 Process oInstr. J-ZJH-COIF

o NSSS Rad. Mon. Cab.J-SQN-C02 (Process &

Csa Stripper Eff. oRsd. Mon.> ReactorPover Cutbnck,Borononeter, S/U oS/U 6 ControlCh. 2) 0

o BOP Analog Instr.Csb. J-ZJH-C02B6D o

o BOP Analog Instr.Cab. J-ZJN-C02F o

o Rsduaste Instr. Cab.oJ-ZRN-COl 6 C02

o CEDMCS (incl.core ninic)

o NSSS Control 0Sys. J-SFN«C03 o(BICS-1 6 2 6SBCS)

o MICDS tlo Reactor Trip Svgr

Currant Monitor C

0 Loose Parts 6Vibration Mon.

o Can. PyrolyseteCollector

E-NNH-D12

RCS-1 & CVCS-1Process Instr.J-ZJN-C01A 6 CNSSS Rsd. Mon. Cab. .J-SQN-C02 (MICD hap.,CEA Display, S/U 6Control Ch. 1)CVCS-3 & SIS/RCP-2Process Instr.J-ZJN C01E 6 0BOP Analog Instr. Csb.J-ZJN-C02A & C 6 -C07BOP Analog Instr. Ceb.J-ZJN-C02E 6 C

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Page 26: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 27: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

Parameteror Control

0Class IE Instrument Distribution Panels

Non-Class IEInstrument

Distribution Panels

E-PNA-D25 E-PNB-D26 E-PND-D27 E-PND-D28 E-'NNN-D11 E-NNN-D12

Neutronlog power

Hot leg-temperature

J-SEAJI-1A

J-RCA-TI-112HA

& TR»112HA

J-SEB-JI-1B

J-RCB-TI-1 12HB

J-SEC-JI-1C

J-RCC-TI-112HC

J-SED-JI-1D

J-RCD-TI-112HD

J-RCN-TT=111X

& TI-lllX

Pressurizerpressure

Pressurizerlevel

J-RCA-PI-102A

& PR-102A

J-RCA-LI-11QX

& LR-110X

J-RCB-PI-102B

J-RCB-LI-110Y

J-RCC-PI-102C

J-RCD-PI-102D

J-RCN-LIC-110LR-110

& LI-113

J-RCN-PIK-110

& PR-100

SG

pressureJ-SGA- J-SGB- J-SGC-

PI-1013A PI-1013B " PI-1013CPI-1023A & PI-1023B & PI-1023C

& PR-1013A

J-SGD-PI-1013D

& PI-1023D

SG

levelJ-SGA-

LI-1113A& LR-1113A

J-SGB-LI-1113B

J-SGC-LI-1113C

J-SGD- J-SGN-LI-1113D LR-1111

(narrowrange)

RWT

levelJ-CHA- J-CHB- J-CHC- J-CHD-

LI-203A LI-203B LI-203C LI-203D& LI-201

J-CHN-LI-200

Chargingflow

J-CHA-FI-212

Chargingpressure

SITpressure

J-S IA-PI-331

& PI-333

J«CHB-PI-212

J-SIB-PI-311

& PI-313

J-SIN-PI-332

J-SIN-PI-312

LPSIpump flow

Shutdowncooling heatexchangerdiff- temp.

J-S IA-FI-306

J-S IA-TR-351

& TR-303K

J-SIB-FO-307

J-SIB-TR-352

& TR-303Y

Atmosphericdump valveontrol

J-SGA- J-SGB-HIC-179A HIC-178A

'& HIC-184A & HIC-185A,

-11-

Page 28: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 29: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

eMotor operated valves, pumps, pressurizer heaters and solenoids required toachieve cold shutdown are powered from buses other than the instrument distri-bution panels.

In response to item 1.c, we have determined that loss of a single instrumentdistribution panel, Class IE or non-IE, will cause a loss of some, of theindicators and recorders available to the control room operator. Theaffected indicators,. which employ a gas-discharge display, will extinguishon the loss o the instrument distribution panel. This failure mode

is'istinguishableand will not offer confusing information to the operator.In addition, the instrumentation and control systems lost will generatealarms and actuation of some equipment as the loop output contacts fail totheir deenergized states. In the non-IE instrument loops affecting safeshutdown circuits, i.e ~ pressurizer level control of the pressurizer backupheaters, selector switches are provided on the main control panel to enablethe operator to provide control from the unaffected control loop ~ No con-trol action generated by the loss of an instrument distribution panel willprevent the operator from controlling the required safe shutdown equipmentor interfere with the safe shutdown functions. Upon detection of loss of aninstrument distribution panel, adequate instrumentation and c'ontrol- functionsfrom the list provided above will be available to the operator to enable theoperator to achieve a cold shutdown condition. No design modifications areproposed ~

Item 2 - Response to be provided by APS ~

IE Circular No. 79-02, Failure of 120 Volt Vital AC Power Supplies has beenre-reviewed in consideration of item 3 to include both Class IE and non-ClassIE instrument distribution panel supplied'or the Class IE inverters, thePVNGS design precludes the possibility of a transient causing a failure ofa Class IE inverter by utilizing a battery source in parallel with a dccharger. The battery source serves to eliminate any undervoltage transientsthat the charger may experience The non-Class IE instrument distributionpanels are not supplied through inverters. Both the normal and back-upsupplies are fed from 480 Vac through a voltage regulator-transformer. Thetransfer switch will automatically transfer, upon loss of power on the normalsource, to the back-up source- Manual transfer is required to return to thenormal source. The switch is also equipped with a mechanical handle whichbypasses electric circuitry and can switch to either source. No designmodifications are proposed .

ACTION 811

Will formal training, equivalent to that provided by a diesel manufacturer,be provided for diesel maintenance personnel? (page 97)

RESPONSE

Response to be provided by APS.

ACTION 812

Discuss how preoperational testing of overall AC power distribution systemverifies voltage drop analysis. (pages 97-101)

-12«

Page 30: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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l

Page 31: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

RESPONSE

Preoperational tests will verify voltage drops by measuring the voltage atthe buses during:

a) Normal plant operation.

b) -Starting the Class IE and Non-Class IE loads which, in accordance withthe voltage regulation study, cause the largest system voltage drops. withnormal loads

running')

Both a) and b) at 95X grid voltage.

ACTION 813

Can the essential chillers be manually cross-tied for backup? (page 119)

RESPONSE

There are no design provisions to manually or automatically cross-tie theessential chillers. However, the present design is in conformance withthe single failure criterion since the single failure of an ESF train oressential chiller train will still leave one ESF train and its associatedessential chiller train intact. In addition, each essential chiller trainis sized to serve only one ESF train.

ACTION /$ 14

Describe how quality control'pplies to the non-IE onsite distributionsystem between the switchyard and the ESF 4.16 KV buses'pages 143-146)

RESPONSE

The Area Field Engineer (AFE) inspects and documents the installation ofraceway utilizing a "Raceway Inspection Record" per Work Plan Procedure/Quality Control Instruction WPP/QCI 251 '. This inspection includes andverifies that raceway is the proper type and size per the latest engineer-ing design document and does not exceed the maximum number of bends betweenpull

points'he

AFE reviews the engineering design drawings to assure that the electrical'quipment, including switchgear, can be installed as shown. The,switchgear

is installed and inspected to verify that it is anchored and grounded properlyand that the bus connections are bolted to the correct torque. The foregoingis documented on the "Equipment Inspection Record" per WPP/QCI 258.0. Theswitchgear bus is meggered and hypotted (tested) by Start-up during componentcheckout. Each component as well as the complete system is functionallytested for electrical equipment and transformers.

Before the large power transformers are installed, the AFE reviews the engi-neering design drawings to ensure that the transformers can be installed asshown. The AFE reviews the vendor instruction manual for proper installation

-13«

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Page 33: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

of the transformers. Based on the information in the instruction manual,the AFE initiates a rigging procedure for setting the transformers. Thetransformer is installed and then inspected to verify that it is anchoredand grounded properly. These inspections are documented .on the "TransformerInspection record" per WPP/QCI 258.'4. Various tests are made on the oilduring oil filling and after'ome of the tests include: dielectricbreakdown, neutralization number, interfacial tension, power factor, andmoisture content.

The AFE verifies that the cables are pulled through the correct raceways,maximum pulling tension is not exceeded, and the cable is identifiedcorrectly.. The AFE's inspection is documented on the "Cable InspectionRecord" per WPP/QCI 254.0. The cable is tested per Engineering require-ments by the AFE to verify that the cable has not been damaged duringpulling operations and that it is acceptable for energization. Hedocuments the results of the megger and hypot tests per WPP/QCI 256.0.

The AFE inspects the cable terminations and documents the results of hisinspection and the acceptance of the terminations per WPP/QCI 255.0.

Quality Control does not generally inspect non-IE installations. In theseareas inspections are performed by Field Engineering with surveillance andaudit by Quality Assurance.

-14-

Page 34: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 35: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

ATTWc OWE~7 ICOOP E R ENE R GY SE RY I CE 5

2.8 load Acceptance Test

.7.

Simulate emergency start signal to engine control panel. Enoinecranks and- accelerates.. Start loaded 2000 HP induction motorwhile engine is still accelerating and is between 57 and 60 Hz(permissive td load signal given by engine control panel).

Note: 10 seconds is maximum permitted for the engine-generatorset to achieve rated frequency and voltage.

Start test with L.O. and J.M. temperature at 120'F + 10'F ~

Start in OGSS mode.

Discussion:

Engine was started by remote OGSS signal.

A fully loaded 2000 HP motor was started automatically by an engineRPH signal as engine was accelerating.

The motor load came on at 57 Hz.

A copy of the visicorder record of the performance parameters isincluded on page 12.

-11-

MO18-) 67- 1

Page 36: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory
Page 37: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 38: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 39: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

COOPER ENERGY SERVlCES

2.9 Load Acce tance Test

Reauirement: (All Units) (Ref . Ill.C.7.b)

Simulate emergency start signal as in 2.8 above. After enginehas reached rated frequency, apply 2700 KW resistive load. Afterfrequency and voltage have been stabilized. simultaneously star:2000 HP induction motor and add block of resistive load (amountyet to be determined).

Start test with L.O. and J.M. temperature at 120 F + 10'F.

Start in DGSS mode.

Discussion:

The engine was started by a remote DGSS signal.

After steady state no load condition was achieved, a 2800 KW

resistive step load was added.

After'teady state conditions were again achieved, a step loadof 2200 KW (2000 HP motor plus 1000 KW resistive) was added.

Copies of the Yisicorder record of performance parameters areincluded on pages 14, 15 and 16.

-13-

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Page 40: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 41: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 43: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 46: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 47: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

COOPER ENERGY SERVICES

2.10 Load Acceptance Test

Reauirement: (All Uni ts) (Ref I I I.C.7.c) .

Simulate emergency start signal as in 2.8 above. After enginehas stabilized at rated frequency, no load, apply 2000 HP

induction motor.

Start test wi th L.O. and J. V,. temperature a t 120'F + 10" F.

Start in DGSS mode.

Discussion:

The engine was started by remote DGSS signal.

After steady state no load condition was achieved, a fully loaded2000 HP motor was added as load.

Copies of the Visicorder record of performance parameters areincluded on pages 18 and 19..

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Page 48: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 49: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 53: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

COOPER ENERGY SERYICES

2.11 Com uter SimulationA

Reouirement: (Ref III.C.7.d)

Data obtained from tests in 2.8 a, b and c above is to be forwardedto Applied Mechanics for computer simulation of performance. Asdictated by results of these tests, and their comparison with thecomputer simulation, adjustments and modifications must be made tothe engine, generator, and control systems and these tests repeateduntil the necessary performance has been attained.

Discussion:

A computer simulation study was made to relate the transientfrequency deviation for a 2800 KW resistive step load measuredduring shop testing to the frequency deviations for the worstload step in the customer's load schedule.

Results of this simulation are presented in a separate report titled"Frequency Deviation for Transient Loading" dated Sept. 20, 1978.This report is included herein as an Appendix, No additional ad-justments or modifications were required as a result of this simu-lation.

2.12 Load Re 'ection Test

(111 Il I l ( I Ill.l.llLoad the engine-generator set to 110~ load. Remove all load simul-taneously. Record frequency and voltage transients.

'Discussion:

The Visicorder record on page 21 shows the engine running steadystate with ll0» load and then this load removed in a single step.

-20-

Q01 B-3 67-1l

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Page 56: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory
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13-MH-018

4.4.2.16.3 Electrical devices, instrumentation and control devices, andcontrol panel ass'emblies which. are s'kid mounted, shall be qualified forthe seismic conditions at the mounting location in accordance with appen-dices 4T ahd 4U.

4.4.2.16.4 - Electrical devices and cabinets end instrumentation control-panel assemblies shall be tested in accordance with the provisions ofIEEE-344. The Bidder shall take into consideration amplifications of theseismic input in accordance with appendix 4U.

4.4.2.16.5 Nonactive pumps, valves, heat exchangers, tanks, air receivers,and other nonactive equipment shall be seismically qualified per appen-dix 4J.

4.4.2.16.6 The Supplier shall cooperate and be responsible in, providingadequate seismic qualification. Seismic tests and calculations shall besubmitted to the Engineer for approval.

4.4.3 Electrical Design Requirements

The diesel generators are a part of the Class IE system as defined inIEEE 308 and function to provide standby power for the operation of emer-gency systems and engineered safety features during and following theshutdown of the reactor when the preferred power supply is not available.

One diesel generator is provided for each load group on each 4.16-kVengineered safety features bus. Ho provisions will exist for automaticallyconnecting redundant load groups or diesel generators together. Thediesel generators will be electrically isolated from each other. Physicalseparation vill be maintained as the diesel generators will be housed inseparate Seismic Category I rooms. Power and control cables for the dieselgenerators will be routed to maintain physical separation.

4.4.3.1 Performance Re uirements

Performance requirements are as follows:

a. The Supplier shall guarantee each diesel-generator unit to becapable of attaining rated frequency and voltage within 10 secondsof receipt of the starting signal.

b. I,oad pickup, after generator has attained rated frequency andvoltage, shall be in accordance with table 4-6.

C. The Supplier shall guarantee the starting and loading ability of itsdiesel generator herein specified to be licensable under currentNRC criteria and regulatory guides in effect at date of purchaseorder. Table 4-.6 of sequential loading, is considered to be themost severe duty requirement that the diesel generator will beexpected to encounter.

4-31

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13-MH-018

d. Starting shall be automatic upon receipt of 'a starting signal. Thediesel engines will normally be shut down manually. For testpurposes, .local and remote manual starting and stopping capabilityshall be furnished.

e. The diesel-generator loading shall be accomplished automatically.This .function will be carried out by the Purchaser-furnished load-sequencing system. The loading shall commence as soon as the gen-erator rated frequency and voltage are reached following enginestart. The first block of load will be applied a maximum of10.5 seconds after the diesel engine start signal is given. Theremaining essential loads will be applied in not more than sevensequenced steps so that all loads shall be energized in not morethan 40 seconds after the engine start signal is received. Theinitial loading of each step or block of load will consist of thelocked-rotor current of the various induction motors being started.Also inrush current will occur on energization of two 4160V/480Vtransformers at 10.0 seconds and 10.2 seconds respectively. Thegenerator, exciter, and regulator shall provide adequate voltageto sustain the applied loads in accordance with the followingrequirements:

At no time during the load sequence shall the voltage andfrequency decrease to less than 75 and 95 percent of nominalvalues, respectively.

Voltage shall be restored to within 10 percent of nominalvoltage in less than 40 percent of each, load-sequence timeinterval.

'. 3. Frequency shall be restored to within 2 percent of nominalfrequency in less than 40 percent of each load-sequence timeinterval.

4.4.3.'2 Startin Initiatin Circuits

The diesel generators will be started on the following:

a. Safety injection actuation signal (SIAS).

b. Loss of voltage to the respective 4.16-kV engineered safetyfeatures bus to which each generator will be connected..

c. Auxiliary feedwater pump actuation signal (AFAS).

The Purchaser will combine these signals to provide two "diesel generatorstarting signals" (DGSS) which are used. to initiate starting. The signalswill be maintained-contact closure.

4-32

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Page 61: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 62: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

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Page 63: S~'KM Palo Nuclear Unit ii Arizona Publi Palo Unit BYNAME Palo … · 2018. 7. 31. · ANPP-16868-JMA/WFQ Dr. H. R. Denton, Director Nuclear Reactor Regulation U.S. Nuclear Regulatory

) .„., -o- o. eu~""-'~'~~COMPANY'ORRESPONOENCE

TO:Sm. 4

John Allen, 3003

November 5, 1980PVNGS-H80-RWK/JGS-51

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FROM: " R. W. Kramers>o. )) '015Ex>.Z .

6314'UBJECT:

NRC IE Biilletin ND 79-27l.oss <>f Non-C]ass II'. Instrumentation 'Ind Control Power SystemBus During Operation

File: 055-026

The following is in response to Item 2 of NRC IE Bulletin 79-27.V

Emergency procedures that will be used by control room operators,including procedures required to achieve a cold shutdown condition,upon loss of fiower to each Class IE and non-Class IE bus supplyingpower to safety and non-safety related instruments and'ontrolsystems will be prepared and then reviewed at least tfiree monthsprior to the operating license. The procedures will include thefollowing information.

a. The diagnostics/alarms/indicators/symtom resulting from thereview and evaluation conducted per item 1 of IE Bulletin No. 79-27.

b. The use of alternate indication and/or control circuits whichmay be powered from other. non-Class IE or Class IE instrumentation andcontrol buses.

c. Hethods for restoring power to the bus.

A description of any proposed design modifications or administrativecontrols to be implemented resuleing from these procedures, and theproposed schedule for implementing the changes will also be provided.

If any further assistance is required on this matter contact JerrySelf at Extension 6315.

JGS/jr

ramer, Support Servi.ces Hanager (Act.ing)PVNG

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G.C.E.E.F.W.W.F.R.R.

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Tl>e Haint.en(»t«e I>eparttt>«nL intends t:o comply vit.h t)>ev<>coma> tt()e<l training requirements in NURE{'/CR-0660 tot:h(l e.:tet>{: Ll>(lt supervisory, tcchnical support, anm>intenat>ce vnr )ters invo)ved t"J.th t)>e Emergency Diese(;e»< rata> ,')aint nance requirements vill have ini.tialLvainit>r. < t> tl>e eq»ipment appr<..ved by the Enginem(>l>u I act. >> l"«l't>< 'lp>(> l a >proved an-<;o)t>g training ad(lressingin-servir:e .ir>spec iottion hand mair>tenance requirements asexprr,).et>ce vi t' '. e a'I t:) ~ P~Jo Verde systems are obtained.On-I;oi.t>g- trair>inr. vi.l.l. also a(idress c»rrent industry>rublems witl> «r,".'gency generating systems.

Tl>is t:raining vi J.l be a form:>l part off the overal.l.training program or >ef tl e PV(it'S Haintenance Department,

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