forwards response to nrc 820225 request for addl info re

John D. O'Toole Vice President S

Consolidated Edison Company of New York, Inc. 4 Irving Place, New York, NY 10003 Telephone (212) 460-2533

May 4, 1982

Re: Indian Point Unit No. 2 Docket No. 50-247

-\.

Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 4

ATTN: Mr. Steven A. Varga, Chief Operating Reactors Branch No. Division of Licensing

Dear Mr. Varga:

Attached is our response to your letter of request for additional information.

February 25, 1982 regarding a

Should you or your staff have any questions, please contact us.

Very truly yours,

Attachments

/1;

8205110389 820504 PDR ADOCK 05000247 P PDR

ATTACHMENT A

Environmental Qualification of Safety Related Electrical Equipment

Response To February 25, 1982 NRC Request For Additional Information

TMI Action Plan Requirements

April 1982

Consolidated Edison Company of New York, Inc. Indian Point Unit No. 2

Docket No. 50-247 Facility Operating License No. DPR-26

ATTACHM-ENT A

The paragraph numbers below correspond to paragraph numbers in the enclosure to the NRC letter from Mr. Steven A. Varga to Mr. John D. O'Toole dated February 25, 1982

Ia.) Identification of all TMI Action Plan equipment installed to date in a harsh environment is included in Attachment B.

lb.) The equipment tables use a format consistent with our original submittal of May 9, 1980 and our updated submittal of October 31, 1980. We have retained this format in order to expedite our response to your request. Nevertheless, the subcategory headings under the Equipment Type Column provide correlation to some of the TMI Action Plan sections.

lc.) Indian Point Unit No. 2 was advanced into the SEP Group for its environmental qualification review and, therefore, the 79-01B format and the SCEW sheets did not apply to our original submittals. Nevertheless, our September 4, 1981 submittal which forwarded our 90 Day Response to the Staff SER did include SCEW sheets for those items that were addressed at that time.

ld.) The bulk of the TMI equipment installations in harsh evironments, particularly containment, were installed during our extended outage from October 1980 through May 1981. For most of those items, the projects were initiated prior to the May 1980 Commission Order on environmental qualification. Where possible, items were upgraded to 1974 qualification, if they did not extend that outage. Individual line items in the Attachment B tables are footnoted appropriately if they are IEEE 323 (1971) qualification items.

2.) Individual qualification reports have-not been provided because of their tremendous volume. These reports are contained in our auditable environmental qualification files at our Corporate Office and are available for review by the NRC Staff.

3.) Con Edison had made references to Standard Owners' Group positions and has requested extensions of implementation dates with respect to the NUREG-0737 technical areas in our original submittal of February 26, 1981 and updated submittals of May 12, 1981 and July 1, 1981. Additional extensions have been requested in our submittals of December 30, 1981, February 4, 1982 and April 16, 1982.

4.) The dose calculations according to the guidelines are extremely conservative and include large margins to account for uncertainties. The normal operating exposures are included in these calculations. These normal exposures are at least two orders of magnitude below the accident exposures and are therefore insignificant for the purposes of qualification testing. With regard to equipment near the sump, no new

now equipment near the sump has been identified in this

submittal. Equipment identified in our original May 9, 1980

submittal and our September 4, 1981 submittal near the sump has

been previously reviewed.

5.) Information concerning radiation environments outside containment

has been provided in our original May 9, 1980 submittal and

updated in our September 4, 1981 submittal. This information has been summarized in the introduction to Attachment B.

ATTACHMENT B

Environmental Qualification of Electrical Equipment

TMI Action Plan Equipment

April 1982

Consolidated Edison Company of New York, Inc. Indian Point Unit No. 2

Docket No. 50-247 Facility Operating License No. DPR-26

ATTAC1LMENT B

This Attachment summarizes the results of an investigation conducted to

review the environmental qualification levels for electrical equipment

installed prior to this date at Indian Point Unit No. 2 in response to

TMI "Lessons Learned" and the TMI Action Plan (NUREG-0737). The

investigation was initiated in response to environmental qualification

requirements appearing in NUREG-0737 as well as NRC's I&E Bulletin 79-01B

as applied to Indian Point 2.

The scope of systems and components listed for investigation was

determined using previously derived levels of inside and outside

containment environmental conditions that could occur as the result of

postulated events consisting of Loss of Coolant Accident (LOCA) or a High

Energy Line Break (HELB). Inside and outside containment service

conditions were specified in the May 9, 1980 and subsequently modified in

the September 4, 1981 submittals to NRC in order to conform to the

requirements specified in the May 21, 1981 NRC Staff Safety Evaluation

Report. The applicable service conditions are summarized below:

Containment Accident Conditions (C)

Maximum Pressure: 40.6 psig

Saturation Temperature: 287°F

Humidity: 100%

Radiation: 2 x 108 rads

Chemical Spray: 2000 ppm boric acid spray with 40% NaOH to

result in pH 10.0

Pipng eneraton reaAccident Conditions (PP)

Maximum Pressure:; Ambient

Saturation Temperature: Ambient

Humidity: Ambient

Radiation: 3.6x10 rads

Chemical Spray: None

Aux. Feed Pump Room Accident Conditions (AP)

Maximum Pressure:

Saturation Temperature:

Humidity:

Radiation:

Chemical Spray:

0.9 psig

215 0 F

100%

Negligible

None

A list of T141 related components installed at Indian Point 2 has been

developed and reviewed to identify equipment that would be exposed to

severe environmental conditions following a postulated accident. This

listing, complete with the service conditions and the qualification data

associated with each component, is included herein. Equipment located

in areas outside the containment considered to be mild environments due

to no change in service conditions following the postulated LOCA or HELB

were excluded from this listing.

Electrical cables in the pipe penetration area, outside containment, a re

still undergoing review for environmental qualification. As soon as this

review is completed, we will submit a table to update this report.

Piping Penetration Area

PARAMETER ABREVIATIONS

Temp Temperature in degrees fahrenheit

Press Pressure in pounds per square inch gauge

R H Relative Humidity in percent

Chem Containment Chemical Spray

Rad Integrated Radiation Dose

Sub Submerged

LOCATION ABREVIATIONS

C Inside containment

PP Pipe penetration area outside of and adjacent

to containment

AP Auxiliary feedwater pump room

QUALIFICATION DATA ABREVIATIONS

Spec Specifications

Qual Qualifications

Ref Reference

NA Not applicable

P Separate Methodology of Qualification

S Sequential Methodology of Qualification

Amb Ambient

Table 1 (1 of 3) INDIAN POINT 2

TMI EQUIPMENT QUALIFICATION FOR HARSH ENVIRONMENT

Time Environmental Qual. Equipment Type Loc. Needed Parameter Spec. Qual. Method Ref. Note

Valve Motor Operators:

Primary Coolant Sample P.P. 30 day Temp Amb NA S (1) Line Valves MOV 5153, Press Amb NA 5154, 956 E&F RH Amb NA Limitorque SMB-000 Chem No NA H-Insulation Rad 3.6x10 6 2x10 8

Sub No NA

RCS Sample Line Valves C 30 day Temp 287 300 5 (1) MOV 955 A&B Press 40.6 70

.Limitorque SMB-000 RH 100 100 H-Insulation Chem YES YES

Rad 2xlO 8 2x10 8

Sub No NA

RCS Sample Line to P.P. 30 day Temp Amb NA (1) Booster Pump Valves Press Amb NA MOV 4396, 4397 RH Amb NA Limitorque SMB-000 Chem No NA H-Insulation Rad 3.6xi0 6 2xlO 8

Sub No NA

Flush Water to RCS P.P. 30 day Temp Amb NA (1) Sample Line Valves Press Amb NA MOV 4394, 4395 RH Amb NA Limitorque SMB-O00 Chem No NA H-Insulation Rad 3.6x10 6 2xlO 8

Sub No NA




Valve Motor Operators (Contt d):

RHR Loop Sample Line P.P. 30 day Temp Ainb. NA S() Valves MOV-958, 959 Press Anab. NA Limitorque SMB-000 RH Amb. NA H-Insulation Chem No NA

Rad 3.6xi0 6 2x10 8

Sub No NA

Recirculation Pump P.P. 30 day Temp Amb. NA S() Discharge Sample Line Press Amb. NA Valves RH Amb. NA MOV-990A & B Chem No NA Limitorque SMB-000 Rad 3.6xi0 6 2x10 8

H - Insulation Sub No NA

RHR Miniflow Line P.P. 30 day Temp Arab. NA (1) Valves MOV 1870, 743 Press Amb. NA LimitorquE SMB-000 RH Amb. NA H - Insulation Chem No NA

Rad 3.6x10 6 2x10 8

Sub No NA

Seal Water Return Valve P.P. 30 day Temp Anb. NA (1) MOV 222 Press Amb. NA Limitorque SMB-O00 RH Amb. NA H - Insulation Chem No NA

Rad 3.6x10 6 2x10 8

Sub No NA

CVCS Charging Line P.P. 30 day Temp Amb. NA (1) Valves Press Amb. NA MOV-205, RH Amb. NA 226, 227 Chem No NA Limitorque Rad 3.6xi0 6 2x10 8

H - Insulation Sub No NA

Table 1 (3 of 3)

INDIA1 POINT 2 TMI EQUIPMENT QUALIFICATION

FOR HARSH ENVIRONMENT

Eauioment Type Loc.Time

Needed

Environmental

Parameter Spec. Oual.Qual. Method Ref. Notes

Valve 'Motor Operators

RC Pump Seal Water

Supply Valves

MOV 4925 thru 4928, 250 A thru D

Limitorque SMB-00 &

SMB-000

H - insulation

Sample Injection

to Containment Sump

MOV 4399, 5132

Limitorque SMB-000

H - Insulation

Safety Injection

Pump

Discharge Valves

MOV 850 A&B

Limitorque SMB-000 H - Insulation

Containment Spray

System

Header: Valves

MOV-869 A&B

Limitorque SHB-000

H - Insulation

(Cont'd):

P.P.

P.P.

P. P.

P.P.

30 day

30 day

30 day

30 day

0

Temp Press

RH Chem

Rad

Sub

Temp

Press

RH Chem

Rad

Sub

Temp

Press

RH

Chem

Rad

Sub

Temp

Press

RH

Chem

Rad

Sub

Amb. Amb. Amb • No 3. 6xl0

6

No

Amb An b Amb No 3. 6x10 6

No

Amb Amb Amb No 3.6x10

6

No

Amb Amb Amb No 3.6xlO

6

No

NA

NA

NA NA

2xlO8

NA

NA

NA

NA

NA

2x108

NA

NA

NA

NA

NA

2xl08

NA

NA

NA NA

NA

2x10 8

NA

Equipment Type




Solenoid Valves:

Nitrogen Seal Valves P.P. 30 day Temp Amb NA S (2) (3) SOV 3500, 3506 thru Press Amb NA 3510 RH Amb NA Valcor V-52600 Series Chem No NA

Rad 3.6x10 6 2x10 8

Sub No NA

Isolation Valve Seal P.P. 30 day Temp Amb NA 5 (2) (3) Water Systemn Press Amb NA SOV 3501 thru 3505, RH Amb NA 3511 thru 3517 Chem No NA Valcor V-52600 Series Rad 3.6x10 6 2x10 8

Sub No NA

Post Accident Liquid P.P. 30 day Temp Amb NA 5 (2) (3) Sample Line Press Amb NA SOV 3426 thru 3431 RH Amb NA Valcor V-52600 Series Chem No NA

Rad 3.6xi0 6 2x10 8

Sub No NA

Containment Hydrogen P.P. 30 day Temp Amb NA 5 (2) (3) Monitor Valves Press Amb NA SOV 5018 thru 5025 RH Anb NA Valcor V-52600 Series Chem No NA

Rad 3.6x10 6 2x10 8

Sub No NA

Nitrogen Supply Valves P.P. 30 day Temp Amb. NA 5 (2) (3) to Reactor Coolant Press Amb. NA Drain Tank RH Amb. NA SOV 3416, 3417 Chem No NA Valcor V-52600 Series Rad 3x10 6 2x10 8

Sub No NA

Table 2 (2 of 2)

INDIAN POINT 2 TMI EQUIPMENT QUALIFICATION


Time Environmental Qual.

Equipment Type Loc. Needed Parameter Spec. Qual. Method Ref. Note

Solenoid Valves (Cont'd):

Nitrogen Supply to P.P. 30 day Temp Amb NA S (2)(3)

Pressurizer Relief Tank Press Amb NA

Valves SOV 3418, 3419 RH Amb NA

Valcor V-52600 Series Chem No NA Rad 3"6xi0 6 2xi0 8

Sub No NA

Post Accident Con- P.P 30 day Temp Amb NA S (2)(3)

tainment Vent System Press Amb NA

SOV EW-I, EW-2 RH Amb NA

ASCO NP Series Chem No Na Rad 3.6xi0 6 2xlO 8

Sub No NA

Relief and Safety C 30 day Temp 287 346 5 (4)(5)

Valves PCV 455C, 456 Press 40.6 110 ASCO-NP Series RH 100 100

Chem YES YES Rad 2x10 8 2xlO 8

Sub No NA

Post Accident Con- P.P. 30 day Temp Amb NA S (4)(5)

tainment Vent System Press Amb NA

SOV E-l, E-lA, E-2, RH Amb NA E-3, E-5 Chem No NA ASCO-NP Series Rad 3.6xi0 6 2x10 8

Sub No NA

Table 3 (1 of 1)INDIAN POINT 2


Equipment Type Loc.Time Needed

Environmental Parameter Spec. Oual.

Qual. Method

TransmItters:

AFWS Flow FT-1200,1201,

1202,1203 Rosemount 1153 HA5

Containment Pressure PT 3300 & 3301 Rosemount 1153 CA

Containment Water Level LT 3300 thru 3302 Barton 764 (Lot 4)

RCS & Wide Range Pressure for Saturation Meter PT 402 & 403 Barton 764 (Lot 4)

Reactor Vessel Level LT 1311 1312

1321 1322 Barton 752 (L;)t 4)

30 days

30 daysP. P.

30 days

30 days

P.P. 30 days

Temp

Press

RH

Chem

Rad

Sub

Temp

Press

RH

Chem

Rad

Sub

Temp

Press

RH

Chem

Rad

Sub

Temp

Press

RH

Chem

Rad

Sub

Temp

Press RH

Chem

Rad Sub

215 0.9 100 No Neglible No

Amb Amb Amb No 3.6x10

6

No

287 40.6 100 YES 1.4x10

7

No

287 40.6 100 YES -52xi0

7

No

Amb Amb Amb No 3. 6x10

6

No

350 120 100 NA 4.4x10

7

NA

NA NA NA NA 2x10

8

NA

380 89.7 100 YES 5x10

7

NA

380 89.7 100 YES 5x10

7

NA

NA NA NA NA 5x10

7

NA

(6) (a)(b)

(6) (a)

(7) (c)(e)

(7) (c)

(7) (c)

Ref. NoteRef. Note




Limit Switches:

Relief and Safety Valves C 30 days Temp 287 340 S (8) PCV 455C, 456 Press 40.6 70 NAMCO EA 180 RH 100 100

Chem YES YES Rad 2x10 8 2x10 8

Sub No NA



Equipment Type Loe .Time Needed

Environmental Parameter SneC.

Terminal Blocks:

Westinghouse Terminal Blocks 542247 (805432)

C/P.P. 30 days Temp

Press RH Chem Rad

Sub

287 40.6 100 YES 107

No

(9)(10) (a)(b) (11)

YES

2x107

Oual.Qual.

Parameter Sr~e.Method Re. otRp . N t


TMI EQUIPMENT QUALIFICATION


Equipment Type Loc.Time

Needed

Environmental Parameter Spec. Oual.

Qual. Method Ref. Nnt-e

Containment High Range Radiation Monitor:

High Range Detector R25 & R26

Victoreen 877-1

Cable/Connector Assembly 878-1 Victoreen

30 days

30 days

Temp Press RH

Chem Rad

Sub

Temp

Press RH

Chem Rad Sub

287 40.6 100 YES 2xlO8

No

287 40.6 100 YES 2x10

8

357 133 100 YES 2xlO 8

(12)

(12) (d)

Oual. Method Ref. Note



Equipment Type Loc.Time

NeededEnvironmental

Pararmtpr n .

Safety Valve Flow Monitor System:

Acoustic Sensors

Accelerometers

FE 3106, 3107,3108

TEC 1414 System Endevco 2273 AMl

Preamplifier

TEC 1414 System

Charge Converters

Model 501

Valve Flow Monitor

Cable Assembly TEC 2273-Cl

30 days

30 days

30 days

Temp

Press

RH Chem

Rad

Sub

Temp

Press RH

Chem

Rad

Sub

Temp

Press

RH

Chem

Rad

Sub

287 40.6 100 YES 2xl0 8

No

287 40.6 100 YES 2x10

8

No

287 40.6 100 YES 2x1 08

No

400 60 100 YES 2x10 8

NA

(1-3)

(13) (d)

(13) (d)

Qual.

Table 8 (I of 1)INDIAN POINT 2


Equipment Type Loc.Time Needed

Environmental Parameter SParameter S Method Ref Nnt-

Resistance Temp. Dectectors-

Reactor Vessel Level TE 1313,1314,1317,1318

1319,1324,1323,1327 1328,1329

NIMCO Model #S8809S8810

ICC Saturation Meter

TE 401 thru 404, 413,423,433,443

Rosemount 176 JA

30 days

Dec. Onal."I

Qual. M~thnd

R~f

30 days

Temp

Press RH Ch em Rad Sub

Temp

Press RH

Chem Rad Sub

(d)287 40.6 100 YES

2xlO 8

No

287 40.6 100 YES 2xiO

8

(d)

Table 9 (1 of 1)

INDIAN POINT 2TMI EQUIPMENT QUALIFICATION


F,.tiinrn"M Type Loc.Time Needed

Environmental

Parameter SiDec. Qual.Qual. Method Ref. Note

Electro-Pneumatic

Transducers

Post Accident Con

tainment Vent System

Valves E-1, E-lA, E-2,

E-3, E-5

Fischer Governor 546

P.P. 30 days Temp

Press

RH

Chem

Rad

Sub

Amb Amb Amb No 3. 6x10 6

No

(d)

0

uipment Type pec -



Equipment 'type Loc.Time Needed

Environmental Parameter Snec.Parameter Soec. Method I? - f TT +

Cable:

2/C #16, 4/C #16 Silicone Rubber

Dielectric Harbour Industry

1/C #12, 1/C #10 7/C #12 XLPE /NEO The Rockbestos Co.

Firewall III

30 days

30 days

Temp

Press RH Chem

Rad

Sub

Temp

Press RH

Chem

Rad

Sub

287 40.6 100 YES 2x10 8

No

287 40.6 100 YES 2xlO8

No

(d)

340 113 100 YES 2x10 8

NA

(14)

Splices:

Heat Shrinkable In-Line Splices Raychem Type WCSF-N

30 days Temp Press

RH

Chem Rad

Sub

287 40.6 100 YES 2xlO

8

No

314 66 100 YES 2x10 8

NA

(15)

Oul].Qual. M~thnd = _ eo

References

i.* Limitorque Corporation, Nuclear Power Station Qualification

Type Test Report, Limitorque Valve Actuators for PWR Service,

Project #600456, December 9, 1975.

2.* Valcor Engineering Corporation, Qualification Test Report for

IEEE Class lE Solenoid Valves, QR 52600-5940-2, July 11, 1979.

3. Valcor Engineering Corporation, Letter, Quality Assurance

Report QR 52600-5940-2, B. Quail to S. Nadipuram, August

26, 1981.

4. Automatic Switch Co., ASCO Qualification Specification AQS

21678, Revision "B" February 15, 1978.

5. Automatic Switch Co., ASCO Qualification Specification AQS

21678/TR Rev. "A" July 1979.

6. Rosemount Inc. Qualification Test Report for Rosemount

Pressure Transmitters Model 1153 Series A Report No. 3788

7.* Westinghouse Corp. WCAP - 9885 Qualification Testing of ITT/

BARTON Transmitters, Production Lot No. 2, April 1981.

8.* ACME-Cleveland Development Company, Test Plan Qualification

of Series EA-180 and EA-740 Switches, August 31, 1977.

9.* US NRC letter: Summary of Meeting held February 1, 1978 con

cerning Yankee Rowe terminal boards. A. Burger to Yankee

Atomic Electric Co.

l0.* Rochester Gas & Electric Co. Minutes of meeting, Nuclear Safety

Audit & Review Board. January 31, 1978.

ll.* Franklin Institute Report F-C4911-l Qualification Tests of

Terminal Blocks in a Simulated Loss of Coolant Accident En

vironment, January 1979.

12. Victoreen Inc. Qualification Type Test Data Report For Class

IE Victoreen High Range Containment Radiation Area Monitor

System, June 19, 1981.

I

References (Cont'd)

13. Technology for Energy Corporation, Final Test Report No. 517-TR-03: Revision 2, December, 1981.

14. Rockbestos Co., Qualification of Firewall III Class IE Electric Cables. Report QR #1806, RevisedMay 1, 1981.

15. Wyle Laboratories, Environmental Qualification Test Report of Raychem WCSF-N Nuclear In-Line Cable Splice Assemblies. No. 58442-1, May 15, 1981.

Qualification report previously identified in Con Edison' May 9, 1980 submittal or its October 31, 1980 update, and already reviewed by Franklin Research Institute.

~. E~

Notes

a) Manufacturer of this component ha~s successfully completed qualification to IEEE 323-1971 Standards. The 1971 qualification level for these components is acceptable on the basis that alternative 1974 qualified equipment were unobtainable within the deadline to meet TI4I lesson learned schedules.

b) Qualification data for these components was included in the May 9, 1980 Con Edison letter from William J. Cahill, Jr. to Steven A. Varga.

c) Qualification tests for these components are being conducted to meet the particular sequence requirements of IEEE 323-1974 Standards. These units are identical to Lot 2 units that have successfully passed environmental qualification in accordance with IEEE 323-1971.

d) These components will either be qualified by testing or replaced with qualified equipment. Qualification by testing or replacement will be achieved by the second refueling outage after March 31, 1982.

(e) Qualification data for these components was included in the September 4, 1981 Con Edison letter from John D. O'Toole to Steven A. Varga.

I

forwards response to nrc 820225 request for addl info re

Documents