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FRC4: DATE OF DOC DATE REC'D LTR TWX RPT OTIERFlorida Power CorporationSt. Petersburg, Fla. 33733J. T. Rodgers 8-7-74 8-9-74 X

TO: ORIG CC OT iER SENT AEC PDR XSENT LOCAL PDR X

Mr. Moore 1 signed

CLASS UNCLASS PROP INFO INPUT MO CYS REC'D | DCCKET NO:

XXXX 1 50-302,

DESCRIPTION: ENCLCSURES:Ltr re 7-29-74 ACRS subcomittee hearing. . . .furt ish-ing info re issues for which the staff's reviewis not complete concerning the SER for theCrystal River Unit # 3 ~5K QOW

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t i*Mr. Voss A. Moore E r-. ;4'r . .Assistant Director for Light ./Q ,|f.'s'4

Water Reactors, Group I /c N,.*Directorate of Licensing S .<v* S W

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Office of Regulation d ; '4,

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In Re: Florida Power Corporation '9[_',Crystal River Nuclear Generating PlantDocket No. 50-302

Dear Mr. Moore:

On July 29, 1974 an ACRS subcommittee hearing was held in Washington,D.C. concerning Crystal River Unit 3 Nuclear Generating Plant. Duringthe course of the hearina list of nineteen (19) g, Mr. Bart Buckley of the AEC staff identifiedissues for which the staff's review is notcomplete. These issues were identified in the staff's Safety EvaluationReport (SER) for Crystal River Unit 3 dated July 5,1974. It was furtherenumerated, at the hearing, that the staff's SER was based on our FinalSafety Analysis Report (FSAR) and its subsequent Amendments 12 through39 inclusive. Amendment No. 40 to FSAR, filed with the Commission byFlorida Power Corporation on July 3,1974, contained our response tomany of the nineteen issues referred to above.

Due to the untimely occurrence of these events, it is our intent in thisletter to provide you with a brief summary of the status of each ofthese nineteen issues with regard to information transmittals to staffand current design and construction status. We feel that these issuesare not unresolved or outstanding in the sense of conflict or disagree-ment. We see them as unreviewed items. The time duration between thesubmittal of Amendment No. 40 and the issuance of the Staff's SER wassimply not sufficient to complete this review.

Following is an item by item discussion which indicate the currentstatus of each:

Item #1 Verification of atmospheric diffusion estimates and meteoro-logical data collection system conformance with RegulatoryGuide 1.23 - Based on present estimates the new meteorologicalsystem will be operational and gathering data (at the toweronly) during the week of December 2,1974. The system willutilize permanent sensors and identical recorders to thoseintended fee control h om use. Our estimate for having thesystem operational irr the control room is March 3,1975.

b.),hGeneral Office 32o1 Tn<y-founn street sou:n . P O. Box 14042. St Peterscu g. Florica 33733 813-866-5151r

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Based on the above schedule, it should be possible to have 4months of representative data prior to fuel loading, which ispresently scheduled for April,1975. One complete year's datawould be available in December,1975.

Item #2 Compliance with the New ECCS Criteria - This issue is coveredin the Babcock & Wilcox Topical Report, BAW 10,0091, datedAugust 5,1974 and is further addressed in our letter toMr. A. Giambusso, Deputy Director for Reactor Projects, datedAugust 6, 1974. A proposed FSAR page revision is attachedlisting the applicable B&W Topical Reports related to ECCS.In addition, all revisions to the Technical Specifications, I

(Section 15.0 of the FSAR) concerning this issue, will be 1

completed by November,1974. i

Item #3 Provisions for redundant and independent indication systemsfor each core flooding tank isolation valve - The informationregarding this issue was submitted to the staff in AmendmentNo. 32 to the FSAR on October 1,1973 and is contained on page j6-5, Section 6.1.2.1.3 of the FSAR.

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Item #4 Steam line break isolation system - The steam line break i

isolation issue was discussed in Amendment No. 32 to the FSAR,(10/1/73) on pages 14-18c and 14-18d, and in Amendment No. 40,(7/3/74) on pages 10-3,10-3a, and 14-53b of the FSAR. De-tailed design drawings relating to this item were sent to theAEC in preliminary form on May 28, 1974, and were officiallyretransmitted on July 19, 1974.

Item #5 Auxiliary feedwater system instrument conformance with IEEEStd. 279-196. This issue was addressed in Amendment No. 32 tothe FSAR (10/1/73) on page 14-18d and in Amendment 40 (7/3/74)on pages 7-29, 10-3, 10-3a, and 14-18d. Detailed designdrawings relating to this system were sent in preliminary formto the AEC on May 28, 1974, and were officially retransmittedJuly 19, 1974.

Item #6 Instrumentation required to follow coarse of an accident -This issue was addressed in Amendment No. 40 (7/3/74) on page,

7-56, Table 7-8 of the FSAR.

-Item #7 Residual heat removal (RHR) system valve interlock provisionswith regard to diverse principles to prevent opening and forautomatic closure of RHR valves - The residual heat removalsystem valve interlock issue was addressed in Amendment No. 32to the FSAR (10/1/73) on

37 (2/4/74)pages 9-15 and 9-16, and again inAmendment No. on pages 9-16 and 9-60. Detaileddesign drawings relating to this item were given to the AEC inApril 1974 and are being retransmitted officially on August 7,

- 1974.

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Item #8 Conformance with criteria of minimum separation between redun-dant safety-related cables - This issue was addressed inAmendment No. 40 (7/3/74) on page 8-7d, section 8.2.2.12.C.9.The design is complete on this issue and barriers will beadded as part of the normal sequence of work. No scheduleproblems are anticipated.

Item #9 Potential flooding of switchgear room as a result of failureof firewater piping - This issue was addressed in AmendmentNo. 40 (7/3/74) to the FSAR on p) ages 9-341 and 9-341a, SectionGilbert Assiciates (GAI9.8.7. will submit bills of materialsby August 15, 1974 for FPC purchase.

Item #10 Verification that battery room ventilation system will precludeaccumulation of explosive hydrogen mixtures - The calculationsconcerning this issue have been performed and the results havebeen added to the FSAR in Amendment flo. 40 (7/3/74) in Section8.2.2.6. Additional design modifications related to thistopic are:

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a) The common door between the battery rooms wil1 be eli-minated and filled with concrete.

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b) The common exhaust duct will be removed from within thebattery rooms.

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The construction drawings for this have been issued.

Item #11 Conformance of 230 kv switchyard breakers control power separa- |1tion with GDC 17 - This issue was addressed in Amendment

No. 40 (7/3/74) on page 8-11, Section 8.2.3.3.d.1

Item #12 Justification for use of manual switches for disconnectingpower to each group of control rods - Standard practice inbuss bar distribution is to put maintenance service disconnectswitches between overhead buss bars that have several loadsconnected to it. The main purpose is for tne safety of per-sonnel working on individual loads connected to it.

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This buss bar system is isolated from the final trip device bya power transformer and thus serves no function in discon-

|necting the power from the CRDM's during a required reactor |trip.

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Each group receives power from two AC breakers. If one of theservice load disconnect switches is opened, the control rod

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group will not drop, .since they are still receiving power fromthe other power source.

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! The sole. function of these service load disconnect switches is'

for maintenance purposes and protection of service personnel.

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Item #13 Conformance of feeder breaker connecting 4160/480 V trans-former with emergency busses with Class IE requirements -Information concerning this issue was added to the FSAR inAmendment No. 40 (7/3/74) in Section 8.2.2.5. The elementarydiagram has been transmitted to the AEC for review on July 19,1974.

Item #14 Verification that diesel generators similar to those used inthis plant have been qualified for use in J,ther Nuclear facili-ties -This issue was addressed in Amendmer t No. 40 (7/3/74) onpage 8-9 of Section 8.2.3.1.

Item #15 Modification of 480V tie breakers to assure independence ofredundant emergency busses - This issue will be addressed inAmendment No. 42. A proposed FSAR page revision is attachedindicating the planned modification. The elementary diagramshave been transmitted to the AEC for review on August 5, 1974.

Item #16 Conformance of redundant d-c systems with GDC 17 and IEEE Std.308-1969 - This issue was addressed in Amendment No. 40 (7/3/74)in Section 8.2.2.6, Page 8-5 of the FSAR. The constructiondrawings have been issued to the field.

Item #17 Modifications to alternate power sources to assure independenceof two of the redundant 120 v vital a-c busses - This issuewas discussed in Amendment No. 40 (7/3/74) of the FSAR on page8-6, Section 8.2.2.7. The construction drawings have beenissued to the field.

Item #18 Verification that the auxiliary feedwater system meets the,

single failure criteria coincident with failure of a highenergy line break - A single failure analysis of the EmergencyFeedwater System has been ctmpleted. Design modifications toassure that system can accomodate any active component failurewithout loss of function have been documented in Sections 7.0and 10.0 of the FSAR in Amendment No. 40 (7/3/74).

Additional modifications to the Feedwater System, not coveredin Item #5 & #18 above, are presented below with their status:

a) S-I Piping - Layout drawings released for construction.Piping support design, including seismic-

analysis, to be finished by 10/1/74.Seismic analysis for upgraded piping to be-

finished by September 15, 1974.!

b) New Valves - Requirement outlines for control valves andmotor operators are complete.The valve list has been modified to show-

motor operators to be added.

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Item #19_ Review and evaluation of operator requalification program forconformance with Appendix A of 10 CFR Part 55 - This issue isbeing addressed in a separate letter to Mr. A. Schwencer dated31, 1974.August 7,1974, in direct response to his letter of July

Based on the above status summaries, we feel that following the completionof the staff's review of the information submitted via detailed drawings

and Amendment No. 40 and the remaining information to be submitted inAmendment No. 42, final resolution of tne nineteen issues will be reachedwithout difficulty.

If further discussion of the above information is required, please feelfree to contact us.

Very truly yours,

J. T. RoogersAsst. Vice President

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(PROPOSED REVISION TO BE INCLUDED IN AMENLMENT NO.h2)

B&W Topical .Date SubmittedReport No. to DOL Title

BAW-10,055 June 1973 Fuel Densification Report (Non-proprietar/Rev. 1 version of BAW-10,054

BAW-10,056 March 1973 Radiation Embrittlement Sensitivity of Reac-tor Pressure Vessel Steels

BAW-10,06h May 1973 Multinode Analysis of Core Flooding Line

Break for B&W's 2568-MWt Internals VentValve Plants

BAW-10,078 September 1973 Operational Parameters for B&W Rodded Plants(Proprietar/)

BAW-1398 Cetober 1973 Crfstal River Unit 3 Fuel Densification Re-port (Non-proprietar/ version of BAW-1397)

HAW-10,091 August 1974 B&W's ECCS Evaluation Model Report withSpecific Application to 177 FA Clasc Plantswith Lovered Loop Arrangement

BAW-10092 July 1974 CRAFT 2-Fortran Program for Digital Simulationof a }hiltinode Reactor Plant During Loss ofCoolant.

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BAW-10093 July 197h REF20D-Description of Model for MultinodeCore Reflood Analysis.

BAW-10094 July 197h Babcock & Wilcox Revisions to THETA 1-B, A. Computer Code for Nuclear Reactor Code Ther=alL Analysis - IN-1kh5

BAW-10095 August 1974 Babcock & Wilcox Revisiens to CONTD!PT -Computer Program for Predicting CoritainmentPressure - Temperature Response to a Loss-of-Coolant Accident.

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(Proposed R:; vision to ba included in Am:ndm:nt No. h2)

The h80V plant euxiliary bus, a bus utilized to supply power to the non-classIE distributien system, is supplied frcs the 4160V engineered safeguards bus 33through a class IE circuit breaker and energized during normal operations. Upondetection of an engineered safeguards condition coincident with loss of off-sitepower the feeder breaker for the bus is automatically tripped and prevented fromclosure by the use of engineered safeguard =atrices and undervoltage relay contactsto preclude inadvertent emergency diesel generator 3B overload. Breaker closureis prevented until both the engineered safeguards signal is manually reset andvoltage to the bus is restored.

Modifications vill be made to the control circuits for 480V tie breakers to provideautomatic tripping of the tie breakers upon loss of off-site power or detectionof an accident condition coincident with loss of off-site power.

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