ML20141F508

Summary of 860402 Meeting W/Util & Gilbert/Commonwealth,Inc in Bethesda,Md Re Fire Protection Items,Including Temp Indication for Reactor Coolant Loop & Deviations Identified in Util 850529 Ltr.Attendees List & Viewgraphs Encl

ML20141F508
Person / Time
Site:	Summer
Issue date:	04/11/1986
From:	Hopkins J Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8604230051
Download: ML20141F508 (22)

Text

,

APR 11 1986 Docket No. 50-395 Distribution:_ _

C Docket W 50h396?

NRC PDR D.' Mil'er Local PDR DELD LICENSEE: South Carolina Electric and Gas Company PAD #2 R/F E. Jordsn L. Rubenstein B. Grimes FACILITY: V. C. Sumer Nuclear Station J. Hopkins ACRS (10)

P. Madden R. Anand

SUMMARY

OF MEETING WITH SOUTH CAROLINA ELECTRIC AND GAS COMPANY J. Wilson B. Mann J. Shapaker i GENERAL A. Singh ,

K. West l On April 2,1986, the NRC staff met with the South Carolina Electric and Gas Company (SCE8G) to discuss fire protection for the V. C. Sumer Nuclear Station. The meeting was held in Bethesda, MD. A list of those persons who attended the meeting is included as Enclosure 1.

DISCUSSION The fire protection items discussed were Tu /T c indication for a reactor coolant loop, the three deviations identified in the Ticensee's letter of May 29, 1985, local control transfer switches, and modification schedule. Copies of the viewgraphs used during discussion are included as Enclosure 2.

The NRC staff stated that they desired additional information on T /T u cindica-tion regarding the capability to read core exit thermocouples, relYabYlity of core subcooling monitor, and cost of the alternative. The NRC staff also requested additional information for deviation Nos one and three regarding walkdowns of the fire areas and the latest Fire Protection Evaluation Report information. The licensee stated that they would provide the requested information. i

/s/

Jon B. Hopkins, Project Manager PWR Project Directorate #2 Division of PWR Licensing-A

Enclosures:

As stated cc: See next page LKi  : PAD #2 di g

)JHopkins:as 0:EA0/2 r LXu6'ehs'tein 4 /86 / 4/ /86 4//v/86 8604230051 860411 PDR ADOCK0500g5

Mr. D. A. Nauman South Carolina Electric & Gas Company Virgil C. Summer Nuclear Station cc:

Mr. William A. Williams, Jr.

Technical Assistant - Nuclear Operations .

Santee Cooper '

P.O. Box 764 (Mail Code 167)

Columbia, South Carolina 29218 J. B. Knotts, Jr. , Esq.

Bishop, Liberman, Cook, Purcell and Reynolds 1200 17th Street, N.W.

Washington, D. C. 20036 Resident Inspector / Summer NPS c/o U.S. Nuclear Regulatory Commission Route 1, Box 64 Jenkinsville, South Carolina 29065 Regional Administrator, Region II b.S. Nuciear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 Chairman, Fairfield County Council .

P.O. Box 293 Winnsboro, South Carolina 29180 Attorney General Box 11549 Columbia, South Carolina 29211 Mr. Heyward G. Shealy, Chief Bureau of Radiological Health South Carolina Department of Health and Environmental Control 2600 Bull Street Columbia, South Carolina 29201

ENCLOSURE 1 ATTENDEES NRC J. Hopkins R.-Anand J. Wilson B. Mann J. Shapaker A. Singh K. West L. Rubenstein P. Madden SCE8G J. Connelly A. Paglia J. Barker L. Lunden T. Keckeisen Gilbert /Comonwealth Inc.

D. Kelley i

i l

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ENCLOSURE 2 PROPOSED AGENDA SCREG and NRR STATUS MEETING AP RI L 2, 1986 I. REVIEW OF STATUS T ABLES P RESENTED IN LETTER TO DR. GRACE FROM D. A.

NAUMAN ON FEB. 27, 1986.

II. DISCUSS USE OF P sat AS AN ALTERNATIVE TO T cold FOR A LIMITED NUMBER OF SPECIFIC FIRE AREAS.

III. DEVIATIONS REQUESTS F ROM M AY 2 9 LETTER.

IV. CLARIFICATIONS ON LOCAL CONTROL

@pendix R CPEN 11 EMS STMui 2-27-86 Itsn/ Doe Date Response Cament 85-26-01 Sept. 4 Ietter to H.R. Denton Method of Analysis & safe stutdown

- Sections 2,3,4,5,7,8,9,10 philoscphy (Currently under NRC evaluation, no SCE&G action at this tine.)

85-26-02 Sept. 4 Intter to H.R. Danton Incal control and spuricus operation Sections 5,6,8 (Currently under NRC evaluation, no SG&G action at this tine.)

May 29 Letter to H.R. Denton Modification and Deviation Requests Sept.16 Ietter to H.R. Denton PORV bbdification Nov.1 Ietter to H.R. Denton ThotNcold discussion MRF-20784,20785,20786,20788, see Rev.1 to Table 14.0 of Sept.

20789,20790,20791,20801,208 % 4 Ietter (enclosure #2 to this letter).

Co su kho 85-26-03 MRF-31971 Wrap tray 3088, field instdlation 1st Qtr 86 alnost ccmplete (will meet date).

Com p O 85-26-04 MRF-31%8 Protect NI-31, 32, work nk in field 1st Qtr 86 (will meet date).

4pendix R CPEN 11DE SDLTtE 2-27-66 Item /Due Date Response Cmment 85-26-05 Supplanental Coordina- (Study couplete, and ready for tion Study closure. )

85-26-06 Report (Report on charging ptmp protection is under develquent.)

85-26-07 Sept. 4th Ietter to H.R. Cbmnon enclosure. (Currently under

- Denton, Section 9 NRC evaluation, no SCE&G action at this time.)

85-26-08 Sept. 4th Letter to H.R. Procedure changes and Bulletin 84-09.

Denton, Section 11 (Currently under NRC evaluation, no SCE&G action at this time.)

FEP 1.0 Rev. 4 Estimated issue 4-1-86 (_crup/off FEP 1.1 Rev. O Estinated issue 4-1-86 Cosu /efy 4th Qtr 86 MRF 20579 Ievel indimtion for R16T 85-26-09 Sept. 4th Ietter to H.R. Timeline Questions (Currently under

- Denton, Section 12 NRC evaluation, no SCE&G action at this time.)

Appendix R CPEN TE!Ni SDdtB 2-27-66 Item /Due Date Response Ccmnent 85-26-10 Sept. 4 Letter to H.R. Denton (bid shutdown (Currently

- Section 12 under NRC evaluation, no SCE&G action at this time.)

3rd Qtr 86 Issue FD 2.X Series Witing cmpletion of engineering analysis, some pr@aration underway.

85-26-11 Verify Training on all FT's Will be done af ter F@ 2.X series are developed.

85-26-12 Sept. 4 to H.R. Denton, Section Emergency lighting (Currently 13 under NRC evaluation, no SCE&G action at this time).

Install additional lighting 2nd Qtr 86 MRF 20840 units. (on schedule) 85-26-13 Repair Fire Barrier 2rk is emplete.

1ppendix R CPEN TEMi STATWi 2-27-86 Item /Due Date Response Ccmnent 85-26-14 Repair raceway wrap hbrk is conplete.

85-26-15 Fire barrier support study. kport is carrplete.

85-26-16 Sept. 20 to H.R. Denton "M" Board Letter Dec. 30 to H.R. Denton Clarifimtion Letter (Currently under NRC evaluation, no SCE&G action at this time.)

85-26-17 Fire watch log corrected and SCE&G actions conplete, special rgort written.

Other NRC 2nd Qtr 86 Rewrite FPER On schedule.

2nd Qtr 86 L grade 023 drawings Required for FPER, on schedule.

V. C. SUMMER NUCLEAR STATION SCHEDULE OF MODIFICATION IMPLEMENTATION Page 1 of 3 ESTIMATES

• SCE&G MRF OUTAGE ENGR. MATERIAL. CONST.

DESCRIPTION REQ. COMPL. DELIVERY COMP L. DATE MRF # DATE DATE Add 2nd power disconnect for Yes 4/86 4/86 3rd Refuel air operated valves 20784 (2nd Qt g. '8 7)

\

Add Thyrite protectors to No Complete Complete 4/86 current transformers 20785 Yes 4/86 4/86 3rd Refuel Add Fire Switches to 480V (2nd Qtr. '8 7) cwitchgear 20786 Yes Complete Complete Complete Upgrade DG-B Controls 20788 Yes 3/86 3/86 3rd Refuel Add Fire Switch to 7.2kV (2nd Qtr. '8 7) cwitchgear 29789 7/86 11/86 3rd Refueling Upgrade Fire Switch for S.W. (2nd Qtr.'87)

Pp. "B" and add Fire Switch for C.C. Pp. "B" 20790 Complete 3rd Refueling Upgrade Chiller B Contr. Yes 4/86 20791 (2nd Otr. '8 7)

Transfer Switch

V. C. SUMMER NUCLEAR STATION SCHEDULE OF MODIFICATION IMPLEMENTATION Page 2 of 3 ESTIMATES

• SCE&G MRF OUTAGE ENGR. MATERIAL. CONST.

DESCRIPTION REQ. COMP L. DELIVERY COMPL. DATE MRF # DATE DATE Yes 10/19/86 10/19/86 3rd Refuel Armor cables for solenoid (2nd Qtr. '8 7) valves (see also 20784) 20800 20784 To be com-Change RC LoophT /Tc instru- Yes pleted as 2/87 3rd Refuel mentation to one power train a resolu- (2nd Qtr. '8 7) per loop 20801 tion to R.G. 1.97 issues (9/86) 4 No Complete Complete Complete Remove cables DGM21B and DGM22B e;f rom tower cable -

spreading room 20788 Complete Complete 2nd Qtr.'86 Install additional self-con- No tained emergency lighting i units 20840, l

Protect conduits for NI-31/ No Complete' Complete 1st Qtr.'86 NI-32 or install transfer switch for NI-33 31968 i

i

~ , . . _ _ . _ _ . _ _ _ . , _ . _ _ . . . _ _ . _ _ _ _ _ _ _ __.._ ___ , _ . . _ . _ . _ . _ . _ _ _ . . _ _ _ _ . _ . . . . . . . . - _ . . _ _ _ . . . . _ . . , . _ _ _ . _ . , _ _ , _ - _

V. C. SUMMER NUCLEAR STATION SCHEDULE OF MODIFICATION IMPLEMENTATION Page 3 of 3 ESTIMATES

• SCE&G MRF OUTAGE ENGR. MATERIAL CONST.

DESCRIPTION REQ . COMPL . DELIVERY COMP L . DATE MRF f DATE DATE Addition of direct reading No 9/86 9/86 4th Qtr.'86 level guage for RWST 20579 Revision of power circuit Yes Complete Complete Complete breaker overcurrent settings for coordination 20846 Yes 9/86 10/86 3rd Refueling Add fire switches to 480V (2nd Qtr. '8 7)

MCC's, XFN-45A-AH, XFN-45B-AH , XFN-4 6B-VL , XFN-8 0B-VL 20896 31971 No Complete Complete 1st Qtr.'86 Wrap Tray 3088 Upgrade S W B Pp 45A barrier No 3/86 4/86 2nd Qtr. '86 (supports) 20895 Change M.S. PORV control logic No 9/86 N/A 4th Qtr.'86 to pre-1980 desig n (IPV-2 000, 2010, 2020-MS)

Upgrade the FPER No 6/86 N/A 2nd Qtr.'86

BASIS FOR GRANTING DEVIATION FROM INTERNAL GUIDANCE ON Th/Tc

1. THE DEVIATION IS REQUIRE D FOR ONLY 4 FIRE AREAS / ZONES IN THE PLANT (NONE OF WHICH REQUIRE THE OPERATORS TO LEAVE THE CONTROL ROOM).

2. A WELL REASONED BACKUP METHODOLOGY IS AVA IL ABL E FOR THESE CASES. (P sat vs.

Tcold)*

3. THE G UIDANCE GIVEN FOR APPENDIX "R" IS NOT CONSISTENT WITH THE WESTINGHOUSE GENERIC AND SUMMER STATION SPECIFIC R EQ UIREME NT S FOR R.G. 1.9 7 TYP E lA or 1B INSTRUMENTATION.

4. THE GUIDANCE GIVEN FOR APPENDIX "R" IS NOT CONSISTENT WITH THE WESTINGHOUSE OWNERS G ROUP , EMERGENCY RESPONSE G UIDELINES.

t

FIRE AREAS /EONES OF INTEREST FOR LOSS OF Th/T c FIRE AREA IB-3 TRAIN A BATTERY CHARGER AND MAIN DISTRIBUTION PANEL ROOM FIRE AREA IB-4 TRAIN B BATTERY CHARGER AN D MAIN DISTRIBUTION P ANEL ROOM FIRE ZONE RB 1.1 WEST SIDE OF REACTOR EUILDING AT 412' ELEVATION FIRE ZONE IB 25.t WEST P ENETRATION ROOM ADJACENT TO REACTOR BUILDING FIRE ZO NE 1.1 NOTE THAT CONTROL ROOM EVAC UATION IS NOT REQUIRED FOR ANY OF THESE AREAS. FULL Th/Tc FOR AT LEAST ONE GENERATOR IS AV AIL A BLE FOR FIRES THAT R EQ UIRE USE OF THE CREP.

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1. WESTINGHOUSE OWNERS GROUP ERG'S AND -

SUMMER STATION EOP 'S GENERATED IN j

RESPONSE TO RG 1. 9 7 REQ UI RE TH AT AT l

LEAST Th or Tc BUT NOT BOTH BE 1

AVAIL ABLE ON EACH STEAM GENERATOR.

) 2. APPENDIX R REQUIRES THAT Th and Tc BOTH BE AVAIL ABLE ON ONE STEAM GENERATOR BUT NOT ON ALL LOOPS.

AP P EN DI X R l.97 _

GUIDANCE

' Tc LOOP Th_ Tc LOOP _ Th_

1 A B 1 A B 2 A B 2 A A B A 3 B B I 3 A SINGLE FAILURE OF A OR B TRAIN POWER WILL ALLOW ONE BUT NOT BOTH TO BE SATSIFIED.

4 1

Westinghouse Owners Group EMERGENCY

RESPONSE

GUIDELINES i

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Executive Volume

BACKGROUND INFORMATION FOR WESTINGHOUSE OWNERS GROUP ,

EMERGENCY RESPONSE GUIDELINES i

GENERIC ISSUE NATURAL CIRCULATION HP/LP-Rev. 1 September 1, 1983' o

The continuous recording will provide trending information on the parameters of importance in order to eliminate the effects of pointwise variations in the readings and minimize the chance of misinterpretation of any one set of readings. Variations in discrete readings, and between the same parameters in different loops, can result from several causes:

o Asymmetry in the heat transfer and heat transport processes between loops.

o Instrument inaccuracies, o Differences in instrument sensing element placement between loops.

o Variations in feed flowrates to steam generators, o Differences in location of various auxiliary system connections to the reactor coolant loop piping (e.g., charging line, letdown line, pressurizer surge line, etc.).

O During natural circulation operations, the primary means avrilable to the operator for verifying the continued safe state of the core in the subcooled convective heat transfer regime at any given time is the verification of at least minimum subcooling based on core exit TCs. Hot leg RTD readings can also be used, but the individual wide range instrumerts for hot leg temperature (THL) have a higher expected error, do not measure the coolant parameter of interest in the location of interest, and are subject to the effects of thermocouple locations; such as, auxiliary system flow impingement, loopwise variations in natural circulation flow, etc., which may cause their instantaneous readings to be non-representative of the actual bulk coolant.

For the purposes of evaluating the progress of the natural circulation core cooling process, wide range THL, c re exit temperature and SG pressure are valuable; the trending of these temperatures and pressure over a relatively long period (say 3 to 4 consecutive sets of readings taken at 20 minute intervals) should show a gradual decrease as decay heat decreases if the RCS is in a stable free convection operating mode.

The cold leg temperature (TCL) readings can be used as additional verifica-tion that heat removal through the steam generators is occurring. The loop y T CL readings in active loops are quite sensitive to changes in heat transfer NAT CIRC 5 HP/LP-Rev. 1 0042V

~

p . _. -. . . -.L.'^ . ....,. = -c: 7 i - = = .- . . . =

2 ;_ .

rates from the reactor to the secondary sides of the steam generators. Actual b tests have shown that loop T CL 's f 11 w als st exactly (in trends) the steam generator steam pressure variations, with minimal time lag. Again, literal acceptance of the individual temperature values is to be cautioned against, since loop T instruments can have errors ranging up to +10*F; trending of CL I

cold leg temperature readings is recommended.

The presence of a loop AT is necessary if any free convection flow is to occur. Calculated AT's for Westinghouse PWRs in a stable free convection mode are in the range of approximately 120% of full power loop AT and downwards, with the higher AT's obtainable only at the highest expected decay heat levels. These higher AT's are probably not observable on RCS j instrumentiation since a stable free convection process will not be set up until core decay heat levels have dropped significantly from their highest theoretically attainable values.

Regardless of the foregoing discussion, the operator should immediately investigate any extreme or suspiciious variation in an instantaneous reading of T

HL rT CL; the key parameter for verification of continued acceptable O system operation is the RCS subcooling based on core exit temperature.

1 l

i 2.2 Relations Describing System Performance I

' If transient equilibrium is assumed, simple analytical expressions for the i mass flowrate and loop temperature difference obtained during natural circulation operations can assist in understanding the effect of various perturbations on the system performance. These expressions, given below, are not intended to replace detailed analyses of the natural circulation process <

d and should be treated as approximate relations for describing the system I performance under quasi-steady-state heat removal conditions. These expressions are, however, useful in predicting the optimum conditions for i natural circulation decay heat removal.

1 i

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NAT CIRC' 6 HP/LP-Rev. 1 ,

0042V . l

DEVIATION REQUEST FROM MAY 29, 1985

LETTER O. W. DIXON TO H. R. DENTON FIRE AREA

AB-1 MH-2 IB-25 L

.. . - . - ..- . . - - -- - .. _ - _ _ . . . .~ .-

H 4

LOCAL CONTROL SWITCHES t

i

1) TABLE 5.3 IN SEPTEMBER 4, 1985 i SUBMITTAL IS STRICTLY TRUE FOR CONTROL ROOM EVACUATION.

t i 2) A) AS DESCRIBt0 IN SECTION 7.0 0F THE SAME SUBMirfAL SOME LOCAL CONTROL MAY BE REQUIRED FOR INDIVIDUAL FIRE AREAS THAT DO NOT REQUIRE CONTROL ROOM EVACUATION.

B) NO REPAIRS ON HOT STAND BY EQUIPMENT NEEDED SOONER THAN 8 HOURS. SOME FUSE PULLING ,

IN THE MAIN CONTROL BOARD AND LOCAL SWITCHGEAR '

I OPERATION AS WELL AS MANUAL OPERATION OF VALVES MAY BE REQUIRED.

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CRANGE TO TABLE 5.3 SEPT 4, 1985 LETTER l

O. W. DIXON TO H. R.'DENTON l CHANGE THE ENTRY FOR COMPONENT COOLING P UMP "B" FROM FIRE SWITCH TO PERMANENT JUMPER PROCEDURE.

i BASIS: 1. THE COMPONENT COOLING SYSTEM IS NOT I f REQUIRED FOR ENTRY INTO NOR MAINTENANCE L OF HOT STAND BY .

i

2. IT IS EASY TO OPERATE FROM ITS ASSOCIATED SWITCHGEAR.

3. SUCH OPERATION HAS NO IMP ACT ON THE TIME LINE FOR REACHING COLD SHUTDOWN WITHIN 72 HOURS.

4. IT OFFERS NO SAFETY HAZARD TO THE OPERATOR.