ML19318H948

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Summary of 840608 Meeting W/Util in Bethesda,Md Re Fire Protection Issues at Plant.List of Attendees & Meeting Agenda Encl
ML19318H948
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 06/26/1984
From: Wagner P
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Ireland R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
TAC-54373, NUDOCS 8810260532
Download: ML19318H948 (20)


Text

{{#Wiki_filter:, ~ UNITED STATES 'k NUCL2Ah AEGU!.ATORY COMMISSION 3%s REGION IV - .} -%....g#y$ $11 RYAN PLAZA DRIVE, SUITE 1000 ARLINGToN TEXAS 78011 - 'j.r'..,,h - u ~! + + 3 JUN 2 61984 h / .l MEMORANDUM FOR: R. E. Ireland, Acting Chief, Special Projects and Engineering Section FROM: P. C. Wagner, Senior Project.Manager t i

SUBJECT:

SUMMARY

OF MEETING TO DISCUSS FIRE PROTECTION ISSUES'AT. FORT ST; VRAIN (FSV) A meeting was held in the NRC Bethesda offices on June 8,1984, to discuss the l fire protection issues, required by Appendix _R to 10 CFR Part 50, for FSV. Representatives of Region IV, NRR, ELD, and Public Service Company of Colorado. (PSC - the licensee) attended the meeting as indicated in Attachment 1. Following introductory remarks and introductions. by NRC and PSC, the licensee presented a brief overview of the review that was performed to ensure compliance 1 with 10 CFR 50, Appendix R. The staff had the following two major comments on j the methodology used in PSC's review: 1. The approach of using a movable 20-foot sphere is questionable. f Item III.G.2 provides for 20-foot separation with nc intervening combustibles and automatic detection-and suppression based on a normal sprinkler head spacing of 15 feet; without automatic detection and suppression, credit cannot be taken for only 20-foot separation. It 1 appears that PSC took credit under questionable situtations. i The NRC has granted exemptions for separations in excess of 20 feet which do not have automatic detection and suppression, and would consider similar requests. I 2. The acceptability of 3-hour and 1-hour fire barriers which do not extend wall-to-wall and floor-to-ceiling is also questionable. It has been the i staff's position that fire barriers fully enclose an area which has full coverage by detection and suppression; any other type of configuration would require an exemption. Guidance on acceptable separation methods is contained in Generic Letter 83-33 and SECY 83-269; these documents were briefly discussed. y 8810260532 880626 fJ REG4 ADDCK 05000267 J CF um

i R. E. Ireland 2 i The following specific problems and/or concerns were discussed: ) 1. The presence of hydraulic oil from various leaks is a serious combustible. which must be considered in any evaluations of fire loadings. 2. The new Building 10, which houses Class IE electrical equipment, must comply with all of the provisions of Appendix R. 3. Appendix R requires an evaluation of unprotected structural steel in many instances. It does not appear that sufficient evaluation of unprotected structural steel has been performed at FSV. 4 It does not appear that sufficient effort has been spent on the advantages of fire protection modifications. The various evaluations appear to be based solely on the existing equipment (which, as a result of NRC review to date, does not appear to be sufficient) rather than evaluating possible enhancements. 5. The question of whether equipment used to fulfill the functior of another piece of equipment lost in a fire is redundant to that lost or is an alternate method of providing protection determines whether compliance is i achieved under Section III.G.2 or III.G.3. The NRC usually expects i redundant (III.G.2) equipment-to be safety grade so that it can be i i powered from the emergency onsite power source. The NRC letter dated June 4, 1984, provided PSC with guidance to be used in lieu of Section III.L for alternate shutdown systems acceptance criteria. This i guidance again accepts the use of the alternate cooling method (ACM) of i cooldown for fires in congested cable areas, but requires post-fire effects in all other areas to be within limits predicted for a loss of normal electrical power. The staff explained that an interpretation of this requirement would be the maintaining of normal forced circulation of the primary helium coolant. However, since normal circulation is interrupted, in some cases, to realign = safe shutdown equipment, PSC requested a revision related to preventing fuel damage. The staff would probably find such an approach acceptable provided it can be proven that any fire would not inhibit the restoration of forced circulation within the predetermined time limits and that the procedures were verified to be adequate to account for all possible fire locations. In addition, it will be necessary to enhance the fire detection capabilities to ensure prompt detection and therefore fire brigade response. I

) t R. E. Ireland 3 Because of interpretation problems and to clarify other requirements (e.g., which NFPA standard (13 or 15) is equired). PSC will provide a commitment in j the form of a revised Enclosure 1 which will contain the requirements for the ? alternate shutdown capability. In addition, PSC will provide a schedule for completing all of the required fire protection evaluations and a schedule for j completing the presently proposed fire protection modifications. This information will be submitted within 14 days of the date of the meeting. y

0. u394 Philip C. Wagner Senior Project Manager Reactor Projects Branch 1 t

Enclosures:

As stated cc: J. Collins, RIV P. Check, RIV R. Denise, RIV E. Johnson, RIV P. Wagner, RIV RIV File NRC PDR l Local POR DELD i E. Jordan, ELD ACRS (10) Each NRC participant NSIC J. Taylor D. Eisenhut, D/DL G. Lainas, DL J. Miller, ORB-3 T. Colburn, ORB-3 Public Service Company of Colorado ATTN:

0. R. Lee, Vice President Electric Production P.O. Box 840 Denver, Colorado 80201 i

D. W. Warembourg, Nuclear Production Manager i i Fort St. Vrain Nuclear Station i P.O. Box 368 Platteville, Colorado 80651 i

^ LIST OF ATTENDEES FORT ST. VRAIN APPENDIX R MEETING June 8,1984 Name Organization "J. T. Collins NRC Region IV, Regional Administrator P. C. Wagner NRC Region IV, Senior Project Manager G. L. Plumlee, III NRC Region IV, SRI, FSV L. E. Whitney IE/DQASIP/ORPB/Section 1 D. J. Kubicki DE/NRC/CMEB M. E. Murphy Region IV

  • P. M. Williams NRC/NRR/DST R. E. Ireland NRC/RIV T. V. Wambach NRC/NRR/DL Bill Shields NRJ/ELD J. M. "Jack" Williams PSC Hazen D. Brown PSC Counsel Fred Tilson PSC M. H. Holmes PSC Engineering H. L. Brey PSC Engineering J. R. Reesy PSC Engineering
  • T. Colburn NRR/DL, Oversite PM
  • Part time attendance

- i i i + l l l l l l AGENDA - FORT-ST. VRAIN APPENDIX 'R' FIRE PROTECTION MEETING-l I l i J 1. INTRODUCTION i 2. PSC FORT ST. VRAIN APPENDIX 'R' I FIRE PROTECT'3N REVIEW + 3. QUALIFICATION UNDER III.G.2 j i 4. QUALIFICATION UNDER III.G.3 l ~ S. FIRE PROTECTION ENHANCEMENTS IN THREE-ROOM COMPLEX AND CONGESTED CABLE AREAS 6. MAXIMUM CONSEQUENCES.0F A POCTULATED FIRE IN NON-CONGESTED CABLE AREAS e ITEM 2: PSC PRESENTATION AND DISCUSSION 1 ITEMS 3-6: FOR DISCUSSION I 1 y + p y_t <-mm w g p>ng- ->-spy

) l 4 FSV FIRE PROTECTION j 1975 ELECTRICAL CABLE EEPARATION AND SEGREGATION REVIEW 1976-79 BRANCH TECHNICAL POSITION 9.5-1 REVIEW 1979 ALTERNATE COOLING METHOD SYSTEM INSTALLED 1981 APPENDIX R ISSUED j 1981 PSC CONCLUDED FIRE PROTECTION AND ACM MET SHUTDOWN j REQUIREMENTS OF APPENDIX R 1 1983 AUGUST - NRC APPENDIX R AUDIT IDENTIFIED ADDITIONAL - CotTERIA CLARIFYING APPENDIX R 1984 FEBRUARY - PSC PERFORMS FIRE PROTECTION REVIEW OF FSV FIRE SEPARATION AND ALTERNATE SHUTDOWN CAPABILITY 1984 MARCH 2 - PSC SUBMITS APPENDIX R EXEMPTICd REQUEST 1984 APRIL 27 - APPENDIX R NRC WORKSHOP AND NRC - PSC 1 MEETING 1984 MAY 11 - PSC T'J3MITS TO NRC - I & E BASIS OF FIRE-PROTECTION REVIEW AND LIST OF PREVIOUS CORRESPONDENCE 1984 JUNE 4 - RECEIPT OF LETTER FROM NRC PROVIDING ADDITIONAL FIRE PROTECTION CRITERIA i 4 is 4 v w -,, + e w .v

e l 4 s i l i FIRE PROTECTION REVIEW I i s i PURPOSE OF REVIEW SECTION III.G.2 HOT SHUTDOWN AND COLD SHUTDOWN SCOPE EXPANDED TO ASSURE THAT THE HEALTH l AND SAFETY OF THE PUBLIC WAS PROTECTED .i I i i l l

.t Fort St. Vrain #1-Revision No. l'- Technie=1 specifications Revision 1 - 5/17/74 2.13 Essetor Pressures Page 2-4 a) Bonnal Working Pressure (NWP)'. 688 psig b) Peak Working Pressure (PWP) = 704 psig c) Esference Pressure (RF) = 845 psig IF is the anziaun PCIF incarnal pressure allowed over'its 1 30-year operating life asnapt for the initial pre.ssure test. J 2.14 assetor shutdoun - The zoactor is considered shut down when either (1) there is no fuel in the reactor, or (2) when the reactor mode switch is locked La the "0FF" position simultaneous with either of j l l the following reactivity conditions: J i a) Ene Shutdoun 1 i A sufficient amount of control is insertad (at say average ~ core temperature* >220*F) that will yield a 0.01 Ao shutdown margin with the average core temperature at 220*F in a -nan free condition. i ~b) Cold Shutdown j 1 A sufficient amount of control is inserted (at say average j core temperature* > 80*7) that will yiald a 0.01 ao shutdoun margin with the average core temperature et 80*F in a Zenon free condition, i i

  • Averare Half m circulater Inlet Temperature plus Averare Core outlet Temperature Divided by Two (2) 0 2.15 Eafuelins cvele 1

] Esfueling cycle is defined as that interval of time bermeen sucassive scheduled refuelirgs of a significant Q one-tanth) portion of. the core. I 1 s .. ~ ~.

~, } l i REQUIRED FUNCTIONS: 8 i

1) CONTROL CORE REACTIVITY.
2) MAINTAIN PCRV INTEGRITY
3) DEPRESSURIZE THE~CORE i
4) MAINTAIN ADEQUATE PCRV l

LINER COOLING l

5) ASSURE THAT THE PUBLIC HEALTH AND SAFETY l

CONSEQUENCES ANALYZED AND PRESENTED IN DBA-1 0F THE FSAR ARE NOT EXCEEDED ~ i l e __._,,r m

~. REQUIRED SYSTEMS: SYSTEM 12 - CONTROL RODS/DRIVES AND RESERVE SHUTDOWN SYSTEM i SYSTEM 23 - HELIUM PURIFICATION SYSTEM 1 SYSTEM 25 - LIQUID NITROGEN SYSTEM l SYSTEM 41 - CIRCULATING WATER SYSTEM i SYSTEM 42 - SERVICE WATER SYSTEM SYSTEM 46 - REACTOR PLANT COOLING WATER SYSTEM SYSTEM 47 - PURIFICATION COOLING WATER 5YSTEM SYSTEM 73 - REACTOR PLANT VENTILATION SYSTEM

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REACTOR'CORE COOLING t o NORMAL SiluTDOWN COOLING-(FORCED COOLING) FEEDWATFR SilPPLIED TO STEAM GENERATOR STEAM SUPPLIED TO HEliUM CIRCULATOR DRIVE OUTSIDE POWER SUPPLIED TO AUXILIARY BUS ' ~ o BACKUP SiluTDOWN COOLING (FORCED COOLING) FEEDWATER OR CONDENSATE SUPPLIED TO STEAM GENERATOR ~ FEEDWATERORCONDENSATESOPPLIEDTOHEL'IUMCIRCULATORPELTONWHEELS DUTSIDE POWER SUPPLIED TO AUXIllARY BUS, OR STANDBY POWER SUPPLIED TO ESSENTIAL Bils 'o SAFE SHUTDOWN COOLING (FORCED COOLING) FIREWATER SUPPLIED TO STEAM GENERATORS FIREWATER SUPPLIED T0' HEllUM CIRCULATOR PELTON WHEELS STANDBY POWER SUPPLIED TO ESSENTIAL BUS . d EMERGENCY COOLING (PCRV LINER C00LDOWN) .r SERVICE WATER OR FIREWATER SUPPLIED TO PCRV LINER COOLING SYSTEM ELECTRICAL'POWER SOURCE.S DUTSIDE POWER h. STANDBY.POWER ~ s ALTERNATE COOLING METHOD POWER 5e + - -= n,

N 3 s ( [ g 3 r l~ PURIFICATION HCLIUM 4 LIOUlO PURIFICATION NITROGEN COOLING RESERVE SYSTEM SYSTEM 6 WATER SHUTDOWN 23 25 m 47 12 p J L I I ' P L LINER HEttOM COOLING PCRV STORAGE SYSTEM SYSTEM 48 24 ,m J L + 1 s 1 r q r SERVICE REACTOR WATER BUILDING I SYSTEM HVAC FIRE ACM 73 l 42 i 4 DIESEL WATER GENERATOR SYSTEM 45 J 6 I S$ im ~ e-MAKEaUP WATER EE i "4 -m f Figure 8.2-25 ACM System Interrelationships

l I l \\ ? hl:h::3:::: -u g (9 - - - - ~ ~ ~ ~ ~{~~~gy4rvE ~ /' i G f ToPHEAD PENETRADONS b HEUuu - e. "" 7-PCRV l l 1 M io 1 t u. i PURIFICAT)oN SMMu WEU. M -zat < ap ,m_ ,h { N$ 6 THERMAL N 1. bTop xcr RErueToR n r-ns %c Couna. Roo - L 7slDE REFLECTOR h. t n -CoRE m y .x REFUEToR %,x " 8"""E' * ~~~ r m.oexs =~ y -l j o e e S.PPORT FLDoR d'P 2 '-9STEAu GENERAToR b r umutzs au w /'h ~ CoRE SUPPORT ,1 . / CIRCULAToR FLooR Cowun- ' ' '[ N M) v a i, C, -

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i FSAR UPDATE l 10.3-18 ^ J

STORAGE, PONDS

-] REHEATER 70 1 M P SECTION NONCLASS 1 PLPING CIRCULATING WATER MAKEUP 3 g I k. PUMPS AND PIT f [1 P [3 g e "~ ECONOMlZER TO ~ EVAPORATOR SERVICE m SUPERHEATER y l WATER r = SECTION SUPPLY l m h CIRCULATOR a 1 P 1 P x FIRE FIRE WATER/ -PCRV e, PUMP PUMP DRIVEf BOUNDARY N M e N, .y ~ ~ ~~ ENGINE DRIVEN ' FIREPUMPSi 7 2 EMERGENCY WATER BOOSTER j DRIVEN PUMPS 2 j g 4 EMERGENCY CONDENSATE LINE 1 i EMERGENCY FEEDWATER LINE 3, Figure 10.3-4 Schematic Flow Diagram: Cooling with Eafe Shutdown Equipment r-. m er t-y--e. ee-= m-se-e-ere ,--*age we.reesam e w-- s*wes.w-*>-ewer-+.w--ar-eomv en-e-r-ine--- e

i i FPR PROCEDURE" i APPLIED SECTION III.G.2 SEPARATION CRITERIA i TO REQUIRED SYSTEMS: i t

1) 3 HOUR BARRIER?
2) 1 HOUR BARRIER OR 20 FEET i

l AND AUTOMATIC FIRE DETECTION AND SUPPRESSION i ?

3) IF SEPARATION CRITERIA 0F 2) WAS MET, BUT NOT AUTOMATIC DETECTION AND SUPPRESSION, THE FIRE l

LOAD WAS REVIEWED TO DETERMINE IF DETECTION/ SUPPRESSION WAS WARRANTED. l e f a ,e a

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r. - i I i l i i 'STRUCTURES i

1) PCRV l

2)OTHERS ' I CONCLUSIONS l I

1) ORIGINALLY SELECTED SYSTEMS ALONE.

DID NOT SATISFf THE CRITERIA~

2) OTHER SYSTEMS WERE CONSIDERED
3) NO SINGLE FIRE WOULD PREVENT FSV FROM ACHIEVING SHUTDOWN AND i

C00LDOWN - r i ? i I - i 1 i --..,r}}