ML19341B905

Summary of 801113 Meeting W/Util in Bethesda,Md Re Containment Overtemp Condition & Request to Defer Implementation of Recirculation Pump Trip Mod.Attendance List & Viewgraphs Encl

ML19341B905
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	01/23/1981
From:	Paulson W Office of Nuclear Reactor Regulation
To:	Crutchfield D Office of Nuclear Reactor Regulation
References
NUDOCS 8102280103
Download: ML19341B905 (32)

Text

{{#Wiki_filter:p N o UNITED STATES WM

q NUCLEAR REGULATORY COMMISSION n

j .. j WASHINGTON, D. C. 20555 'o \\..Y..** JAN 2 3 ISBI Docket No. 50-155 MEMORANDUM FOR: Dennis M. Crutchfield, Chief Operating Reactors Branch d5 Division of Licensing FROM: Walter A. Paulson, Project Manager l Ocerating Reactors Branch #5 l Division of Licensing

SUMMARY

OF MEETING CN NOVEMBER 13, 1980 WITH f-CONSUMERS POWER COMPANY REGARDING (1) CONTAINMENT OVERTEMPERATURE CONDITION RESULTING FRCM A POSTL' LATED STEAM LINE BREAK AT BIG ROCK POINT, AND (2) LICENSEE'S REQUEST TO DEFER IMPLEMENTATION 0F RECIRCULATION PUMP TRIP MODIFICATION i On November 13, 1980, a meeting was held in Bethesda, Maryland with 1 Consumers Power Comany. A list of attendees is enclosed (Enclosure 1). t The purpose of the meeting was to discuss (1) the licensee's proposed solution to the calculated containment high temperature resulting I from postulated steam line breaks, and (2) the licensee's forthcoming request for a delay in the implementation of the recirculation pump trip from December 31, 1980 until April 1,1981. With regard to the calculated containment high temperature following a postulated steam line break, the licensee discussed proposed modifi-cations to the containment spray system that will add spray nozzles in the steam drum cavity to assure that the vital equipment within that enclosure is not subjected to temperatures in excess of design temperature. In addition, the modifications will incorporate a prompt automatic containment spray system and a remote manual backup contain-ment spray system. For small steam line breaks, manual actuation of the containment spray will be required. Because containment spray and core spray are supplied water from the same source (fire systems), y the licensee will have to demonstrate that there is adequate flow in P the core spray system if the containment spray system is actuated. The NRC staff also indicated concerns regarding the environmental qualification of essential electrical equipment in the steam drum cavity in the event of containment spray actuation. Consumers Power Company representatives stated that the proposed changes will be submitted for our review. A copy of the viewgraphs used during this presentation is shown in Enclosure 2. 810sg80100 g

i a. ! JAN 2 31991 The ifcensee also discussed a forthcoming request to delay implementation of the recirculation pump trip (RPT) from December 31, 1980 to April 1, 1981. The Comission issued a Confirmatory Order on February 21, 1980 that requires implementation of the RPT before operation in 1981. The licensee indicated that work had been initiated to implement RPT but new preliminary information from a Probabilistic Risk Assessment (PRA) of Big Rock Point indicated there may be other modificatiens that are more effective in mitigating the effects of an ATWS. The licensee discussed the role of the Big Rock Point safety valve capacity of 200% of the normal steaming rate in maintaining system pressure below the ?700 psia design value without RPT. However, for some transient sequences, RPT appears to significantly reduce peak containment pressure. The licensee stated that work has been stopped on RPT. A request for a delay in the implementation of RPT until April 1,1981 will be submitted by the licensee. Results of the PRA, including ATWS effects, will be submitted to the NRC in March 1981. Copies of the viewgraphs used during the presentation are shown in Enclosure 3. YeL{U t b~ Walter A. Paulson, Project Manager Operating Reactors Branch #5 Division of Licensing

Enclosures:

As stated cc w/ enclosures: See next page l l

1 l Cc Mr. Paul A. Perry, Secretary U. S. Environmental Protection Consumers Power Cocpany Agency 212 West Michigan Avenue Federal Activities Branch Jackson, Michigan 49201 Region V Office i i ATTN: EIS C0ORDINATOR Judd L. Bacon, Esquire 230 South Dearborn Street Consumers Pcwer Co pany Chicago, lilinois 60504 212 West Michigan Avenue ~ I Jackson, Michigan 49201 Herbert Grossman, Esq., Chairman i Atomic Safety and Licensing Board Joseph Gallo, Esquire U. S. Nuclear Regulatory Comission i Isham, Lincoln & Beale Washington, D. C. 20555 1120 Connecticut Avenue } Room 325 Or. Oscar H. Paris Washington, D. C. 20036 Atomic Safety and Licensing Board U. S. Nuclear Regulatory Comission j. Peter W. Steketee, Esquire Washington, D. C. 20555 l; 505 Peoples Building Grand Rapids, Michigan 49503 Mr. Frederick J. Shon Atomic Safety and Licensing Board Alan S. Rosenthal, Esq., Chairman U. S. Nuclear Dewhtory Comission Atomic Safety & Licensing Appeal Board Washington, O. C. 20555 U. S. Nuclear RegJiatory Comission Washington, D. O. 20555 Big Rock Point Nuclear Power Plant ATTN: Mr. C. J. Hartman Mr. John O'Neill, Plant Superintendent Route 2, Box 44 Charlevoix, Michigan 49720 Maple City, Michigan 496t chri s ta-Mr. a Charlevoix Public Liorary '. dox 10BC n.- 107 Clinton Street Charlevoix, Michigan 49720 Charlevoix, 'iichigan i William J Scanlon, Esquire Chairman 2034 Pauline Boulevard County Board of Supervisors Ann Arbor, Michigt.n 48103 Charlevoix County Charlevoix, Michigan 49720 Rtsident Inspector Big Rock Point Plant Office of the Governor (2) c/o U.S..NRC Room 1 - Capitol Building RR #3, Box 600 Lansing, Michigan 48913 Charlevoix, Micnigan 49720 Director, Criteria and Standards Mr. Jim E. Mills j Division Route 2, Box 108C Office of Radiation Programs Charlevoix, Michigen 49720 (ANR-460) U. 5. Environmental Protection Thomas S. Moore Agency Atomic Safety & Licensing Appeal Board .fi Washington, D. C. 20460 U. S. Nuclear Regulatory Comission Washington, D. C. 20555 /

i ~ l 1.. L Cc Dr. John H. Buck Atomic Safety and Licensing Appeal Boarc ( U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Ms. JcAnn Bier 204 Clinton Street j ) Charlevoix, Michigan 49720 Mr. David P. Hoffman fluclear Licensing Administrator Consumers Power Company 1945 W. Parnall Road Jackson, Michigan 49201 9 I' I i gi i I t i

ENCLOSURE 1 4 ATTENDANCE LIST NOVEMBER 13, 1980 MEETING WITH NRC AND CONSUMERS POWER COMPANY Consumers Power Comoany F. Buckman i D..Hoffman G. Withrow W. Brigger P. Wood, SAI

0. VandeWalle A. Sevener NRC (Containment Overtemperature)

W., Paulson G. u,13 san S. Browr. P. DiBenedetto-J. Lombardo D. Crutchfield t l D.. Pickett (Recirculation Pump Trip) W. Paulson G. Holahan W. Minners S. --Israel-l i i 1, ,,,..,,.. ~,,, _, -

e ENCLOSURE 2 BIG ROCK POI:rf Containnent High Te=perature due to Stea= Line Breaks (SL3) Presentation to NRC 0.ata :

c.*e=ber 13,1930 (1 - 3 M!)

Iocation: NRO Headquarters, Bethesda, MD Maryland Bank Building - Rec = 6110

References:

1) IIR S0-023 frc= D P Loffman to J G Keppler dated August 26, 1980

2) Letter from G C Withrow to D M Crutchfield dated October 15, 1980 A.

Proble= Discussica (Reference 1) 1. Existing contain=ent/ core spray syste: 2. E005 Perfer=a=ce - Present Syste 3. Interi: Sclution 1. Modified :entain=ent/ccre spray system g 2. Plant Precedure 3 E00S Perfor=ance k. Effect en EEQ C. Iong-Ter= Solution (Reference 2) 1. Proposed contairment/ core spray syste= 2. ECOS Perfor ance i I 3 Effect on EER i I L _

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6 BIC ROCI POINT CONTAIhMENT SPuY SYSTEM INTERDf SCDIFICATICN 1. PRCVIDE SPRAY FOR STDM DALH CAVITY. 2. IIFIAG SPAAY NO" *S ON BOTH SPRAY }E.WEAS. 3. PRIMARY CNTAI.44ENT SPtAY INITIATED OK C0hTAI. 4ENT HIQf PtISL"/I 4 SETPOINT. 4. CLOSE BRIAIER FCR MCrJP CONTAIDENT SPitAY HEADER. 1 I t 6 I l l l P a. --3 4 9 y p e -w --,---p-y e -y,w w y m-

^ 0 i i =. I I r r e ao t lt zc wrc ea za hge oe rrr nr a opn on t si ti L 1 6 7 C q 0 l 7 O 0 M 7 I 0 n 7 0 0 7 7 8 0 O 60 5 7 0 1 n Y AS I y S t i E n mv R o aa O i bt ec C t / a ~ sm f c u N i n r n f id i li f d l o A M r f m f A 0 i ) C re K t C n 4 O I R 607 G I 0 B H ~ er i p F cm ib l rI e t sp ce em er i u li EF D. P p

h _0PERATIONS MEMO # 29-80 REchsVED I To Shift S vervisors and Operators. NOV 7 1980 N CllAR UCTNSING . rnose. ACS..e.vener. Consumsts care November 6, 1980 pgg SweJccv BIC ROCK POINT PLANT - PRL%UtY SYSTEM STEAM LI2iE BREAK INTERNAL Co nac s pe=ocanc t cc Shitt Technical Advisors QA-05A (2) Shift Supervisor's Log Document Control 740-22.07.02 ~ Control Room Log Training Depart =ent n Oi - QA-05 This memo is an update of Operations Memo #23-80. An analysis of Steam line brea'<s was recently co=pleted by the Nuclear Activities Department. '"' e :2: alt.: =f the analysis indica:e that the containment

• tempera-ture could increase beyond the existing equip =ent LOCA qualification temperature of 235'F.

.#;ci. 2.t. N.3 Because of this analysis, you vill operate according to the following: ..Q .:.:r f. - Se on the alert for any indication of steam line leaks. This could ~~'. be indicated in several ways including the following: 5;. 1. Audible sounds of ' steam blowing 2. Pipeway dew cell,high te=perature alarm 3. Dew cell recorder in control room high te=perature

1. 7 4.

An increase of feedvater flow without a corresponding increase in steam flow 5. Possible dacrease in turbine ' load. ~ Should the following three sv=pto=s appear simultaneously, manually scram the reactor and use the E=ergency Condenser to reduce reactor ~ ~ ' pressure. I 1. High containment camperature 2. An increase in feedwater flow with no corresponding increase in steam flow l 3. Unexplained drop in generator output. If containment pressure is rising, place both the electric and diesel fire pumps in service, control containment pressure by use of the con-tainment sprays. When only one fire pump is operating, contain=ent sprays may be used until reactor pressure approaches 200 psig. l 1

[ ~ o IhTERIM MODIFICATION ECCS PERFCRMANCE - TI'si WRSI SINGLE FAILURE (niE DIESEL CENEPATOR) CORE SPRAY REACTOR SPARGER FLOW PRESSURE 279 gpm 75 psig 294 70 308 63 - WITH SECN) NOF.ST SINGLE FAILLit2 (3ACCP CONT. SPRAY VALVE FAILS OPEN) N02:12 FI4W = 311 GPM i 7S PSIG. L - RATED CORE SPRAY OF 292 GPM OCCURS AT

• 71 PSIG VERSUS HIS1VRICAL

\\. 7S TSIG. r - REACTOR PRESSURE WILL RE' MIN LESS 71 PSIG FCLLCWING RDS BLOWDOWN. PEAK CDNTAIhMF.NT PRESSURE = 20 PSIG. RDS VALVE OPE"ING AP IS 4 50 PSIG l l I f l (_ ~

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v-f. EFFECT 3 ELECTRICAL EQUIP M QUALIFICATION - XITH PRCHFT SPRAY CON'!AIEVT TDGERAT2 JuY 3RIEFLY (/ MINUTES) "N UfE EQUIPMENT QUALIFICATION TEMPERATURE, BUT THE EQUIPMENT TNRATURE SHOULD REMAIN BELOW 235 F. FOR PWRs A SHORT DURATION TD&ERAWRE SPIIE - 50 to 100 F ABOVE DESIGN TEMPERATURE FOR 60 to 100 SEC0 hts - HAS 3EEX SHOWN M NOT RESULT IN EXCESSIVE ECU ? cT "ibT=2.tTMS (?I: :417EG-0458). I 4 i )

s h r e gtc t , c c , a a e ge r r apn , n gi si 1 1 7 6 0 0 7 7 -0 0 6 1 0 X 1 7 5% 0 07 7 ) 0 M 1 YA S X R tL } E R O n C o /iT t N a EI ic N f I i A d T o F M OC a rr T e N T X a I U g I no K I CO R X 0 1 1 1 p P m c i u ] ll r e t se ce er er l t A-l EI t ) t' 'f w 2 i ,l!!- O

ErlCLOSURE 3 M P SIG ROCK PCI C PLA'C 4 Recirculation ?u=p Trip (RP'") Effects en A73 at Big Rock Point (3??) Presentatien to NRC Cate: Nove=ter 13, 1930 ',3 - 5 FM) Location: NRC Headquarters, 3'ethesda, 2C Marfland Sank 3uilding - Rec = ello A. Introduction 3. A7a*S Applied to 3?? 1. PCS pressurization resulting frc: A$a'S a. FESR consideration / analysis and revised analysis as provided by C?Cc sut=ittal dated July li., 19S0. b. Relief valve capability to avoid POS overpressuri:a,ien. 2. Centain=ent pressuri:ation resulting fr0= A7a*S a. Results of analysis for contain=ent pressure resulting fr== A745 as affected by R?!. b. Result s cf analysis for silevatie centai. e.: pressure. C. ?_M vorth in =1*1 gating consequences of A745 1. Probabilistic Ris'd Assessment (FRA) findings with respect to RPT. 4 D. Su= nary j 1. Censu=ers Power C =pany vill not install the F27 .=odification as previously planned. 2. Requested a: tion frc= NRC is to give an extensien on the order to install RPT until the results of the ??.A are c:=plete at wh* -x * *-a appropriate plant =edifications will be proposed to replace PST. n .,..m.__ ,i

l I AT45 i PCS PRESSURE PISPONSE i e - SIX PRDtARY STEMt DRDI SAFETI VALVES - TOTAL CAPACITY 200', I CF NCR:-LAL STEMtING RATE PEAF. PCS ?Ri35URE.' 170] ?SIA FOR TUR3INE TRIP WITdCU 3Y? ASS ATdS EVENT - PCS DESIGN PPISSURE IS 1700 PSIA, CODE ALLOWABLE PRESSUPS IS 1870 PSIA a 1 i l

b e i VOL 70 AVG. PRESS. IFSI) p53 1430

• 1510 15'30 1570 1750 l

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) s r ATWS CONTAINMENT RESPONSE 4 7.'P3!NE TR!? N/ BYPASS ASD N/0 RPT .' !NCR CONTA!.'2ENT P.USSURICA!!;N TURBINE TRIP W/0 BYPASS, W/0 RPT AND W/0 FEEDWATER MAILABLE - PEAK CONTAINMENT PRESSURE 4 35 PSIG WRBINE TRIP W/0 BYPASS, W/FEEDWATER AVAILABLE, AND WITH RPT AND POISON INJECTION AT 5 MINUTES - PEAK CONTAINMENT PRESSURE = 57.7 PSIG TURBINE TRIP W/O BYPASS, W/FEEDWATER AVAILABLE, W AUTO RPT, W/ POISON INJECTION AT S MINUTES - PEAK CONTAINMENT PRESSURE = 23 PSIG i t e l: I 2 i l i t<

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SUMMARY

OF PRESENTATION o ATWS SEQUENCES PRESENT RISK COMPARABLE TO OTHER SEQUENCES AT BRP o RPT' DOES NOT ADVERSELY AFFECT RISK o RPT DOES NOT SIGNIFICANTLY REDUCE RISK o OTHER MODIFICATIONS APPEAR TO BE GREATER VALUE 4 i..

~' ~ s n } NITROGEN , }, BOTTLES I s s y 9 N- .x 1 VP - 300 A CV 4020 I l i /\\ y POISON TANK STEAM DRUM N n l v - / REACTOR if i V YP - 302 VP - 301 a d>CV 4050 j, i REACTOR CIRC. PUMP #1 REACTOR CIRC. PUMP #2 /s ~ 9 9 G LIQUID POISON SYSTEM FLO'd DIAGRAM w

TIME FOLLOWING VARIOUS TRANSIENTS AVAILABLE TO BEGIN LPS INJECTION (SEC) INITIAL / FINAL POWER LOW LEVEL 111 PRESSilRE 111 PRESSURE FW (MWT) TRANSIENT [1.0I NOFW[0.2.] FROM110lWELL[0.2' PREVEt[I [2EVENI EREVENL RDS RECRIT RDS RECRIT RilS l<ECRIT 2f!0/120 AUTO RCPT 155 218 1 611 fl6'l NO RCPT l'iti l'ill 267 TRANSIENTS * [.l:0] TURBINE TRIP 011 LOSP [.0filIURBINETRIP [.10] IPR FAILURE [.00fL LOAD RFJECT [.01] IPR FAILURE [.06] BYPASS OPEN (N0 BYPASS) (N0 BYPASS) .10 LOSP $06l MAIN COND. FAIL .10 LOSS AllX. POWER }06LMSIVCLOSURE [.06 LOSS FW (WITil BYPASS) [.0fl]LOADREJECT [.fl03 LOAD REJECT (FW MAf'UAL RESTART) (ALL WITil BYPASS)

• NUMBERS IN BRACKETS INDICATE FREQUENCY OF GCCURRENCE OF TilAT PARTICULAR 1RANSIENT PER YEAR

=. EFFECTIVENESS OF PROPOSED MODIFICATIONS ON ATWS CORE DAMAGE PROBABILITY AS IS AUTO RCPT AUiG SLC !IMITED FW 5 4.7 x 10 5 5 4.7 x 10 1.6 x 10 5 5.0 x 10 5 4.7 x 10 1.1 x 10 5 AUTO RCPT 1.3 x 10 5 AUTO SLC FW (LIMITED) 5 1.1 x 10 1 AUTO SLC & (Abi0 RCPT e

I ~@ DISTRIBUTION FOR MEETING SUMMARIES JAN 2 31931 Docket 50-155 NRC PDR l 4ecahPOR-TERA NSIC ORB #5 Reading 'e H. Denton O q g; E. Case 6 1 D. Eisenhut g R. Purple \\1 0 gggi7 G. Lainas g7 7 -9 T. Novak 9 u.5 g ** g esi R. Tedesco J. Heltemes 'b o m D. Crutchfield W. Paulson s ,5 OELD 7G OI&E (3) W. Russell C. Berlinger R. Herrman H. Smith F ACRS (16) J. Olshinski j H. Holahan W. Minners S. Israel S. Brown P. DiBenedetto ,t-J. Lombardo it D. Pickett F. Buchman, CPCo D. u ffman, CPCo o j G. Withrow, CPCo h W. Brigger, CPCo P. Wood, SAI D. VandeWalle, CPCo A. Sevener, CPCo l P I

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