ML20128K004

Summary of 930107 Meeting W/Utils in Rockville,Md to Provide Forum for Licensees to Present Staff W/Info Re Design, Operational & Testing Experience & Justification for long- Term Operability of Alternate Min Flow Path

ML20128K004
Person / Time
Site:	Beaver Valley, Millstone, Vogtle, Comanche Peak
Issue date:	02/11/1993
From:	Le N Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
TAC-M84220, NUDOCS 9302180037
Download: ML20128K004 (71)

Text

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q WASHING 10N, U. C. 20%5 February ll, 1993 Docket Nos. 50-412, 50-423, 50-424, 50 425, 50-445, and 50-446 LICENSEES: DUQUESNE LIGHT COMPANY, NORTHEAST NUCLEAR ENERGY COMPANY, GEORGIA POWER COMDANY, AND TEXAS UTILITIES ELECTRIC COMPANY FAtlllTY:

BEAVER VALLEY UNIT 2, MILLSTONE UNIT 3, V0GTLE UNITS 1 AND 2, AND COMANCHE PEAK UNITS 1 AND 2

SUMMARY

OF MEETING HELD ON JANUARY 7, 1993, WITH DUQllESNE LIGH1 COMPANY, NORTHEAST NUCLEAR ENERGY COMPANY, GEORGIA POWER COMPANY, AND TEXAS UTILITIES ELECTRIC COMPANY (TAC NO. M84220)

A meeting was conducted on January 7,1993, at One White Flint in Rockville, Maryland with Duquesne Light Company, Northeast Nuclear Energy Company, Georgia Power Lompany, and Texas Utilities Electric Company, licensees for Beaver Valley Unit 2, Millstone Unit 3, Vogtle Units 1 and 2, and Comanche Peak 1 and 2.

The purpose of this meeting was to provide a forum for licensees to present tne staff with information regarding the design, operational and testing experience, and justification for long-term operability of the alternate minimum flow (AMF) path in the high head / pressure safety injection systems installed at Beaver Valley 2, Millstone 3, Vogtle I and 2, and Comanche Peak 1 and 2, nuclear power plants. The Nuclear Steam Supply System (NSSS) vendor (Westinghouse Electric Corporation) for these plants also participated in the meeting.

The presentation closely followed the meeting agenda (Enclosure 1) and the handouts (Enclosure 2). Meeting attendees are listed in Enclosure 3.

At the conclusion of the meeting, the staff requested that each licensee document and docket their presented information-for the staff to review.

Three licensees (Duquesne Light Company, Northeast Nuclear Energy Company, and Georgia Power Company) committed to submit the requested information.

With regard to information provided by the Texas Utilities Electric Company (TVECo), the licensee for Comanche Peak 1 and the applicant for the Comanche Peak 1, TUEco stated, during the meeting, that during the' December 1992 time frame they performed and successfully passed an operability test on their AMF system. This test result and their subsequent commitment made by letter dated January lf,, 1993, to improve the frequency of surveillance testing for their relief valves (i.e., beyond that required by ASME Code requirements) should demonstrate the long-term operability of their AMF. systems. TUEco contends that this justifies the long-term operability of their AMF systems.

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_2-1 The staf f plans to~ review infonnation presented at the meeting, during-follow-up phone calls, and in licensee submittals to determine the acceptability of -

i all AMF systems installed at the above-mentioned facilities,

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Ngoc B. Lo,. Project Manager Project Directorate 11-1 '

Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulations

Enclosures:

1.

Meeting Agenda 2.

Handvuts-3.

Attendees List cc: -See next page:

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m Fet,ruary 11. 1993 s' The staff olans to review informatior. presented at the meeting, durin9 follow-up phone calls, and in-licensee submittals to determine the acceptability of all AMF systems installed at the above-mntioned facilities.

ORIGINAL SIGNED BY:

Ngoc B. Lo, Project Manager Project Directorite 11-1 Division of Reactor Projects - 1/Il-Office of Nuclear Reactor Regulations

Enclosures:

1.

Meeting Agenda 2.

flandouts 3.

Attendees List cc:

See next page E

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• SEE PREVIOUS CONCURRENCE

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Beaver Valley Power Station Units-1 & 2 d

icc' Jay E. Silberg, Esquire Bureau:of Radiation Protection Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street, NW.

Environmental Resources.

Washington, DC 20037

' ATTN:- k. Janati-Post Office Box 2063-Nelson Tonet, Manager llarrisburg, Pannsylvania 17120:

Nuclear Safety Duquesne Light Company-Mayor of th'e Borrough..off Post Office Box 4-Shippingport e

Shippingport, Pennsylvania 15077 Post Office Box 3 q

Shippingport, Pennsylvania 115077 Commissioner Roy M Smith West Virginia Department of Labor Regional Administrator, Region:l!

Building 3, Room 319 U.S. Nuclear Regulatory _Comission._

Capitol Complex.

475 Allendale Road:

Charleston,-West Virginia 25305

~ King of Prussia._ Pennsylvania l19406 o

' John 0, Borrows Resident-Inspector.

Director, Utilities Department U,5, Nuclear Regulatory Commission Public Utilities Comission-Post Office Box 181 180 East Broad Street-Shippingport, Pennsylvania 15077-

-Columbus,. Ohio 43266-0573 Mr.-J. D. Sieber, Vice President:-

a Director, Pennsylvania Emergency Nuclear Groui Management Agency Duques s Ligit-Company Post Office Box 3321 Post Office-Bux 4

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g Harrisburg,_ Pennsylvania 17105-3321 Shippingport, Pennsylvania?l5077; ij Ohio EPA-DERR.

ATTN: Zack A. Clayton Post OfficeJBox 1049-Columbus.-Ohio 43266-0149 i

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u Comanche Peak Steam ' Electric Station,.

Unitt I-and 2

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Jack R.~ Newman, Esq.1 t

Senior Resident Inspector-U.S. Nuclear Regulatory Commission Newman'6 Holtzinger f;

P. O. Box =1029 1615 L Streat, N.W.;

Granbury, Texas 76048-Suite 10C0 Washington,-'D. C.

20036:

Regional Administrator, Region;1V U.S. Nuclear Regalatory Commission Chief, Texas. Bureau of Radiation Control.

U 611 Ryan Plaza Drive, Suite 1000 Arlington, Texas 76011 Texas Department of Health -

1100 West-49th Street-

-Austin, Texas =78756:

Mrs. Juanita' Ellis, President Citizens Association for Sound Energy Honorable Dale McPherson-n 1426 South Polk County Judge-Dallas, Texas 75224_

P._0. Box.651 Glen Rose,:Teaas 76043 1

Owen L. Thero, President

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Quality Technology-Company Mr. William J.-Cahill.:Jr.

Lakeview Mobile Home Park,' Lot 35 Group Vice President 4793 East Loop 820. South TU Electric:-

4 Fort Worth, Texas 76119-400 North Olive Street, L.B. 81=

Dallas, Texas 75201~

- Mr. Roger D. Walker, Manager -

Regulatory Affairs for Nuclear 1'

Engineering-Organization.

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. Texas Utilities Electric Company-400 North' Olive Street, L.B. 81-'

Dallas, Taxas. 75201 4

3 Texas Utilities Electric Company-e

. c/o Bethesua Licensing 3 Netro Center,' Suite:610-Bethesda, Maryland 20814

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$1111am'A.Burchette,Eq.

Counsel for Tex-La Eleceic Cooperative of. Texas.

i Jorden,-Schulte, & Burchette j

1025 Thomas Jefferson Street,-N.W..

. Washington, D.C.

20007-GDS: Associates Inc.

- Suite 720 1

-1850 Parkway Place Marietta,? Georgia-30067-8237-h '

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Millstone Nuclear Power Station Unit 3 cc:

Gerald Garfield, Esquire R. M. Kacich, Director Day, Berry and Howard Nuclear Licensing Counselors at Law Northeast Utilities Service Company City Place Post Office Box 270 Hartford, Connecticut 06103-3499 Hartford, Connecticut 06141-0270 W. D. Romberg, Vice President D, 0. Nordquist-Nuclear, Operations Services Director of Quality Services Northeast Utilities Service Company Northeast Utilities Service Company Post Office Box 270 Post Office Box 270 Hartford, Connecticut 06141-0270 Hartford, Connecticut 06141-0270 Kevin McCarthy, Director Regional Administrator Radiation Control Unit Region I Department of Environmental Protection U.S. Nuclear Regulatory Commission State Office Building 475 Al'lendale Road Hartford, Connecticut 06106 King of Prussia, Pennsylvania 19406 Allan Johanson, Assistant Director First Selectmen Office of Policy and Management Town of Wsterford Policy Development and Planning Division Hall of Records 80 Washington Street 200 Boston Post Road Hartford, Connecticut 06106 Waterford, Connecticut 06385 S. E. Scace, Nuclear Station Director P. D. Swetland, Resident Inspector Hillstone Nuclear Power Station

-Millstone Nuclear Power Statian Northeast Nuclear Energy Company c/o U.S. Nuclear Regulatory Commission Post Office Box 128 Post Office Box 513 Waterford, Connecticut 06385 Niantic, Connecticut 06357 C. H. Clement, Nuclear Unit Dircctor M. R. Scully, Executive Director Millstone Unit No. 3 Connecticut Municipal Electric Northeast Nuclear Energy Company Enorgy Cooperative Post Office Box 128 30 Stott Avenue Waterford, Connecticut 06385 Norwich, Connecticut 06360 Burlington Electric Department David W. Graham c/o Robert E. Fletcher, Esq.

Fuel Supply Planning Manager 271 South Union Street Massachusetts Municipal Wholesale Burlington, Vermont 05402 Electric Company Post Office Box 426 Nicholas S. Reynolds Ludlow, Massachusetts 01056 Winston & Strawn 1400 L Street, NW Hr. John F. Opeka-Washington, DC ~20005-3502 Executive Vice President, Nuclear Connecticut Yankee Atomic Power Company Northeast Nuclear Energy Company Post Office Bt 270 Hartford, Connecticut 06141-0270

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Vogtle Electric Generating Plant Cc:

Mr. J. A. Bailey Joe J. Tanner, Commissioner-Manager - Licensing Department of Natural Resources-Georgia Power Company 205 Outler Street, SE. Suite 1252 P. O. Box 1295 Atlanta, Georgia 30334 Birmingham, Alabama 35201 Attorney General Mr. W. B. Shipman Law Department General Manager, Vogtle Electric 132 Judicial building Generating Plant Atlanta, Georgia 30334 P. O. Box 1600 l

Waynesboro, Georgia -30830 Mr. Alan R. Herdt Project Branch 33 Regional Administrator, Region 11 U. S. NL. clear Regulatory Commission U. S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 i

101 Marietta Street,-NW., Suite 2900 Atlanta, Georgia 30323 Atlanta, Georgia 30830 Mr. Dan Smith Office of Planning and budget Program _ Director of Power Room 6158 Production 270 Washington Street, SW.

Oglethorpe Power Corporation Atlanta, Georgia 30334

-2100 East Exchange Place Tucker, Georgia 30085-1349 Mr. C. K. McCoy Vice President - Nuclear Charles A. Patrizia, Esquire Vogtle Project Paui, Hastings,.Janofsky & Walker.

1 Georgia Power Company lEth Floor-P. O. Box 1295 1050 Connecticut' Avenue, NW.

Birmingham, Alabana 35201

. ashington, DC 20036 W

Mr. R. P. Mcdonald Art Domby, Esquire Executive Vice President -

Troutman,: Sanders, Lockerman Nuclear Operations and'Ashmore-Georgia Power Company l?.7 Peachtree Street P. O. Box 1295

' Atlanta, Georgia 30303-1810-d Birmingham, Alabama 35201 Mr. W. G. Hairston, III i

Senior Vice Presider.t --

Nuclear Operations Georgia Power Company P. O. Box 1295 Birmingham, Alabama 35201 l

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DISTRIBUTION:

iDocket' file:

NRC/ Local PDRs PC 11 1 Reading file T. Murley 12-G-18 F. Miraglia 12-G-18 J. Partlow 12-G-18 S. Varga 14-E-4 J. Calvo 24-A-2 G. Lainas 14-H-3 J. Mitchell N. B. Le P. Anderson OGC E. Jordan MNBB 3701 ACRS (10)

M. Virgilio 13-A-2 J. Stolz 14-C-7 D. Matthews 14-H-25 S. Black 13-H-15 W. Butler 14-0-)

R. Jones 8-E-23 J. Norberg 7-E-23 J. Wermiel 10-D-24 F. Orr 8-E-23 V. Rooney 14-D-1 A. De Agazio 14-C-7 G. Edison 14-D-1 D. Hood 14-H T. Bergman 13-H-15 J. Ramsey-ll-A-1 L. Gundrum MNBB 9715 T. Scarbrough 7-E-23

1. Ahmed 8-H-3 H. Shaw 7-E-23

5. Long E-4 J. Ramsey ll-A-1 D. Smith 7-0-4 E. Goodwin 0-23 L. Plisco, EDO 17-G-21 J. Beall, R-I E. Merschoff, R-11 B. Bonser. R-Il

__________-._______________________o

- ENCLOSURE 1-AGENDA MEETING TO ADDRESS ISSUES ASSOCIATED WITH THE ALTERNATE MINI-FLOW SYSTEM JANUARY 7,1993 1.

AGENDA /RECENT HISTORY ll.

WESTINGHOUSE PRESENTATION A.

DESIGN BASES OF SYSTEM B.

INTERIM MODIFICATIONSIDESIGN CHANGE C.

CURRENT ALTERNATE MINI-FLOW (AMF) DESIGN D.

SPECIFICATIONS, RELIEF VALVE DISCUSSION E.

PERFORMANCE CALCULATIONS 1.

SIMILARITIES TO COMANCHE PEAK 2.

DIFFERENCES FROM SHEARON HARRIS F.

SUMMARY

CONCLUSIONS Ill.

UTILITY PRESENTATION -

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-A.

COMANCHE PEAK 1 & 2 B.

BEAVER VALLEY 2 i

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MILLSTONE 3 D.

VOGTLE 1 & 2

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SUMMARY

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WESTINGH.OUSE PRESENTATION ON l

ALTERNATE MINIFLOW SYSTEM 1

k DESIGN BASES OF SYSTEM a

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- PROVIDE M INI M U M' RECIRCUL'ATION FLOWRATE TO' PROTECT THE CHARGING / SAFETY INJECTION PUMPS'

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-T R A N S 1.E N T W H i C Hi A L L O W-S REPRESSURIZATION OF THE RCS-STEAMLINE, FEEDLINE BREAKS

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ALTERNATE MINIFLOW SYSTEM o

INTERIM MODIFICATIONS INTERIM MODIFICATIONS e

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'S' SIGNAL FROM NORMAL MINIFLOW.

VALVES, USE OPERATOR ACTIONS TO CLOSE VALVESL IF RCS PRESEU7E DROPS, AND REOPEN VALVES IF RCS PRESSURE RISES INTERIM MODIFICATION 1 USE NORMAL MINIFLOW PATH, DIRECT TO SUCTION OF PUMPS INTERIM MODIFICATION 2-.

ROUTE MINIFLOW BACK TO VCT APPROXIMATELY 1/2 OF THE PLANTS WITH W NSSS USE EITHER MOD 1. OR MOD 2 1

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REFERENCE:

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SHEARON HARRIS COMANCHE PEAK MILLSTONE VOGrLE BEAVER VALLEY VALVE ID:

1-1/2RV79EXA 1-1/2RV78SXC 1-1/2RV785WA l

VALVE SPECIFICATION:

G-952845 G-952845 G-952845 VALVE MANUFACTURER: -

CROSBY CROSBY CROSBY VALVE DRAWING:

DS-C-68354 DS-C-66785 DS-C-69550 VALVE STYLE:

JLT-JB-65-TD JBAK-55 JO-WR-SPL SIZE (in):

1-1/2 x 2-1/2 1-1/2 x 2 1-1/2 x 2 ORIFICE AREA (sq. in.)

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STAMPED CAPACITY (gpm):

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SUMMARY

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AMF RELIEF VALVES WERE SPECIFIED TO MEET THE FOLLOWING CRITERIA:

j OPEN WITHIN PLUS OR MINUS 3% OF THE DESIGN SET PRESSURE OF 2200 PSIG i

ATTAIN ITS FULL RATED' LIFT AT A

PRESSURE NO MORE

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ACCUMULATION OF THE-VALVE'S SET PRESSURE RELIEVE WATER AT THE STAMPED FLOW CAPACITYL OF 96 GPM AT 10%

ACCUMULATION OF THE SET PRESSURE RESEAT AT A PRESSURE AT 90% OF THE SET PRESSURE I

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NOMENCLATURE & DEFINITIONS MALME_C11ATTER D_EEINITION 1.

l ABNORMAL RAPID RECIPROCATING OF - THE MOVABLE PARTS OF A REllEF VALVE IN WHICH THE DISK CONTACTS THE SEAT i

P_0TENTIAL EFFFmCTS OF V.ALV_E3HATTE_R i

RAPID OPENING AND CLOSING OF THE VALVE EFFECTIVELY REDUCES THE-ACTUAL VALVE. FLOW RATE BELOW THE REQUIRED DESIGN FLOW RATE j

RAPID OSCILLATIONS CAN.CAUSE LOAD BEARING SURFACES TO DETERIORATE, CRACK, AND CAN CAUSE.THE VALVE TO BE STUCK OPEN OR CLOSE-t t

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ALTERNATE MINIFLOW RELIEF VALVE NOMENCLATURE & DEFINITIONS P_OTENTIALCAVEES._OF VAL,YE _CH ATIEB ACTUAL FLOW RATE DURING VALVE OPENING IS CONSIDERABLY LESS THAN THE STAMPED CAPACITY BLOWDOWN IS SET TOO LOW CAUSING THE VALVE TO BECOME UNSTABLE AND CHATTER AS SMALL PERTURBATIONS IN THE UPSTREAM PRESSURE MAY CAUSE THE VALVE TO OPEN AND CLOSE W ATER RELIEF VALVES WHEN ACTUATING ON AIR MAY " POP" OPEN AND THEN INSTANTANEOUSL-Y = STRIKE THE VALVE DISC SINCE THE FORCE TO

" GRADUALLY" OPEN THE RELIEF VALVE IS NOT SUSTAINED I

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WESTINGHOUSE PRESENTATION ON ALTERNATE MINIFLOW SYSTEM PERFORMANCE CALCULATIONS REVIEW PIPING LAYOUT AND RESISTANCES FOR PLANTS WITH AMF BEAVER VALLEY UNIT 2 COMANCHE PEAK UNITS 1 AND 2 MILLSTONE 3 VOGTLE UNITS 1 AND 2 CONSIDER PUMP

CURVES, ELEVATIOMS, AND LIMITING PATH RESISTANCES

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OPERATION PRESSURE ABOVE.

RESEAT (BLOWDOWN) PRESSURE-FLOW ABOVE MINIMUM SPECIFIED FLOWRATE ALL PLANTS HAVE ACCEPTABLE OPERATION 4

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January 7, 1993 Deaver Valloy N.R. Tonet Duquonno Light i

G.S. Thomas Duquesne Light J.D. Ga->bor Duquesno Light S.A. Hass Duquesno-Light D.G. McLain Duquonno Light F.D.

Schuster Duquosno Light Millstone M.D. Itoss llortheast Ut1 N.D. Ilulmo Northeast Utl.

R.G. Joshi Northeast Utl.

commancho Peak Joseph E. Thompson TU Electric Fred W. Madden TU Electric Vogtic Lovis A. Ward Southern Nuclear Kevin L. Glandon Southern Nuclear-liarry Hajors Southern Nucioar Westinghouse Preston A. Vock J a:nc e !!o m Tom Gerlowcki 4

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1, November 92 3

Comanche Peak Successful Test, November 92 NRC Requests Utility Meetings, December 92 j

NRC/ Utility Meeting, January 7,1993 e

BEAVER VALLEY POWER STATION UNIT 2 PRESENTATION I

SYSTEM OVERVIEW ll MAINTENANCE ANDTESTING HISTORY lli SYSTEM OPERABILITY IV CONCLUSIONS o

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BEAVER VALLEY POWER STATION UNIT 2 ALTERNATE MINI FLOW REl.lEF VALVES [2CHS RV450A & B].

Prooperational Experience September 1986 Prooperational Test 2.07.01," Charging Pump and Controls Test" HHSI pumps run on multiple mini flow paths Leakago past closed AMF motor operated valves caused e

chattar of rollof valve

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Preoperational Experience May 1987

- i Preoperational Test 2.36A.02, " Electrical AC Independence Test" EDG and ECCS pump auto start on Safety injection signal l

Test run with HHSI on normal mini-flow, (ncrrnal mini flow closure on Si defeated for test) 2CHS-MOV380A & D opened on SI signal Operated in this condition for approximately 20 minutes b

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July 1987

-j 2CHS RV-450A, Maintenance Work Roquest (MWR) Issued for valvo leakage due to bellows failuro I

November 1987 Original (AMF) BVPS 2 design used bellows type rollef valves,.

Crosby JBAK.55. The valves were changed to non bellows type Crosby #J0-WR SPL to reduce maintenance with Westinghouse concurrance.

1 1

4

/

.m-

-_.....-..~....._-.-.._......;-,-

a

h i

BEAVER VALLEY POWER STATION UNIT 2 ALTERNATE MINI-FLOW RELIEF VALVES [2CliS RV450A & B)

_ Operational Experience

\\

September 1988 2CHS RV4508, MWR issued for minor gaskot/fittinD loakago April 1989 2CHS RV450A IST rollof test satisfactory, no leakage November 1990 1-2CHS RV450A, MWR issued for minor gaskot/ fitting loakage A

e e

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BEAVER VALLEY POWER STATION UNIT 2 r

ALTERNATE MINI FLOW RELIEF VALVES [2CHS RV450A & B]

pperational Experience September 1991 INPO issued SER 20 91, Degraded SI system due to damaged rollef valves in alternate mini flow lines, concerning Shearon Harris event December 1991 Position on SER 20-91 issued: AMF relief valves to be setpoint checked at 3R 5

M j

z..

g BEAVER VALLEY POWER STATION UNIT 2 ALTERNATE MINI FLOW RELIEF VALVES [2CHS RV450A & B)

_ Operational Experience March 1992 AMF relief valves checked during 3R 2CHS RV-450A No leakage or apparent valve damage Lift point ~5% above setpoint 2CHS RV 450B No leakrige or apparent valve damage Setpoint check satisfactory AMF Motor Operated Valves are stroked quarterly por the IST program

+

SXSIEM O_PlBABILITV DLC Hydraulic Analysis, validated 1

by Westinghouse, indicates operability

~

Similar Design to Comanche Peak which was tested successfully Shearon-Harris differs in respect to relief valve si7.e and setpoint Procedure enhancements

~

Will continue to use. Alternate Mini-Flow with periodic setpoint testing of one valve per refueling.

~

3 l

6 f

e

.eg,.

,..,w

,me._..,

.....,-r.

,-.,e.,

.-w, e~,

vcww..--

BVPS E0P 2.53A.I uw noe E0 ReactorTripOrSafetyinjection

!$50E 1A REVISION 3 SIEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTA150 YJtLt.f L Sl SLthLt

a. Check all valve indicatir.g lights

a. Manually align valves.

with RED SIS mark LIT

b. Charging /HHS1 Pumps TWO RUNNING

b. Manually start pumps.

if only one charging /HHS! pump s running, JJliN check if the alternate minifTow relief valves have failed by performing the following:

1) within(2SISF1943)BLE Check HHS! Flow the ACCEPTA OPERATION region of Attachment A 4.10.

2) JE flow is 801 within the ACCEPTABLE OPERATION region, lhINclose(2 SIS *H0V383A.

B ' Chargi g Pum s Alternate H niflow sol V vs.

a) Once a failure of the alternate miniflow relief valves has been detected, further control of

[2 SIS *H0V383A B should be3erformedIn)accordance wit 1 the left Hand Page,

c. L(NDICATED2 SIS FI943) HHSI Flow - FLOW

c. Start pumps and align valves to establish flow,

d. LHS! Pumps BOTH RUNNING

d. Manually start pumps,

e. RCS Pressure - GREATER THAN 185

c. LHS1 Pump Olsch Flow FLOW PSIG INDICATED

. (2 SIS *F1945)

+ (2 SIS *F1946]

tto-1 tr/ttne 8 of 22

~

Altemate Mini-flow isolation Criteria 500 i

i i

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l t

)

1 i

l j

j j

450 I

i I

~

I 400 ACCEPTABLE OPERATION l

3

[

l e 350 c

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E-

=

i w

i, E 300 E

l i

4 i

in E

CLOSE [2CHS*MOV383A B]

55 CHARGING PUMPS

}

250 ALTERNATE MN-FLOW

}

ISOLATION VALVES l

I l

1 I

I I

I i

200 i

l l

i i

150 600 700 800 900 1000 1100 1200 1300 1400 1500 1600 1700 1800 1900 2000 2100 2200

- [2CHS-P1121] Ch igg Header Pressure S&_9 M W W T

7AF

1 DVPS - EOP E 0, Roccior Trip Or Saf:ty inj:ction l

4.

CHARGING PUMP ALTERNAlE MINifLOW CRHERIA

[

Operate the charging pump miniflow isolation valves as follows when alternate miniflow relief valves have failed:

Open [2CHS*H0V383A B' Charging Pumps Alternate Miniflow 1501 a.

Vlvswhen[2CHSPil2)ChargingPumpHeaderPressureisgreater than 2000 r>SIG.

b.

Close [2CHS*H0V383A B' Charging Pumps Alternate Miniflow Isol Vivswhen(2CHSPilEl Charging Pump Header Pressure is less than 2000 PSIG.

5.

AQVERSE CN,til CRITERis a.

CNMT radiation GREATER THAN OR EQUAL TO lE45 R/HR 0R-b.

CNMT Pressure GREATER THAN OR EQUAL TO 1.5 PSIG k

f

!!0 1 -!!/il/92

.,-a _. -.

.C_O.NCLUSLORS I

ALTERNATE MINI-FLOW SYSTEM IS OPERABLE FOR ALL COMBINATIONS OF HHSI PUMPS l

1 J

0 4

4 CENTRIFUGAL CHARGING PUMP ALTERNATE MINI-FLOW RELIEF VALVE TEST-COMANCHE PEAK STEAM ELECTRIC STATION TU ELECTRIC 1

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TEST PURPOSE A.

THE PURPOSE OF THE TEST WAS TO VALIDATE THE TRANSIENT ANALYSIS PERFORMED FOR COMANCHE PEAK UNITS 1 AND 2.

THIS ANALYSIS ADDRESSED BOTH VALVE CHATTER AND-WATER HAMMER EFFECTS AND CONCLUDED THAT NO SIGNIFICANT FLUID TRANSIENTS'WOULD occur.

B.

DEMONSTRATE THAT THE ALTERNATE MINI-FLOW RELIEF VALVES PERFORM THEIR INTENDED FUNCTION.

f L

i II. ACCEPTANCE CRITERIA A.

VALVE SHALL NOT DEMONSTRATE SIGNIFICANT VIBRATION OR CHATTERING UNDER FULL FLOW CONDITIONS.

l B.

TRANSIENT VIBRATION / CHATTERING DURING TRANSITION OF FLOW STREAMS (I.E.

CLOSING AND OPENING OF THE COLD LEG INJECTION VALVES) MAY OCCUR FOR SEVERAL SECONDS.-

THIS WOULD BE ACCEPTABLE.

C.

ACCEPTANCE CRITERIA WERE BASED ON EXISTING PREOPERATIONAL COMANCHE 4

PEAK PROJECT PROCEDURES FOR PIPING VIBRATION TESTING.

a

-,, ~,,,.

--.......~,,,e,-_,

m-.

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..i----4._~.,

W III.

SYSTEM OPERATING MODE / TEST SEQUENCE A.

THE TEST WAS PERFORMED ON THE UNIT 2 TRAIN A ALTERNATE MINI-FLOW SYSTEM RELIEF VALVE (2-8510 A).

THE REMAINING TRAINS WERE DETERMINED TO BE HYDRAULICALLY EQUIVALENT.

B.

THE CHARGING PUMP WAS STARTED WITH THE SYSTEM IN ITS INITIAL TEST CONFIGURATION:

SYSTEM ON NORMAL MINI-FLOW TAKING SUCTION FROM THE REACTOR WATER STORAGE TANK (RWST).

FLOW PATHS FROM THE VOLUME CONTROL TANK AND TO REACTOR COOLANT SYSTEM WERE-ISOLATED.

C.

THE PIPING SYSTEM WAS MONITORED FOR VIBRATION,

STRAIN, PRESSURE AND FLOW AT THE LOCATIONS SHOWN ON FIGURE 1.

D.

AFTER NORMAL MINI-FLOW HAD BEEN ESTABLISHED, THE ALTERNATE MINI-FLOW UPSTREAM ISOLATION VALVE (2-8511A) WAS OPENED PROVIDING PUMP DISCHARGE PRESSURE TO THE ALTERNATE MINI-FLOW RELIEF VALVE.

E III.

SYSTEM OPERATING MODE / TEST SEQUENCE (CONT'D)

E.

THE RELIEF VALVE LIFTED PASSING FLOW BACK TO THE RWST UNTIL THE TEST WAS TERMINATED.

~.

i

~

,.4.

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n IV. TEST: RESULTS l

A.

THE VALVELOPERATED SMOOTHLY, FREE FROM ANY CYCLING.OR CHATTER.

B.

VIBRATION - AND STRAIN DATA WERE SHOWN TO BE WITHIN ACCEPTANCE RANGES.

C.

FLOW THROUGH THE RELIEF VALVE TO THE RWST WAS MEASURED AT 170 GPM.

THE EFFECTS OF THIS INCREASED FLOW:

WAS ASSESSED AND FOUND TO HAVE NO AFFECT ON SAFETYoANALYSIS CONCLUSIONS, INCLUDING ALL NON-LOCA STEAM LINE BREAK ANALYSES AND UNITS' 1 AND12 LOCA ANALYSES.

E.

POST TEST BENCH. TESTING OF THEL s

l RELIEF VALVE SHOWED SET POINT DRIFT OF APPROX.

4%,

THIS WAS SHOWN TO BE ACCEPTABLE.

ADDITIONALLY, MINOR SEAT-LEAKAGE WAS-OBSERVED, DURING-L THE BENCH 1 TEST, DUE TO A SHARP EDGE' ON THE DISK RING.

THE EDGE:WAS' SMOOTHED,-THE VALVE WAS-RESET TO L

2200 PSIG AND-TESTED AGAIN WITH-NO LEAKAGE.

p l

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-, +

V.

CONCLUSION AS EXPECTED, THE AMF TEST RESULTS 1

DEMONSTRATED THAT NO SIGNIFICANT VALVE CHATTER OR WATER HAMMER EFFECTS OCCURRED.

THERE WERE NO VISUAL CHANGES TO THE RELIEF VALVE OR THE AMF SYSTEM DURING THE TEST.

NO SIGNIFICANT STRAIN OR VIBRATION WAS MEASURED.

THE TEST VERIFIES THAT THE ALTERNATE MINIFLOW SYSTEMS AT CPSES PERFORM AS ANYICIPATED AND ARE CAPABLE OF FULFILLING THEIR FUNCTIONS.

m P

P

m FIGURE 1 ALTERNATE MINIFLOW VERIFICATION TEST SETUP p

i M

M Slia t w A T u n MINIFLOW k k

HEAT CCP.

2-8111 2-8110 EXCHANGER Bypass +

LOCAL Orifice PRESSURE

' FROM VCT (ISOLATED)

CCP-LO1 TO. RCS 1

l l

4 FROM RWST (ISOLATED) l T

-- FLOW 2

1

_3 7A,7H,7V - On Valve

-- 4 M

M 3

1 Strain Guages and Accelerometers 2-8510A k

l Ms 7A,H,V-Accelerometers on Valve Body 2-8511A' 2.-8510B.

8 - Accelerometer

-6 y '

FLOW - Tokyo Keiki Flow Transducer

- ALTERNATE MINIFLOW J k PRESS - Pressure Transducer

-8 PRESS

> TO RWST

• VALVE OPENS ON. "SI" SIGNAL

. s CS1393001

.w m

7

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lil.C Millstone 3

Alternate Miniflow System for the Charging Pumps j

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1 1

A

r lli C Millstone 3: -Alternate Miniflow System for the Charging Pumps 1.

System Overview a

System-Schematic and Isometric Diagrams b.

Relief Valve History 2.

Testing and Maintenance -History-3.

Operability Assessment 4.

Analytical Actions y

a Evaluation of Safety Analysis b.

EOP Changes L

5.

Future Actions b

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_k lIll.C.1.b 1Rellof-Valve

' History 4

Start-up _.(August 1985):

The ibellowsl ruptured' during--

integratedi safety? injection

testin'g.

AtfthisJtime,4 there were no vents-near the? relief 3

. valve.

.3 Start-up -(December 1985) installed L vents approximately nin_e; inches-belo_w: the -relief valve.

L Ahril 1986

. Commercial Operation 1of:

Millstone 3..

.Refuell'ng(December 1987)

- Removed bellows-from the; relief valves.

1 Refueling (March.1991) _

Performed 5-year'ISI per IWV _3511..

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7 111 4. 2 ;

Testing and Maintenance History Relief valves were challenged during integrated safety injection test in August' 1985.

Relief valves were repaired and reinstalled.

Relief valves were challenged three times prior-to April 1986 (commercial operation).

Relief valve bellows removed in December 1987.

and reset valve setpoints.

As found setpoints had dropped to 1650 and 1950 psig.

Performed 5-year ISI test per 3WV-3511 In March a

1991.

p As found setpoints satisfactory for one relief valve 'and 2350--psig for:other.

9 N

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y jN0 m

V~*

lil;C.3:

Operability!

Assess' ment-Millstone 3' relief valve capacity:(96"gpm)-vs.

=

Shearon Harrisirelief valve capacity (277.gpm).

Valvo sized to open and remain open under.

)

secondary break with RCS re-pressurized.

Relief valve chatter potential conside~ red unlikely.

- Relief valve opens gradually vs.

Instantaneously.

j Current: practice is to fill and vent piping after-any maintenance.

?

Piping system was stress analyzed as satisfactory.

H R_

Direct--comparison.to. Comanche-Peak test, y

.q Conclusion The-relief valves and; piping would not be-1 damaged by initiationlof:a: safety Injection.

The! alternate miniflow system:would; function as required.

s Current. configuration operable..

+

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1 F

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a.

lil.C 4 Analytical-Actions Evaluation of the setpoint pressures of the relief valve-on the safety analysic which rely on the BIS Set pressures of relief-valve Assumed the relief valve is fully open when the charging pump discharge pressure is 1650 psig.

Relief valve 'does not ressat until the s

inlet pressure decreases below 90% of the set pressure.

Effect of the revised charging pump flow on the

+

current licensing basis safoty analyses.

LOCA analysis Large break analysis results unaffected

[

ECCS flow not credited during blowdown Relief valve reseated before end-of blowdown High head flow is unimportant 8

m

.i -

L -

\\_

s k

111.C;4 An'alytical Actions

-(cont.).

LOCA analysis-(cont.)

Small break analysis -results unaffected-

-Licensing analysis considers. two, three, and four inch breaks-Pressure drops below ressat point 1

for all breaks. considered Smaller (loss than two: inch)

, s breaks will have no RCS. voiding' above relief - valve ' reseat. pressure.

Larger. (greater than four inch):

breaks have more rapid pressure:

L reductions below reseat ' point 1

i

..t L

Non-LOCA analysis L

Steam line-break - safety injection

?

pumps (and not the charging pumps) are

_A L

credited in the analysis:

j L'

Feed line, break -

evaluation done for-l no charging case-3 L

l suf ficient margin u to? accommodate :

l change

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' Analytical Action's -(cont,)-

Non-LOCA analysis (cont.)L Steam generator tube rupture)- no.

Impact on analysis analysis assumes maximum safety injection flow any flow. diversion make.

. consequences less sovere Mass / Energy rele se LOCA - large break,results not affected by change as discussed above Steam line break - small changes in safety injection-flo.w do' not significantly -affect: results No significant change In.results-Containment J analysis 4

^

Mass / energy! release rates :not.

sigriffitantly. changed;ftherefore,-

containment Lansly' sis lalso1not.

significantly! affected.:

+

d I

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'+

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i Nl J1

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Ill.C.4 Analytical Actions (cont.)

The conclusion and results of the safety analyses presented in the Millstone 3 FSAR remain valid.

Existing EOPs were reviewed; no changes necessary.

h 9

6 11

\\

111, 0. 5 Futuro Actions Existing design is satisfactory and no further analysis required.

Continue to ensure piping is filled and vented after any maintenance.

Setpoint verification testing in place or bench

- - At least one relief valve per refueling R

6 a

'\\

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e

4 e

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[? 1 YQGT]& k%BCTRI.C_.9E&ERhT))]CLEhhMT UMLTG 1 k 2 SECTION III.D D1.

SYSTEM OVERVIEW D2.

HISTORICAL INFORMATION D3.

SYSTEM OPERABILITY 1

D4.

CONCLUSIONS i

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D2. HISTORICAL INFORMATLQH MAY 1987 COMMERCIAL OPERATIONS - UNIT #1 MAY 1989 COMMERCIAL OPERATIONS - UNIT #2

SUMMARY

1 NO SPECIFIC FUNCTIONAL TESTS PERFORMED RELIEF VALVE OPERABILITY BASED ON BENCH TESTS ALTERNATE MINIPLOW LINES WERE NOT ADEQUATELY VENTED RELIEF VALVES LIFTED DURING ESPAS SURVEILLANCE TESTING PROBLEMS NOTED WITH BELLOWS FAILURES AND SETPOINT DRIFT DECEMBER 1990 POSSIBLE VALVE CHATTER NOTED DURING 1R2 ESFAS TEST - PUMP DISCHARGE FLOW WAS OSCILLATING FROM 50-60 GPM WITH NORMAL AND ALTERNATE MINIFLOW SEPTEMBER 1991 INPO ISSUED SER 91-20 REVISED FILL AND VENT PROCEDURES TO VENT THRU DRAIN VALVES REVISED ESFAS TEST PROCEDURES TO LEAVE HOV ISOLATED INCORPORATED SER 91-20 INTO OPERATOR REQUALIFICATION TRAINING

P L HISTORICAL INFORIMTIQN (CONTIt{UEp1 AUGUST 1992 NRC NOTIFICATION AND ISSUANCE OF IN 92-61 SMALL COLUMN NOT VENTED POTENTIAL FOR TRANSIENT JUDGED TO DE SMALL, BUT NOT EASILY QUANTIFYABLE INVESTIGATED HOW TO PERFORM TEMPORARY VENTING PROCEDURE VALVE CHATTER CONSIDERED UNLIKELY DUE TO LOWER RELIEF VALVE CAPACITY AND PRESSURE LOSSES POSSIBLE VALVE CHATTER NOTED DURING 1R2 ATTRIBUTED TO IMPROPER VENTING OCTOBER 1992 REQUESTED WESTINGHOUSE EVALUATION OF CURRENT DESIGN RELATIVE TO VALVE CHATTER ISSUE TO CONFIRM VEGP EVALUATION NOVEMBER 1992 COMANCHE PEAR PERFORMED SUCCESSFUL TEST OF ALTERNATE MINIPLOW SYSTEM VEGP SITE IMPLEMENTED TEMPORARY VENTING PROCEDURE RESULTS:

A) ONE LINE JUDGED TO HAVE SOME AIR, OTHER 3 JUDGED TO BE WATER SOLID B) 2PSV8510B OPENED OUTSIDE TOLERANCE INSTALLED 04/92, LIFTED 2410 PSIG VALVE NEVER LIFTED C) 2PSV8510A OPENED OUTSIDE TOLERANCh INSTALLED 10/90, LIFTED 1960 PSIG LIFTED 3 TIMES DURING 2R1 ESFAS (11/90)

2

,I P2. H UlORLCAklllEORMATlDON_.lCQHTDIVED1 NOVEMBER 1992 NRC ISSUANCE OF IN 92-61 SUPPLEMENT 1 (continued)

REQUESTED WES*INGHOUSE TO INCORPORATE SUPPLEMENT 1 CONCERNS INTO OH-GOING EVALUATION NRC REQUESTED MEETING RELATIVE TO ALTERNATE MINIPLOW OPERABILITY DECEMBER 1992 CROSBY P.O. INITIATED TO INVESTIGATE ROOT CAUSE OF SETPOINT DRIFT AND VALIDATE BENCH TEST PROCEDURE WESTINGHOUSE AND UTILITY MEETING REGARDING OPERABILITY OF ALTERNATE HINIPLOW SYSTEM' AND POSSIBLE JOINT NRC PRESENTATION

. MAINTENANCE /SURVE1LLANCE HISTORY.

SET SET LOCATION S/N INSTAILED PRESSURE REMOVED PRESSURE RFASON CORREGVEAGONS IPSVa510A 12 START-UP 2215/2200 11/881R1 1638 SURV RESETSETPRESSURE 18 11/881R1 2225/2230 11/881R1 NOT'IESTED LEAKAGE NOZZLE & DISK REPIACED 12 11/881R1 2222/2217 03S01R2 2210/2100 SURV BF1 LOWS REPLACED 20 03901R2 MANF.

10B2 2150 VENT CURRENTLY INSTALLED 1PSV8510B 10 START-UP 2200/2200 11/881R1 2200 LEAK SURV BELLOWS & DISK HOLDER 2900 LIFT REPIACED 19 11/881R1 2175/2180 10/89 NOT'IISTED LEAKAGE REFURBIS1 FED VALVE L

10 10/89 2200/2200 03B01R2 2300 SURV RESETSETPRESSURE 21 03/9G IR2 MANF.

10S11R3 NOTTESTED LEAKAGE BELLOWS REPLACED 13 10B11R3 2260/2260 1092 2240 VENT CURRENTLYINSTAllED p

1 2PSV8510A 9

START-UP 2200/2200 10SO 2R1 1930/1925 SUR

NOZZLE & BELLOWS REPIACED 12 10B02R1 2223/2250 1032 1960 VENT ROOTCAUSE INVESI1GATION 21 10B2 2220'2260 CURRENTLYINSTAllED

' 2PSV8510B 13 START-UP 2140/2140 10902R1 2200/2200 SURV SPARE 18 10B0 2R1 -

2250/2250

' 04S2 2R2 2260/2260 SURV VALVE REFURBIS1IED 10 04S2 2R2 22202180 04S22R2 NOTTESTED LEAKAGE VALVE REFURBISIIED 18 04S2 2R2 2240/2240 1092 2410 VENT ROOTCAUSE EVALUATION 9

10B2 2180/2175 CURRENILYINSTALLED

-\\

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p_3 SYSTEM-OPERABILITY

• WESTINGHOUSE ANALYSIS ILLUSTRATES THAT THE "A" AND "B" TRAIN ALTERNATE MINIFLOW RELIEF VALVES WILL' OPERATE SATISFACTORILY FOR-VOOTLE UNITS.1 &'2

.l-j

• WESTINGHOUSE ANALYSIS-FOR VOGTLE IS CONFIRMED BY THE COMANCHE PEAK TEST

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p_4. CONG.US1QNS

• HIGH HEAD BAFETY INJECTION SYSTEM IS OPERADLE

• PERFORM SETPOINT VERIFICATION TESTING OF AT LEAST ONE RELIEF VALVE PER OUTAGE

• CONTINUE TO REVIEW ALTERNATIVES TO IMPROVE RELIABILITY OF THE RELIEF V3LVES 4

9

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IV. DVERAILSDMMARY WESTINGHOUSE ANALYSIS HA8 SHOWN THAT THE' l

ALTERNATE NINIFLOW SYSTEMS ARE OPERABLE FOR:

COMANCHE PEAK - UNIT 8 1 & 2 BEAVER VALLEY - UNIT 2 NILLSTONE - UNIT 3 VOGTLE - UNITS 1 & 2 l

t WESTINGHOUSE ANALYSIS HAS BEEN VERIFIED BY TESTING AT COMANCHE PEAK NO CLASSICAL SIGNS OF WATER HAMMER HAVE BEEN ODBERVED.FROM PREVIOUS RELIEF VALVE CHALLENGES AT THE8E UTILITIES 4

BEVERAL UTILITIES PLAN TO INCREASE-8ETPOINT TESTING BUCH THAT AT LEAST ONE RELIEF VALVE IS TESTED EVERY REFUELING OUTAGE TO-PROVIDE ADDITIONAL DATA RELATED TO SETPOINT DRIFT 3.

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b D1Q10SURE 3 AMF EVENT FOLLOW-UP MEETING (1/7/93)

NRC/DLC0/NNEC0/GPC0/TUEC0/W NAMES ORGANIZATIONS Tommy Le NRC/NRR/ Project Manager

1. Ahmed NRC/NRR/ Inst. & Control Gary Hammer NRC/NRR/DE/EMEB Horace Shaw NRC/NRR/DE/EMEB E. G. Adensam NRC/NRR/DRPE/PD 11-1 Harry Majors Southern Nuclear Operating Company John D. Sieber Duquesne Light Co. - Sr. V.P.

Joseph E. Thompson TU Electric / Licensing Thomas A. Bergman NRR/PM-CPSES James Hom Westinghouse Steve Nass Duquesne Light Mike Hess Northeast Utilities Linda Gundrum NRC/AE0D/DSP/R0AB Steve Long NRC/NRR/DSSA/SPSB-Risk Analyst Bill Pegg NRC/AE00/DSP/ROAB Robert J. Barkanic PA DER /BRP Jack Ramsey NRC/NRR/0EAB Donna Smith NRC/NRR/DRCH Kamal Manoly NRC/NRR/EMEB Gordon Edison NRC/NRR/DRP Roger Waters Westinghouse James Beall NRC/ Region 1 Al DeAgazio NRC/NRR/DRP Walt Butler NRC/NRR/PD l-3 Vernon Rooney NRC/NRR/DRP R. G. Joshi Northeast Utilities George Thomas Duquesne Light Kevin L. Glandon Southern Nuclear - Vogtle Project Darl S. Hood NRC/NRR/ Project Manager Brian Bonser NRC/R-II/Sr. Res. Insp. Vogtle Nelson R. Tonet DLC - Mgr. Nuclear Safety Fred D. Schuster DLC - BV-2 Ops. Mgr.

Dennis G. McLain DLC - Mgr. Maint. Eng. Assessment Lewis A. Ward Southern Nuclear - Mgr. Maint.-Sup. Vogtle Nelson D. Hulme Northeast Utilities, Millstone 3 Edward F. Goodwin NRC/NRR/ DORS /0EAB Robert C. Jones NRC/NRR/SRXB Frank Orr NRC/NRR/SRXB Preston A. Vock Westinghouse Fred N. Madden TU Electric Tom J. Gerlowski Westinghouse - Fluid Systems Gary B. Barrett Westinghouse - Nuclear Safety l

1

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