ML20235N066

Summary of 890213 Meeting W/Util & State of Nj Re Air Sys Relating to MSIVs & Reactor Bldg to Torus Vacuum Breakers. Util Should Document Overall Methodology Used for MSIV Leakage Problems Prior to Startup.Viewgraphs Encl

ML20235N066
Person / Time
Site:	Oyster Creek
Issue date:	02/21/1989
From:	Dromerick A Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8903010013
Download: ML20235N066 (27)

Text

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d UNITED STATES E s NUCLEAR REGULATORY COMMISSION

• g ;E WASHINGTON, D. C. 20655

,.....,o February 21, 1989 Docket No. 50-219 l

L LICENSEE: GPU Nuclear Corporation FACILITY: Oyster Creek Nuclear Generating Station

SUMMARY

OF MEETING REGARDING AIR SYSTEMS AS THEY RELATE TO THE.

OYSTER CREEK NUCLEAR GENERATING STATION MAIN STEAM ISOLATION VALVES AND REACTOR BUILDING TO TORUS VACUUM BREAKERS On Monday, February 13, 1989 a meeting was held at One White Flint North, Rockville, Maryland, with GPU Nuclear Corporation (GPUN/ licensee) to discuss air systems as they relate to .the Oyster Creek Nuclear Generating Station main steam isolation valves and reactor building to torus vacuum breakers.

Enclosure 1 is.the list of individuals participating in the discussion.

Enclosure 2 is the licensee's agenda regarding the main. steam isolation valve (MSIV) problem. Enclosure 3 is the licensee's agenda regarding reactor building to torus vacuum breaker problems. The following is a sumary of the significant items discussed.

With respect to MSIV leakage, the licensee indicated that they determined the leakage as a function of drywell pressure and actuator pressure varying with time. To determine integrated leakage, the licensee assumed design basis accident conditions (loss of normal air / nitrogen) and conducted MSIV leakage tests. They also compared the results with bounding SEP analysis for MSIV leakage. The SEP integrated leakage was 16,560 SCF as compared to the licensee's limiting case integrated leakage of 7,665 SCF.

Based on detailed discussions with the licensee regarding this matter, the staff advised the licensee that prior to start up they should document GPUN's overall methodology regarding the MSIV leakage problem and identify all critical- assumptions associated with the analysis. This document should be accompanied with a company statement that the analysis has been confirmed and that GPUN concludes that no safety problem exists. Further, this should be followed in a timely fashion with a complete description and supporting justification of GPUN's analysis.

to torus vacuum breaker butterfly Withrespecttothereactorbuildin!designbasiswastoprovidevacuumrelief valves, the licensee stated that th I under all design conditions and to provide containment isolation. In the  !

event of loss of air, containment isolation would only be provided by a check l

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valve. Detailed discussions were held regarding this matter. Based on these discussions, the staff advised the licensee that we do not consider this matter as a startup issue. However, the licensee should document their position.

Also, this issue remains open until the staff's review upgrading this issue is completed.

j original signed by Alexander W. Dromerick, Project Manager Project Directorate I-4 Division of Reactor Projects I/II Office of Nucle r Reactor Regulation

Enclosures:

1. List of Attendees

2. Agenda for MSIVs

3. Agenda for Reactor Building Torus Vacuum Breaker Problem cc w/ enclosures:

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SUMMARY

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valve. Detailed discussions were held regarding this matter. Based on these i discussions, the staff advised the licensee that we do not consider this matter I as a startup issue. However, the licensee should document their position.

Also, this issue remains open until the staff's review upgrading this issue is completed.

original signed by Alexander W. Dromerick, Project Manager l Project Directorate I-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosures:

1. List of Attendees

2. Agenda for MSIVs

3. Agenda for Reactor Building Torus Vacuum i Breaker Problem cc w/ enclosures:

See next page 1

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02/41/89 02/ /89 02/tl/8 1

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Oyster Creek Nuclear Generating Station Oyster Creek Nuclear Generating Station cc:

Ernest L. Blake, Jr. Resident Inspector Shaw, Pittman, Potts and Trowbridge c/o U.S. NRC 2300 N Street, NW Post Office Box 445 Washington, D.C. 20037 Forked River, New Jersey 08731 J.B. Liberman, Esquire Commissioner Bishop, Liberman, Cook, et al.- New Jersey Department of Energy 1155 Avenue of the Americas 101 Commerce Street New York, New York 10036 Newark, New Jersey. 07102 Jennifer Moon, Acting Chief Regional Administrator, Region I New Jersey Department of Environmental' U.S. Nuclear Regulatory Commission Protection 475 Allendale Road Bureau of Nuclear Engineering King of Prussia, Pennsylvania 19406 .CN'415 Trenton, New Jersey 08625 BWR Licensing Manager Mr. E. E. Fitzpatrick GPU Nuclear Corporation Vice President and Director 1 Upper Pond Road Oyster Creek Nuclear Generating Station Parsippany, New Jersey 07054 Post Office Box 388-Forked River, New Jersey 08731 Deputy Attorney General State of New Jersey Department of Law and Public Safety 36 West State Street - CN 112 Trenton, New Jersey 08625 Mayor Lacey Township 818 West Lacey Road Forked River, New Jersey 08731 Licensing Manager Oyster Creek Nuclear Generating Station Mail Stop: Site Emergency Bldg.

P. O. Box 388 Forked River, New Jersey 08731

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ENCLOSURE 1 OYSTER CREEK MEETING - FEBRUARY 13, 1989 '!

LIST OF ATTENDEES NAME ORGANIZATION A. Dromerick NRR-PDI-4 A. Thadani NRR-DEST J. F. Stolz NRR-PDI-4 J. L. Sullivan Jr. 'GPUN G. Capodanno GPUN i M. Leggart GPUN S. Singh Dept. of Env. Prot., State of N.J.

A. H. Rone GPUN K. G. Wolf GPUN M. J. Slobodien 0.C. Radiological Controls Director, GPUN F. Orr NRR PDI-4 L. Lanese GPUN T. M. Dempsey GPUN D. J. Masiero GPUN J. Martin NRR/PRPB J. Kudrick NRR/SPLB J. W. Craig NRR/SPLB C. Cowgill NRC/RI S. Stasolla NJ/BNE N

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i AGENDA I. INTRODUCTION / PURPOSE '

II. CONCERN / APPROACH III. PLANT CONFIGURATION IV. MSIV LEAKAGE ASSESSMENT METHOD V. CONCLUSIONS l

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1 PURPOSE  !

o RESOLVE OUTSTANDING CONCERNS IN SUPPORT OF OYSTER CREEK RESTART FROM 12R (CURRENTLY SCHEDULED FOR 2-20-89) i MSIV LEAKAGE (SLIDE PRESENTATION)

RX BUILDING TO TORUS VACUUM BREAKER OUTSTANDING VALVE CONCERNS  :

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o ASSUMING DESIGN BASIS ACCIDENT CONDITIONS, MSIV WILL NOT MAINTAIN SPECIFIED LEAKAGE RATE FOR THE TIME PERIOD ASSUMED IN ACCIDENT SCENARIOS  !

o CONCERN IDENTIFIED BY:

POTENTIAL SAFETY CONCERN (A GPUN INTERNAL PROCEDURE)  ;

GENERIC LETTER 88-14 E0P INSPECTION TEAM COMMENT o CONCERN IS NOT UNIQUE TO 0YSTER CREEK 4

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Il CONTAINMENT FUNCTION o TO LIMIT PRIMARY CONTAINMENT LEAKAGE RATE o MSIV LEAKAGE IS THE MAJOR CONTRIBUTOR

, , MSIV DOSE CONTRIBUTION o FSAR OFF-SITE DOSE ANALYSIS DOES NOT IDENTIFY MSIV CONTRIBUTION o SEP ASSESSMENT (TOPIC XV-19) CALCULATED 0FF-SITE DOSE TO BE:

1 REM WHOLE-B0DY 341 REM THYROID

...A SIGNIFICANT CONTRIBUTION TO THE CALCULATED OFF-SITE DOSE (334 REMS) WAS FROM MSIV LEAKAGE." (98%)

RESULTS WERE ACCEPTABLE TO THE STAFF ALL ASSUMPTIONS NECESSARY TO DUPLICATE

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RESULTS WERE NOT IDENTIFIED IN SEP CORRESPONDENCE. '

o SEP RECOMMENDED A MORE REALISTIC ANALYSIS BE PERFORMED FACTORING IN THE EFFECTS OF DRYWELL PRESSURE VERSUS.MSIV. LEAKAGE RATE -=

AS A FUNCTIONL0FJIME  ;

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9 GPUN APPROACH o DETERMINE MSIV LEAKAGE AS A FUNCTION OF DRYWELL PRESSURE AND ACTUATOR PRESSURE VARYING WITH TIME.

ASSUMED DESIGN BASIS ACCIDENT CONDITIONS (LOSS OF NORMAL AIR / NITROGEN)

CONDUCTED MSIV LEAKAGE TESTS '.

DETERMINED INTEGRATED LEAKAGE o COMPARED RESULTS WITH B0UNDING SEP ANALYSIS FOR MSIV LEAKAGE

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N2 (0R AIR) SUPPLIED FOR ACTUATION OF NS03A/B (INSIDE DW)

AIR SUPPLIED FOR ACTUATION OF NSO4A/B (0UTSIDE DW) i

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1 MSIV LEAKAGE ASSESSMENT METHOD TEST VALVES; COLLECT DATA DETERMINE MSIV LEAKAGE AS A FUNCTION OF DRYWELL PRESSURE AND ACTUATOR PRESSURE UTILIZING CONTAINMENT PRESSURE PROFILE, DETERMINE TOTAL VALVE SEATING FORCE i

USE VALVE SEATING FORCE AND FUNCTIONAL CHARACTERISTIC LEAK RATE FLOW THRU VALVE DETERMINE LEAK RATE VERSUS TIME FOR RANGE OF ACTUATOR PRESSURE DECAY RATES 1

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l CONCLUSIONS o MSIVs ARE TESTED IN COMPLIANCE WITH APPENDIX J

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ENCLOSURE 3

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. REACTOR BUIDING TO TORUS VACVUMBREAKERAN1BUTTERflYVALVES DESIGNBASIS i

PROVIDETORUSVACVUMREL;EFUNDERALLDESIGNBASES CONDITIONS.

PROVIDECONTAINMENTIS0LiIION(CHECKVALVEONLYONLOSSOf AIR).

DESIGNCONFIGURATION

- SYSTEMCONSISTSOfTWOV,l.VETRAINS EACHTRAINCONTAINSONE:.0.BUTTERflYVALVEANDONECHECK

. VALVE.

A.0.BUTIERflYVALVESFALOPEN0NLOSSOFNORMALAIR SUPPLYUSINGACCUMULATORVOLUME.

1980REVIEWFORNUREG-05~8-ADDEDCONTAINMENT ISOLATIONSIGNAL-CONflMEDAPPROPRIATENESSOfFAILURE MODE.

00CXETEDINFORMATION REPORTEDFAILOPENFEATU.EINYEAR-END50.59(b) REPORT.

CONTAiNMENTISOLATIONSYIEMREVIEWEDPER DESCRIBE 9INUfSt.R 5905M /.19 l M ' '

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! TESTRECUIREMENTS BUTIERflYVALVES VALVEEXERCISE(PERFORME; MONTHLY-T.S.REQUIRESQUARTERLY)

. VERIfICATIONOfSTRXEANDSTR0KETIME.

. BINDINGOBSERVATION.

. CEKPOSITIONINDIATION.

. TEST AND CALIBRATE :P SWITCHES

. VERIfYALARMS SEAT LEAK TEST (PERf0RME EVERY REFUELING OUTAGE).

CHECKVALVES VALVEEXERCISE(PERFORME; QUARTERLY). .

. VERIfYOPERATIONOhSIMULATEDDP.

. OBSERVE FULL OPENlfil CLOSE OPERABILITY.

. BINDINGOBSERVATION SEAT 1EAKIEST(PERFORME)EVERYREFUELINGOUTAGE) 5905M/2111't/ 3

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CONCLUSION EXISTINGSYSTEMCONFIGURATIONSUPPORTSDESIGNSAFETYFUNCTION.

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REACTORBUILDINGTOTORUS VACVUNBREAKER.UTTERflYVALVES ACTUATORDIAGRAM ACCUMULATOR CONTROL AIR

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SEISMICQUALIFICATIONBfiNGREVIEWED.

FUNCTIONAL TESTING SCHE [1ED FOR 13R; LEAK TESTING ONG0ING.

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