ML20151Z421

Summary of 880818 Meeting W/Util in Rockville,Md Re License Amend Application to Permit Performance of Leak Rate Tests of Containment Isolation Valves in Parallel W/Refueling Operations

ML20151Z421
Person / Time
Site:	River Bend
Issue date:	08/25/1988
From:	Paulson W Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 8808290326
Download: ML20151Z421 (17)

Text

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. August 25, 1988 C Docket No. 50-458 LICENSEE: Gulf States Utilities FACILITY: River Bend Station, Unit No.1

SUMMARY

OF AUGUST 18, 1988 MEETYNG On August 18, 1988, members of the NRC staff met with representatives of Gulf States Utilities Ccmpany (GSU) in Rockville, Maryland. The purpose of the -

meeting was to discuss a forthecming license amendnient application that would pennit the performance of certain local leak rate tests of containment isolation ,

valves in parallel with refueling operations. A list of attendees is enclosed (Enclosure 1).

The current River Bend Station technical specifications regarding refueling operations, require that containment integrity be established and that all penetrations be closed that are required to be closed during accident conditions.

To perform Type C local leak rate tests, certain containment isolation valves require that 3/4-inch vent and drain valves be opened to drain liquid from the lines. This process provides a containnent leakage path through the 3/4-inch lines. Thus, the local leak rate tests for these valves cannot currently be performed during refueling operations.

The licensee is planning to submit a proposed technical specification change i that will allow up to 20 of thest 'ines to be open at one time for the purpose  !

of perfonning the leak rate tests. The proposed change is discussed in the enclosed handouts provided by the licensee (Enclosure 2). The licensee has  !

performed an analysis of the consequences of a fuel handling accident inside containment assuming that the proposed amendnent is approved. As shown in ,

Enclosure 2, the radiological effects calculated by the licensee are small i fractions of the regulatory limits.

The licensee estimates that eight days will be saved during the next refueling outage if this change is approved. >

Walter A. Paulson, Project Manager 8808290326 DR 880825 Project Directorate - IV P

ADOCK 050 8 Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated cc w/ enclosures:

See next page DISTEIBUTION 4focket File NRC PDR Local PDR PD4 Reading J. Calvo W. Paulson OGC-Rockville E. Jordan B. Grimes I. Spickler D. Lynch J. Kudrick s ACRS ( )) T. Martin (Region IV) PD4 Plant File I

PDh WPW n:sr io 08/p /88 r

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1. ~g 'o UNITED STATES

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NUCLEAR REGULATORY COMMISSION

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) WASHINGTON, D. C. 20555 August 25, 1988 Docket No. 50-458 LICENSEE: Gulf States Utilities FACILITY: River Bend Station, Unit No. 1

SUMMARY

OF AUGUST 18, 1988 MEETING On August 18, 1988, members of the NRC staff met with representatives of Gulf States Utilities Company (GSU) in Rockville, Maryland. The purpose of the meeting was to discuss a forthcoming license amendment application that would permit the performance of certain local leak rate tests of containment isolation valves in parallel with refueling operations. A list of attendees is enclosed (Enclosure 1).

The current River Bend Station technical specifications regarding r ueling operations, require that containment integrity be established and tt 't all penetrations he closed that are required to be closed during acciden, conditions.

To perform Type C local leak rate tests, certain containment isolation valves require that 3/4-inch vent and drain valves be opened to drain liquid from the lines. This process provides a containment leakage path through the 3/4-inch lines. Thus, the local leak rate tests for these valves cannot currently be perforned during refueling operations.

The licensee is planning to submit a proposed technical specification change that will allow up to 20 of these lines to be open at one time for the purpose of perfortning the leak rate tests. The proposed change is discussed in the enclosed handouts provided by the licensee (Enclosure 2). The licensee has perforred an analysis of the consequences of a fuel handling accident inside containment assuming that the proposed anendnent is approved. As shown in Enclosure 2, the radiological effects calculated by the licensee are small fractions of the regulatory limits.

The licensee estimates that eight days will be saved during the next refueling outage if this change is approved, hbh Walter A. Paulson, Project Manager Project Directorate - IV Division of Reactor Projects - III, IV, V and Special Projects

Enclosures:

As stated cc w/ enclosures:

See next page

Mr. Ja'es m C.' Deddens Gulf States Utilities Company River Bend Nuclear Plant CC' Troy B. Conner, Jr. , Esq. Mr. J. E. Booker Conner and Wetterhahn Manager-River Bend Oversight 1747 Pennsylvania Avenue, NW P. O. Box 2951 Washington, D.C. 20006 Betumont, TX 77704 Mr. Les England Mr. Willian H. Spell, Administrator Director - Nuclear Licensing Nuclear Energy Division Gulf States Utilities Company Office of Environmental Affairs P. O. Box 220 P. O. Box 14690 St. Francisville, LA 70775 Baton Rouge, Louisiana 70898 Richard M. Troy, Jr. , Esq.

Assistant Attorney General in Charge Mr. J. David McNeill, III State of Louisiana Department of Justice William G. Davis, Esq.

234 Loyola Avenue Department of Justice New Orleans, Louisiana 70112 Attorney General's Office 7434 Perkins Road Resident Inspector Baton Rouge, Louisiana 70808 P. O. Box 1051 St. Francisville, Louisiana 70775 H. Anne P1ettinger 3456 Villa Rose Drive Gretchen R. Rothschild-Reinike Baton Rouge, Louisiana 70806 Louisianians for Safe Energy, Inc.

2108 Broadway Street New Orleans, Louisiana 70118-5462 President of West Feliciana Police Jury Regional Administrator, Region IV P. O. Box 1921 U.S. Nuclear Regulatory Commission St. Francisville, Louisiana 70775 Office of Executive Director for Operations Mr. Frank J. Uddo 611 Ryan Plaza Drive, Suite 1000 Uddo & Porter Arlingten, Texas 76011 6305 Elysian Fields Avenue Suite 400 Philip G. Harris New Orleans, Louisiana 70122 Cajun Electric Power Coop. Inc.

10719 Airline Highway P. O. Box 15540 Baton Rouge, LA 70895

ENCLOSURE 1 AT_TENDANCE LIST HEETING ON AUGUST 18, 1988 NRC STA_FF AND GULF STATES, UTILITIES REPRESENTATIVES NAFE ORGANIZATION W. A. Paulson NRC/NRR

0. A. Shelton GSU/ Nuclear Licensing R. J. King GSU/Supv. - Nuc. Licensing Marvin Morris GSU/Sr. Nuc. Engineer Irwin Spickler NRR/PRPB

0. D. T. Lynch, Jr. NRR/PRPB/RMHES Joseph P.-Schippert GSU/Sr. Operations Eng.

David M. Rothberg Stone & Webster Jack Kudrick NRR/SPLB S. R. Radebaugh GSU/ Outage Management 4

. ECLOSURE2 i

GSU/NRC August 18, 1988 Meeting Agenda Primary Containment Integrity License Amendment

- INTRODUCTION R. King y,

- REVIEW OF RF2 ACTIVITIES AND MILESTONES S. Radebaugh .

- RBS DESIGN OVERVIEW / M. Morris

- LEAK RATE TESTING M. Morris [

o Perfor1ance Method o Engineering Justification ,

- DISCUSSION i

- CONCLDSION ,

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I RF-2 STATISTICS I 50 Days ,

e Duration

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e Primary Containment in effect 4 Days e

Additional Containment Integrity Estimated Shutdown Margin Bundles For CRD Removal And 199 4 . e Total LLRT Valves 47 s

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O PURPOSE OF PROPOSED TECHNICAL SPECIFICATION CHANGE PERMIT PERFORMANCE OF LLRT IN PARALLEL WITH REFUELING OPERATIONS O CURRENT TECHNICAL SPECIFICATIONS REQUIRE CONTAINMENT INTEGRITY

- REQUIRE SUSPENSION OF CORE ALTERATIONS, HANDLING OF IRRADIATED FUEL AND OPERATIONS WITH THE POTENTIAL FOR .

DRAINING THE REACTOR VESSEL IF CONTAINMENT INTEGRITY IS NOT MAINTAINED '

,/

e REQUIRE THAT ALL PENETRATIONS REQUIRED TO BE CLOSED DURING

• ACCIDENT CONDITIONS ARE CLOSED O REVISED TECHNICAL SPECIFICATIONS ALLOW OPENING OF DRAIN AND VENT LINES FOR SURVEILLANCE TESTING REQUIRE ADMINISTRATIVE CONTROL OF DRAIN LINE OPENING REQUIRE 80 HOURS DECAY BEFORE FUEL MOVEMENT

SHIELD BUILDING C O N T R I N t1EN T

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' ISOLATE TEST VOLUME BY CLOSING VALVES VI and V2

• 0 PEN TEST VALVE V3, DRAIN VALVE V4, AND VENT VALVE V7

'AFTER DRAINING TEST VOLUME, CLOSE V4

• CONNECT TEST APPARATUS TO V3

• CLOSE VALVE TO BE TESTED (VS)

• CONDUCTLEAKRATETESTUSINGINFLOWTESTMEiHOD

• 0 PEN VALVE V5 AND CLOSE VALVE V6 ,

' TEST VALVE V6

' RESTORE SYSTEM TO ORIGINAL LINEUP ,

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CURRENT LICENSING BASIS l

o FUEL BUILDING - I'UEL HANDLING ACCIDENT 123 RODS DAMAGED 24 HOUR DECAY AFTER SHUTDOWN -

ALL RELEASES OCCUR WITHIN 2 liOURS

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CREDIT P OR FILTERED RELEASE LPZ DOSES NOT CALCULATED o CONTAINMENT - FUEL HANDLING ACCIDENT l

NOT ANALYZED BECAUSE OF LOW CONTAINMENT LEAK RATE I

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PROPOSED LICENSING BASIS ,

o FUEL BUILDING - FUEL HANDLING ACCIDENT SAME AS CURRENT BASIS EXCEPT CREDIT FOR 80 HOUR DECAY o CONTAINMENT - FUEL HANDLING ACCIDENT ,c ,

125 RODS DAMAGED ,

80 HOUR DECAY AFTER SHUTDOWN ,#

UNFILTERED RELEASE

_ BOUNDING LEAK RATE

- MIXING IN PRIMARY CONTAINMENT

- LPZ DOSES CALCULATED l

k F1IEL HANDLING JCCIDENT PADIOIDGICAL rrrrf15 .

FUEL CCNIAINMENT BUIIDING III REGUIATORY BUIIDING (rm) LIMIT (rm) CASE 1 CASE 2 (rm)

EXCLUSION AREA BOUNDARY

'DIYROID 2.1 1.68 0.34 75 II

-3 GAlf4A 1.3 0.012 2.3x10 6(2)

~3 BEIA 2.0 0.017 3.4x10 NOT SPKIFIID .

IEW POPUIATION ZOE

'HIYROID N/A 2.61 E.18 -3 7 (2) 2)

GAMMA N/A 2.13x10[3 2 1.4x10 ~3 6

BETA N/A 3.66x10 2.3x10 Nor SPKIFIED PAIN CONTROL ROCt4 I4I

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'IEYROID 0.4 0.49 -3 5.5x10.4 GA M 0.07 7.0x10 4.0x10-2 5 BEIA 3.8 0.45 2.6x10 30 (1) CASE 1 - UNMITIGATED RELEASE, CASE 2 'IMENIY MINUTE OPERATOR 7CTION (2) 25% OF 10CFR100 LIMIT (3) 10CFR50, APPENDLX A, GENERAL DESICH CRITERIA 19 (4) NO CREDIT TAKEN MR FACIOR OF 4 REDUCTICN ALIDhD BY SRP 6.4 MR DUAL, SELE. TABLE AIR INIEIS

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CONSERVATISMS ,

AS USED IN ANALYSIS REALISTIC ROD PEAKING FACTOR 15 1.0 NUMBER OF RODS DAMAGED 125 104 RADIONUCLIDES RELEASED FROM FUEL L NOBLE GASES 100% ,

1.8%

ICDINE 10% ,0.32%

PARTICULATES 10% , 0%

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CONTAINMENT UNIDENTIFIED LEAKAGE 0.26%/ DAY 0.0: =

LEAKAGE FLOWS 58 6fm 0.0 RELEASE PATHWAY AUX BLDG SPLIT BETWEEN AUX & FUEL BLDG 9

NO CREDIT TAKEN FOR:

1. INITIATION OF SGTS

2. ISOLATION OF RELEASE PATHS

3. REDUCTION OF CR DOSES DUE TO DUAL INLETS

4. CONTROL ROOM RECIRCULATION

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CONCLUSION: ,

- OFFSITE DOSES BELOW DESIGN BASIS FUEL HANDLING ACCIDENT WITHOUT MITIGATIVE ACTIONS 9

INSIGNIFICANT OFFSITE DOSE IF CREDIT TAKEN FOR MITIGAT'IVE ACTIONS l

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