ML20056H078

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Summary of 930722 Meeting W/Util Re Resolution of NRC Bulletin 93-03, Resolution of Issues Related to Reactor Vessel Water Level Instrumentation in Bwrs, at Plant
ML20056H078
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 09/01/1993
From: Stephen Dembek
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
GL-92-04, GL-92-4, IEB-93-003, IEB-93-3, IEIN-92-054, IEIN-92-54, NUDOCS 9309080194
Download: ML20056H078 (22)
v • d • e


Text

ga atog 6 Q. A b, e, f 4"I S UNITED STATES 5 i'  ! NUCLEAR REGULATORY COMMISSION

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jf WASHINGTON, D C. 20555-0001 September 1, 1993 Docket No. 50-354 LICENSEE: Public Service Electric and Gas Company FACILITY: Hope Creek Generating Station

SUBJECT:

MEETING

SUMMARY

, RESOLUTION OF NRC BULLETIN 93-03, " RESOLUTION OF ISSUES RELATED TO REACTOR VESSEL WATER LEVEL INSTRUMENTATION IN BWRS" AT HOPE CREEK On July 22, 1993, a meeting was held between Public Service Electric and Gas Company (the licensee) representatives and the NRC staff. The licensee requested the meeting to discuss its response to Bulletin 93-03 and present justification for deviating from the bulletin's requested action to implement hardware modifications during the next cold shutdown beginning after July 30, 1993.

Backaround As discussed in NRC Information Notice 92-54, " Level Instrumentation Inaccuracies Caused by Rapid Depressurization," and Generic Letter 92-04,

" Resolution of the Issue Related to Reactor Vessel Water Level Instrumentation in BWRs pursuant to 10 CFR-50.54(f)," the NRC is concerned that noncondensible gases may become dissolved in the reference leg of BWR water level instrumentation and lead to a false high level indication after a rapid depressurization event. The generic letter requested that the licensees take short-term compensatory measures and also provide the staff with long-term  ;

corrective actions, including any proposed hardware modifications. Bulletin '

93-03 has requested that each licensee implement hardware modifications necessary to ensure that the level instrumentation system design is of high .

functional reliability for long-term operation and requested that these i modifications be implemen'ted ~at the next cold shutdown beginning after July 30, 1993.

l Summarv The licensee requested the meeting to discuss its response to Bulletin 93-03 i and present justification for deviating from the bulletin's requested action  !

to implement hardware modifications during the next cold shutdown beginning l after July 30, 1993. The licensee requested that the hardware modifications j be deferre.1 to the next refueling outage (RF0) in March 1994.

The licensce opened the meeting with a historical perspective of the issue, beginning in 1985 during startup testing through operation in 1992. Previous design modifications on the Reactor Pressure Vessel (RPV) instrumentation installed constant volume chamber hermocou condensate chambers to monitor pe, ' htepgogrjnck Mgg{ples on the four i

93090B0194 PDR 930901 M I G ADOCK 05000354 PDR L

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. The licensee discussed nperations- and engineering-related actions. The operations-related actions include implementation of the BWR Owners Group's (BWROG) operator guidance and the following compensatory actions: (1) cautions in procedures governing line-ups when in and going to shutdown cooling, and (2) establishment of enhanced RPV level monitoring. The licensee is currently assessing the capability and risk of backfill prior to going to shutdown cooling. Engineering-related actions include backfill modification outage and non-outage work, study / evaluation of other possible modifications, such as the ABB modification, and technical specification implications. (The ABB modification is on the condensing chambers. The inlet steam and return water are not mixed so that noncondensible gases will not be dissolved in the reference leg water.) The licensee would like to delay the installation of a modification and evaluate the results of EPRI testing and analytical work when it becomes available. However, the licensee is currently installing the non-outage portions of the backfill modification and intends to complete this modification prior to startup from the next entry into cold shutdown after July 30,1993. The backfill modification will tap off the control rod drive system and inject a flow into each of the four safety channel reference legs to purge noncondensible gases.

The NRC staff considered the licensee's presentation and determined that the licensee has not provided specific concerns regarding the reactor water level issue. The NRC staff concludes that at this time the licensee has not provided adequate justification for the deferment of the hardware modification until March 1994.

/S/

Stephen Dembek, Project Manager Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation

Enclosures:

1. Licensee Handouts
2. List of attendees cc w/ enclosures:

L1censee and Service List DISTRIBUTION w/ Enclosures 1 and 2 DISTRIBUTION w/ Enclosure 2 only Docket File TMurley/FMiraglia TCollins NRC & Local PDRs JPartlow DWheeler PDI-2 Reading SVarga TQuay EWenzinger, RGN-I JCalvo JClifford JWhite, RGN-I MBoyle AThadani SDembek JZimmerman ACRS(10)

M0'Brien VMcCree, EDO OGC

  • Previously Concurred EJordan 0FFICE PDI-2/,tA, o PDI-2/PEdl PDI;2fPM , , SRXB* PDI-2/D g_

NAME M0'B k h Y JZimmerman:rb SNeb TCollins MBoyle W DATE // / /93 7/ //93 'f// /93 08/03/93 6 /1 /93 0FFICIAL RECORD COPY DOCUMENT NAME: HC7-22.MTS

. The licensee discussed operations- and engineering-related actions. The operations-related actions include implementation of the BWR Owners Group's (BWROG) operator guidance and the following compensatory actions: (1) cautions in procedures governing line-ups when in and going to shutdown cooling, and (2) establishment of enhanced RPV level monitoring. The licensee is currently assessing the capability and risk of backfill prior to going to shutdown cooling. Engineering-related actions include backfill modification outage and non-outage work, study / evaluation of other possible modifications, such as the ABB modification, and technical specification implications. (The ABB modification is on the condensing chambers. The inlet steam and return '

water are not mixed so that noncondensible gases will not be dissolved in the ,

reference leg water.) The licensee would like to delay the installation of a '

modification and evaluate the results of EPRI testing and analytical work when it becomes available. However, the licensee is currently installing the non-outage portions of the backfill modification and intends to complete this modification prior to startup from the next entry into cold shutdown after July 30, 1993. The backfill modification will tap off the control rod drive system and inject a flow into each of the four safety channel reference legs to purge noncondensible gases.

t The NRC staff considered the licensee's presentation and determined that the licensee has not provided specific concerns regarding the reactor water level issue. The NRC staff concludes that at this time the licensee has not provided adequate justification for the deferment of the hardware modification  !

until March 1994.

&AM Step en Dembek, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Cffice of Nuclear Reactor Regulation

Enclosures:

1. Licensee Handouts
2. List of attendees i I

cc w/ enclosures: i Licensee and Service List I

l l

Public Service Electric & Gas Hope Creek Generating Station Coinpany l

l cc:

M. J. Wetterhahn, Esquire Mr. J. A. Isabella Winston & Strawn MGR. - Generation Department 1400 L Street, N.W. Atlantic Electric Company Washington, DC 20005-3502 Post Office Box 1500 1199 Black Horse Pike Pleasantville, New Jersey 08232 R. Fryling, Jr., Esquire Law Department - Tower SE Richard Hartung l 80 Park Place Electric Service Evaluation  !

i Newark, New Jersey 07101 Board of Regulatory Commissioners  !

2 Gateway Center, Tenth Floor 1 Hope Creek Resident Inspector Newark, NJ 07102 I U.S. Nuclear Regulatory Commission i Drawer I Lower Alloways Creek Township 1 Hancocks Bridge, New Jersey 08038 c/o Mary O. Henderson, Clerk Municipal Building, P.O. Box 157 M r ._ J. Hagan Hancocks Bridge, NJ 08038 Vice President - Nuclear Operations Nuclear Department Mr. Steven E. Miltenberger P.O. Box 236 Vice President and Chief Nuclear Hancocks Bridge, New Jersey 08038 Officer  !

Public Service Electric and Gas Mr. R. Hovey Company General Manager - Hope Creek Operations Post Office 236  !

Hope Creek Generating Station Hancocks Bridge, New Jersey 08038 l P.O. Box 236  ;

Hancocks Bridge, New Jersey 08038 l Mr. Frank X. Thomson, Jr., Manager Licensing and Regulation Nuclear Department P.O. Box 236 i Hancocks Bridge, New Jersey 08038 Region &l Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs ,

NJ Department of Environmental l

Protection and Energy CN 415  ?

Trenton, New Jersey 08625-0415 k

ENCLOSURE 1 O PS

' Public Service l

f '

Electric and Gas Company l

l 1

HOPE CREEK i

i REACTOR VESSEL WATER LEVEL INSTRUMENTATION i

MEETING

! JULY 22,1993 l i 1 l

i HOPE CREEK l GENERA TING STA TION  !

bd dd .

I REACTOR WATER LEVEL INSTRUMENTATION -l I

AGENDA i l

INTRODUCTION STAN LA BRUNA l

.l MEETING OBJECTIVES STAN LA BRUNA f i

DESCRIPTION OF HOPE CREEK JERRY ROSAS LEVEL INSTRUMENTATION HISTORICAL PERSPECTIVE JERRY ROSAS ACTIONS TAKEN TO ADDRESS ISSUE BILL BERG /

CLIVE ATKINSON j TECHNICAL CONSIDERATIONS CLIVE ATKINSON l SAFETY ASSESSMENT CLIVE ATKINSON.

CONCLUSIONS STAN LA BRUNA m w.i I

_____ _ __ _ L

REACTOR WATER LEVEL INSTRUMENTATION MEETING OBJECTIVES e PROVIDE AN HISTORICAL PERSPECTIVE OF WATER LEVEL INSTRUMENTATION AT HOPE CREEK e PROVIDE A

SUMMARY

OF THE ACTIONS TAKEN TO, ADDRESS THE NONCONDENSIBLE GAS ISSUE e PRESENT BASIS FOR REQUESTING RELIEF FROM  ;

SCHEDULE REQUIREMENTS OF BULLETIN 93-03 FOR HARDWARE MODIFICATIONS '

- TECHNICAL CONSIDERATIONS

- SAFETY ASSESSMENT e ESTABLISH AN OPEN DIALOGUE ON THE WATER LEVEL ISSUE SPECIFIC TO HOPE CREEK ,

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REACTOR WATER LEVEL INSTRUMENTATEN ,

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HOPE CREEK DESCRIPTION  !

  • HOPE CREEK LEVEL INSTRUMENTATION l

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- ROSEMOUNT TRANSMITTERS 1

- FOUR INDIVIDUAL INSTRUMENT RACKS l

- FOUR CONDENSING CHAMBERS o

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l REACTOR WATER LEVEL INSTRUMENTATION I l

HOPE CREEK DESCRIPTION TYPICAL A/B CHANNEL TYPICAL C/D CHANNEL NARROW RANGE NARROW RANGE 1 a

REACTOR LEVEL CONTROL -

RPS TRIP RFP TURBINE TRIP -

NS4 ISOLATION MAIN TURBlNE TRIP

  • ADS PERMISSIVE RPS TRIP NS4 ISOLATION WlDE RANGE WIDE RANGE i

NS4 ISOLATION AND

  • NS4 ISOLATION j
RRCS (ATWS) RRCS (ATWS) ]

a HPCI TURBINE TRIP o RCIC TURBINE TRIP )

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PRIMARY CONTAINMENT = PRIMARYCONTAINMENT l l ISOLATION (LOCA 2) ISOLATION (LOCA 2)

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HPCI INITIATION CS/RHR/AJS INITIATION

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PCIS (LOCA 1)

PAMS (INDICATION) 93VV712 l

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REACTOR WATER LEVEL INSTRUMENTATION f

HISTORICAL PRESPECTIVE l

i STARTUP TESTING - 1985

  • RPV INSTRUMENTATION SENSITIVITY DURING INITIAL ,

SURVEILLANCE TESTING (ROSEMOUNT TRANSMITTERS)

POWER ASCENSION TESTING - 1986 e INSTALLATION OF CAGES AROUND THE RPV INSTRUMENT RACKS

  • RPV INSTRUMENTATION " RINGING" PROBLEM DURING LOAD REJECT TESTING f

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HISTORICAL PERSPECTIVE l 1

COMMERCIAL OPERATION - 1987 e BUILT" MOCK UP" OF RPV INSTRUMENT RACK FOR .

TECHNICIAN TRAINING OF TRANSMITTER SENSITIVITY

  • INSTALLATION OF ROSEMOUNT 1153 TRANSMITTER FILTERING ON RPV INSTRUMENT TRANSMITTERS -

RICSIL 012, SIL 463

  • INSTALLATION OF TIME DELAY RELAYS ON LEVEL 8 TRIP CIRCUlTRY COMMERCIAL OPERATION - 1988-91
  • PERFORMED EVALUATION AND CONFIRMATION THAT HCGS CONFORMS TO SIL 470 AND ITS SUPPLEMENTS ,

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REACTOR WATER LEVEL INSTRUMENTATION  !

HISTORICAL PERSPECTIVE :J i

I COMMERCIAL OPERATION - 1992 l 4

  • IMPLEMENTED A DESIGN MODIFICATION FOR l INSTALLATION OF CONSTANT VOLUME CHAMBERS ON l RPV INSTRUMENTATION i
  • COLLECTED DATA OF WIDE RANGE RPV  !

INSTRUMENTATION DURING NORMAL RFO4 REACTOR I COOLDOWN FOR POSSIBLE " NOTCHING ERRORS"- NO j ANOMALIES OBSERVED i

e INSTALLED TEMPORARY THERMOCOUPLES ON 'l CONDENSATE CHAMBERS, DURING RFO4, TO MONITOR l

CHAMBER PERFORMANCE  !

  • IMPLEMENTFD PROCEDURE FOR RPV INSTRUMENT  !

RACK LEAKAdiE INSPECTION IN RESPONSE TO GL 92-04 i 1

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i REACTOR WATER LEVEL INSTRUMENTATION i ACTIONS TAKEN TO ADDRESS ISSUE i l

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i e OPERATIONS RELATED ACTIONS

- IMPLEMENTED BWROG OPERATOR GUIDANCE

- IMPLEMENTED COMPENSATORY ACTIONS i l

  • ENGINEERING RELATED ACTIONS i

- PROGRESS ON BACKFILL MODIFICATION i

- EVALUATION OF ABB MODIFICATION 1

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REACTOR WATER LEVEL INSTRUMENTATION l OPERATIONS RELATED ACTIONS i

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  • HOPE CREEK HAS IMPLEMENTED BWROG OPERATOR - I

, GUIDANCE I

- OPERATORS SENSITIZED TO SYMPTOMS i

- OPERATORS TRAINED TO RESPOND e HOPE CREEK HAS IMPLEMENTED COMPENSATORY ACTIONS j

- CAUTIONS ADDED TO PROCEDURES GOVERNING l LINE UPS WHEN IN AND GOING TO SHUTDOWN '

COOLING ,

- ENHANCED LEVEL MONITORING (CRIDS)

A REAL TIME ,

A READY CHANNEL COMPARISON  ;

A SIMILAR TO SPDS SYSTEM  ;

A FIVE SECOND UPDATE I A REQUIRED TO BE AVAILABLE DURING -

SHUTDOWN A PAGE: DISPLAY NUMidER ONE i e ASSESSING CAPABILITY AND RISK OF BACKFILL PRIOR TO GOING TO SHUTDOWN COOLING i mm l

REACTOR WATER LEVEL INSTRUMENTATION  :

ENGINEERING RELATED ACTIONS  !

4 e BACKFILL MODIFICATION .- NON OUTAGE INSTALLATION

- DESIGN CHANGE PACKAGE APPROVED BY SORC ON JULY 12 i

- INSTALLATION IN PROGRESS .

I e MODIFICATION - OUTAGE WORK l

- DESIGN CHANGE PACKAGE SCHEDULED FOR SORC ON JULY 28

  • CONTINUE TO STUDY / EVALUATE OTHER MODIFICATIONS

- ABB MODIFICATION $

e STATUS OF EPRI TESTING I

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REACTOR WATER LEVEL INSTRUMENTATION l

l TECHNICAL CONSIDERATIONS e BACKFILL MGDIFICATION AT HOPE CREEK

- NOT A PASSIVE SOLUTION

- MAY NOT BE OPTIMAL SOLUTION j A POTENTIAL FOR INADVERTENT  !

TRIPS /ACTUATIONS ,

A MAY MASK LEAKAGE l A DOES NOT ELIMINATE SOURCE OF GASES I

  1. FURTHER STUDY / INVESTIGATION REQUIRED

- ABB MODIFICATION A AT A GLANCE, TECHNICALLY ACCEPTABLE A DESIGNED FOR TEMPERATURE MONITORING  ;

CAPABILITIES TO TREND POT PERFORMANCE l A TRACK RECORD IN SWEDISH PWRs A COMPLETELY PASSIVE MODIFICATION A COST EFFECTIVE OVER THE LIFE OF THE PLANT

- OPTIMUM FLOW RATE FOR BACKFILL MODIFICATION FROM EPRI

- TECHNICAL SPECIFICATION IMPLICATIONS l

- WANT TO "DO THE RIGHT THING" 03MM77 l

REACTOR WATER LEVEL INSTRUMENTATION SAFETY ASSESSMENT i e MINIMAL SAFETY IMPACT DUE TO THE FOLLOWING

- NO OBSERVED WATER LEVEL ANOMAllES A OPERATOR OBSERVATIONS A TEST DATA

- OPERATOR GUIDANCE CURRENTLY ADDRESSES CONSEQUENCES

- COMPENSATORY ACTIONS A COMPENSATORY ACTIONS ENSURE EXISTING CONDITIONS DO NOT CONSTITUTE ANY l SIGNIFICANT CHANGES IN PLANT SAFETY l MARGIN FROM INITIAL PLANT DESIGN A USE OF COMPENSATORY ACTIONS FOR INTERIM PERIOD IS AN APPROPRIATE ALTERNATIVE AND l

ACHIEVES THE LOWEST TOTAL PLANT RISK

- ABILITY TO QUICKLY IDENTIFY WATER LEVEL PROBLEMS l

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REACTOR WATER LEVEL INSTRUMENTATION '

i CONCLUSIONS  ;

F i

i e PSE&G HAS HISTORICALLY BEEN PROACTIVE IN

, ASSURING STATE OF THE ART LEVEL INSTRUMENTATION  !

  • PSE&G HAS AGGRESSIVELY PURSUED A RESOLUTION TO THE NONCONDENSIBLE GAS ISSUE 1
  • SAFETY SIGNIFICANCE IS LOW  !

i l

  • ADDITIONAL TIME REQUIRED TO EVALUATE INFORMATION i

AND EMERGING SOLUTIONS '

e DELAYING IMPLEMENTATION OF MODIFICATION IS l JUSTIFIED e WANT TO "DO THE RIGHT THING" TO MAXIMlZE SAFETY

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ENCLOSURE 2

SUMMARY

OF ATTENDANCE MEETING BETWEEN PUBLIC SERVICE ELECTRIC & GAS AND THE USNRC ,

JULY 22. 1993 P

HAME ORGANIZATION J. Zimmerman NRC/NRR M. Boyle NRC/NRR T. Collins NRC/NRR J. Clifford NRC/NRR T. Quay NRC/NRR D. Wheeler NRC/0E00 ,

S. LaBruna PSE&G F. Thomson PSE&G 4 D. Smith PSE&G i J. Rosas PSE&G -

C. Atkinson PSE&G W. Berg PSE&G K. Krueger PSE&G A. Faulkner PSE&G C. Manges PSE&G L. James Bechte' 'SERCH M. Scharp Newman & Holtzinger .

S. Singh NJ Dept. of Environmental ,

Protection & Energy  :

P I

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