ML20046C599

Forwards Response to NRC Bulletin 93-003, Resolution of Issues Related to Rv Water Level Instrumentation in BWRs & Info Necessary to Allow Closure of GL 92-04 for Facility

ML20046C599
Person / Time
Site:	Hope Creek
Issue date:	07/30/1993
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-04, GL-92-4, IEB-93-003, IEB-93-3, NLR-N93126, NUDOCS 9308110206
Download: ML20046C599 (5)

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. Put*c Semce Elecinc and Gas company Stanley LaBruna Pubhc Service ElcMnc and Gas Company P.O. Box 236. Hancocks Bndge. NJ 08038 609-339-1700 Vice Prevdent Nuclear Engirefing JUL 3 01993 NLR-N93126 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

RESPONSE TO NRC BULLETIN 93-03 RESOLUTION OF ISSUES RELATED TO REACTOR VESSEL WATER LEVEL INSTRUMENTATION IN BWRs FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 This letter submits our response to NRC Bulletin 93-03 and provides information necessary to allow closecut of Generic Letter 92-04 for the Hope Creek Generating Station. The attachment to this letter provides a description ~of the short term compensatory actions taken and the status of our hardware modifications planned for implementation. Should you have any questions or comments on this submittal, please do not hesitate to contact us.

Sincerely, 7/j.an-Attachment Affidavit 100068

/ I 9308110206 930730 1% #

DR "4 ADOCK 05000354 f

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PDR

'JUL 3 01993 ]

Document Control Desk 2 NLR-N93126 i.

C Mr. T. T. Martin, Administrator - Region I U. S. Nuclear Regulatory Commission i 475 Allendale Road King of Prussia, PA 19406 Mr. S. Dembek, Licensing Project Manager U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson (SOS)  ;

USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV NJ Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625 i

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REF: NLR-N93126 STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM )

S. LaBruna, being duly sworn according to law deposes and says:

I am Vice President - Nuclear Engineering of Public Service Electric and Gas Company, and as such, I find the matters-set forth in the above referenced letter, concerning the Hope Creek Generating Station, are true to the best of my knowledge, information and belief.

fM~ ~

r Subscribed and Swor before me this k bk day.'of . h LIo -

, 1993 vv1 u)]r /> A 61oA ~

NtaryPublcdfNewJersey KIMBERLY JD BROWN NOTARY PUBtlC OF NEW JERSEY My Commission expires on 14 Canissim Esphs April 21,19]B

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. i ATI7c MENT RESIDEE TO NRC IUIIEPIN 93-03 l

RE90IITTICH OF ISSUES REIATED TO REACIIR VIESEL WNIER IEVIL INS'IRMENIATICH IN IMRs

'IDPE CREEK GENERATING SIATICH FN'rT:fTY OPERATIIC IJCE2EE NPF-57 007Er 10. 50-354 NIR-N93126 I. Introdtrtion This attachment contains our response to NRC Bulletin 93-03 for the Hope Creek Generatirg Station. Our response consists of a description of the short term ccxrpensatory actions taken and the hantware modifications '

planned for implementation at the next cold shtitdown after July 30, 1993.

II. Ibscription of Short Term Cwuxe,atory r Actierr; Hope Creek has taken the following short term unipirusatory actions:

A. Short Term Actions to be Talma Within Fifteen Days The following actions were completed within 15 days of the date of the bulletin.

1. Enhanced monitoring of RW level instruments was established to provide early detection of level anomalies associated with de-gassing frcra the reference legs.

The enhanced monitoring consists of the availability of water level information on the control room integrated display systan (CRIDS) screens. The inputs for the CRIDS abstracts consist of reactor water level signals frcxn five separate rarges (narrow, wide, upset, shutdown, ard fuel zone) and five separate condensing chambers. These abstracts are available to the '

operators at nine CRTs located within the main control room and at two CRTs just outside the main control room area. The CRIDS systan provides real time information with five secord updates and allcus ready channel cx'xnparison.

2. Enhancements to procedures for valve alignments and maintenance that have the potential to drain the vessel during Mode 3 were completed. The enharm.wa.uis consist of the addition of cautions within the applicable procedures to remind operators of the potential for confusirg or misleading level irdication.

Specifically, cautions have been added to the followiry proxdurus:

HC.OP-SO.DC-0001(Q), "RHR System Operation" HC.OP-IO.ZZ-0004(Q), " Shutdown frcxn Rated Power to Cold Shutdown" HC.OP-IO.ZZ-0007(Q), " Operations frcxn Hot Standby (MSIVs Closed)"

HC.OP-IO.ZZ-0008(Q), " Shutdown frcxn outside the Control Room" Page 1 of 2

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'i 3-LAtt'achment NIR-N93126 ,

..Re'sponse-to NRC Bulletin 93-03

3. Operators were alerted to potenthily confusing or misleadirg i level . indication that may occur during accidents or transients  ;

initiating in Mode 3.

B. Short Tenn Actions to be Taken by July 30. 1993

'Ihe following action was otmpleted prior to July 30, 1993.

1. Augmented operator training on. loss of RW inventory scenarios i during Mode 3, including RW drairM$own events and cracks or

• breaks in piping, was ocmpleted.  ;

III. Descriptim of Harthdare Modifications A meeting was held on July 22, 1993 between PSE&G and the NRC to open a -

dialogue between PSE&G and the NRC staff on the issue of reactor water  !

level instrumentation and to share our concern that the current schedule iW_ by Bulletin 93-03 for inplementation of a hardware nodification  :

may not provide sufficient time to fully evaluate emerging information. ,

Specifically, it was stated that additional time would be beneficial in '!

order to confirm our conclusions and to refine our understanding of the -

potential that' exists relative to inadvertent trips /actuations. ,

Implementation of. a modification in accordance with the i=w=3 schedule may not provide time to fully evaluate the EPRI test data'and to develop potentially more effective hardware nodifications. . During our meeting, l it was determined that plant specific information sufficient-to grant schedule relief may not be available until-the modification is installed i ard tested.

PSE&G has been responsive and agressive in pursuing a solution to the ~l level instrumentation issue and is ready to couplete installation of a -  !

modification at the next entry into cold shutdown. 'Ihe pseu t modification will tap off of the control rod drive (CRD) system and inject a flow into each of the four, safety channel reference legs to purge rx ualensible gases. PSE&G is currently installing the non-outage portions of the modification and' intends to couplete this modification -

prior to startup from the next entry into cold shutdown after July 30, -l 1993.

We will continue to evaluate emerging information to obtain the best I urderstanding of its impact on our currently approved design. We will -

also continue to investigate other potential modifications and will  :

provide guvt. notification should our plans change as a result of our '

continuing efforts.

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