ML20046C563

Forwards Corrected Page,Citing Monthly TCV Surveillance Test That Produces half-scram Signal That Verifies Bypass Status of RPS Bypass Circuit,Per 930222 Response to NRC Bulletin 90-001,Suppl 1

ML20046C563
Person / Time
Site:	Hope Creek
Issue date:	08/02/1993
From:	Hagan J Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-90-001, IEB-90-1, NLR-N93116, NUDOCS 9308110156
Download: ML20046C563 (4)

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l' Pubhc Service EJectnc and Gas Company Joseph J. Hagan Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-1200 vice Praxiem - Neer ormat*>ns AUG 0 21933 NLR-N93116 i

U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Y

Gentlemen:

CORRECTION - RESPONSE TO NRC BULLETIN 90-01, SUPPLEMENT 1 HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-50 DOCKET NO. 50-354 Public Service Electric & Gas Company (PSE&G), hereby submits a correction to letter NLR-N93032, dated February 22, 1993 which provided our response to NRC Bulletin 90-01, Supplement 1, for our Salem and Hope Creek Generating Stations.

During a review of our Hope Creek response, we have noted a minor technical error relating to our enhanced surveillance program and justification for transmitters ISBPT-N052(A thru D)-C71. The error was in citing the weekly Turbine Stoo valve surveillance procedure as verifying that the TSV/TCV 30% Reactor Protection System Bypass Circuit is not bypassed. This test does not produce a half-scram and, therefore, would not verify the circuit. It is the monthly Turbine Control Valve surveillance test that produces the half-scram signal that verifies the bypass status.

The monthly Turbine Control Valve test is an existing Technical Specification-required surveillance which has not been added or changed due to Bulletin 90-01 and is, therefore, not part of our R

" enhanced surveillance program" for the Rosemount transmitters.

The discrepancy has no impact upon our justification for these transmitters, but is being corrected to properly identify the testing used in our justification. A copy of the original  ;

response page and the corresponding corrected page are attached. '

100073 ,

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9308110156 930802 PDR ADDCK 05000354 [? ' , p' L  !

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- AUG 0 21993 Document Control Desk NLR-N93116 Should you have any question regarding this correction, we will be pleased to discuss it with you.

Sincerely, Attachment C Mr. T. T. Martin, Administrator - USNRC Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. S. Dembek, Licensing Project Manager U.S. Nuclear Regulatory Commission One White Flint North (MS 14 E-21) 11555 Rockville Pike Rockville, MD 20852 Mr. T. P. Johnson USNRC Senior Resident Inspector Mr. K. Tosch, Manager IV New Jersey Department of Environmental Protection and Energy Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

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ATTACHMENT 2 NRC 90-01 SUP 1 ITEM.1.C TRANSMITTER EXCEPTIONS

• COMPONENT ID M DESCRIPTION Attachment IBGFT-11479A ESF CALI6MTION INTERVAL WITH OIL LOSS LIFTIME EXCEEDING 32 YEARS.

1BGFT-11479D ESF CAVS FLOW TO RNCU DIFF FLOW ISOL ENHANCED SURVEILLANCE

^

v~v ~ -

SEE 1BB

[1SDPT-N052A-C71 RPS HP TURB iST STG STM PRESS WREELY" N _ PROGRAM /JUSTIFICATIOJ[~:

OPERATIONS FUNCTIONAL TEST FOR TURBINE STOP VALVE CLOSURE TO VERIFY 30% POWER E

BYPASS LOGIC; 18 MONTH CALIBRATION TO {

g g ( g j} c llds /)cNS F CHECK FOR SLUGGISH RESPONSE.

JUSTIFICATION: THE FUNCTION OF 1SBPT-N052A-C71 THRU N052D-C71 IS TO MEASURE TURBINE FIRST STAGE PRESSURE AND PROVIDE SIGNALS TO AUTONATICALLY BYPASS TIIE TURBINE STOP VALVE AND CONTROL VALVE I CLOSURE SCRAM AND EOC-RPT TRIP FUNCTIONS BEIDN 30% THERMAL PONER. THIS FUNCTION IS \

CONTINUOUSLY CHECKED VIA AN OVERHEAD )

ANNUNCIATOR TIIAT ALARMS WHEN ANY OHE OF /

THE FOUR CHANNELS IS IN A BYPASS .

CONDITION; WEEKLY FUNCTIONAL TESTS VERIFY THE INDIVIDUAL STOP VALVE CIASURE SCRAM \)

FUNCTIONS ARE NOT BYPASSED. LOSS OF (

TRANSMITTER FILL OIL WOULD RESULT IN LOSS i OF RESPONSE TO INCREASING PRESSURE AND SETPOINT DRIFT IIIGH; THIS FAILURE MODE NOULD NOT PREVENT RPS OR EOC-RPT TRIP FUNCTIONS; DURING PLANT START-UPS, OPERATIONS PROCEDURES REQUIRE TESTING TO (

VERIFY THAT TIIE TURBINE VALVE SCRAM )

FUNCTIONS ARE ACTIVATED PRIOR TO EXCEEDING /

30% PONER. /

IS2PT-N052B-C71 RPS HP TURB IST STG STM PRESS ~ SEE ISBPT-N052A-C71 ,'

1SZPT-N052C-C71 RPS HP TURD IST STG STM PRESS SEE ISBPT-N052A-C71 ./

IS;PT-N052D-C71 RPS HP TURB IST STG STM PRESS SEE ISBPT-N052A-C71 -

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ATTACHMENT 2 (REV 1)

NRC 90-01 SUP 1 ITEM 1.C TRANSMITTER EXCEPTIONS .

COMPONENT ID CLASS DESCRIPTION Attachment ISBPT-N052A-C71 RPS HP TURB 1ST STG STM PRESS ENHANCED SURVEILLANCE PROGRAM: 18 MONTH CALIBRATION CIIECK FOR SLUGGISH RESPONSE. JUSTIFICATION: TIIE FUNCTION OF 1SBPT-N052A-C71 TIIRU N052D-C71 IS TO MEASURE TURBINE FIRST STAGE PRESSURE AND PROVIDE SIGNALS TO AUTOMATICALLY BYPASS THE TURBINE STOP VALVE AND CONTROL VALVE CLOSURE SCRAM AND EOC-RPT TRIP FUNCTIONS BELOW 30% THERMAL POWER. THIS FUNCTION IS CONTINUOUSLY CHECKED VIA AN OVER11EAD ANNUNCIATOR THAT ALARMS WilEN ANY ONE OF THE FOUR CHANNELS IS IN A BYPASS CONDITION. MONTHLY FUNCTIONAL TESTS VERIFY TIIE INDIVIDUAL CONTROL VALVE CLOSURE SCRAM FUNCTIONS ARE NOT BYPASSED. LOSS OF TRANSMITTER FILL OIL WOULD RESULT IN LOSS OF RESPONSE TO INCREASING PRESSURE AND SETPOINT DRIFT IIIGII; THIS FAILURE MODE WOULD NOT PREVENT RPS OR EOC-RPT TRIP FUNCTIONS; DURING PLANT START-UPS, OPERATIONS PROCEDURES REQUIRE VERIFICATION TilAT Tile TURBINE VALVE SCRAM FUNCTIONS ARE ACTIVATED PRIOR TO EXCEEDING 30% POWER.

ISBPT-N052B-C71 RPS 11P TURB 1ST STG STM PRESS SEE ISBPT-N052A-C71 1SBPT-N052C-C71 RPS IIP TURB IST STG STM PRESS SEE ISBPT-N052A-C71 ISBPT-N052D-C71 RPS 11P TURB 1ST STG STM PRESS SEE ISBPT-N052A-C71 Page 1