ML20236X795

From kanterella
Jump to navigation Jump to search

Requests for Addl Info Re Safety/Relief Valve Setpoint Tolerance Change for Plant
ML20236X795
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 08/06/1998
From: Richard Ennis
NRC (Affiliation Not Assigned)
To: Keiser H
Public Service Enterprise Group
References
TAC-MA1674, NUDOCS 9808100263
Download: ML20236X795 (4)


Text

- _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _

Mr. Harold W. Keiser August 6, 1998 Chief Nuclear Officer & President Nuclear Business Unit

  • ~

Public Service Elecinc & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SAFETY / RELIEF VALVE SETPOINT TOLERANCE CHANGE FOR HOPE CREEK GENERATING STATION (TAC NO. MA1674)

Dear Mr. Kaiser:

In a letter dated April 28,1998, Public Service Electric and Gas Company (PSE&G) submitted an application for an amendment to the Technical Specifications (TSs) for Hope Creek Generating Station. The proposed amendment would modify the TSs associated with the Safety / Relief Valves (SRVs) to replace the *1% setpoint tolerance with a i3% setpoint tolerance.

The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure. We mquest that the additional information be provided within 60 days of receipt of this letter, if you have any questions, please contact me at (301) 415-1420.

j Sincerely,

/s/

Richard B. Ennis, Acting Project Manager Project Directorate 1-2 Division of Reactor Projects - 1/il Office of Nuclear Reactor Regulation Docket No. 50 354

Enclosure:

Request for AdditionalInformation

[-] [^ "

J

+

n

.,y.,,,

~

s cc w/ encl: See next page DISTRIBUTION.

, Docket File REnnis TCollins OGC PUBLIC TClark MChatterton ACRS PDI-2 Reading RWessman GThomas JZwolinski DTerso JLinville, RGN-1 RCapra GHammer OFFICE PDI-2/PM PDl-2/LA EMEB/SC a PDI-2/D NAME REnnis:mw M TCladb DTeraob b

DATE 3"/9 /98

$/4198 3 / 1 /98

@ff/98 I

OFFICIAL RECORD COPY DOCUMENT NAME: A:\\hHCMA1674.RAI i

\\

W,_ \\

s

~

9808100263 980806 PDR ADOCK 05000354 P

PDR

a 4

VA Kt% k UNITED STATES y

g j

NUCLEAR REGULATORY COMMISSION t

o, WASHINGTON, D.C, 308e6 4001

%,,,,,8 August 6, 1998 l

Mr. Harold W. Kaiser Chief Nuclear Officer & President Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236 l

Hancocks Brid9e, NJ 08038

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING SAFETY / RELIEF 4

VALVE SETPOINT TOLERANCE CHANGE FOR HOPE CREEK GENERATING STATION (TAC NO. MA1674)

Dear Mr. Keiser:

In a letter dated April 28,1998, Public Servica Electric and Gas Company (PSE&G) submitted an application for an amendment to the Technical Specifications (TSs) for Hope Creek Generating Station. The proposed amendment would modify the TSs associated with the Safety / Relief Valves (SRVs) to replace the t1% setpoint tolerance with a i3% setpoint tolerance.

The NRC staff is reviewing your submittal and has determined that additional ir.farmation is required to complete the review. The specific information requested is addressed in the enclosure. We request that the additional information be provided within 60 days of receipt of this letter.

If you have any questions, please contact me at (301) 415-1420.

Sincerely,

$b8-s-Richard B. Ennis, Acting Project Manager Project Directorate I-2 Division of Reactor Projects - t/ll

'J Office of Nuclear Reactor Regulation Docket No. 50 354

Enclosure:

Request for AdditionalInformation cc w/ encl: See next page

i Mr. Harold W. Kaiser Hope Creek Generating Station Public Service Electric & Gas Company cc:

Jeffrie J. Keenan, Esquire Manager-Joint Generation Nuclear Business Unit-N21 Atlantic Energy P.O. Box 236 6801 Black Horse Pike Hancocks Bndge, NJ 08038 Egg Harbor Twp., NJ (2234 4130 l

Hope Creek Resident inspector Richard Hartung l

U.S. Nuclear Regulatory Commission Electric Service Evaluation l'

Drawer 050g Board of Regulatory Commissioners I

Hancocks Bridge, NJ 08038 2 Gateway center Tenth Floor Newark, NJ 07102 Mr. Louis Storz Sr. Vice President - Nuclear Operations Lower Alloways Creek Township Nuclear Department clo Mary O. Henderson, Clerk P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 Gene:al Manage'r - Hope Creek Opeistions Mr. Elbert Simpson Hope Creek Generating Station Senior Vice President-P.O. Box 236 Nuclear Engineering Hancocks Bridge, NJ 08038 Nuclear Department P.O. Box 236 Manager-Licensing and Regulation Hancocks Bridge, NJ 08038 Nuclear Business Unit-N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Adrninistrator, Region l U.S. Nuclear Regulatory Commission 475 Allendale Road i

King of Prussia, PA 19406 1

I Dr. Jill Upoti, Asst. Director i

Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415

REQUEST FOR ADDITIONAL INFORMATION SAFETY / RELIEF VALVE SETPOINT TOLERANCE CHANGE FOR i

HOPE CREEK GENERATING STATION (TAC NO. MA1674) 1.

In Ucensee Event Report (LER)97-024, the licensee reported the setpoint performance I

for the plant Target Rock 2-Stage safety / relief valves (SRVs). Several as-found setpoint values were much in excess of the t1% tolerance in the current technical specifications (TS) and the A3% tolerance proposed by the licensee. The LER states that platinum ion-beam implanted pilot disks were installed in 7 of the 14 SRVs and that the effectiveness 1

of this modification would be evaluated following Cycle 8. If the evaluation of the 7 l

platinum ion-beam implanted disks indicates that they are ineffective, what additional corrective actions would be necessary to assure that the SRVs will operate within the i3% tolerance? If the evaluation of the disks indicates they are effective in reducing the setpoint drift to within 13%, is it planned tnat the new disks would be installed in all 14 1

SRVs?

l 2.

Uncertainties of analysis parameters should be accounted forin the safety analyses used to bound limits defined by the plant TS. Provide a discussion of the SRV setpoint testing instrument accuracy and how this source of uncertainty is accounted for in the licensee's safety analysis associated with the proposed TS SRV setpoint tolerance.

l

)

I l

i ENCLOSURE 4

l