ML20095H531

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Transmits Clarification of Util License Change Request 94-26 Re Removal of Explosive Gas Mixture
ML20095H531
Person / Time
Site: Hope Creek 
Issue date: 12/18/1995
From: Jamie Benjamin
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20095H533 List:
References
LR-94-26, NUDOCS 9512260082
Download: ML20095H531 (3)


Text

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OPSEG Putilic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit DEC 18 895 LR-N95200 LCR 94-26 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

4

- SUPPLEMENT TO LICENSE CHANGE REQUEST 94-26 REMOVAL OF EXPLOSIVE GAS MIXTURE FROM THE TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354 i

This letter transmits a clarification of Public Service Electric 4

& Gas Company's (PSE&G) License Change Request (LCR) 94-26 (Ref.

NLR-N94209 dated January 20, 1995).

The original submittal proposed the removal of Section 3/4.11.2.6

" Explosive Gas Mixture" and associated references from the Technical Specifications in accordance with the NRC's " Final Policy Statement on Technical Specifications Improvements for Nuclear Power Reactors" ( 58 FR 3 913 2 ).

This encompassed elimination of the Limiting Conditions for Operation (LCOs) while relocating the Bases to the Hope Creek Updated Final Safety Analysis Report (UFSAR) and the Surveillance Requirements to the applicable surveillance procedures.

As noted in the original submittal, PSE&G acknowledged the significance of the main condenser offgas treatment explosive gas monitoring system and it's function of maintaining hydrogen concentrations at safe levels.

It was PSE&G's intent to continue j

monitoring and maintaining main condenser hydrogen levels below the existing 4% limit and to continue with current monitoring instrumentation surveillances.

Pursuant to conversations with the NRC staff, PSE&G was informed that the intent of continued hydrogen monitoring and instrumentation surveillances should be clarified and formalized in the Administrative Controls portion of the Technical Specifications.

The establishment of an explosive gas monitoring program in the Administrative Controls section would satisfy the NRC's go yer future management of the main condenser offgas Db IheputTisinjunlkhls.

~~ 9512260082 951218' PDR ADOCK 05000354 m-

_P.

_ PDR_

o DEC 18 ES5 Document Control Desk LR-N95200 4

treatment explosive gas monitoring system while continuing to provide the benefits of removing the LCO from the Technical Specifications.

The addition of an explosive cas monitoring program as an j

administrative control does nc siter the intent of the original j

submittal nor does it change the conclusion reached in the previously submitted significant safety hazards analysis.

The 1

wording of the proposed addition to the Administrative Controls section of the Technical Specifications, provided in Attachment 1,

is consistent with the NRC's recommendation in the Standard Technical Specifications, NUREG-1433 Rev 1.

2 Should you have any questions regarding this supplement, we will be pleased to discuss them with you.

Sincerely, l

'h enjamin Director -

l QA/ Nuclear Safety Review i

i Attachment C

Mr. T.

T. Martin, Administrator - Region I U.

S.

Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D.

Jaffe, Licensing Project Manager - Hope Creek U.

S.

Nuclear Regulatory Commission i

3 One White Flint North 11555 Rockville Pike Mail'Stop 14E21 Rockville, MD 20852 Mr. R.

Summers (S09)

USNRC Senior Resident Inspector l

Mr. K.

Tosch, Manager IV NJ Department of Environmental Protection Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 a

ATTACHMENT 1 i

NEW TECHNICAL SPECIFICATION PAGE SUPPLEMENT TO LICENSE CHANGE REQUEST 94-26 REMOVAL OF EXPLOSIVE GAS MIXTURE FROM THE TECHNICAL SPECIFICATIONS HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSE NPF-57 LR-N95200 DOCKET NO. 50-354 LCR 94-26 1

The following Technical Specification for Facility Operating License No. NPF-57 is affected by this License Amendment Request:

Technical Soecification Pace New 6.8.4.d New 6-16a l

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