ML20151W423

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Informs That Design,Const & Preoperational Testing Will Be Substantially Completed in Accordance W/Fsar to Support NRC Issuance of Low Power OL on 860307.List of Sys Removed from Proposed List of Deferral Sys Per Util Encl
ML20151W423
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 02/10/1986
From: Corbin McNeil
Public Service Enterprise Group
To: Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8602120061
Download: ML20151W423 (4)


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OS :b Pubhc Service Electric and Gas Company

. Corbin A. McNelli, Jr.

Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609 339-4800 Vice President -

Nuclear February 10, 1986 Mr. Harold R.

Denton, Director Office of Nuclear Reactor Regulation U.S.

Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Denton:

REQUEST FOR LOW POWER OPERATING LICENSE-HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company (PSE&G) will be ready for issuance of the low-power operating license on March 7, 1986 for the Hope Creek Generating Station.

The design,. construction and preoperational testing of the Hope Creek Generating Station (HCGS) will be substantially completed in accordance with the Final Safety Analysis Report to support NRC issuance of a low-power' license at that time.

' Substantial progress has been made with respect to completing those systems that were identified as post-fuel load completion

-items in a letter from C.A. McNeill (PSE&G) to E. Adensam (NRC) dated November 29, 1985 and. updated in a letter dated January 15, 1986.

Attachment.I identifies those systems that have been removed from the proposed list of deferral systems as presented in our January 15, 1986 letter.

These systems will be substantially completed in support of fuel load.

Attachment II-identifies those systems which will not be completed by fuel load.

As stated in our letter of January 15, 1986, a safety evaluation for each deferral system has been performed.

Each safety evaluation has been reviewed by both the Station Operations Review Committee (SORC) and the Offsite Safety Review Group (OSR).

The results of these reviews demonstrate that post fuel load completion of the systems pose'no undue risk to the health and safety of the public and should not preclude issuance of a low-power operating license.

8602120061 860210 PDR ADOCK 05000 4,

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b Mr. Harold R.

Denton, 2

2/10/86 Director PSE&G is reviewing the recent publication in 10CFR Part 50 of the Final Rule, " Specific Exemptions; Clarifications of Standards" (50.12 specific exemptions).

Any exemption request (s) required pursuant to this rule will be submitted as soon as possible.

PSE&G is looking forward to the NRC's Management visit to ascertain the readiness of HCGS to receive a low power operating license.

Please contact 2SE&G if any additional information is required ir. the interim.

Sincerely, Attachments C

E.G. Adensam USNRC Director, Project Directorate 3 D.H. Wagner USNRC Licensing Project Manager R.W.

Borchardt USNRC Senior Resident Inspector

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. ATTACHMENT.I Ths following systems, which were identified'as post-fuel load completion items'in our November 29, 1985 and January 15,E1986 letter will be completed prior to-fuel load.

Each item identified below is correlated.to its respective identifier as presented in Attachment I to our November 12 9, 1985 submittal.

A.

Radwaste HVAC Systems B.

Reactor Building Filtration Recirculation and

~ Ventilation System (FRVS)-

C.. Liquid Radwaste System L

G.-

Main Turbine Control (EHC) System H.

-Radwaste Building and Turbine Building.

Fire' Protection Water Systems (Automatic Suppression Systems) and Early Warning Smoke Detection Systems

'J.

Containment Pre-purge Clean-up System (CPCS).

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3 ATTACHMENT II The following systems are scheduled for completion after fuel load as detailed in the November 29, 1985, and updated in the January 15, 1986-letter.. Each item identified below is correlated.to its respective identifier as presented in Attachment.I to our November 29,:1985 submittal.

D.

Solid Radwaste System E.

Radiation Monitoring System, Area / Process-

-F.

Transverse In-Core Probe Monitoring i-

.I.

Gaseous Radwaste*

  • The_ Gaseous Radwaste System will-be available when the reactor vessel head is in place and the head bolts are tensioned.

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