ML20066B736

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Application for Amend to License NPF-57,removing License Condition 2.C.(5) Re Solid State Logic Modules Which Have Been Satisfied & Replacing Condition W/New Requirement
ML20066B736
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 12/28/1990
From: Miltenberger S
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20066B738 List:
References
LCR-90-07, LCR-90-7, NLR-N90223, NUDOCS 9101080305
Download: ML20066B736 (7)


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4 Pabc Service Electric and Oas -

Cornpany St yen E. Mittenberger Pubhc Service Electric and Gas Company P.O. Box 236, Hancocks Bridge. NJ 08038 609-339-1100 ;

v.co nesiooni ano cne Nacmar omcer DEC 28 1990 NLR-N90223

Reference:

LCR 90-07 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Gentlemen:

REQUEST FOR AMENDMENT FACILITY OPERATING LICENSE NPF-57 HOPE CREEK GENERATING STATION DOCKET NO. 50-354 Public Service Electric and Gas Company-(PSE&G) hereby transmits an application to amend Facility' Operating License No. NPF-57-in accordance with-10CFR50.90. This amendment request would remove an existing License Condition-which has been satisfied and replace it with a.new-requirement.

A description of the requested amendment, supporting information and analyses for the change, and the basis for a no significant hazards consideration determination are provided in Attachment 1.

The License page affected by the proposed-change is marked-up in-Attachment 2. ..

Upon NRC approval of this proposed change, PSE&G requests that-_the -

amendment be made effective on the date of issuance, but implementable within' sixty days to provide-sufficient time for-completion of associated administrative activitiese Pursuant to the requirements of 10CFR50.91(b) (1), PSE&G has provided a-copy of this~ amendment request to-the State of'New Jersey.

0<0 9101080305 901228 PDR ADOCK 05000354 -k-

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1 Document Control Desk DEC 2 81000 NLR-N90223 ,i Should you have any questions regarding this request, We will be pleased to discuss them with you.

Sincerely,

, k /$d *hyr jg Attachments Affidavit C Mr. T. T. Martin, Administrator USNRC Region I Mr. S. Dembek USNRC Licensing Project Manager Mr. T. P. Johnson USNRC Senior Resident Inspector Mr. K. Tosch, Chief, Bureau of Nuclear Engineering New Jersey Department of Environmental Protection i

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Ref: NLR-N90223 STATE OF NEW JERSEY )

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COUNTY OF SALEM )

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

I am Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in our letter dated DEC 2 8 1990 , concerning the Hope Creek Generating Station, are true to the best of my knowledge, information and belief, br_

Subscribed and Sworn to hefore me this / NI day of (/r y /O -(/ 1990 J'

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Notary Public of New Jersey DnORISD HADDEN Notary Public of New Jersey W Commission Empires Me.2 29,1996 My Commission expires on i

Ref: LCR 90-07 ATTACllMENT 1 PROPOSED LICENSE CONDITION CilANGE 1

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  • 4 I-PROPOSED CilANGE TO TIIE TECIINICAL SPECIFICATION 8 -

FACILITY OPERATING LICENSE NPF-57 ilOPE CREEK GENERATING STATION DOCKET NO. 50-354 <

4 ret: LCR 90 t DESCRIPTION OF THE CHANGE As shown on the marked-up page in Attachment 2, PSE&G requests that the Hope-Creek Generating Station (HCGS) Facility Operating License .be modified by replacing existing License Condition 2.C. (5), Solid State logic Modules with a new requirement for the modules as~follows:

"(5) Solid State Logic Modules PSE&G shall continue, for the-lif'e'of' the plant, a reliability program to monitor the performance of.the Bailey 862 SSLMs-installed-at Hope Creek Generating Station. -This program'should:obtain'-

reliability data, failure characteristics, and root cause:of failure of both safety-related and non-safety-related Baileyn862 SSLMs. The.

results of the reliability program shall be maintained--on-site and-made available to the NRC upon, request."

REASON FOR THE CHANGE In a letter dated November 15, 1990, the NRC concluded that reliability information provided by PSE&G_in-several submittals pertaining..to the-Bailey Solid State Logic Modules (SSbMs) in use at the llope. Creek Generating Station la acceptable and has onatisfied existing License Condition 2.C. (5) ..

As stated in PSE&G's September-10, 1990 letteri the SSLM reliability program- -

developed by PSE&G will monitor the performancesof the SSIMs for the ~1if e of the plant. However, the NRC staff feels that the SSLM reliability program-is--

important enough to warrant continuing the program-as a license condition and-  :"

has recommended that PSE&G propose a license' amendmentf to paragraph 2.C. (5)'. _

Since PSE&G agrees-as to t_he importance of monitoring SSLMJreliability, the NRC recommendation is submitted herein. ,

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JUSTIFICATION-FOR THE CHANGE Since the NRC staf f has concluded that the original License ' Condition .2.C. (5) >

has been satisfied, it should be removed. However, as PSE&G and the NRC staff agree, the Bailey 862 SSLM reliability program is sufficiently.important'to warrant a license condition that ensures the program's continuation for the life of the Hope Creek plant. Therefore, a new license condition, as stated above, is appropriate.

PSE&G's current Bailey 862 SSLM reliability program, and the information from it, were found by the NRC to be acceptable and to-satisfy the original license condition, as stated in their November 15, 1990 letter. -This existing program; will be continued;for the life-of-the plant. In the interest of clarity, the_

PSE&G interpretation of the license condition program is as follows:- ,

reliability data vill consist of logging and trending SSLM failures discovered '

on installed SSLMs; failure characteristics will-consist of determination and  ;

documentation of failure effects on equipment performance of design functions. '

with emphasis on safety functions; root cause of failure will consist of determination of SSLM failure mode within the capabilities of plant test equipment and investigation of causes'for.any adverse trends in SSLH failure rates.

10CFR50.92 SIGNIFICANT HAZARDS CONSIDERATION ANALYSIS PSE&G has, pursuant to 10CFR50.92, reviewed-the proposed ~ amendment to determine whether our request involves a significant-hazards consideration. We have determined that:

The operation of Hope Creek Generating Station (HCGS) in'accordance with the.

proposed-change will not involve a significant increase in the probability or.

consequences of an accident previously evaluated.

The proposed amendment does not. involve'a physical or~ procedural change to any structure, component or system that affects the probability or consequences of-any. accident or. malfunction of equipment-importantLto safety previously evaluated in the Updated Final Safety Analysis Report- (UFSAR). The proposed

. changes will simply add a condition to the-license-that continues a monitoring program for the life of the plant.

This change is administrative in: nature and has no significant impact on the-probabilities-or consequences of any evaluated accident;or: malfunction of-safety important equipment.

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i The operation of Hope Creek Generating Station (HCGS) in accordance with the. ,

proposed chance will not create the possibility of a new or different kind of=

accident from_any previously evaluated z There are no physical changes to the plant or to the manner in which plant systems are operated involved in the proposed revision. The change mandates that an existing monitoring program continue. This_ change is administrative in nature; therefore, no new or different accident is created.

The operation of Hope Creek Generating Station (HCGS) in accordance with the proposed chance does not-involve a significant reduction in a margin of saf ety.

The continuation of a reliability monitoring program:for the life of the plant, therefore, this proposed administrative change, will enhance plant safety by-its' adoption. There would be no negative impact on any safety margin.

Conclusion:

Based upon the above, we have determined' that this proposed change does not involve a Significant Hazards Consideration.

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