LR-N970218, Submits 1996 Summary of Revised Regulatory Commitments

Submits 1996 Summary of Revised Regulatory Commitments

ML20138C281
Person / Time
Site:	Hope Creek
Issue date:	04/22/1997
From:	Eric Simpson Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LR-N970218, NUDOCS 9704300081
Download: ML20138C281 (2)

Text

- . --

4 4,

Pubhc Serwce Elecuc aM Gas Company E. C. Simpson P.O. Box 236, Hancccks Bridge, NJ 08038 609 4 39-1700 w .n~.--w ,

Public Service APR Electric 22 and Gas CompNa LR-N970218 United States Nuclear Regulatory Commission Document Control Desk

, Washington, DC 20555 1996

SUMMARY

OF REVISED REGULATORY COMMITMENTS HOPE CREEK GENERATING STATION EACILITY OPERATING LICENSE NPF-57 DOCKET NO. 50-354

~

Gentlemen:

In accordance with the Nuclear Energy Institute (NEI) process for managing NRC commitments and associated NRC notification, this correspondence is being submitted as the annual summary of changes for those commitments with initial due dates between January 1 and December 31, 1996. The following information is provided regarding the changed commitments and their source documents.

LER 354/95-020-01, entitled " Automatic Actuation of the High Pressure Coolant Injection System's Suction Path Swapover Engineered Safety Feature", Corrective Action #7 states that potential design changes are being evaluated to minimize nitrogen leakage from the drywell due to the Primary Containment Instrument Gas (PCIG) system and will be implemented during a PCIG system outage in 1996. Replacement of the system's moisture separators was the resultant design change. The implementation of this design change was extended into March 1997 due to fabrication and vendor difficulties. This design change has since been implemented.

LER 354/95-037-00, entitled "Both Loops of Safety Auxiliaries Cooling Syster (SACS) Inoperable", states that "The system operating and Ourveillance procedures for six risk significant systems will be reviewed to validate that the key design basis operating limits are incorporated. This validation will be completed by December 31, 1996. The results of this validation will be reviewed to determine if the scope of the review should be expanded." The actions in this commitment are captured in the actions and commitments discussed in PSE&G's response, dated #

I 9704300001 970422 PDR ADOCK 05000354 P PDR,,  ; W Ol ll I.l..ll llI.ll.Illi . ll O.-, _ .

i

1. 1. APR 221997 1 Document Control Desk LR-N970218 be expanded." The actions in this commitment are captured in the actions and. commitments discussed in PSE&G's response, dated February 11, 1997, to the NRC's " Request for Information Pursuant - .

to 10CFR50.54(f) Regarding Adequacy and Availability of Design Bases Information."

LER 354/96-006-01, entitled " Incorrect Installation of Backdraft Isolation Dampers Resulted in Plant Operation Outside of the Design Basis" states, "All hands meetings will be conducted by August-1, 1996 to discuss the backdraft damper issue and reiterate the-importance of operation within the Design and Licensing Basis. The meeting will include a discussion of actions to be taken upon discovery of a condition contrary to the Design and Licensing basis." This action was changed to an article in a site-wide newsletter instead of conducting all hands meetings. The newsletter article was published on June 28, 1996.

NLR-N90021 is the Salem and Hope Creek Generating Stations' response to NRC Generic Letter 89-13, entitled " Service Water System Problems Affecting Safety Related Equipment." Attachment 3 to NLR-N90021 includes the Hope Creek specific commitments _to GL 89-13. Item 2 in attachment 3 states, " Hope Creek is planning to conduct an annual test between March and May." The annual test referred to in this commitment is the heat exchanger  ;

performance test c;f the Safety Auxiliary Cooling System (SACS)  !

heat exchangers. This commitment has been changed to performing j the testing annually, but not limited to the "between March and May" time frame. Spring detritus releases in the Delaware River l and weather conditions are factors that resulted in this change.  !

This change was not applicable to the Salem Generating Station, l Should you have any questions regarding this information, please contact us. I l

I Sincerely, I 7

/ ,

I l

+

96-4933

~

s< Document Control Desk -3 APR 221587 LR-N970218 C Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. D. Jaffe, Licensing Project Manager - HC U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. R. Summers (X24)

USNRC Senior Resident Inspector - HC Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 i

l l

l l

l