ML20136D009

Revised Application for Amend to License DPR-16,revising Tech Spec Change Request 141 to Incorporate Applicable Procedures to Verify Instrument Communication W/Reactor Vessel

ML20136D009
Person / Time
Site:	Oyster Creek
Issue date:	11/16/1985
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Zwolinski J NRC
Shared Package
ML20136D013	List: ML20136D009 ML20136D052
References
NUDOCS 8511210208
Download: ML20136D009 (3)

Text

e GPU Nuclear Mg g7 P.O. Box 388 Forked River, New Jersey 08731 609-693-6000 Writer's Direct Dial Number November 16, 1985 Mr. John A. Zwolinski Chief BWR Project Directorate No. I U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 License NO. DPR-16 Technical Specification Change Request (TSCR) No. 141 Based on a discussion with NRC staff management on November 15, 1985, GPU Nuclear is proposing an amendment to TSCR 141 (ammended pages enclosed).

Because concern remains in not having positive assurance of instrument communication with reactor level differential pressure, TSCR 141 provisions are proposed only until the conclusion of outage 11R. In addition, an added level of administrative control on verifying proper lineup will be provided during the time that TSCR 141 conditions will be in effect.

It is understood that the NRC desires more information in reviewing and comparing the modification with General Design Criteria (GDC) 21. GPU Nuclear will either develop and propose to the staff an alternate design to be implemented during the 11R outage or justify the existing instrument configuration. Details of this evaluation will be submitted to you no later than the commencement of the 11R outage. In addition, the company will meet with members of your staff, on a mutually convenient schedule to discuss the evaluation.

During the period of operation wherein TSCR 141 as ammended is in effect, GPU Nuclear will report the loss of communication with the Reactor Pressure Vessel of any of the non-indicating reactor water level instruments immediately (within one hour) to the NRC Operations Center.

The details of an added process to assure instrument communication is provided in Attachment I. Our procedures will be modified to adopt this

" valving-in-verification" at the next scheduled surveillance for each Instrument following Oyster Creek's return to service from the 10M outage.

1 0511210200 851116 19 i F DR ADOCK 0000 I \\

GPU Nuclear is a part of the General Pubhc Uhhties System

f s' t-In the event that any comments or questions arise, please contact Mr. Drew Holland of my-staff.

Very truly yours, Vice President and Director Oyster Creek PBF/DH/kal(0166X)

Enclosures cc: Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Mr. Jack N. Donohew, Jr.

U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Phillips Bldg.

Bethesda, MD 20014 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, New Jersey 08731

e. ,

Mr. John A. Zwolinski, Chief U.S. Nuclear Regulatory Commission ATTACHMENT 1 .

t The following " valve-in" operation for each level instrument will be incorporated in applicable procedures to verify communication with the reactor vessel. The process will consist of valving-in the reference leg such that the corresponding water level alarm in the Control Room actuates. This confirms communication of the instrument reference leg with the reactor vessel. The variable leg will then be valved-in clearing the alarm. This confirms ,

communication between the variable leg and the reactor vessel. ,.

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