ML20070R505

From kanterella
Jump to navigation Jump to search
Forwards TS Change Request 218 to License DPR-16,revising TS Sections 3.1 & 4.1 for Protective Instrumentation.Ge Repts MDE-98-0485,Rev 1 & RE-004 Also Encl in Support of Proposed Changes.Rept MDE-98-0485,Rev 1 Withheld (Ref 10CFR2.790)
ML20070R505
Person / Time
Site: Oyster Creek
Issue date: 05/12/1994
From: J. J. Barton
GENERAL PUBLIC UTILITIES CORP.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML19304C150 List:
References
C321-94-2075, NUDOCS 9405200237
Download: ML20070R505 (2)


Text

GPU Nuclear Corporation

. Nuclear o

en:r888 Forked River, New Jersey 08731-o388 609 971-4000 Writer's Direct Dial Number:

C321-94-2075 May 12, 1994 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 Facility Operating License No. DPR-16 Technical Specification Change Request No. 218 Pursuant to 10 CFR 50.90, GPU Nuclear Corporation (GPUN), operator of the Oyster Creek Nuclear Generating Station (OCNGS), Facility Operating Liceast No. DPR-16, requests a change to Appendix A of that license.

The proposed Technical Specification changes contained herein are revisions to J +

Technical Specification Sections 3.1 and 4.1 for Protective Instrumentation, the associated bases, and tables to increase the surveillance test intervals (STIs) and add allowable out-of-service times (A0Ts). All proposed STI and c A0T changes are in accordance with General Electric Company Licensing Topical Reports (LTRs) which have been previously reviewed and apprcved by the NRC staff. Also, A0Ts are clarified in accordance with the most recently approved RWR Owners' Group letters which were used in the development of NUREG 1433

" Standard Technical Specifications, General Electric Plants, BWR/4." The Technical Specification changes will permit specified Channel Tests to be conducted quarterly rather than weekly or monthly. This amendment will enhance operational safety by reducing 1) the potential for inadvertent plant scrams, 2) excessive test cycles on equipment and 3) the diversion of plant personnel and resources on unnecessary testing.

Two additional technical changes are proposed. The first change involves extending the Channel Calibration interval for APRM Scram instrumentation from weekly to quarterly. GPUN has evaluated the effect of drift on the setpoint over the longer interval for this instrumentation and found it to be acceptable. The second change would add a quarterly Channel Calibration requirement for High Drywell Pressure (for Core Cooling) and Turbine Trip Scram instrumentation. This would be a new requirement not currently incorporated in the Technical Specifications.

Editorial changes have been incorporated in Instrumentation Sections 3.1 and 4.1 to provide clarity and consistency. These items are editorial only and do '

not alter the meaning or intent of any requirements. Examples of editorial ,

20o03 nRs2ggg gqgp ,7p A

i e

GPU Nuclear Corporabon is a subscary of General Pubnc Ubhbes Corporabon Q [

6%9 Y . & M , , $/'

C321 2075 Page 2 changes are: 1) capitalize definitions where used 2) punctuation and grammatical corrections, 3) ensuring consistency in STI nomenclature and 4) reformat of tables. A table note and its associated footnote were deleted which involved a 1985 licensing condition which is no longer applicable.

Also, Section 3.1 and 4.1 do not reflect proposed changes in Technical Specification Change Request No. 214 dated April 6, 1994.

Included in this license amendment request are the required plant-specific evaluations by General Electric in support of the proposed changes.

Information contained in the Reactor Protection System plant-specific report is considered by General Electric to be proprietary and an affidavit to that effect is enclosed. Pursuant to 10 CFR 2.790, it is requested that the proprietary information contained in this report be withheld from public disclosure.

This license amendment request has been reviewed in accordance with Section 6.5 of the OCNGS Technical Specifications, and using the standards in 10 CFR 50.92 we have concluded that the proposed changes do not constitute a significant hazards consideration. Assuming approval, please issue a license amendment which will be effective upon issuance and implemented within 90 days of issuance. This permits appropriate procedural / program revisions and training necessary to implement proposed changes.

We consider this license amendment request to be a Cost Beneficial Licensing Action (CBLA) which will result in a savings of $1.1 million for the duration of the current license. This estimate is based upon projected man-hour savings from fewer surveillance tests. Additional benefits will accrue from a reduction in occupational exposure, less equipment degradation from testing and a lower probability of inadvertent scrams. In addition, we anticipate improved flexibility in scheduling outage work. Since we consider this request a CBLA of high priority, please apply the appropriate resources to allow issuance by July 1994. This will also allow sufficient time to integrate the revised instrument surveillance testing frrauencies into the upcoming 15R outage schedule.

Pursuant to 10 CFR 50.91 (b) (1), a copy of this change request has been sent to the State of New Jersey Department of Environmental Protection.

inc rely

(

(N J. J Barton Vi:e ' resident and Director ster Creek cc: Administrator, NRC Region I NRC Senior Resident Inspector, Oyster Creek Oyster Creek NRC Project Manager l