ML19268B777

From kanterella
Jump to navigation Jump to search
Forwards Tech Spec Change Request 69 for App a to Provisional License DPR-16,for Section 3,1,3.6,4.6 & 6. Requests Incorporation of Tech Spec Changes One Year After Approval.Appropriate Fee & Certificate of Svc Encl
ML19268B777
Person / Time
Site: Oyster Creek
Issue date: 06/01/1979
From: Finfrock I
JERSEY CENTRAL POWER & LIGHT CO.
To:
Office of Nuclear Reactor Regulation
Shared Package
ML19268B778 List:
References
NUDOCS 7906070259
Download: ML19268B777 (2)


Text

% a m Jersey Central Pcwer & Light Company Madson Avenue at Punch Bowl Road Mornstown, New Jetsov 07960 (201)455 8200 June 1, 1979 Director of Nuclear Reactor Regulation United States Nuclear Regulatory Cmmission Washington, D. C. 20555

Dear Sir:

Subject:

Oyster Creek Nuclear Generating Station Docket !b. 50-219 Technical Specification Change Request No. 69 In accordance with 100FR50.59 and 10CFR50.90, Jersey Central Power &

Light Company, owner and operator of the Oyster Creek Nuclear Generating Station, Provisional Operating License No. DPR-16, requests changes to Appendix A of that license.

This Technical Specification Change Request will modify Sections 3.1, 3 6, 4.1, 4.6, and 6 of our Technical Specificctions to incorporate the requirements of 10CFR20, 10CFR50.34a, 10CFR50.36a, 10CFR50 Appendix I, and 40CFR190. These are being submitted as requested by Mr. Brian K. Grimes in his letter of November 15, 1978. This Technical Specification Change has been developed considering the guidcnce provided by drafts of NUREG-0473 and NUREG-0133 which were provided as enclosures to the letter from Mr. Grimes.

In addition, Mr. Ziemann requested in his letter of October 3,1978 that limiting conditions for operation and surveillance requirements for explosive gas monitoring be included in the Oyster Creek Technical Specifiestior.s for the Augmented Offgas System, which were submitted in May of 1978. In response to this letter, limiting conditions for operation and surveillance requirements on the Augmented Offgas bbnitoring System have been included in this submittal . In addition, it is requested that our license application of May 3,1978 be cancelled since all of the requirements of that application have been included in this submittal.

We have not included with these specifications the Offsite Dose Calculation Manual and Process Control Program. We feel this material is best included in plant procedures. Those procedures are developed, reviewed and approved in accordance with our Technical Specifications and are available for review by the NRC Office of Inspection and Enforcement. No regulatory requirement exists for the submission of those procedures to the NRC Office of Nuclear Reactor Regulation for review and approval.

Our proposed specifications do not include specifications dealing with 95005302 7906070A5%

Jersey Central Power & Light Company is a Member of the General Public Utilities System

i .

the solidification of liquid radioactive wastes. Solidification of wastes to meet the requirements of 10 CFR 20 and 10 CFR 71 is carried out in accordance with the plant procedures. We believe that is commensurate with the safety and environmental signficance of this issue.

40CFR141, the Safe Drinking Water Act, is not addressed by our specifications because Oyster Creek discharges to salt water (fernegat Bay).

Your mcdel technical specification titled "!brk I or II Containment" has not been included in our proposed specifications. Oyster Creek does not purge or vent the drywell through the Standby Gas Treatment System. Our Appendix I analysis assured that the drywell vent / purge was untreated. No regulatory requirement exists to vent and purge through the SGTS, which is designed for (mergency use.

Our proposed specfications do not address the subject of operability and use of liquid and gaseous radwaste treatment systems in the szme detail as your model specifications. We require that the equipment be maintained and operated as necessary to meet the design objectives and limiting conditions for operation of Appendix I. Conformance with the guidelines of Appendix I is a conclusive stuwing that 10CFR50.34a and 10CFR50.36a are being met. The detailed specifications that have been propased are beyond those necessary to meet the regulations.

This Technical Specification Change Request has been reviewed and approved by the Station Suparintendent, the Plant Operations Review Corrnittee, and an Independent Safety Review Group in accordance with Section 6.5 of the Oyster Creek Technical Specifications.

Due to changes in Facility Procedures, computer sof tware and potential hardware changes, it is requesed that these Technical Specification Changes not be incorporated into the Technical Specifications until one year after approval .

We have determined that this submittal is Class III per 10CFR170.22 and have enclosed a check for $4000 pursuant to that section.

Very truly yours, f .

9dMR) *.

Ivan R. Finf k, r.

Vice President 95005303