ML19209B137
| ML19209B137 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 10/03/1979 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19209B138 | List: |
| References | |
| TASK-05-06, TASK-5-6, TASK-RR NUDOCS 7910090219 | |
| Download: ML19209B137 (2) | |
Text
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Jersey Central Power & Light Company N.[
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j Morristown, New Jersey 07960 (201)455-8230 October 3, 1979 Director of Nuclear Reactor Regulation Nuclear Regulatory Comission Washington, D. C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Technical Specification Change Request No. 77 Fracture Toughness Requiremenu Enclosed is three originals and fifty-seven conformed copies of Technical Specification Change Request No. 77 which, when approved, will revise existing fracture toughness requirements so that they will conform with the requirements imposed by 10 CFR 50. This Change Request revises and supercedes Technical Specification Change Request No. 33 on the same subject submitted to the former U. S. Atanic Energy Comission on January 9,1975.
The design bases and analysis methods for the reactor vessel pressure / temperature limits of the proposed Technical Specifications are the same as for the earlier pressure / temperature limits previously submitted in Supplement No. 6, Addendum No. 3 to the Application for a Full Term Operating License forwarded Le the former U. S. Atomic Energy Commission on April 8,1974, except for the followinc:
1.
'Ihe 1)77 edition of the ASME,Section III Code was used; 2.
The 1978-79 edition of 10 CFR 50, Appendix G was used; 3
Fl'aence was calculated at the 1/4T (one-quarter wall thick-noss) location for ten effective full power years of operation.
'nis was accomplished by multiplying the fluence values on the inside wall surface of the reactor vessel by 0.75 as recomended by the General Electric Company.
4.
Irradiation damage curves for the worst case copper and phosphorus content of the reactor vessel wall material provided in Regulatory Guide 1.99, " Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials,"
dated April, 1977, were used.
This Technical Specification Change Request has been reviewed and approved by the Station Manager, the Plant Operations Review Comittee, and an Independent Safety Review Group in accordance with Section 6.5 of the Oyster 1112 287 C
7910000 P
Jersey Central Power & Ught Company is a Member of the General Pubhc Utihti ystem
Creek Technical Specifications.
Since this submittal is a revision to a previously submitted Technical Specification Change Request, we have determined that no fee is necessary.
Very truly yours, Ivan R. Finfr k,
Vice Presid la 11i2 288
JERSEY CENTRAL POWER 6 LIGllT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION 9
Provisional Operating License No. DPR-16 Technical Specification Change Request No. 77 Docket No. S0-219 s
Applicant submits, by this Technical Specification Change Request No. 77 to the Oyster Creek Nuclear Generating Station Technical Specifications, changes to the fracture toughness requirements in Section 3.3.
JERSEY CENTRAL POWER 6 LIGIIT COMPANY BY:
Vice Vre dent STATE OF NEW JERSEY COUNTY OF MORRIS Sworn and subscribed to before me this,
,f day of 1979.
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' Notary Public 1112 289