ML19312B873
| ML19312B873 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/10/1977 |
| From: | Parker W DUKE POWER CO. |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19312B874 | List: |
| References | |
| NUDOCS 7911250070 | |
| Download: ML19312B873 (4) | |
Text
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NT C Feau.195 U.S. NUCLEAR REGULATonY COMMISSION NRC DISTRIBUTION FOR PART 50 DOCKET M ATERIAL TO: Mr. B.C. Rusche FROM: Duke Power Company OATE OF OCCUMENT 3-10-77
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Charlotte, N.C.
28242 Wm. O. Parker, Jr.
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,3 sl 6,>o rd EORICINAL gU NC L ASSl FIE D o co-oescRIPTION LCr notarized 3-10-77 requesting ENCLOSURE Proposed replacement Tech Spec pages..
for exemptions & revisions from the provisio 1s of 10CFR50, Appendix H which will permit (2P)
,,,the reinstitution of the Oconee surveillance j
program....& trans the following:
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g Mr. Benard C. Rusche, Director
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Re: Oconee Nuclear Station U
Docket Nos. 50-269, -270, -287 g
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Dear Mr. Rusche:
On March 26, June 25 and April 16, 1976, the Commission issued exemptions from the provisions of 10CFR50, Appendix H, which authorized operation of the Oconee Units 1, 2 and 3, respectively for the duration of their current fuel cycles. These exemptions permitted operation with reactor vessel material surveillance capsules removed from their reactor vessels.
In addition, on October 23, 1976, the Commission issued another exemption for Oconee 3 which authorized operation for one additional fuel cycle with the reactor vessel material surveillance capsules removed from the Oconu 3 reactor vessel.
In your letter of November 16, 1976, you requested that a course of action be identified for the Oconee units which would reinstitute the reactor surveillance program.
If plans did not involve resinstallation of the capsules in the Oconee reactors, information requested by Enclosure 1 to your letter was to be provided. Additionally, it was requested that infor-mation be submitted on plans to satisfy the fracture toughness requirements of Appendix G to 10CFR50, possibly through the use of data from the surveil-lance programs at several other reactors.
In letters dated December 9, 1976 and January 14, 1977, it was stated that it was our intention to continue the irradiation of the Oconee surveillance capsules in Florida Power Corporation's Crystal River, Unit 3 reactor vessel.
An agreement has been formalized with Florida Power Corporation to this end.
Additionally, we have participated in the B&W user's group effort to support additional surveillance capsule irradiation at other operating and test reactors in veder to satisfy the fracture toughness requirements of Appendix G to 10CFR50.
Specific descriptions of the Oconee surveillance program were provided in the responses to questions in our January 4, 1977 letter.
As stated in the response to Question 1, B&W has developed a combined pro-gram for irradiating surveillance specimens of welds of interest between operating reactors and test reactors.
This synergistic program will offer protection against an extended outage of a host reactor.
Redundancy will be incorporated in the combined program by ensuring that most of the repre-sentative welds to be irradiated in operating reactors will also be irradi-ated in test reactors.
The fluence levels in these test reactors will 390 ] foO 3
Mr. Benard C. Rue-'o P2g2 2 March'10, 1977 ensure that the surveillance material will remain ahead of the corres-ponding reactor vessel beltline region. Due to the variety of sources of information which can be useful for the Oconee reactor vessels, a rigid withdrawal schedule for the Oconee surveillance capsules is not considered prudent.
Rather, a flexible program which will assure the availability of data needed to update Specification 3.1.2 would be appropriate.
Pursuant to 10CFR50, 550.90 and 10CFR50, 550.12, Technical Specification revisions and exemptions from the provisions of 10CFR50, Appendix H are requested which will permit the reinstitution of the Oconee surveillance pro 3 ram.
The proposed Technical Specification revision is indicated on the attached replacement page.
This change permits the irradiation of surveillance specimens representative of materials present in the reactor vessel beltline region in Oconee or similar power reactors or in test reactors. The specific withdrawal schedule has been deleted in favor of a general requirement for obtaining results necessary for updating Techni-cal Specification 3.1.2.
Annual reviews shall be conducted to assure the adequacy of the program.
It is considered that this program meets the intent of 10CFR50, Appendix H, in that fracture toughness test data will be obtained from material specimens shi,ch will permit the determination of the conditions under which the reactor vessels can be operated, with adequate margins of safety against fracture throughout its life.
Ver truly yours, u Ei 20. p N
William O. Parker, Jr MST:gh Attachment
Mr. B; nard C. Runcha
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Peg 2 3 March 10, 1977' WILLIAM 0. PARKER, JR., being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this request for amendment of the Oconee Nuclear Station Facility Operating Licenses DPR-38, DPR-47, and DPR-SS; and that all statements and matters set forth therein are tr e and correct to the best of his knowledge.
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William O. Parker, Jr., Side President Subscri'ed and sworn to before me this 10th day of March, 1977.
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' bi 1, y Notary Public (Notarial Seal)
My Commission Expires:
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