ML19340A172
| ML19340A172 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 03/22/1976 |
| From: | Parker W DUKE POWER CO. |
| To: | Rusche B Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19340A173 | List: |
| References | |
| NUDOCS 8001100657 | |
| Download: ML19340A172 (4) | |
Text
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REQUESTI"G PERMISSICN TO REMOVE THE REACTOR wcj w
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.a VESSELL SURVEILLiTCE CAPSULES AND PUSH RODS AT PRESENT TIME UNTIL END OF PRESENT FUEL CYCLE..
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s l-Mr. Benard C. Rusche
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Director of Nuclear Reactor Regulation l-comssen l
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Re: Oconee Unit 3 4-l Docket No. 50-287
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Dear Mr. Rusche:
My letter of March 16, 1976 reported that Duke Power Company had been appraised of damage to the reactor vessel surveillance holder tubes which had occurred in another Babcock and Wilcox reactor. A description was provided of an inspection of the Oconee 1 surveillance specimen tube holders, and it was stated that the following actions would be taken during Oconee 1, Cycle 3 operation:
1.
The' reactor vessel surveillance capsules and push rods will be removed.
2.
The reactor vessel surveillance holder tubes will be secured i
from motion by a spring loaded retaining device which will be
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loaded into the upper end of each holder tube.
l Requests for an exemption to the requirements of 10 CFR 50, Appendix H l
and a revision tio the Oconee Nuclear Station Technical Specifications were
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filed to permit this action.
In an effort to minimize the possibility of wear damage to the Oconee 3 reactor vessel surveillance specimen holder-tubes, the decision has been made to remove.the reactor vessel surveillance capsules and push rods at I -
the present time and, subsequently, to continue operation in a manner similar.to Oconee 1 until the end of the present fuel cycle.
An inspection of the' surveillance holder tubes will be conducted, similar in extent to L
chat performed on Oconee 1, and an evaluation will be performed to confirm their acceptability for operation for the remainder of the present fuel cycle.
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-3 "Mr. Benard C. Ruscha Pcga 2 March 22, 1976 l
Oconee 3, Cycle 1 has currently accumulated 0.96 full power years of exposure for an equivalent capsule irradiation of 2.29 effective full power years, since the capsule receives 2.4 times the exposure of the inside \\ wall thickness (kt) location of the reactor vessel beltline.
Since available Oconee 3, Cycle 1 reactivity will allow operation for a maximum of approximately 486 EFPD (1.33_EFPY), there is ample margin between the present capsule irradiation of 2.29 EFPY and the maximum achievable exposure at t.he kt reactor vessel beltline irradiation at the end of Cycle 1.
In accordance with Technical Specification 4.2.9, a type
-B capsule removed from Oconee 3 during the present outage will be analyzed as part of the Reactor Vessel Surveillance Program.
l Pursuant to 10 CFR 50, 550.12, an exemption from the requirements of 10 CFR 50, Appendix H, Section II.C.2 is requested to permit the continued operation of Oconee 3, Cycle I with the reactor vessel surveillance specimens removed from the reactor vessel.
It is also requested, pursuant to 10 CFR 50, 550.90, that the Oconee Nuclear Station Technical Specifications be revised to indicate that the specimens will l
be removed from the reactor vessel for the remainder of Cycle 1 operation l
and that the surveillance withdrawal schedule will be revised prior to l
Cycle 2 operation. The attached proposed Technical Specification replacement page shows this change.
It is considered that the operation, for the duration l
of this fuel cycle, with the reactor vessel surveillance specimens removed l
will not be inimical to the health and safety of the public.
Oconee 3 is scheduled to resume operation on April 5,1976 following removal of the surveillance capsules.
It is requested that this request be proved no later than April 2, 1976.
ry truly yours, l
Guw. n. L I
William O. Parker, Jr.
MST:mmb l
Attachment l
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- 'Mr. Benard C. Rusch 2 Pega 3 March 22, 1976 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 Technical Specifications, Appendix A to Facility Operating Licenses DPR-38, DPR-47 and DPR-55; and that all statements and matters set forth therein are true and correct to the best
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of his knowledge.
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William O. Parker, Jr., Wite President ATTEST Ak
~J Ddrothea Stroupe Assistant Secretary Subscribed and sworn to before me this 22nd day of March 1976.
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