ML19312B919
| ML19312B919 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/21/1973 |
| From: | Thies A DUKE POWER CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML19312B920 | List: |
| References | |
| NUDOCS 7911270711 | |
| Download: ML19312B919 (3) | |
Text
AEC D M IBUTION FOR PART 50 DOCKET MA7 TRIAL 8395 (TDiPORARY FORM)
CONTROL NO:
a FILE:
FROM:
DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Duke Power Company Charlotte, N.C. 28201 "r. A.C. Thien 11-21-73 11-23-73 X
l TO:
ORIG CC OTHER SENT AEC PDR YXX A. Gianbusso 3 signed SENT LOCAL PDR xvx CLASS UNCLASS PROP INFO INPUT NO CYS REC'D DOCKET NO:
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40 270 DESCRIPTION:
ENCLOSURES:
Ler notarized 11-21-73, trans the following...
Renuest for change to tech specs consist of replace e
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DuxE POWER' COMPANY Powza Curr.nneo 4aa SouTu Caunca Srazzr, CuAntarrz,N. C. asaca A. C. THits P.O. Box as7e semion vecs Passicsis?
PRODUC?lom AND T.eanseessseDes November 21, 1973
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8g Mr. Angelo Giambusso
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Deputy Director for Reactor Projects h
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Oconee Units 1 d2 Docket No 9 and -270
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Dear Mr. Giambusso:
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K/5-The Oconee Nuclear Station Technical Specifications, Appendix A to F 3,s \\
Operating Licenses DPR-38 and DPR-47, specify that the turbine bypass system shall have four valves operable, except that one valve may be removed from service for maintenance for a period not to exceed 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
(Technical Specification 3.4.3)
It is requested that this technical specification be deleted since the capability to remove decay heat from the reactor core is assured by Technical Specification 3.4.2, which requires the 16 steam system safety valves to be operable. Additional capability for decay heat removal is assured by manually-operated steam relief valves and manual operability of the turbine bypass valves.
Furthermore, the deletion of Technical Specificatica 3.4.3 will facilitate turbine testing since this test requires the four turbine bypass valves be isolated.
Section 7.2.3.3.4 of the Oconee FSAR states that the combined actions of the control system and the turbine bypass valves permit a 40 percent load rejection without main steam safety valve action.
Section 14.1.2.8.2 of the Oconee FSAR states that with unit operation with 1 percent defective fuel and 1 gpm steam generator tube leakage, the total integrated thyroid dose is 0.8 millirem at the one mile exclusion distance due to main steam relief following a loss of load from 100 percent power.
The dose to the thyroid could not be increased by more than 40 percent or 1.12 millirem without turbine bypass system actuation.
The turbine bypass system will normally be operable during plant operation; however, there is no need to require its availability in the Technical Specifications. Decay heat removal capability is assured by other means, and the additional contribution to the dose at the site boundary for loss of load considerations when operating without the turbine bypass system is negligible.
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Mr. Angelo Giambusso Page 2 November 21, 1973 Please find attached replacement pages for Technical Specification 3.4 which reflect the requested change.
Since turbine testing for Cconee Unit 1 is scheduled to begin December 1, 1973, your prompt consideration of this chcage is requested.
Very truly yours, A. C. Thies A. C. THIES, being duly sworn, states that he is Senior Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Atomic Energy Commission this request for amendment of the Oconee Nuclear Station Technical Specifications, Appendix A to Facility Operating Licenses DPR-38 and DPR-47; and that all statements and matters set forth therein are true and correct to the best of his knowledge.
A. C. Thies, denior Vice President AITEST:
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_ John C. Goodmah,.fr.
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Assistant Secretary Subscribed and sworn to before me this 21st day of November, 1973.
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Notary Public My Commission Expires:
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