ML19312C519
| ML19312C519 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/06/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Parker W DUKE POWER CO. |
| Shared Package | |
| ML19312C520 | List: |
| References | |
| NUDOCS 7912160082 | |
| Download: ML19312C519 (4) | |
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. - l The Caunission bas issued the ewelosed huondsents Nos. G9, W, and 55)for Licenses Nos. OPR-38. DPR-47 and DPR-55 for the Oconee Nuclear Stattee, Units Nos. 1, 2 and 3.
These amanhents consist of changes to the Station's cessen Technical Specifications and are in response to i
your request dated June 22, 1978.- Extensive changes have been made to your rogmest to meet regulatory requirements. These have been discussed with and agreed to by your staff. You were previously notified of these amendments by telephone on June 27, 1978, as confirmed by telecopy dated.
June 27,1978.
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These amanheats revise the Technical specification to permit on a one time hesis, conditional relief free the pouer reduct. fos requiremset of 5pecification 3.5.2.2.1 with aspect to the.isoperability of Red 6 of:' - ~
Group 4 of the Ocemee Nuclear Station, Unit No. ?, control rod system-from June 27, 1978 to July 1,1978.
In commeeties with this actica you are advised that surveillance need est be pw L - 2 on equipment that has been declared inoperable. Yoe arv
.also advised that this actica is conditioned en your comunitment contained
.in year letter of 4=e 23,1978. to shutdeum Oconee 2 for. repair of Red. s
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u You will note that the enclosed Safety Evaluation ' addresses your.fa llum' m
. to declare Rod 6 of Safety Group 4 to be inoperable per Specificatim 3.5.2.2.b.
We recognize that because you believed the rod to be capable of perfoming its assigned Safety Function, you may not have considered it to be inoperable. Nevertheless, because you had good reason to believe that the rod could not be esercised in the normal fashion, the rod should have been declared inoperable per the literal definition given in spect-fication 3.5.2.2.b.
Accordingly, you a n advised that in the future you should adhere literally to the definitions of inoperability as set forth 1
.in the Technical Specifications. Yew are fWrther advised that should
. ou desire to de so, you may schai! for our nyiew a request fbr modif1-?c' ?
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' cation of the Station's Technical 5,.scifications to clarify the definitions of rod inoperability.
1 We note that this ifcensing action' sight have been avoided. had the Standard
-Technical Specifications fbr Babcock and Wilcox-designed reactors been in force at the Oconee Station. In addition, because of the operating experi-ence that has gone into their development it is probable that adoption of Ue standard Technical Specifications at Oconee would eliminate the need for same licensing actions in the future. Accordingly. we urge you
.to seriously consider the advantages of adoption of the Standard Technical specifications' for the Oconee Station. Because of the interrelationships between various sections of the Standard Technical specifications, however, we de not favor, as a matter of policy, fragmentary or piecemeal adoption of selected portions of this document.
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Sincerely, t
'e E Robert W. Reid, Chief c
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Operating Reactors Branch 14 Division of Operating Reactors
Enclosures:
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Amendment No. G2,to DPR-38 2.
Amendment No. 69. to DPR-47 s
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Amendment No. 59~ to DPS.55 a
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-e You will nets that the enciesed safety Evaluation addresses'your failure
'ste declare Rod 6 of safety Group 4 to be inoperable per Specification ~
4 3.5.2.2.b.
We recep12e that because you believed the rod te be capable l
' L of perfoming its assigned safety function, you may not have considosed W
it to be inoperable.- Nevertheless, because you had good reason to believe
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l that'the red could not be esercised in the no$est fashion. the red should have been declared inoperable per the literal definition given in..
Specification 3.5.2.2.b.. Accordingly, you are advised that in the future cyou should e6ere literally to the definitions of inoperability as set forth in the Technical Specifications. You are further advised that..
endification of the Station'you any submit for our review a request for. s should you desire to da so, s Technical Spe:ificettens to clarify the definitions of red inoperability.
We note that'this licensing action might have been avoided, had the standard Technical Specifications for Babcock and Wilcox-designed reactors been in force at the Oconee Staties. In addition, because of the operating experience that has gene into their developasst, it is probable that adoption of the Standard Technical Specifications at Oconee would elini-nate the need for sans licensing actions in the fkture. M.wJingly, we urge you to seriously consider the advantages of adoption of the Standard Technical Specifications for the Oconee Station. Because of the interslationships between various sections of the Standard Technical
~ Specifications, however, we de not favor, as a matter of policy, frag-mentary or piecemeal adoption _of selectcd portions of this document.
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a Sincerely,
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Robert W. Reid, Chief Operating Reactors Branch f4 a
Division of Operating Reactors
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Enclosures:
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cc w/ enclosure (s):
Mr. William L. Porter Duke Power Company P. O. Box 2178 422 South Church Street Charlotte, North Carolina 28242 i
J. Michael McGarry, III, Esquire DeBevoise & Liberman 700 Shoreham Building 806-15th Street, NW.,
Washington, D.C.
20005 Oconee Public Library 201 South Spring Street Walhalla, Soutn Carolina 29691 l
Honorable James M. Phinney l
County Sucervisor of Oconee County Walhalla, South Carolina 29621 l
Chief, Energy Systems Analyses Branch (AW-459)
Office of Radiation Programs U. S. Environmental Protection Agency Room 645, East Tower 401 M S tree t, S. W.
Washington, D. C.
20460 U. S. Environmental Protection Agency Region IV Office ATTN-EIS COORDINATOR 345 Coutland Street, N. E.
Atlanta, Georgia 30308 cc w/ enclosures & incoming dtd:
6/22/78 Office of Intergovernmental Relations 116 West Jones Street Raleigh, North Carolina 27603 t
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