ML20107F210
| ML20107F210 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/26/1984 |
| From: | Fay C WISCONSIN ELECTRIC POWER CO. |
| To: | Harold Denton, John Miller Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20107F212 | List: |
| References | |
| TAC-56313, TAC-56314, NUDOCS 8411050349 | |
| Download: ML20107F210 (3) | |
Text
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Wisconsin Electnc eowca couesur 231 W. MICHIGAM, P.O. BOX 2046. MILWAUKEE, WI 53201 October 26, 1984 CERTIFIED MAIL Mr. H. R. Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D. C.
20555 Attention:
Mr. J. R. Miller, Chief Operating Reactors, Branch 3 Gentlemen:
DOCKET NOS. 50-266 AND 50-301 TECHNICAL SPECIFICATION CHANGE REQUEST NO. 100 AUXILIARY FEEDWATER PUMPS AND STEAM GENERATOR INSERVICE INSPECTION POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 In accordance with 10 CFR 50.59 (c), Wisconsin Electric Power Company hereby requests amendments to Facility Operating Licenses DPR-24 and DPR-27 for the Point Beach Nuclear Plant, Units 1 and 2, respectively.
The purpose of these license amendments is to incorporate changes into the Technical Specifications.
The proposed changes involve deletion of_a limiting condition for operation concerning the auxiliary feedwater system and clarification of the inservice inspection requirements for the steam generators.
On May 4, 1983 the Commission issued License Amendments 73 and 78 to the Point Beach licenses.
These amendments allowed temporary isolation of the shared motor-driven auxiliary feedwater pumps for a unit during period of startup, shutdown, and surveillance testing provided the turbine-driven auxiliary feedwater pumps were operable and capable of automatically delivering feedwater flow.
This change was necessary to meet the requirements of Specification 15.3.4 that all four auxiliary feedwater pumps normally be operable with no more than one of the pumps permitted to be out of service for a limited period of time.
In our application for these amendments dated March 24, 1984 we noted that we were studying hardware modi-fications to resolve NRC staff concerns regarding interpretations of auxiliary feedwater system operability and to provide automatic feedwater flow from the motor-driven auxiliary feedwater pumps under all circumstances.
Details of these modifications were submitted to you with our letter dated June 20, 1983.
Your letter dated September 15, 1983 concurred with our proposed modifications.
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2i jMri-H..R. Denton October 26, 1984-o On' July 6, 1984'we sent you a letter reporting that the
-modificationsEto the auxiliary.feedwater system motor-operated
-discharge valve: operating logic had.been completed.
As you know,
'this modification 'provides assurance that automatic initiation
~
lofLauxiliary.feedwater flow to an.affected unit's. steam generators
- will' occur even if the-motor-operated pump discharge valves are
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- initially ' closed. : We, -therefore, believe that the provisions
~
of' Specification 15.3.4.A.2.c are no longer necessary to permit temporary closingfof these discharge valves and that this specification"should'be deleted.
t
. The second series of changes in this amendmenth application L
' concerns Specification 15.4.~2.'A,
" Steam Generator Tube Inspection ll Requirements".,. Item 2.a of'this specification has oeen clarified to. indicate.that selection of one steam generator for inspection b
.is permissible._ Item 3'of this specification has been rewritten
- to acknowledge.that strict compliance with Appendix IV.to Section XI
~of the ASMEJCode would prohibit utilization of state-of-the-art inspection techniques not_yet recognized by the Code.
Item 7
~
'offthe specification is revised to acknowledge that reporting be
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in.accordance with 10 CFR 50.73.ii rather than the superseded LER
- reporting specification.-
We have also rewritten the basis for this 'section to make it consistent with the specifications and our
, current practices.
~
. Proposed Technical Specification pages, with the
' changes. discussed in this. application identified by margin bars, ara attached. 'We have also_ enclosed page 15.6.10-1 with a change to Item'3:of that page_to conform the specification to present
! terminology.- This change 1was requested by the NRC staff.
As required by/10 CFR 50.91, we-have examined these changes :to determine whether the proposed revisions constitute a significant hazards consideration as defined by 10 CFR 50.92.
.'In-' examining these changes we have_ considered the guidance previously provided by.the NRC in the. statement.of consideration published
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with this-rule at-48' Federal Register 14864.- For the change to l
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. Specification 15.3.4 we believe that deletion of this restriction
~ onstitutes relief _from an operating restriction that was imposed c
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because acceptable: operation.was not yet demonstrated.
The t
~ modifications discussed'in_our previous. correspondence and reported as;completeLin our letter dated July 16~ constitute demonstration of
' acceptable operation; therefore, this change does not constitute a
-significant hazards consideration.
'~
' The. changes to Specifications 15.4.2-and 15.6.10'are administrative: changes necessary to clarify the specifications and to(achieve consistency in reporting requirements.
Accordingly,
=these' changes also do not constitute a significant hazards
-consideration.
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k' Mr.
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R. Denton. October 26, 1984 Enclosed ~are three signed originals and forty copies of this amendments application and attachments.
Also enclosed is a check in the amount of $150 for the application fee specified by 10.CFR.170.12.
Please contact us if you have any questions concerning these proposed changes.
Very truly yours, scf Vice President-Nuclear Power C. W.
Fay
' Enclosures (Check No. 813438)
Copies to NRC Resident Inspector R. S. Cullen, PSCW Subscribed and sworn to before me this 29xJL day of October 1984.
I:f h 'Q.
w Notary Public, State of Wisconsin My Commission expires Ow /2198/.
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