RC-95-0283, Application for Amend to License NPF-12,consisting of TS Change TSP 950010,allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days

Application for Amend to License NPF-12,consisting of TS Change TSP 950010,allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days

ML20094N884
Person / Time
Site:	Summer
Issue date:	11/21/1995
From:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
To:	Stephen Dembek NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20094N887	List: ML20094N888 RC-95-0283, Application for Amend to License NPF-12,consisting of TS Change TSP 950010,allowing One Time Extension of AOT Specified in TS 3/4.5.2 for Each RHR Train from 72 H to 7 Days
References
RC-95-0283, RC-95-283, NUDOCS 9511280214
Download: ML20094N884 (4)

Text

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. South CIrrlins Electric & Gr.s Comptny GIry J.Trylor I '

+ - P.O. Box 88 Vice President ,

' *4 Jenkinsville, SC 29065 Nuclear Operations (803) 345-4344 Asamacam November 21,1995 RC-95-0283 Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. Stephen Dembek Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS)

DOCKET NO.50/395 OPERATING LICENSE NO.NPF-12 TECHNICAL SPECIFICATION CHANGE-TSP 950010 ONE TIME EXTENSION OF ALLOWABLE OUTAGE TIME FOR RHR TRAINS South Carolina Electric & Gas Compan (SCE&G), acting for itself and as agent for South Carolina Public Service Autho , hereby requests an amendment to the Virgil C. Summer Nuclear Station'(V NS) Technical Specifications (TS). This change is being submitted pursuant to 10 CFR 50.90. This proposed change will allow a one time extension of the allowable outage time specified in TS 3/4.5.2 for each residual heat removal (RHR) train from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days.

A'similar request for an allowed outage extension was approved by the NRC on May 31,1994

- (CDF) fo' r VCSNS for Georgia Power's is the same as thePlant Vogtle.

increase notedThe increase by Vogtle m Core in their Damage Frequency request.

The one time extension is necessary to allow maintenance and modification to the RHR system while the plant is in Mode 1. Performance of the maintenance and modification at power will result in a significant reduction in personnel radiation exposure compared to performing it after plant shutdown. Also, performance of the maintenance and modification at power will increase the availabihty of both trains of RHR during refueling.

. The maintenance involves the replacement of the RHR heat exchanger (HX) head gasket and is necessary to eliminate minor leakage from the RIiR HXs. The r- modification is to be performed on the suction header valve to each RHR pump and involves drilling a hole in the valve disk to provide additional assurance against pressure locking. The modification is being implemented to address.IEN 95-14,

. Susceptibility of Containment Sump Recirculation Valves to Pressure Locking".

. The time requested is based on experience gained from previous repair evolutions on the components, The maintenance for each RHR HX and modification to the suction header velve of the same train will be worked concurrently. The redundant RHR train will be maintained operable during the time of the maintenance and modification.

I r r

-9511 h4 95112195 P_ ._._.__ a en _ %g

Document Control D:sk

. TSP 950010 RC-95-0283 -

Page 2 of 3 An evaluation of the effects of the one time increase in the allowable outage time on the calculated core damage frequency (CDF) has been performed. The evaluation was based on the IPE model which has been updated to include ?lant modifications and equipment history changes through Cycle 7. The PRA modeL has a CDF of 1.006E-4 per reactor year. The calculation mdicated that the cumulative effect ofincreasing the allowable outage time from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 7 days would change the CDF from 1.024E-4 to 1.050E-4 per reactor year for the maintenance and modification for both trains of RHR.

The TS change request (TSCR) is contained in the following attachments:

AttachmentI Description ofChanges Chart Marked-up Technical Specification Pages Revised Technical Specification Pages AttachmentII Description of Amendment Request and the Supporting Safety Evaluation i AttachmentIII Description of Amendment Request and the Associated No Significant Hazards Evaluation This proposed change has been reviewed and approved by both the Plant Safety Review Committee and the Nuclear Safety Feview Committee.

SCE&G requests approval of this change to the VCSNS TS by December 31,1995.

This will allow the maintenance and modification for at least one train of RHR to be implemented prior to our ninth refueling outage (RF9). The redundant train maintenance and modification is also being considered for implementation prior to RF9, but,if necessary, the maintenance may be deferred until prior to RF10 with the valve modification performed during RF9.

I declare that these statements and matters set forth herein are true and correct to the best of my knowledge, information and belief.

Should,you have any questions, please call Mr. Jim Turkett at (803) 345-4047 at your convemence.

Very truly yours,

, Gary . yf6r JT/GJT/dr Attachments (3) c: See page 3 of 3 NUCLEAR EXCELLENCE - A SUMMER TRADITION!

Documtnt Control Desk TSP 950010 RC-95-0283 -

Page 3 of 3 c: J. L. Skolds (w/o Attachments)

O. W. Dixon R. R. Mahan (w/o Attachments)

R. J. White S. D. Ebneter NRC ResidentInspector

' J.M.

B.K.Knotts Jr.

Batavia K. R. Jackson Central File System RTS(TSP 950d10)

File (813.20)

STATE OF SOUTHCAROLINA  :

TO WIT :

COUNTY OF FAIRFIELD  :

I hereby certify that on the .2/ 'I day of/2 w ,b l9 94before me, the subscriber, a Notary Pubhc of the State of South Carolina, personally appeared Gary J. Taylor, being duly sworn, and states that he is Vice President, Nuclear Operations of the South Carolina Electric & Gas Company, a corporation of the State of South Carolina, that he provides the foregoing response for the purposes therein set forth, that the statements made are true and correct to the best of his knowled; l belief, and that he was authorized to provide the response on be.;e, information, and aalfofsaid i Corporation.

WITNESS my Hand and NotarialSeal 28/ __

gNotary Public My Commission Expires MyCommission Exp!res Ju!y13,2005 -

l Date I l

i NUCLEAR EXCELLENCE - A SUMMER TRADITION!

Document Control Desk Attachment I TSP 950010 RC-95-0283 -

Page 1 of1 -

SCE&G -- Explanation of Changes  !

Affected Bar Description of Chance PAGE Reason for Chance Section f_

l 3/4 5-3 3.5.2 1 Added Asterisk (*). Toidentify applicable footnote. l 3.5.2 2 Added Asterisk (*). Toidentify applicable footnote.

Action a.

Footnote 3 Added Footnote. To allow extension for maintenance to RHR heat exchangers and modification to RHR pump suction header valves.

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