RC-98-0185, Forwards non-proprietary Trs,Including Rev 0 to WCAP-15101, Analysis of Capsule W from Sce&G VC Summer Unit 1 Rv Radiation Surveillance Program & Rev 0 to WCAP-15103, Evaluation of PTS for VC Summer Unit 1

Forwards non-proprietary Trs,Including Rev 0 to WCAP-15101, Analysis of Capsule W from Sce&G VC Summer Unit 1 Rv Radiation Surveillance Program & Rev 0 to WCAP-15103, Evaluation of PTS for VC Summer Unit 1

ML20154K774
Person / Time
Site:	Summer
Issue date:	10/09/1998
From:	Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20154K776	List: ML20154K790 ML20154K804 RC-98-0185, Forwards non-proprietary Trs,Including Rev 0 to WCAP-15101, Analysis of Capsule W from Sce&G VC Summer Unit 1 Rv Radiation Surveillance Program & Rev 0 to WCAP-15103, Evaluation of PTS for VC Summer Unit 1
References
RC-98-0185, RC-98-185, NUDOCS 9810190019
Download: ML20154K774 (2)

Text

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October 9,1998 s

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gggg RC-98 0185 l A SCANA COMPANY

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$ 1; Document Control Desk l

. _ u U.S. Nuclear Regulatory Commission

'm Washington, D.C. 20555 1

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Gentlemen:

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Subject:

VIRGIL C. SUMMER NUCLEAR STATION

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DOCKET. NO. 50/395 1

e w ~ . .. OPERATING LICENSE NO. NPF-12 16spJlToyl"l REACTOR VESSEL RADIATION SURVEILLANCE PROGRAM

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' Enclosed is WCAP-15101, Revision 0, Analysis of Caosule W from the South a Carolina Electric & Gas Company V. C. Summer Unit 1 Reactor Vessel

, j Radiation Surveillance Proaram. as required by 10CFR50, Appendix H. This 9 . j report reflects the results of tests performed on Capsule W which was I

• ;% , I withdrawn from the reactor vessel during the tenth refueling outage at the

,,y , , Virgil C. Summer Nuclear Station (VCSNS). ,

Also enclosed is WCAP-15103, Revision 0, Evaluation of Pressurized JN th asina0emic& Gas (c Thermal Shock for V. C. Summer Unit 1 which included the results of the tests 7 hgilC. Saner Nudem Statim performed on Capsule W and has determined that the RTers values for all the il South Cardino :

, beltline materials in the VCSNS Unit 1 reactor vessel are below the screening i 290F/

l criteria of 270 F for plates, forgings or longitudinal welds and 300 F for x , circumferential welds at End of License (32 EFPY).

f 803.3414344 -

803.3415209.

'" " ' " A proposed surveillance capsule removal schedule is included for your review '/

and is contained in the report on page 7-1. The proposed revision to the

removal schedule is technically justified since the projected 32 EFPY fluence l f

for the reactor vessel beltline material is greater than the estimated fluence exposure of Capsule W.

"[ y" Additionally, per 10CFR50, Appendix G, WCAP-15101 has verified that an L upper shelf energy greater than 50 ft-lbs is expected throughout the life of the g;g vessel for all beltline materials.

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j 9810190019 981009 e< PDR ADOCK 05000395?

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] NUCLEAR EXCELLENCE- A SUMMER TRADITION!

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Document Control Desk RC-98-0185 Page 2 of 2 i

The existing heatup (Technical Specification Figure 3.4-2) and cooldown curves (Technical Specification Figure 3.4-3), are valid until the thirteenth effective full power year (EFPY). Prior to the thirteenth EFPY (Spring of 1999), a proposed amendment to the Technical Specifications will be submitted to update the heatup and cooldown curves, incorporating the test results of Capsule W.

Should you have any questions, please call Mr. Michael J. Zaccone at (803) 345-4328. I Very truly yours, I

'N s

A Gary aylo GJT/MJZ Enclosures (2) c: (Enclosures on file in NL&OE)

J. L. Skolds (w/o enclosures)

R. R. Mahan (w/o enclosures)

W. F. Conway R. J. White L.A.Reyes L. M. Padovan NRC Resident inspector J. B. Knotts, Jr.

NSRC DMS (RC-98-0133)

RTS (RR 5100)(w/o enclosures)

File (818.23-2) l 1

1 J

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