RC-17-0134, Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 1

Response to Request for Supplemental Information, License Amendment Request - LAR-15-01424; Implementation of WCAP-15376-P-A, Revision 1

ML17270A203
Person / Time
Site:	Summer
Issue date:	09/27/2017
From:	Lippard G South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
LAR-15-01424, RC-17-0134
Download: ML17270A203 (8)

Text

George A. Lippard Vice President, Nuclear Operations 803.345.4810 A SCANA COMPANY September 27, 2017 RC-17-0134 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Subject:

VIRGIL C. SUMMER NUCLEAR STATION, UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 LICENSE AMENDMENT REQUEST - LAR-15-01424 IMPLEMENTATION OF WCAP-15376-P-A, REVISION 1 RESPONSE TO REQUEST FOR SUPPLEMENTAL INFORMATION

Reference:

1. T. D. Gatlin, SCE&G, letter to Document Control Desk, NRC, "License Amendment Request - LAR-15-01424 Implementation of WCAP-15376-P-A, Revision 1 - 'Risk-Informed Assessment of the RTS and ESFAS Surveillance Test Intervals and Reactor Trip Breaker Test and Completion Times'," dated December 16, 2015 [ML15356A048]

2. S.A. Williams, NRC e-mail to B. Thompson, SCE&G, "V.C. Summer Nuclear Station, Unit 1 - TSTF-411 application TS page 3/4 3-37" Supplemental Information Needed to correct Typographical error, dated September 13, 2017 South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent for South Carolina Public Service Authority pursuant to 10 CFR 50.90, submitted License Amendment Request per Reference 1 concerning the implementation of WCAP-15376-P-A, Revision 1.

During NRC staff review of the Technical Specification (TS) pages provided with the application dated December 16, 2015 (Reference 1), NRC staff identified an administrative error in Table 4.3-2 on TS Page 3/4 3-37 (Reference 2). This submittal contains SCE&G's corrected TS page.

This letter does not contain any new regulatory commitments.

If there are any questions or if additional information is needed, please contact Bruce L.

Thompson at (803) 931-5042.

V. C. Summer Nuclear Station

• P. 0. Box 88

• Jenkinsville, South Carolina

• 29065

• F (803) 941-9776

• www.sceg.com

Document Control Desk CR-15-01424 RC-17-0134 Page 2 of 2 I certify under penalty of perjury that the foregoing is correct and true.

BD/GAL/hk Attachments: : Description of Technical Specification Administrative Error : Mark-Up Technical Specification Page Correcting the Administrative Error : Clean Copy of Technical Specification Page Correcting the Administrative Error c: K. B. Marsh S. A. Byrne J. B. Archie N. S. Cams J. H. Hamilton G. J. Lindamood W. M. Cherry C. Haney S. A. Williams NRC Resident Inspector K.M. Sutton S.E. Jenkins Paulette Ledbetter NSRC RTS (CR-15-01424)

Files (813.20)

PRSF (RC-17-0134)

Document Control Desk CR-15-01424 RC-17-0134 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ENCLOSURE 1 DESCRIPTION OF TECHNICAL SPECIFICATION ADMINISTRATIVE ERROR

Document Control Desk Enclosurel CR-15-01424 RC-17-0134 Page 2 of 2 1 Description of Typographical Error During NRC staff review of the Technical Specification (TS) pages provided with the application dated December 16, 2015 (Reference 1), NRC staff identified an administrative error in Table 4.3-2 Engineered Safety Feature Actuation System Instrumentation Surveillance Requirements on TS Page 3/4 3-37.

The administrative error is a duplicate line item in Table 4.3-2 Functional Unit 4.d. "Steam Flow in Two Steam Lines -- High Coincident with Tavg --Low-Low". Only one line is required to specify the surveillance requirements for Functional Unit 4.d. This error has been in the VCSNS TSs since the issuance of the facility operating license on August 6, 1982.

This request is specific to deleting the duplicate line in Table 4.3-2 Functional Unit 4.d on TS Page 3/4 3-37.

2. Corrections to the Affected TS Pages The Mark-Up of Technical Specification Page Correcting the Administrative Error is found in . The Clean Copy of Technical Specification Page Correcting the Administrative Error is found in Enclosure 3.

Document Control Desk CR-15-01424 RC-17-0134 Page 1of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ENCLOSURE 2 MARK-UP TECHNICAL SPECIFICATION PAGE CORRECTING THE ADMINISTRATIVE ERROR

TABLE 4.3-2 (Continued^

CO c

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION m SURVEILLANCE REQUIREMENTS 3J CI 2 TRIP H ANALOG ACTUATING MODES FOR CHANNEL DEVICE ACTUATION MASTER SLAVE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL LOGIC RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST ' TEST TEST TEST IS REQUIRED

4. STEAM LINE ISOLATION

a. Manual NA N.A. N.A. R N.A. N.A. N.A. 1,2, 3

b. Automatic Actuation Logic NA N.A. N.A. NA M(1) M(1) R(3) 1,2,3 and Actuation Relays

c. Reactor Building S R Q N.A. N.A. N.A. N.A. 1,2, 3 1 Pressure-High-2 V d, Steam Flow in Two Steam S R Q N.A. N.A. N.A. N.A. 1,2, 3

-vj Lines-High Coincident with Tavo-Low-Low © S 0SE Mi Remove duplicate line

e. Steam Line Pressure Low S R Q N.A. N.A. N.A. N.A. 1. 2, 3

5. TURBINE TRIP AND FEEDWATER ISOLATION

a. Steam Generator Water S R Q N.A. N.A. N.A. N.A. 1,2 Level-High-Htgh 3 b. Automatic Actuation Logic NA N.A. NA N.A. M(1) M(1) R(3) 1,2 CD

=3 and Actuation Relay p

3 6, EMERGENCY FEEDWATER CD a a, Manual N.A. NA N.A. R NA N.A. N.A. 1,2,3 2

O b; Automatic Actuation Logic N.A. N.A. N.A. N.A. M(1) M(1) R(3) 1,2, 3 On and Actuation Relays

• X CD c. Steam Generator Water S R Q NA NA N.A. N.A. 1,2,3

. J.

Level-Low-Low J4 CO

Document Control Desk CR-15-01424 RC-17-0134 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 ENCLOSURE 3 CLEAN COPY OF TECHNICAL SPECIFICATION PAGE CORRECTING THE ADMINISTRATIVE ERROR

CO TABLE 4.3-2 (Continued)

<z ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION m

73 SURVEILLANCE REQUIREMENTS c

z H TRIP ANALOG ACTUATING MODES FOR CHANNEL DEVICE ACTUATION MASTER SLAVE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL LOGIC RELAY RELAY SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST TEST TEST TEST IS REQUIRED

4. STEAM LINE ISOLATION

a. Manual N.A. N.A. N.A. R N.A. N.A. N.A. 1, 2, 3

b. Automatic Actuation Logic N.A. N.A. N.A. N.A. Q(1) Q(1) R(3) 1, 2, 3 and Actuation Relays CO S R SA N.A. N.A. N.A. N.A. 1, 2, 3

c. Reactor Building CO Pressure-High-2 I

CO N.A.

-vl d. Steam Flow in Two Steam S R SA N.A. N.A. N.A. 1, 2, 3 Lines-High Coincident with TavgLow-Low

e. Steam Line Pressure Low SA N.A. N.A. N.A. N.A. 1, 2, 3

5. TURBINE TRIP AND FEEDWATER ISOLATION

a. Steam Generator Water S R SA N.A. N.A. N.A. N.A. 1, 2

> Level-High-High 3

0 b. Automatic Actuation Logic N.A. N.A. N.A. N.A. Q(1) Q(1) R(3) 1, 2 D

Q. and Actuation Relay 3

0

=3 6. EMERGENCY FEEDWATER

a. Manual N.A. N.A. N.A. R N.A. N.A. N.A. 1,2,3 to b. Automatic Actuation Logic N.A. N.A. N.A. N.A. Q(1) Q(1) R(3) 1,2,3 (53 and Actuation Relays

c. Steam Generator Water R SA N.A. N.A. N.A. N.A. 1, 2, 3 Level-Low-Low (5)

• nI 00 J si ro o

CD