RC-17-0098, Completion of Expedited Seismic Evaluation Process Report Modifications

Completion of Expedited Seismic Evaluation Process Report Modifications

ML17208A300
Person / Time
Site:	Summer
Issue date:	07/26/2017
From:	Lippard G South Carolina Electric & Gas Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
RC-17-0098
Download: ML17208A300 (5)

Text

George A. Lippard Vice President, Nuclear Operations 803.345.4810 July 26, 2017 A SCANA COMPANY RC-17-0098 Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555

Subject:

VIRGIL C. SUMMER NUCLEAR STATION (VCSNS), UNIT 1 DOCKET NO. 50-395 OPERATING LICENSE NO. NPF-12 COMPLETION OF EXPEDITED SEISMIC EVALUATION PROCESS REPORT MODIFICATIONS

References:

1. Letter from T.D. Gatlin (SCE&G) to Document Control Desk (NRC),

"South Carolina Electric & Gas (SCE&G) Expedited Seismic Evaluation Report (CEUS Sites), Response to NRC Request for Information Pursuant to 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated December 17, 2014 [ML14357A168]

2. Letter from T.D. Gatlin (SCE&G) to Document Control Desk (NRC),

"Transmittal of Updated Expedited Seismic Evaluation Process Pages,"

dated August 13, 2015 [ML15229A089]

3. Letter from T. D. Gatlin (SCE&G) to Document Control Desk (NRC),

"Transmittal of Expedited Seismic Evaluation Process Report for V.C.

Summer Nuclear Station, Revision 1," dated January 28, 2016

[ML16032A167]

South Carolina Electric & Gas Company (SCE&G), acting for itself and as agent for South Carolina Public Service Authority is submitting notification of completion of the SCE&G Expedited Seismic Evaluation Process Report modifications, as required by References 1 through 3. The referenced correspondence contained commitments that were to be performed as a result of the Expedited Seismic Evaluation Process.

Attachments I and II provide a list of completed commitments established by the three referenced correspondence. Attachment II also contains the reason why the modification of the Digital Rod Position Indication Cooling Unit Outlet Fleader Isolation Valve, XVT03169-SW, was determined to not be required (Action 4).

V. C. Summer Nuclear Station

• P. 0. Box 88

• Jenkinsville, South Carolina

• 29065

• F (803) 941-9776

• www.sceg.com

Document Control Desk CR-12-01097 RC-17-0098 Page 2 of 2 Should you have any questions, please call Bruce L. Thompson at 803-931-5042.

I declare under penalty of perjury that the foregoing is true and correct.

Executed on TS/GAL/wm Attachment I: Regulatory Commitments Completion Attachment II: Section 8.4 Regulatory Commitments Completion cc: Without Attachments unless noted K. B. Marsh S. A. Byrne J. B. Archie N. S. Cams J. H. Hamilton S.M. Shealy W. M. Cherry C. Haney S. A. Williams S. M. Wyman (with Attachments)

F. G. Vega (with Attachments)

NRC Resident Inspector K. M. Sutton NSRC RTS (CR-12-01097)

File (815.07)

PRSF (RC-17-0098) (with Attachments)

Document Control Desk Attachment I CR-12-01097 RC-17-0098 Page 1 of 1 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 Attachment I Regulatory Commitments Completion Action # Commitment Due Date/ Event Complete walkdowns of Inaccessible Prior to completion of Fall 2015 1 Items listed in Table 7.1 of Expedited Outage - Complete as documented Seismic Evaluation Process report prior in Reference 3 to end of Fall 2015 refueling outage.

Submit letter to NRC stating walkdowns have been completed and provide 2 February 1, 2016 - Complete as HCLPF results in Attachment B of documented in Reference 3 Expedited Seismic Evaluation Process report.

60 days following completion of the Submit letter to NRC stating all second Unit 1 refueling outage after 3 Expedited Seismic Evaluation Process December 31, 2014 report Modifications, Actions 1 through 9 (Tentative Spring 2017) - Complete of Section 8.4, are complete.

as documented in Attachment II

Document Control Desk Attachment II CR-12-01097 RC-17-0098 Page 1 of 2 VIRGIL C. SUMMER NUCLEAR STATION (VCSNS) UNIT 1 Attachment II Section 8.4 Regulatory Commitments Completion Action Equipment ID Equipment Action Description Completion Date

1. Description  :

Modify FLEX Support Procedures to include 7.2KV December 2016 -

1 XSW1DA operator actions to reset Switchgear Complete relays with HCLPF values less than the RLGM.

Modify FLEX Support Procedures to include 480V December 2016 -

2 XSW1DA1 operator actions to reset Switchgear Complete relays with HCLPF values less than the RLGM.

Modify FLEX Support Procedures to include 480V December 2016 -

3 XSW1DA2 operator actions to reset Switchgear Complete relays with HCLPF values less than the RLGM.

No later than the end Modify the seismic DRPI Cooling of the second Unit 1 interaction to provide Unit Outlet refueling outage after sufficient shake space, or 4 XVT03169-SW Header December 31, 2014 modify piping system Isolation (Tentative Spring supports such that HCLPF Valve 2017)-Deleted See

> GMRS.

Note*

Main Steam Modify valve or handrail to Header December 2016 -

5 IPV02000-MS provide sufficient shake Power Complete space.

Relief Valve No later than the end of the second Unit 1 125V DC Modify rack to reduce front refueling outage after 6 XBA-1A Distribution rail gaps. December 31, 2014 Bus Battery (Tentative Spring 2017) - Complete

Document Control Desk Attachment II CR-12-01097 RC-17-0098 Page 2 of 2 Action Equipment ID Equipment Action Description Completion Date

1. Description No later than the end of the second Unit 1 125V DC Modify rack to reduce front refueling outage after 7 XBA-1B Distribution rail gaps. December 31, 2014 Bus Battery (Tentative Spring 2017) - Complete No later than the end of the second Unit 1 Main Steam Trim the steel angle post to XVT02843B- refueling outage after 8 Header Drain mitigate potential seismic MS December 31, 2014 Valve interaction.

(Tentative Spring 2017) - Complete DRPI Cooling Unit Inlet Modify the handrail to December 2016 -

9 XVT03164-SW Header mitigate potential seismic Complete Isolation interaction.

Valve

• Note for Action #4:

The modification for Action 4 was not required. Digital Rod Position Indication (DRPI) Cooling Unit Outlet Header Isolation Valve, XVT03169-SW is a fail close solenoid operated valve on the downstream side of the DRPI Cooling Unit, which is designated Non-Nuclear Safety (NNS).

DRPI Cooling Unit Outlet Header Check Valve, XVC03168-SW, is a check valve between XVT03169-SW and the DRPI Cooling Unit, which acts as the Code Break Boundary and prevents back flow into the NNS DRPI cooling unit during postulated failure of the cooling unit.

XVC03168-SW is an ANS 2b, ASME Code Class 3 check valve and is modeled as part of the seismic analysis previously completed to qualify XVT03169-SW (note the valves are 12 inches apart). The failure mode of XVT03169-SW, noted in Technical Report TR00080-005, "Expedited Seismic Evaluation Process Report for V.C. Summer Nuclear Station," is loss of functionality of the air operator. No loss of integrity of the piping system is expected at the review level ground motion (RLGM) levels. Even if XVT03169-SW fails to close, XVC03168-SW will prevent flooding into the Reactor Building during a postulated FLEX event. Also, XVT03169-SW is on the downstream side of the Reactor Building Cooling Unit (RBCU) and all necessary cooling required by the water through the RBCU coils would have already been accomplished.

In addition, EPRI Technical Report 3002000704, "Seismic Evaluation Guidance - Augmented Approach for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1:

Seismic," Section 3.2 specifically excludes piping, piping supports, and check valves from the ESEP; therefore no change is required to add the XVC03168-SW to the Expedited Seismic Equipment List (ESEL). Thus, the modification to XVT03169-SW to prevent seismic interaction was determined to not be required.