NL-13-2423, Response to Request for Information Regarding VEGP-ISI-ALT-05 Version 1 and VEGP-ISI-ALT-06 Version 1 (NL-13-2423)

Response to Request for Information Regarding VEGP-ISI-ALT-05 Version 1 and VEGP-ISI-ALT-06 Version 1 (NL-13-2423)

ML13329A494
Person / Time
Site:	Vogtle
Issue date:	11/25/2013
From:	Pierce C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-13-2423, VEGP-ISI-ALT-05, Version 1, VEGP-ISI-ALT-06, Version 1
Download: ML13329A494 (14)

Text

Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.

40 Inverness Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205.992.7872 Fax 205.992.7601 November 25, 2013 SOUTHERN ' \

COMPANY Docket Nos.: 50-424 NL-13-2423 50-425 U. S. Nuclear Regulatory Commission ATIN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Response to Request for Information Regarding VEGP-ISI-ALT-05 Version 1 and VEGP-ISI-ALT-06 Version 1 Ladies and Gentlemen:

By letter dated August 29, 2012 (Agencywide Documents Access and Management System Accession (ADAMS) No. ML12243A248), Southern Nuclear Operating Company, Inc. requested the U.S. Nuclear Regulatory Commission (NRC) approval of proposed inservice inspection (lSI) alternatives VEGP-ISI-ALT 05, Version 1 and VEGP-ISI-ALT-06, Version 1. These alternatives propose onetime extensions of examination of category B-A reactor vessel welds and selected examination category B-D reactor vessel nozzle welds and reactor vessel inside radius sections from a ten-year examination period to a twenty-year examination period.

By letter dated October 29,2013 (ADAMS No. ML13296A789) the NRC issued a Request for Additional Information (RAI) containing three additional questions. provides the SNC response to the RAI questions. Enclosure 2 provides the requested evaluation per RAI question 2.

This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at (205) 992-7369.

Respectfully submitted, C. R. Pierce Regulatory Affairs Director CRP/RMJ

Enclosures:

1. SNC Response to NRC RAls

2. Requested Evaluation per !'JRC RAI Question 2

U. S. Nuclear Regulatory Commission NL- 13-2423 Page 2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bost, Executive Vice President & Chief Nuclear Officer Mr. T. E. Tynan, Vice President - Vogtle Mr. B. L. Ivey, Vice President - Regulatory Affairs Mr. B. J. Adams, Vice President - Fleet Operations RType: CVC7000 U. S. Nuclear Regulatory Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager - Vogtle Mr. L. M. Cain, Senior Resident Inspector - Vogtle

Vogtle Electric Generating Plant Response to Request for Information Regarding VEGP-ISI-ALT-05 Version 1 and VEGP-ISI-ALT-06 Version 1 Enclosure 1 SNC Response to NRC RAls to NL-13-2423 SNC Response to NRC RAls

1. NRC RAI Request for alternative VEGP-ISI-ALT-05 states that VEGP, Unit 1, reactor pressure vessel (RPV) examinations currently scheduled for 2015 will be deferred until 2026, plus or minus one refueling outage, and request for alternative VEGP ISI-ALT-06 states that VEGP, Unit 2, RPV examinations currently scheduled for 2016 will also be deferred until 2026, plus or minus one refueling outage. These dates are not identical to those mentioned in the cover letter dated August 29, 2012. In the safety evaluation of the relief requests, the NRC staff plans to reference only the dates appearing in VEGP-ISI-ALT-05 and VEGP-ISI-ALT-06 .

Please comment if you disagree.

SNC Response to NRC RAI # 1 SI\JC agrees with the plans of the NRC staff to reference only the dates appearing in VEGP-ISI-ALT-05 and VEGP-ISI-ALT-06. The dates provided in the cover letter dated August 29, 2012 are consistent with the refueling outages projected during the third period of the fourth 10-Year Inservice Inspection Interval in which SNC anticipates that the applicable reactor pressure vessel examinations will be performed. These projected refueling outages are within the dates appearing in VEGP-ISI-ALT-05 and VEGP-ISI-ALT-06.

E1-1 to NL-13-2423 SNC Response to NRC RAls

2. NRC RAI Regarding evaluation of indications identified in past inservice inspection (lSI) examinations, Table 2 of VEGP-ISI-ALT-05 and Table 2 of VEGP-ISI-ALT-06 state that "these indications are acceptable per Table IWB-3510-1 of Section XI of the ASME Code." Please provide these evaluations to support the conclusion.

SNC Response to NRC RAI # 2 As indicated in alternative VEGP-ISI-ALT-05, there were two indications identified on unit 1 in the beltline region during the most recent inservice inspection. These two indications are contained within two welds. As indicated in alternative VEGP ISI-ALT-06, there were six indications identified on unit 2 in the beltline region during the most recent inservice inspection . These six indications are contained within three welds.

Unit 1 inspections occurred during the 1R13 (Fall 2006) refueling outage and unit 2 inspections occurred during the 2R12 (Spring 2007) refueling outage.

Those welds identified to contain indications on unit 1 were as follows:

• 11201-V6-001-W15 (Intermediate Shell Longitudinal Weld at 0 Degrees)

• 11201-V6-001-W17 (Intermediate Shell Longitudinal Weld at 240 Degrees)

Those welds identified to contain indications on unit 2 were as follows:

• 21201-V6-001-W17 (Intermediate Shell Longitudinal Weld at 240 Degrees)

• 21201-V6-001-W18 (Lower Shell Longitudinal Weld at 90 Degrees)

• 21201-V6-001-W20 (Lower Shell Longitudinal Weld at 330 Degrees)

Also, as indicated in the two alternatives the indications found in the welds were evaluated as being acceptable when utilizing Table IWB-3510-1. The following page contains a table indicating the results from the respective reactor vessel examination summary for the welds listed above.

E1-2

Enclosure 1 to NL-13-2423 SNC Response to NRC RAls Vogtle Unit 1 Reactor Vessel Examination Summary - Year 2006 Examinations Code WeldNolume Weld Recordable Comments /

Category Description Numbers Indications Resolutions Intermediate Shell Allowable per ASME XI 8-A 11201-V6-001-W15 1 Longitudinal Weld @ 0 0 1989,IW8-3510-1 Intermediate Shell Allowable per ASME XI 8-A 11201-V6-001-W17 1 LonQitudinal Weld @ 240 0 1989,IW8-3510-1 Vogtle Unit 2 Reactor Vessel Examination Summary - Year 2007 Examinations Code WeldNolume Weld Recordable Comments /

Category Description Numbers Indications Resolutions Intermediate Shell Allowable per ASME XI 8-A 21201-V6-001-W17 1 Longitudinal Weld @ 2400 1989, IW8-351 0-1 Lower Shell Longitudinal Allowable per ASME XI 8-A 21201-V6-001-W18 3 Weld @ 90 0 1989,IW8-3510-1 Lower Shell Longitudinal Allowable per ASME XI 8-A 21201-V6-001-W20 2 Weld @ 3300 1989,IW8-3510-1 Enclosure 2 contains the evaluation data sheet or the "indication assessment" completed during the respective refueling outage for the welds identified to contain indications.

E1-3 to NL-13-2423 SNC Response to NRC RAls

3. NRC RAI The neutron fluence for all RPV materials and the chemistry factors for the RPV materials based on surveillance data (in Table 3 in VEGP-ISI-ALT-05 for Unit 1 and Table 3 in VEGP-ISI-ALT-06 for Unit 2) are different from their corresponding values in the license renewal application that was approved in 2009. Please provide the basis for these changes, including a list of additional surveillance capsule reports and updated neutron fluence evaluations which contributed to the changes.

SNC Response to NRC RAI # 3 Vogtle Unit 1:

The reactor vessel neutron fluence values used for the Vogtle Unit 1 lSI interval extension evaluation were based on ex-vessel neutron dosimetry data documented in WCAP-17239-I\lP, Revision 1 (Ref. 1). This data was taken from the most recent reactor vessel neutron fluence evaluations at the time the lSI interval extension evaluation was completed . The reactor vessel neutron fluence values used for the license renewal application submitted in 2007 were taken from capsule data obtained prior to the use of ex-vessel neutron dosimetry documented in WCAP-17239-NP, Revision 1.

Chemistry factor values are a function of material properties (Regulatory Guide 1.99, Revision 2 (Ref. 2), Position 1.1) or the most recent surveillance capsule test results (Regulatory Guide 1.99, Revision 2, Position 2.1). The chemistry factor values used in the Vogtle Unit 1 lSI interval extension evaluation are documented in WCAP-17076-NP, Revision 0 (Ref. 3). The most recent surveillance capsule data is documented in WCAP-17009-NP, Revision 1 (Ref.

4). The chemistry factor values used for the license renewal application submitted in 2007 were the result of data obtained prior to the development of WCAP 17076-NP, Revision 0, and WCAP-17009-NP, Revision 1.

Vogtle Unit 2:

The reactor vessel neutron fluence values used for the Vogtle Unit 2 lSI interval extension evaluation were based on ex-vessel neutron dosimetry data documented in WCAP-17350-NP, Revision 0 (Ref. 5). This data was taken from the most recent reactor vessel neutron fluence evaluations at the time the lSI interval extension evaluation was completed. The reactor vessel neutron fluence values used for the license renewal application submitted in 2007 were taken from capsule data obtained prior to the use of ex-vessel neutron dosimetry documented in WCAP-17350-NP, Revision O.

Chemistry factor values are a function of material properties (Regulatory Guide 1.99, Revision 2, Position 1.1) or the most recent surveillance capsule test results (Regulatory Guide 1.99, Revision 2, Position 2.1). The chemistry factor values used in the Vogtle Unit 2 lSI interval extension evaluation are documented in WCAP-17353-NP, Revision 0 (Ref. 6). The most recent surveillance capsule E1-4 to NL-13-2423 SNC Response to NRC RAls data is documented in WCAP-17343-NP, Revision 0 (Ref. 7). The chemistry factor values used for the license renewal application submitted in 2007 were the result of data obtained prior to the development of WCAP-17353-NP, Revision 0, and WCAP-17343-NP, Revision O.

References:

1) WCAP-17239-NP, Revision 1, Ex-Vessel Neutron Dosimetry Program for A.

W. Vogt/e Unit 1 Cycle 15," July 2010.

2) NRC Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials, May 1988.

3) WCAP-17076-NP, Revision 0, Vogt/e Unit 1 Heatup and Cooldown Limit Curves for Normal Operation, July 2009.

4) WCAP-17009-NP, Revision 1, Analysis of Capsule W from the Vogtle Unit No. 1 Reactor Vessel Radiation Surveillance Program, April 2009 (ADAMS Accession Number: ML091550356).

5) WCAP-17350-NP, Revision 0, Ex-Vessel Neutron DOSimetry Program for A.

W. Vogtle Unit 2 Cycle 14, December 2010.

6) WCAP-17353-NP, Revision 0, Vogtle Unit 2 Heatup and Cooldown Limit Curves for Normal Operation, August 2011.

7) WCAP-17343-NP, Revision 0, Analysis of Capsule Z from the Southern Nuclear Operating Company Vogtle Unit 2 Reactor Vessel Radiation Surveillance Program, March 2011 (ADAMS Accession Number:

ML110800303).

E1-5

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