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| number = ML12165A107 | | number = ML12165A107 | ||
| issue date = 06/14/2012 | | issue date = 06/14/2012 | ||
| title = Request for Additional Information | | title = Request for Additional Information | ||
| author name = Martin R | | author name = Martin R | ||
| author affiliation = NRC/NRR/DORL/LPLII-1 | | author affiliation = NRC/NRR/DORL/LPLII-1 | ||
| addressee name = Ajluni M | | addressee name = Ajluni M | ||
| addressee affiliation = Southern Nuclear Operating Co, Inc | | addressee affiliation = Southern Nuclear Operating Co, Inc | ||
| docket = 05000348, 05000364, 05000424, 05000425 | | docket = 05000348, 05000364, 05000424, 05000425 | ||
| license number = | | license number = | ||
| contact person = Martin R | | contact person = Martin R | ||
| case reference number = TAC ME7839, TAC ME7840, TAC ME7846, TAC ME7847 | | case reference number = TAC ME7839, TAC ME7840, TAC ME7846, TAC ME7847 | ||
| document type = Letter, Request for Additional Information (RAI) | | document type = Letter, Request for Additional Information (RAI) | ||
Line 18: | Line 18: | ||
=Text= | =Text= | ||
{{#Wiki_filter:..."..1\ REG U{ UNITED STATES | {{#Wiki_filter:.:;,V" | ||
/ll | ..."..1\ REG U{ | ||
<< 0 'in 1 June 14,2012't/. ***1<'" Mr. M. J. Nuclear Licensing Southern Nuclear Operating Company, 40 Inverness Center Post Office Box 1295, Bin -Birmingham, AL JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840) | "I r UNITED STATES | ||
... 01' NUCLEAR REGULATORY COMMISSION | |||
/ll | |||
-'<' WASHINGTON, D.C. 20555-0001 | |||
<< 0 | |||
'in 1 June 14,2012 | |||
~ ~ | |||
't/. ~ | |||
~., ~o | |||
***1<'" | |||
Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. | |||
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 | |||
==SUBJECT:== | |||
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840) | |||
==Dear Mr. Ajluni:== | ==Dear Mr. Ajluni:== | ||
By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. | |||
The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure. | By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure. | ||
Please provide the additional information within thirty (30) days of the date of this letter. Sincerely, Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425 Request for Additional cc w/encl: Distribution via Listserv REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (FNP) VOTGLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (VEGP) SOUTHERN NUCLEAR OPERATING COMPANY (SNC) The purpose of the reactor coolant pump (RCP) flywheel inspection program defined in the Technical Specifications (TSs) is to ensure that the probability of a flywheel failure is sufficiently small such that additional safety features are not needed to protect against a flywheel failure. The Southern Nuclear Operating Company submitted a license amendment application (LAR) dated January 12, 2012, proposed to change the TS inspection interval for the RCP flywheels from 10 to 20 years for the FNP and the VEGP. In the Federal Register (FR) Notice of October 22,2003 (68 FR 60422), the U.S. Nuclear Regulatory Commission (NRC) staff announced the availability of a model LAR, no significant hazards consideration determination and safety evaluation for use by licensees in proposing extension of the flywheel examination frequency. | Please provide the additional information within thirty (30) days of the date of this letter. | ||
The associated change to the Standard Technical Specifications (STS) for Westinghouse plants (NUREG-1431), designated as Technical Specification Task Force (TSTF)-421, was based on the premise that licensee's TS would be consistent with the STS, as follows: TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program" This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide [RG] 1.14, Revision 1, August 1975. In lieu of Position C.4.b(1) and CA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals. | Sincerely, | ||
Regulatory Guide (RG) 1.14, "Reactor Coolant Pump Flywheel Integrity," Revision 1, Position C.4.b includes five parts. Regarding Parts CA.b(1) and CA.b(2), the NRC staff finds that the current FNP and VEGP TS are consistent with the provisions of the second STS paragraph above for an inspection interval of 10 years. However, since the current FNP and VEGP TS do not include the provisions of the first STS paragraph above, there would be no requirements in the proposed revised FNP and VEGP TS for the actions required by RG 1.14, positions CA.b(3), CA.b(4), and CA.b(5). Please provide either (a) a justification for the extension of the inspection interval from 10 to 20 years absent the inclusion of the provisions of RG 1.14, positions CA.b(3), CA.b(4) and CA.b(5) in the FNP and VEGP TS, or (b) propose a revision to the LAR of January 12, 2012, to include a paragraph comparable to the first STS paragraph, as noted above. Enclosure June 14,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. 40 Inverness Center Parkway Post Office Box 1295, Bin -038 Birmingham, AL 35201-1295 JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840) | (/2~/J1~ | ||
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425 | |||
==Enclosure:== | |||
Request for Additional Information cc w/encl: Distribution via Listserv | |||
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (FNP) | |||
VOTGLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (VEGP) | |||
SOUTHERN NUCLEAR OPERATING COMPANY (SNC) | |||
The purpose of the reactor coolant pump (RCP) flywheel inspection program defined in the Technical Specifications (TSs) is to ensure that the probability of a flywheel failure is sufficiently small such that additional safety features are not needed to protect against a flywheel failure. | |||
The Southern Nuclear Operating Company submitted a license amendment application (LAR) dated January 12, 2012, proposed to change the TS inspection interval for the RCP flywheels from 10 to 20 years for the FNP and the VEGP. In the Federal Register (FR) Notice of October 22,2003 (68 FR 60422), the U.S. Nuclear Regulatory Commission (NRC) staff announced the availability of a model LAR, no significant hazards consideration determination and safety evaluation for use by licensees in proposing extension of the flywheel examination frequency. The associated change to the Standard Technical Specifications (STS) for Westinghouse plants (NUREG-1431), designated as Technical Specification Task Force (TSTF)-421, was based on the premise that licensee's TS would be consistent with the STS, as follows: | |||
TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program" This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide | |||
[RG] 1.14, Revision 1, August 1975. | |||
In lieu of Position C.4.b(1) and CA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals. | |||
Regulatory Guide (RG) 1.14, "Reactor Coolant Pump Flywheel Integrity," Revision 1, Position C.4.b includes five parts. Regarding Parts CA.b(1) and CA.b(2), the NRC staff finds that the current FNP and VEGP TS are consistent with the provisions of the second STS paragraph above for an inspection interval of 10 years. | |||
However, since the current FNP and VEGP TS do not include the provisions of the first STS paragraph above, there would be no requirements in the proposed revised FNP and VEGP TS for the actions required by RG 1.14, positions CA.b(3), CA.b(4), and CA.b(5). | |||
Please provide either (a) a justification for the extension of the inspection interval from 10 to 20 years absent the inclusion of the provisions of RG 1.14, positions CA.b(3), CA.b(4) and CA.b(5) in the FNP and VEGP TS, or (b) propose a revision to the LAR of January 12, 2012, to include a paragraph comparable to the first STS paragraph, as noted above. | |||
Enclosure | |||
June 14,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc. | |||
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295 | |||
==SUBJECT:== | |||
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840) | |||
==Dear Mr. Ajluni:== | ==Dear Mr. Ajluni:== | ||
By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. | |||
The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure. | By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure. | ||
Please provide the additional information within thirty (30) days of the date of this letter. Sincerely, IRA! Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425 | Please provide the additional information within thirty (30) days of the date of this letter. | ||
Sincerely, IRA! | |||
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425 | |||
==Enclosure:== | ==Enclosure:== | ||
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1R1F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource RidsNrrDssStsb Resource SSheng, NRR/DE/EVIB RidsNrrPMFarley Resource RidsNrrPMVogtle Resource SAnderson, NRR ADAMS Accession No.: ML12165A107 | Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1R1F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource RidsNrrDssStsb Resource SSheng, NRR/DE/EVIB RidsNrrPMFarley Resource RidsNrrPMVogtle Resource SAnderson, NRR ADAMS Accession No.: ML12165A107 | ||
* By memo dated OFFICE DORULPl2-lIPM DORUlPL2-1/PM DORUlPL2-1/LA DElEVIB/BC NAME RMartin PBoyle SFigueroa SRosenberg DATE 06/07/12 06/07/12 06/13/12 lQ6/07/12 OFFICE NRRlDSS IITSB/BC DORUlPL2-1/BC NAME RElliott (CSchulten for) NSalliado In DATE 06/08/12 06/14/12 06/14/12 OFFICIAL RECORD COpy}} | * By memo dated OFFICE DORULPl2-lIPM DORUlPL2-1/PM DORUlPL2-1/LA DElEVIB/BC NAME RMartin PBoyle SFigueroa SRosenberg DATE 06/07/12 06/07/12 06/13/12 lQ6/07/12 OFFICE NRRlDSS IITSB/BC DORUlPL2-1/BC ~Pl2-1/PM NAME RElliott (CSchulten for) NSalliado In DATE 06/08/12 06/14/12 06/14/12 OFFICIAL RECORD COpy}} |
Latest revision as of 15:46, 20 March 2020
ML12165A107 | |
Person / Time | |
---|---|
Site: | Vogtle, Farley ![]() |
Issue date: | 06/14/2012 |
From: | Martin R Plant Licensing Branch II |
To: | Ajluni M Southern Nuclear Operating Co |
Martin R | |
References | |
TAC ME7839, TAC ME7840, TAC ME7846, TAC ME7847 | |
Download: ML12165A107 (3) | |
Text
.:;,V"
..."..1\ REG U{
"I r UNITED STATES
... 01' NUCLEAR REGULATORY COMMISSION
/ll
-'<' WASHINGTON, D.C. 20555-0001
<< 0
'in 1 June 14,2012
~ ~
't/. ~
~., ~o
- 1<'"
Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840)
Dear Mr. Ajluni:
By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure.
Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely,
(/2~/J1~
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 (FNP)
VOTGLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 (VEGP)
SOUTHERN NUCLEAR OPERATING COMPANY (SNC)
The purpose of the reactor coolant pump (RCP) flywheel inspection program defined in the Technical Specifications (TSs) is to ensure that the probability of a flywheel failure is sufficiently small such that additional safety features are not needed to protect against a flywheel failure.
The Southern Nuclear Operating Company submitted a license amendment application (LAR) dated January 12, 2012, proposed to change the TS inspection interval for the RCP flywheels from 10 to 20 years for the FNP and the VEGP. In the Federal Register (FR) Notice of October 22,2003 (68 FR 60422), the U.S. Nuclear Regulatory Commission (NRC) staff announced the availability of a model LAR, no significant hazards consideration determination and safety evaluation for use by licensees in proposing extension of the flywheel examination frequency. The associated change to the Standard Technical Specifications (STS) for Westinghouse plants (NUREG-1431), designated as Technical Specification Task Force (TSTF)-421, was based on the premise that licensee's TS would be consistent with the STS, as follows:
TS 5.5.7, "Reactor Coolant Pump Flywheel Inspection Program" This program shall provide for the inspection of each reactor coolant pump flywheel per the recommendations of Regulatory Position C.4.b of Regulatory Guide
[RG] 1.14, Revision 1, August 1975.
In lieu of Position C.4.b(1) and CA.b(2), a qualified in-place UT examination over the volume from the inner bore of the flywheel to the circle one-half of the outer radius or a surface examination (MT and/or PT) of exposed surfaces of the removed flywheels may be conducted at 20 year intervals.
Regulatory Guide (RG) 1.14, "Reactor Coolant Pump Flywheel Integrity," Revision 1, Position C.4.b includes five parts. Regarding Parts CA.b(1) and CA.b(2), the NRC staff finds that the current FNP and VEGP TS are consistent with the provisions of the second STS paragraph above for an inspection interval of 10 years.
However, since the current FNP and VEGP TS do not include the provisions of the first STS paragraph above, there would be no requirements in the proposed revised FNP and VEGP TS for the actions required by RG 1.14, positions CA.b(3), CA.b(4), and CA.b(5).
Please provide either (a) a justification for the extension of the inspection interval from 10 to 20 years absent the inclusion of the provisions of RG 1.14, positions CA.b(3), CA.b(4) and CA.b(5) in the FNP and VEGP TS, or (b) propose a revision to the LAR of January 12, 2012, to include a paragraph comparable to the first STS paragraph, as noted above.
Enclosure
June 14,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 AND VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. ME7846, ME7847, ME7839, AND ME7840)
Dear Mr. Ajluni:
By letter dated January 12, 2012 (Agencywide Documents Access and Management System Accession No. ML120130175), Southern Nuclear Operating Company, Inc. (SNC or the licensee), submitted a license amendment request to change the Technical Specifications to extend the inspection interval for the reactor coolant pump flywheels. The U.S. Nuclear Regulatory Commission staff finds that additional information is needed as set forth in the enclosure.
Please provide the additional information within thirty (30) days of the date of this letter.
Sincerely, IRA!
Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348, 50-364, 50-424 and 50-425
Enclosure:
Request for Additional Information cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPL2-1R1F RidsNrrDorlLpl2-1 Resource RidsAcrsAcnw_MailCTR Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrLASFigueroa Resource RidsOgcRp Resource RidsNrrDssStsb Resource SSheng, NRR/DE/EVIB RidsNrrPMFarley Resource RidsNrrPMVogtle Resource SAnderson, NRR ADAMS Accession No.: ML12165A107
- By memo dated OFFICE DORULPl2-lIPM DORUlPL2-1/PM DORUlPL2-1/LA DElEVIB/BC NAME RMartin PBoyle SFigueroa SRosenberg DATE 06/07/12 06/07/12 06/13/12 lQ6/07/12 OFFICE NRRlDSS IITSB/BC DORUlPL2-1/BC ~Pl2-1/PM NAME RElliott (CSchulten for) NSalliado In DATE 06/08/12 06/14/12 06/14/12 OFFICIAL RECORD COpy