ML15181A214: Difference between revisions
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==SUBJECT:== | ==SUBJECT:== | ||
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE STEAM GENERATOR TECHNICAL SPECIFICATIONS TO REFLECT TSTF-510 AND TO REVISE ALLOY 800 SLEEVE TECHNICAL SPECIFICATIONS (TAC NOS. MF6054 AND MF6055) | BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE STEAM GENERATOR TECHNICAL SPECIFICATIONS TO REFLECT TSTF-510 AND TO REVISE ALLOY 800 SLEEVE TECHNICAL SPECIFICATIONS (TAC NOS. MF6054 AND MF6055) | ||
==Dear Mr. Larson:== | ==Dear Mr. Larson:== | ||
By letter dated April 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15092A569), | By letter dated April 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15092A569), FirstEnergy Nuclear Operating Company (the licensee), submitted a license amendment request to revise the Beaver Valley Power Station, Unit Nos. 1 and 2, Technical Specifications (TSs) to incorporate the guidance of Technical Specification Task Force Traveler (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection" (ADAMS Accession No. ML 110610350). | ||
FirstEnergy Nuclear Operating Company (the licensee), | The license amendment would modify the requirement to remove tubes with Alloy 800 sleeves from service. The guidance of TSTF-510 revises TS 3.4.20, "Steam Generator (SG) Tube Integrity"; | ||
submitted a license amendment request to revise the Beaver Valley Power Station, Unit Nos. 1 and 2, Technical Specifications (TSs) to incorporate the guidance of Technical Specification Task Force Traveler (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection" (ADAMS Accession No. ML 110610350). | |||
The license amendment would modify the requirement to remove tubes with Alloy 800 sleeves from service. | |||
The guidance of TSTF-510 revises TS 3.4.20, "Steam Generator (SG) Tube Integrity"; | |||
TS 5.5.5, "Steam Generator (SG) Program"; | TS 5.5.5, "Steam Generator (SG) Program"; | ||
and TS 5.6.6, "Steam Generator Tube Inspection Report." | and TS 5.6.6, "Steam Generator Tube Inspection Report." To complete its review, the U.S. Nuclear Regulatory Commission staff requests a response to the enclosed Request for Additional Information. | ||
To complete its review, the U.S. Nuclear Regulatory Commission staff requests a response to the enclosed Request for Additional Information. | |||
The draft questions were sent to Mr. Phil Lashley to ensure that they were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. | The draft questions were sent to Mr. Phil Lashley to ensure that they were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. | ||
Please respond to the enclosure within 30 days of the date of this letter. | Please respond to the enclosure within 30 days of the date of this letter. | ||
| Line 41: | Line 36: | ||
Request for Additional Information cc w/enclosure: | Request for Additional Information cc w/enclosure: | ||
Distribution via Listserv Sincerely, Taylor A. Lam , Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO REVISE STEAM GENERATOR TECHNICAL SPECIFICATIONS TO REFLECT TSTF-510 AND TO REVISE ALLOY 800 SLEEVE TECHNICAL SPECIFICATIONS FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. | Distribution via Listserv Sincerely, Taylor A. Lam , Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO REVISE STEAM GENERATOR TECHNICAL SPECIFICATIONS TO REFLECT TSTF-510 AND TO REVISE ALLOY 800 SLEEVE TECHNICAL SPECIFICATIONS FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated April 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15092A569), FirstEnergy Nuclear Operating Company (the licensee), submitted a license amendment request to revise the Beaver Valley Power Station, Unit Nos. 1 and 2, Technical Specifications (TSs) to incorporate the guidance of Technical Specification Task Force Traveler (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection" (ADAMS Accession No. ML 110610350), and would modify the requirement to remove tubes with Alloy 800 sleeves from service. The guidance of TSTF-510 revises TS 3.4.20, "Steam Generator Tube Integrity"; | ||
UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated April 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15092A569), | |||
FirstEnergy Nuclear Operating Company (the licensee), | |||
submitted a license amendment request to revise the Beaver Valley Power Station, Unit Nos. 1 and 2, Technical Specifications (TSs) to incorporate the guidance of Technical Specification Task Force Traveler (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection" (ADAMS Accession No. ML 110610350), | |||
and would modify the requirement to remove tubes with Alloy 800 sleeves from service. | |||
The guidance of TSTF-510 revises TS 3.4.20, "Steam Generator Tube Integrity"; | |||
TS 5.5.5, "Steam Generator (SG) Program"; | TS 5.5.5, "Steam Generator (SG) Program"; | ||
and TS 5.6.6, "Steam Generator Tube Inspection Report." | and TS 5.6.6, "Steam Generator Tube Inspection Report." To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests a response to the questions below. 1. The guidance in TSTF-510 distinguishes between plugging and repair (e.g., sleeving of tubes). Please discuss any plans to modify TSs 5.5.5.2.c.1, 5.5.5.2.c.4, 5.5.5.2.d.3, 5.5.5.2.d.4, and 5.6.6.2.3 to clearly indicate "plugging or repair," rather than just "repair," to clarify that tubes may either be plugged or repaired if flaws exceeding the "plugging or repair" criteria are identified. | ||
To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests a response to the questions below. 1. The guidance in TSTF-510 distinguishes between plugging and repair (e.g., sleeving of tubes). Please discuss any plans to modify TSs 5.5.5.2.c.1, 5.5.5.2.c.4, 5.5.5.2.d.3, 5.5.5.2.d.4, and 5.6.6.2.3 to clearly indicate "plugging or repair," | : 2. Proposed TS 5.5.5.2.d.2 was not modified to reflect the guidance in a June 17, 2013, letter (ADAMS Accession No. ML 13120A541), in which the NRC acknowledged a correction to paragraph d.2 of TSTF-510, Revision 2. Please discuss your plan to modify your application to be consistent with the June 17, 2013, letter. Enclosure E. Larson If you have any questions, please contact me at (301) 415-7128 or Taylor.Lamb@nrc.gov. | ||
rather than just "repair," | |||
to clarify that tubes may either be plugged or repaired if flaws exceeding the "plugging or repair" criteria are identified. | |||
: 2. Proposed TS 5.5.5.2.d.2 was not modified to reflect the guidance in a June 17, 2013, letter (ADAMS Accession No. ML 13120A541), | |||
in which the NRC acknowledged a correction to paragraph d.2 of TSTF-510, Revision | |||
Docket Nos. 50-334 and 50-412 | Docket Nos. 50-334 and 50-412 | ||
| Line 61: | Line 46: | ||
Request for Additional Information cc w/enclosure: | Request for Additional Information cc w/enclosure: | ||
Distribution via Listserv DISTRIBUTION: | Distribution via Listserv DISTRIBUTION: | ||
Sincerely, IRA/ Taylor A. Lamb, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation PUBLIC LPLl-2 R/F RidsRgn1 MailCenter Resource RidsNrrDorlLpl1-2 Resource | Sincerely, IRA/ Taylor A. Lamb, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation PUBLIC LPLl-2 R/F RidsRgn1 MailCenter Resource RidsNrrDorlLpl1-2 Resource RGrover, NRR RidsACRS_MailCTR Resource RidsNrrPMBeaverValley Resource RidsNrrDeEsgb Resource RidsNrrLALRonewicz Resource AJohnson, NRR ADAMS Accession No.: ML15181A214 | ||
*via memo OFFICE LPL 1-2/PM LPL 1-2/LA DE/ESGB* LPL 1-2/BC LPL 1-2/PM NAME TLamb LRonewicz GKulesa DBroaddus TLamb DATE 7/6/15 7/1/15 6/4/15 7/14/15 7/14/15 OFFICIAL RECORD COPY}} | |||
*via memo OFFICE LPL 1-2/PM LPL 1-2/LA DE/ESGB* | |||
LPL 1-2/BC LPL 1-2/PM NAME TLamb LRonewicz GKulesa DBroaddus TLamb DATE 7/6/15 7/1/15 6/4/15 7/14/15 7/14/15 OFFICIAL RECORD COPY}} | |||
Revision as of 01:08, 9 July 2018
| ML15181A214 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/14/2015 |
| From: | Lamb T A Plant Licensing Branch 1 |
| To: | Larson E A FirstEnergy Nuclear Operating Co |
| Lamb T A, NRR/DORL/LPLI-2, 415-7128 | |
| References | |
| TAC MF6054, TAC MF6055 | |
| Download: ML15181A214 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 14, 2015 Mr. Eric A. Larson, Site Vice President Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 -REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO REVISE STEAM GENERATOR TECHNICAL SPECIFICATIONS TO REFLECT TSTF-510 AND TO REVISE ALLOY 800 SLEEVE TECHNICAL SPECIFICATIONS (TAC NOS. MF6054 AND MF6055)
Dear Mr. Larson:
By letter dated April 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15092A569), FirstEnergy Nuclear Operating Company (the licensee), submitted a license amendment request to revise the Beaver Valley Power Station, Unit Nos. 1 and 2, Technical Specifications (TSs) to incorporate the guidance of Technical Specification Task Force Traveler (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection" (ADAMS Accession No. ML 110610350).
The license amendment would modify the requirement to remove tubes with Alloy 800 sleeves from service. The guidance of TSTF-510 revises TS 3.4.20, "Steam Generator (SG) Tube Integrity";
TS 5.5.5, "Steam Generator (SG) Program";
and TS 5.6.6, "Steam Generator Tube Inspection Report." To complete its review, the U.S. Nuclear Regulatory Commission staff requests a response to the enclosed Request for Additional Information.
The draft questions were sent to Mr. Phil Lashley to ensure that they were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed.
Please respond to the enclosure within 30 days of the date of this letter.
E. Larson If you have any questions, please contact me at (301) 415-7128 or Taylor.Lamb@nrc.gov.
Docket Nos. 50-334 and 50-412
Enclosure:
Request for Additional Information cc w/enclosure:
Distribution via Listserv Sincerely, Taylor A. Lam , Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO REVISE STEAM GENERATOR TECHNICAL SPECIFICATIONS TO REFLECT TSTF-510 AND TO REVISE ALLOY 800 SLEEVE TECHNICAL SPECIFICATIONS FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated April 1, 2015 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 15092A569), FirstEnergy Nuclear Operating Company (the licensee), submitted a license amendment request to revise the Beaver Valley Power Station, Unit Nos. 1 and 2, Technical Specifications (TSs) to incorporate the guidance of Technical Specification Task Force Traveler (TSTF)-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection" (ADAMS Accession No. ML 110610350), and would modify the requirement to remove tubes with Alloy 800 sleeves from service. The guidance of TSTF-510 revises TS 3.4.20, "Steam Generator Tube Integrity";
TS 5.5.5, "Steam Generator (SG) Program";
and TS 5.6.6, "Steam Generator Tube Inspection Report." To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests a response to the questions below. 1. The guidance in TSTF-510 distinguishes between plugging and repair (e.g., sleeving of tubes). Please discuss any plans to modify TSs 5.5.5.2.c.1, 5.5.5.2.c.4, 5.5.5.2.d.3, 5.5.5.2.d.4, and 5.6.6.2.3 to clearly indicate "plugging or repair," rather than just "repair," to clarify that tubes may either be plugged or repaired if flaws exceeding the "plugging or repair" criteria are identified.
- 2. Proposed TS 5.5.5.2.d.2 was not modified to reflect the guidance in a June 17, 2013, letter (ADAMS Accession No. ML 13120A541), in which the NRC acknowledged a correction to paragraph d.2 of TSTF-510, Revision 2. Please discuss your plan to modify your application to be consistent with the June 17, 2013, letter. Enclosure E. Larson If you have any questions, please contact me at (301) 415-7128 or Taylor.Lamb@nrc.gov.
Docket Nos. 50-334 and 50-412
Enclosure:
Request for Additional Information cc w/enclosure:
Distribution via Listserv DISTRIBUTION:
Sincerely, IRA/ Taylor A. Lamb, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation PUBLIC LPLl-2 R/F RidsRgn1 MailCenter Resource RidsNrrDorlLpl1-2 Resource RGrover, NRR RidsACRS_MailCTR Resource RidsNrrPMBeaverValley Resource RidsNrrDeEsgb Resource RidsNrrLALRonewicz Resource AJohnson, NRR ADAMS Accession No.: ML15181A214
- via memo OFFICE LPL 1-2/PM LPL 1-2/LA DE/ESGB* LPL 1-2/BC LPL 1-2/PM NAME TLamb LRonewicz GKulesa DBroaddus TLamb DATE 7/6/15 7/1/15 6/4/15 7/14/15 7/14/15 OFFICIAL RECORD COPY