RS-12-191, Supplemental Information Supporting License Amendment Request to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection
| ML123380149 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 12/03/2012 |
| From: | Gullott D Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| RS-12-191 | |
| Download: ML123380149 (3) | |
Text
RS-12-191 10 CFR 50.90 December 3, 2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Supplemental Information Supporting License Amendment Request to Revise Technical Specifications to Adopt TSTF-510, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection"
References:
1)
Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Application to Revise Technical Specifications to Adopt TSTF-510, 'Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection,"' dated March 22, 2012 2)
Letter from M. Mahoney (U. S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 - Issuance of Amendments Re:
Revise Technical Specifications 5.5.9 and 5.6.9 for Permanent Alternate Repair Criteria (TAC Nos. ME8296, ME8297, ME8298, and ME8299)," dated October 5, 2012 In Reference 1, Exelon Generation Company, LLC, (EGC) requested a license amendment to revise Technical Specifications (TS) requirements for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, regarding steam generator tube inspections and reporting as described in TSTF-510, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection."
As described in Reference 1, EGC had proposed certain variations from TSTF-510, including the following variation to delete the TS requirements associated with the tungsten inert gas (TIG)-welded sleeving repair methodology for Braidwood, Unit 2, and Byron, Unit 2:
)
1 RS-12-191 10 CFR 50.90 December 3,2012 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-001 Braidwood Station, Units 1 and 2 Facility Operating License Nos. NPF-72 and NPF-77 NRC Docket Nos. STN 50-456 and STN 50-457 Byron Station, Units 1 and 2 Facility Operating License Nos. NPF-37 and NPF-66 NRC Docket Nos. STN 50-454 and STN 50-455
Subject:
Supplemental Information Supporting License Amendment Request to Revise Technical SpeCifications to Adopt TSTF-510, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection"
References:
- 1) Letter from D. M. Gullott (Exelon Generation Company, LLC) to U. S. Nuclear Regulatory Commission, "Application to Revise Technical Specifications to Adopt TSTF-51 0, 'Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection,'" dated March 22, 2012
- 2) Letter from M. Mahoney (U. S. Nuclear Regulatory Commission) to M. J. Pacilio (Exelon Generation Company, LLC), "Braidwood Station, Units 1 and 2, and Byron Station, Unit Nos. 1 and 2 -Issuance of Amendments Re:
Revise Technical Specifications 5.5.9 and 5.6.9 for Permanent Alternate Repair Criteria (TAC Nos. ME8296, ME8297, ME8298, and ME8299)," dated October 5, 2012 In Reference 1, Exelon Generation Company, LLC, (EGC) requested a license amendment to revise Technical Specifications (TS) requirements for Braidwood Station, Units 1 and 2, and Byron Station, Units 1 and 2, regarding steam generator tube inspections and reporting as described in TSTF-51 0, Revision 2, "Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection."
As described in Reference 1, EGC had proposed certain variations from TSTF-510, including the following variation to delete the TS requirements associated with the tungsten inert gas (TIG)-welded sleeving repair methodology for Braidwood, Unit 2, and Byron, Unit 2:
December 3, 2012 U. S. Nuclear Regulatory Commission Page 2 2.
EGC proposes to revise the existing requirements of TS 5.5.9.c.2 and TS 5.5.9.f.2 by deleting the ABB Combustion Engineering Inc. (Westinghouse) TIG welded sleeving repair methodology. There are no ABB Combustion Engineering Inc. (Westinghouse)
TIG-welded sleeves currently installed in the Braidwood Station, Unit 2, and Byron Station, Unit 2, SGs. EGC has been informed by the sleeve vendor that TIG welded sleeves are no longer commercially available. As a result of this change, there are no available SG tube repair methods at Braidwood Station or Byron Station; therefore, the proposed amendment deletes TS 5.5.9.f, TS 5.5.9.c.2, TS 5.5.9.c.3, and references to tube repair and sleeves in various TS.
In Reference 2, the NRC approved amendments to revise TS requirements, establishing permanent alternate repair criteria for portions of the SG tubes within the tubesheet of the Braidwood, Unit 2, and Byron, Unit 2, Model D5 SGs. In addition to the requested permanent alternate repair criteria, the amendments deleted TS 5.5.9.f, which provided provisions for SG tube repair methods in lieu of plugging when flaws are found that exceed the applicable tube repair criteria in TS 5.5.9.c.
Tube repair criteria in TS 5.5.9.c.2 and TS 5.5.9.c.3, which were applicable to the sleeves, are no longer needed and were, therefore, deleted as part of Reference 2. For editorial consistency, all uses of the words "plugged or repaired" and "plug or repair" in TS 3.4.19 and TS 5.5.9 were changed to "plugged" or "plug," as appropriate. As stated in Reference 2, these changes, in aggregate, eliminated EGC's option to repair tubes by sleeving when applicable tube repair criteria are not met in lieu of removing the tubes from service by plugging the tube ends.
The variation from TSTF-510 referenced above has been fully addressed in Reference 2; therefore, the variation is no longer applicable to the TSTF-510 license amendment request (Reference 1).
EGC has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration that were previously provided to the NRC in Attachment 1 of Reference 1. The additional information provided in this supplement does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. In addition, the additional information provided in this supplement does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b),
a copy of this letter is being provided to the designated State of Illinois official.
There are no regulatory commitments contained in this supplement.
Should you have any questions concerning this letter, please contact Ms. Lisa A. Simpson at (630) 657-2815.
December 3,2012 U. S. Nuclear Regulatory Commission Page 2
- 2. EGC proposes to revise the existing requirements of TS 5.5.9.c.2 and TS 5.5.9.f.2 by deleting the ABB Combustion Engineering Inc. (Westinghouse) TIG welded sleeving repair methodology. There are no ABB Combustion Engineering Inc. (Westinghouse)
TIG-welded sleeves currently installed in the Braidwood Station, Unit 2, and Byron Station, Unit 2, SGs. EGC has been informed by the sleeve vendor that TIG welded sleeves are no longer commercially available. As a result of this change, there are no available SG tube repair methods at Braidwood Station or Byron Station; therefore, the proposed amendment deletes TS 5.5.9.f, TS 5.5.9.c.2, TS 5.5.9.c.3, and references to tube repair and sleeves in various TS.
In Reference 2, the NRC approved amendments to revise TS requirements, establishing permanent alternate repair criteria for portions of the SG tubes within the tubesheet of the Braidwood, Unit 2, and Byron, Unit 2, Model D5 SGs. In addition to the requested permanent alternate repair criteria, the amendments deleted TS 5.5.9.f, which provided provisions for SG tube repair methods in lieu of plugging when flaws are found that exceed the applicable tube repair criteria in TS 5.5.9.c.
Tube repair criteria in TS 5.5.9.c.2 and TS 5.5.9.c.3, which were applicable to the sleeves, are no longer needed and were, therefore, deleted as part of Reference 2. For editorial consistency, all uses of the words "plugged or repaired" and "plug or repair" in TS 3.4.19 and TS 5.5.9 were changed to "plugged" or "plug," as appropriate. As stated in Reference 2, these changes, in aggregate, eliminated EGC's option to repair tubes by sleeving when applicable tube repair criteria are not met in lieu of removing the tubes from service by plugging the tube ends.
The variation from TSTF-51 0 referenced above has been fully addressed in Reference 2; therefore, the variation is no longer applicable to the TSTF-51 0 license amendment request (Reference 1).
EGC has reviewed the information supporting a finding of no significant hazards consideration and the environmental consideration that were previously provided to the NRC in Attachment 1 of Reference 1. The additional information provided in this supplement does not affect the bases for concluding that the proposed license amendment does not involve a significant hazards consideration. In addition, the additional information provided in this supplement does not affect the bases for concluding that neither an environmental impact statement nor an environmental assessment needs to be prepared in connection with the proposed amendment.
In accordance with 10 CFR 50.91, "Notice for public comment; State consultation," paragraph (b),
a copy of this letter is being provided to the designated State of Illinois official.
There are no regulatory commitments contained in this supplement.
Should you have any questions concerning this letter, please contact Ms. Lisa A. Simpson at (630) 657-2815.
December 3, 2012 U. S. Nuclear Regulatory Commission Page 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 3rd day of December.
Respectfully, David M. Gullott Manager - Licensing Exelon Generation Company, LLC cc.
NRC Regional Administrator, Region III NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station NRR Project Manager - Braidwood and Byron Stations December 3, 2012 U. S. Nuclear Regulatory Commission Page 3 I declare under penalty of perjury that the foregoing is true and correct. Executed on the 3rd day of December.
Respectfully, David M. Gullott Manager - licensing Exelon Generation Company, LLC cc:
NRC Regional Administrator, Region III NRC Senior Resident Inspector, Braidwood Station NRC Senior Resident Inspector, Byron Station NRR Project Manager - Braidwood and Byron Stations