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| | issue date = 09/23/2010 | | | issue date = 09/23/2010 |
| | title = Relief Request ANO2-ISI-005 to Extend the Inservice Inspection Interval for the Visual Examination of Accessible Interior to Reactor Vessel Attachment Weld, for Fourth 10-Year Interval | | | title = Relief Request ANO2-ISI-005 to Extend the Inservice Inspection Interval for the Visual Examination of Accessible Interior to Reactor Vessel Attachment Weld, for Fourth 10-Year Interval |
| | author name = Markley M T | | | author name = Markley M |
| | author affiliation = NRC/NRR/DORL/LPLIV | | | author affiliation = NRC/NRR/DORL/LPLIV |
| | addressee name = | | | addressee name = |
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| {{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 23, 2010 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. |
| September 23, 2010 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc. 1448 S. R. 333 Russellville, AR 72802 SUB..ARKANSAS NUCLEAR ONE, UNIT 2 -REQUEST FOR RELIEF AN02-ISI-005, REQUEST TO EXTEND THE INSERVICE INSPECTION INTERVAL FOR THE VISUAL EXAMINATION OF ACCESSIBLE INTERIOR TO REACTOR VESSEL ATTACHMENT WELD (TAC NO. ME2566) | | 1448 S. R. 333 Russellville, AR 72802 SUB..IECT: ARKANSAS NUCLEAR ONE, UNIT 2 - REQUEST FOR RELIEF AN02-ISI-005, REQUEST TO EXTEND THE INSERVICE INSPECTION INTERVAL FOR THE VISUAL EXAMINATION OF ACCESSIBLE INTERIOR TO REACTOR VESSEL ATTACHMENT WELD (TAC NO. ME2566) |
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| ==Dear Sir or Madam:== | | ==Dear Sir or Madam:== |
| | |
| By letter dated November 4,2009, Entergy Operations, Inc. (the licensee), submitted, pursuant to paragraph 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), a request for relief for the Arkansas Nuclear One, Unit 2 (ANO-2), for visual examination of the accessible interior attachment welds within and beyond the beltline region and a visual examination of the accessible core support structure surfaces of the reactor pressure vessel once each 10-year inservice inspection (lSI) interval. | | By letter dated November 4,2009, Entergy Operations, Inc. (the licensee), submitted, pursuant to paragraph 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), a request for relief for the Arkansas Nuclear One, Unit 2 (ANO-2), for visual examination of the accessible interior attachment welds within and beyond the beltline region and a visual examination of the accessible core support structure surfaces of the reactor pressure vessel once each 10-year inservice inspection (lSI) interval. |
| Specifically, the licensee requested permission to extend, from 10 to 20 years, the lSI interval that is required by Examination Categories B-N-2 and B-N-3 of Table IWB-2500-1 of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2001 Edition, 2003 Addenda for the third 10-year lSI interval for ANO-2. This proposed alternative is applicable to the third 10-year lSI for the examination categories B-N-2 and B-N-3, Items B13.50, B13.60, and B13.70 visual examinations. | | Specifically, the licensee requested permission to extend, from 10 to 20 years, the lSI interval that is required by Examination Categories B-N-2 and B-N-3 of Table IWB-2500-1 of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2001 Edition, 2003 Addenda for the third 10-year lSI interval for ANO-2. This proposed alternative is applicable to the third 10-year lSI for the examination categories B-N-2 and B-N-3, Items B13.50, B13.60, and B13.70 visual examinations. |
| The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the NRC staff authorizes relief request AN02-ISI-005, until the end of the third 1 O-year lSI interval for Examination Categories B-N-2 and B-N-3, Items B13.50, B13.60, and B13.70, at ANO-2, which are scheduled to be performed in 2018. All other requirements of the ASME Code, Section XI for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. | | The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the NRC staff authorizes relief request AN02-ISI-005, until the end of the third 1O-year lSI interval for Examination Categories B-N-2 and B-N-3, Items B13.50, B13.60, and B13.70, at ANO-2, which are scheduled to be performed in 2018. |
| -2 The NRC staffs safety evaluation is enclosed. | | All other requirements of the ASME Code, Section XI for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. |
| If you have any questions, please contact Kaly Kalyanam at (301) 415-1480 or via e-mail at kaly.kalyanam@nrc.gov. | | |
| Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. | | -2 The NRC staffs safety evaluation is enclosed. If you have any questions, please contact Kaly Kalyanam at (301) 415-1480 or via e-mail at kaly.kalyanam@nrc.gov. |
| Safety cc w/encl: Distribution via UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR RELIEF REQUEST REQUEST TO EXTEND B-N-2 AND B-N-3 COMPONENT ENTERGY OPERATIONS, ARKANSAS NUCLEAR ONE, UNIT DOCKET NO. | | Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368 |
| | |
| | ==Enclosure:== |
| | |
| | Safety Evaluation cc w/encl: Distribution via ListServ |
| | |
| | UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST AN02-ISI-005 REQUEST TO EXTEND B-N-2 AND B-N-3 COMPONENT EXAMINATIONS ENTERGY OPERATIONS, INC. |
| | ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-382 |
| | |
| | ==1.0 INTRODUCTION== |
| | |
| | By letter dated November 4, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093090314), Entergy Operations, Inc. (Entergy, the licensee), |
| | submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the approval for use of an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, Paragraph IWB-2412, Inspection Program B. The proposed alternative was requested under Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(a)(3)(ii). |
| | The licensee requested approval for the use of alternative AN02-ISI-005, to extend the inservice inspection (lSI) interval for visual examinations of the Category B-N-2 components (Interior Attachments Within Beltline Region and Interior Attachments Beyond Beltline Region) and B-N-3 components (Core Support Structure), so that the examinations will be performed at the same time as the examinations of the B-A and B-D components (which are scheduled to occur in 2018). |
| | |
| | ==2.0 REGULATORY EVALUATION== |
| | |
| | In accordance with 10 CFR 50.55a(g)(4), the licensee is required to perform lSI of ASME Code Class 1, 2, and 3 components and system pressure tests during the first 1O-year interval and subsequent 1O-year intervals that comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), |
| | subject to the limitations and modifications listed therein. |
| | The ANO-2 Code of record for the inspection of ASME Code Class 1, 2, and 3 components is the 2001 Edition through 2003 Addenda of the ASME Code, Section XI. The regulations in 10 CFR 50.55a(a)(3) state, in part, that the Director of the Office of Nuclear Reactor Regulation may authorize an alternative to the requirements of 10 CFR 50.55a(g). For an alternative to be authorized, as per 10 CFR 50.55a(a)(3)(ii), the licensee must show that following the ASfVlE Enclosure |
| | |
| | -2 Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. |
| | 2.1 Background The visual inspection of Category B-N-2 and B-N-3 components to discover whether flaws have initiated, whether pre-existing flaws have extended, and whether pre-existing flaws may have been missed in prior examinations has always been done at the same time as the visual and ultrasonic lSI of Category B-A and B-D components. The licensee submitted a request (Request for Alternative AN02-ISI-004) to extend the lSI of the Category B-A and B-D components from 10 to 20 years by separate letter dated October 29, 2009 (ADAMS Accession No. ML093030136). By letter dated September 21, 2010 (ADAMS Accession No. ML102450654), the NRC staff authorized Request for Alternative AN02-ISI-004. The examinations of Category B-A and B-D components are required to be performed at regular intervals, as defined in Section XI of the ASME Code. Performing all of these inspections at the same time reduces the number of times that the unit's full core and internals must be moved to gain access for the examinations, in addition to significant savings in dose and outage duration. |
| | |
| | ==3.0 TECHNICAL EVALUATION== |
| | |
| | 3.1 Description of Proposed Alternatives In AN02-ISI-005, the licensee proposes the interval for Category B-N-2 and B-N-3 inspections be the same as that for Category B-A and B-D inspections. |
| | 3.2 Components for Which Relief is Requested Examination Category Item Number Description B-N-2 B13.50 Interior Attachments Within Beltline Region B-N-2 B13.60 Interior Attachments Beyond Beltline Region B-N-3 B13.70 Core Support Structure 3.3 Basis for Proposed Alternatives The basis for the alternative is that performing the visual inspections of the B-N-2 and B-N-3 components on a different schedule than the Category B-A and B-D components would result in significant hardship without a compensating increase in safety. The licensee indicates that the Category B-N-2 and B-N-3 components have been inspected regularly in the past and no significant indications were noted. Likewise, a review of the same Category B-N-2 and B-N-3 inspections at other, similar nuclear power plants have been performed many times without finding a significant indication. |
| | Furthermore, in its letter dated November 4, 2009, the licensee notes that: |
| | The reactor vessel would undergo, as a minimum, the Section XI Examination Category B-P pressure tests and visual examination conducted at the end of |
| | |
| | -3 each refueling before plant start-up, as well as leak tests with visual examinations that precede each start-up following maintenance or repair activities. |
| | 3.4 NRC Staff Evaluation The NRC staff notes that the inspection of B-N-2 and B-N-3 components can only be done after the fuel and internals are removed from the reactor pressure vessel (RPV), and is usually only done at the same time as the lSI of Category B-A and B-D components. In addition, the licensee's request is consistent with the industry practice of performing the Category B-N-2 and B-N-3 on the same schedule for the lSI for Category B-A and B-D welds. |
| | The licensee's request for alternative, AN02-ISI-004, to perform the B-A and B-D welds on a 20-year interval instead of a Code-required 10-year interval (i.e., postpone it to until the end of the third interval for Categories B-A and B-D components at ANO-2 on March 25, 2020, with the lSI examinations scheduled to occur in 2018) was reviewed by the NRC staff and by letter dated September 21, 2010 (ADAMS Accession No. ML102450654), the staff authorized the request. |
| | The current relief request, AN02-ISI-005, to extend the lSI interval that is required by Examination Categories B-N-2 and B-N-3, is consistent with the industry practice stated in the previous paragraph. |
| | The radiation exposure to establish the conditions for and perform the ASME examination categories B-N-2 and B-N-3 examinations would essentially double if the subject examinations were performed in an outage different from the RPV shell, lower head, and nozzle weld examinations. Additionally, the NRC staff notes that an unnecessary risk is created by the removal of the core barrel to perform a visual examination without a compensating increase in quality or safety. |
| | Finally, all of the previous inspections of Category B-N-2 and B-N-3 components at ANO-2 have not found any significant indications of cracking or any other problems. No evidence of service induced degradation has been noted in the same inspections at other similar nuclear power plants. Additionally, the NRC staff notes that the change in interval for the inspections does not impact the defense-in-depth philosophy. |
| | Based on the above, the NRC staff concludes that performing the examination of the RPV interior attachments and core support structure in an outage different from the RPV shell, head, and nozzle welds inspections would result in hardship or unusual difficulty without a compensating increase in quality or safety. Therefore, the proposed alternative is acceptable under the provisions of 10 CFR 50.55a(a)(3)(ii) until the end of the third interval, March 25, 2020. |
|
| |
|
| ==1.0 INTRODUCTION== | | ==4.0 CONCLUSION== |
|
| |
|
| By letter dated November 4, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093090314), Entergy Operations, Inc. (Entergy, the licensee), submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the approval for use of an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), Section XI, Paragraph IWB-2412, Inspection Program B. The proposed alternative was requested under Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(a)(3)(ii).
| | The NRC staff has completed its review of the submittal for AN02-ISI-005 regarding ANO-2. |
| The licensee requested approval for the use of alternative AN02-ISI-005, to extend the inservice inspection (lSI) interval for visual examinations of the Category B-N-2 components (Interior Attachments Within Beltline Region and Interior Attachments Beyond Beltline Region) and B-N-3 components (Core Support Structure), so that the examinations will be performed at the same time as the examinations of the B-A and B-D components (which are scheduled to occur in 2018).
| | The staff concludes that performing the lSI of Category B-N-2 and B-N-3 components every 10 years as required by Section XI of the ASME Code would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The staff concludes |
|
| |
|
| ==2.0 REGULATORY EVALUATION==
| | -4 that the Category B-N-2 and B-N-3 inspections may be performed as proposed and the alternative is authorized according to the provisions of 10 CFR 50.55a(a)(3)(ii) until the end of the third interval for Categories B-N-2 and B-N-3 components at ANO-2, which are scheduled to be performed in 2018. |
| | All other requirements of the ASME Code, Section XI for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector. |
| | Principal Contributor: C. Fairbanks Date: September 23, 2010 |
|
| |
|
| In accordance with 10 CFR 50.55a(g)(4), the licensee is required to perform lSI of ASME Code Class 1, 2, and 3 components and system pressure tests during the first 1 O-year interval and subsequent 1 O-year intervals that comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b), subject to the limitations and modifications listed therein. The ANO-2 Code of record for the inspection of ASME Code Class 1, 2, and 3 components is the 2001 Edition through 2003 Addenda of the ASME Code, Section XI. The regulations in 10 CFR 50.55a(a)(3) state, in part, that the Director of the Office of Nuclear Reactor Regulation may authorize an alternative to the requirements of 10 CFR 50.55a(g).
| | -2 The NRC staffs safety evaluation is enclosed. If you have any questions, please contact Kaly Kalyanam at (301) 415-1480 or via e-mail at kaly.kalyanam@nrc.gov. |
| For an alternative to be authorized, as per 10 CFR 50.55a(a)(3)(ii), the licensee must show that following the ASfVlE Enclosure
| | Sincerely, |
| -2 Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. 2.1 Background The visual inspection of Category B-N-2 and B-N-3 components to discover whether flaws have initiated, whether pre-existing flaws have extended, and whether pre-existing flaws may have been missed in prior examinations has always been done at the same time as the visual and ultrasonic lSI of Category B-A and B-D components.
| | /RA! |
| The licensee submitted a request (Request for Alternative AN02-ISI-004) to extend the lSI of the Category B-A and B-D components from 10 to 20 years by separate letter dated October 29, 2009 (ADAMS Accession No. ML093030136).
| | Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368 |
| By letter dated September 21, 2010 (ADAMS Accession No. ML 102450654), the NRC staff authorized Request for Alternative AN02-ISI-004.
| |
| The examinations of Category B-A and B-D components are required to be performed at regular intervals, as defined in Section XI of the ASME Code. Performing all of these inspections at the same time reduces the number of times that the unit's full core and internals must be moved to gain access for the examinations, in addition to significant savings in dose and outage duration.
| |
| 3.0 TECHNICAL EVALUATION 3.1 Description of Proposed Alternatives In AN02-ISI-005, the licensee proposes the interval for Category B-N-2 and B-N-3 inspections be the same as that for Category B-A and B-D inspections.
| |
| 3.2 Components for Which Relief is Requested Examination Category Item Number Description B-N-2 B13.50 Interior Attachments Within Beltline Region B-N-2 B13.60 Interior Attachments Beyond Beltline Region B-N-3 B13.70 Core Support Structure 3.3 Basis for Proposed Alternatives The basis for the alternative is that performing the visual inspections of the B-N-2 and B-N-3 components on a different schedule than the Category B-A and B-D components would result in significant hardship without a compensating increase in safety. The licensee indicates that the Category B-N-2 and B-N-3 components have been inspected regularly in the past and no significant indications were noted. Likewise, a review of the same Category B-N-2 and B-N-3 inspections at other, similar nuclear power plants have been performed many times without finding a significant indication.
| |
| Furthermore, in its letter dated November 4, 2009, the licensee notes that: The reactor vessel would undergo, as a minimum, the Section XI Examination Category B-P pressure tests and visual examination conducted at the end of
| |
| -3 each refueling before plant start-up, as well as leak tests with examinations that precede each start-up following maintenance or 3.4 NRC Staff Evaluation The NRC staff notes that the inspection of B-N-2 and B-N-3 components can only be done after the fuel and internals are removed from the reactor pressure vessel (RPV), and is usually only done at the same time as the lSI of Category B-A and B-D components.
| |
| In addition, the licensee's request is consistent with the industry practice of performing the Category B-N-2 and B-N-3 on the same schedule for the lSI for Category B-A and B-D welds. The licensee's request for alternative, AN02-ISI-004, to perform the B-A and B-D welds on a 20-year interval instead of a Code-required 10-year interval (i.e., postpone it to until the end of the third interval for Categories B-A and B-D components at ANO-2 on March 25, 2020, with the lSI examinations scheduled to occur in 2018) was reviewed by the NRC staff and by letter dated September 21, 2010 (ADAMS Accession No. ML 102450654), the staff authorized the request. The current relief request, AN02-ISI-005, to extend the lSI interval that is required by Examination Categories B-N-2 and B-N-3, is consistent with the industry practice stated in the previous paragraph.
| |
| The radiation exposure to establish the conditions for and perform the ASME examination categories B-N-2 and B-N-3 examinations would essentially double if the subject examinations were performed in an outage different from the RPV shell, lower head, and nozzle weld examinations.
| |
| Additionally, the NRC staff notes that an unnecessary risk is created by the removal of the core barrel to perform a visual examination without a compensating increase in quality or safety. Finally, all of the previous inspections of Category B-N-2 and B-N-3 components at ANO-2 have not found any significant indications of cracking or any other problems.
| |
| No evidence of induced degradation has been noted in the same inspections at other similar nuclear power plants. Additionally, the NRC staff notes that the change in interval for the inspections does not impact the defense-in-depth philosophy. | |
| Based on the above, the NRC staff concludes that performing the examination of the RPV interior attachments and core support structure in an outage different from the RPV shell, head, and nozzle welds inspections would result in hardship or unusual difficulty without a compensating increase in quality or safety. Therefore, the proposed alternative is acceptable under the provisions of 10 CFR 50.55a(a)(3)(ii) until the end of the third interval, March 25, 2020.
| |
|
| |
|
| ==4.0 CONCLUSION== | | ==Enclosure:== |
|
| |
|
| The NRC staff has completed its review of the submittal for AN02-ISI-005 regarding ANO-2. The staff concludes that performing the lSI of Category B-N-2 and B-N-3 components every 10 years as required by Section XI of the ASME Code would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The staff concludes
| | Safety Evaluation cc w/encl: Distribution via ListServ DISTRIBUTION: |
| -4 that the Category B-N-2 and B-N-3 inspections may be performed as proposed and the alternative is authorized according to the provisions of 10 CFR 50.55a(a)(3)(ii) until the end of the third interval for Categories B-N-2 and B-N-3 components at ANO-2, which are scheduled to be performed in 2018. All other requirements of the ASME Code, Section XI for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
| | PUBLIC LPL4 r/f RidsAcrsAcnw_lVIailCTR Resource RidsNrrDciCptb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMANO Resource RidsOgcRp Resource RidsRgn4MailCenter Resource CFairbanks, NRR/DCINIB ADAMS Accession No. ML102500128 *SE email I OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRIDCI/CPTB NRR/LPL4/BC NAME NKalyanam ...1Burkhardt MMitchell* MMarkley II DATE 9/22/10 9/17/10 8/31/10 9/23/10 OFFICIAL RECORD COpy}} |
| Principal Contributor:
| |
| C. Fairbanks Date: September 23, 2010
| |
| -2 The NRC staffs safety evaluation is enclosed.
| |
| If you have any questions, please contact Kaly Kalyanam at (301) 415-1480 or via e-mail at kaly.kalyanam@nrc.gov.
| |
| Sincerely, /RA! Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No.
| |
| Safety cc w/encl: Distribution via DISTRIBUTION: | |
| PUBLIC LPL4 r/f RidsAcrsAcnw_lVIailCTR Resource RidsNrrDciCptb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMANO Resource RidsOgcRp Resource RidsRgn4MailCenter Resource CFairbanks, NRR/DCINIB ADAMS Accession No. ML 102500128 | |
| *SE email I OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRIDCI/CPTB NRR/LPL4/BC NAME NKalyanam | |
| ...1 Burkhardt MMitchell* | |
| MMarkley II DATE 9/22/10 9/17/10 8/31/10 9/23/10 OFFICIAL RECORD COpy}} | |
Letter Sequence Other |
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MONTHYEARML0935004562009-12-16016 December 2009
Arkansas, Unit 2 - Acceptance Review E-mail, Relief Request ANO2-ISI-005 to Extend the Inservice Inspection Interval for the Visual Examination of Accessible Interior to Reactor Vessel Attachment Weld, for Fourth 10-Year Interval
Project stage: Acceptance Review
ML1025001282010-09-23023 September 2010
Relief Request ANO2-ISI-005 to Extend the Inservice Inspection Interval for the Visual Examination of Accessible Interior to Reactor Vessel Attachment Weld, for Fourth 10-Year Interval
Project stage: Other
2009-12-16
[Table View] |
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|---|
Category:Code Relief or Alternative
MONTHYEARML23142A1062023-05-24024 May 2023
Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035
ML22073A0952022-04-0707 April 2022
Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (EPID L-2021-LLR-0084) (NON-PROPRIETARY)
ML21299A0032021-10-28028 October 2021
and Waterford Steam Electric Station, Unit 3 - Approval of Request for Alternative EN-20-RR-003 from Certain Requirements of the ASME Code
ML21293A0962021-10-28028 October 2021
Relief ANO2-R&R-012 Concerning Proposed Alternative for Repair of Reactor Vessel Closure Head Penetration 46
ML21168A0562021-07-0909 July 2021
Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code
ML21118B0392021-05-19019 May 2021
Approval of Request for Alternative from Certain Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code
CNRO-2020-00016, Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)2020-08-12012 August 2020
Entergy Nuclear Operations, Inc - Relief Request EN-RR-20-002: Proposed Use of Subsequent ASME Code Edition and Addenda in Accordance with 10 CFR 50.55a(g)(4)(iv)
ML20121A1932020-05-0606 May 2020
Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves
ML20119A0732020-04-29029 April 2020
Withdrawal of Requested Alternatives for the Fifth 10-Year Interval Inservice Testing of Service Water Pumps and Visual Examination of Snubbers
ML20083J9682020-03-26026 March 2020
Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping
ML19254A6032019-09-19019 September 2019
Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1
2CAN071902, Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping2019-07-25025 July 2019
Request for Alternative ANO 2-PT-002 End-of-Interval System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping
ML19184A5542019-07-15015 July 2019
Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval
ML19156A4002019-06-11011 June 2019
Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code
CNRO-2019-00002, Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 12019-01-31031 January 2019
Relief Request Number EN-19-RR-1, Proposed Alternative to Use ASME Code Case N-831-1, Ultrasonic Examination in Lieu of Radiography for Welds in Ferritic or Austenitic Pipe Section XI, Division 1
ML18128A0672018-06-0808 June 2018
Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4
1CAN041801, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period2018-04-23023 April 2018
Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements Fourth 10-Year Interval, Second and Third Period
CNRO-2017-00022, Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 12017-11-17017 November 2017
Relief Request Number EN-17-RR-1 - Proposed Alternative to Use ASME Code Case N-513-4, Evaluation Criteria for Temporary Acceptance of Flaws in Moderate-Energy Class 2 or 3 Piping, Section XI, Division 1
ML17174B1442017-07-12012 July 2017
Relief Request for EN-ISI-16-1 Regarding Use of Later Edition and Addenda of the ASME Code
ML16130A4712016-12-0909 December 2016
Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants (CAC Nos. MF7537 and MF7538)
ML16237A0822016-08-29029 August 2016
Relief Request No. ANO1-ISI-025, Relief from American Society of Mechanical Engineers Section XI Table IWB-2500-1 Requirements
ML16096A2692016-06-0606 June 2016
Arkansas; Grand Gulf; James A. Fitzpatrick; Indian Point; Palisades; Pilgrim; River Bend; and Waterford - Relief Request RR-EN-15-2, Proposed Alternative to Use ASME Boiler and Pressure Vessel Code Case N-786-1
CNRO-2015-00017, Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, D2015-06-0505 June 2015
Entergy Submits Relief Request RR EN-15-1 - Proposed Alternative to Use ASME Code Case N-789-1, Alternative Requirements for Pad Reinforcement of Class 2 and 3 Moderate Energy Carbon Steel Piping for Raw Waster Service, Section XI, Division
ML15070A4282015-03-16016 March 2015
Relief Request ANO2-ISI-017, Alternative to Utilize ASME Code Case N-513-4 for the Fourth 10-Year Inservice Inspection Interval
ML15030A2392015-02-0909 February 2015
Correction to Relief Request ANO1-ISI-024 Issued December 23, 2014; Revises 10 CFR 50.55a Citations as a Result of Changes from Final Rule Effective December 5, 2014
ML14330A2072014-12-23023 December 2014
Relief Request ANO1-ISI-024, Alternative from Volumetric/Surface Examination Frequency Requirements of ASME Code Case N-729-1, Fourth 10-year Inservice Inspection Interval
ML14282A4792014-10-29029 October 2014
Relief Request ANO1-ISI-023, Volumetric Examination Frequency Requirements, for the Fourth 10-Year Inservice Inspection Interval
ML14150A1632014-06-0606 June 2014
Relief Request ANO2-ISI-004 - Alternative to Extend the Third 10-Year Inservice Inspection Interval for Reactor Vessel Weld Examinations
ML14099A4522014-04-15015 April 2014
Relief Request ANO2-ISI-016, from ASME Code Case N-770-1 Successive Examination, for the Fourth 10-Year Inservice Inspection Interval
ML13179A1162013-07-24024 July 2013
Request for Relief ANO1-ISI-022 from ASME Code Examination Requirements for Pressure-Retaining Welds in Piping; Fourth 10-Year Inservice Inspection Interval
ML13179A1102013-07-16016 July 2013
Request for Relief No. ANO1-ISI-021, from ASME Volumetric Requirements for Full Penetration Welded Nozzles in Vessels - Inspection Program B; Fourth 10-Year ISI Interval
ML13161A2412013-06-27027 June 2013
Relief Request ANO2-ISI-015, from Pressure Testing Requirements for Reactor Vessel Flange Seal Leak Detection Piping for the Fourth 10-Year Inservice Inspection Interval
ML13071A6342013-03-22022 March 2013
Relief Request ANO2-ISI-014, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Austenitic Stainless Steel, Third 10-Year Inservice Inspection Interval
ML13071A6632013-03-21021 March 2013
Relief Request ANO2-ISI-010, from Volumetric and Surface Exam Requirements for Pressure Retaining Welds in Piping, Third 10-Year Inservice Inspection Interval
ML13032A5732013-02-21021 February 2013
Relief Request Nos. ANO2-ISI-009, ANO2-ISI-011, and ANO2-ISI-012, ASME Code Volumetric and Surface Exam Requirements for Integral Attachment and Pressure-Retaining Welds, Third 10-Year Inservice Inspection Interval
ML12319A3672012-11-27027 November 2012
Relief Request ANO2-ISI-007, Alternative to Use ASME Code Case N-770-1 Baseline Examination, Fourth 10-Year Inservice Inspection Interval
1CAN071202, Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period2012-07-25025 July 2012
Requests for Relief from American Society of Mechanical Engineers (ASME) Section XI Volumetric Examination Requirements, Fourth 10-Year Interval, First Period
2CAN111101, Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-0072011-11-30030 November 2011
Use of Alternate ASME Code Case N-770-1 Baseline Examination Request for Alternative ANO2-ISI-007
ML1117107982011-08-10010 August 2011
Relief, ANO1-R&R-016, Request for Use of Non-ASME Code Repair to Service Water Piping in Accordance with Generic Letter 90-05, Fourth 10-Year Interval. ME6107
ML1034301562011-01-10010 January 2011
Relief Request ANO1-R&R-013, Proposed Alternative to Requirements Associated with Repair of Components, for Duration of ANO-1 Spring 2010 Refueling Outage 1R22
ML1035005322011-01-0505 January 2011
Request for Alternative ANO2-ISI-006, Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716 for the Fourth 10-Year ISI Interval
ML1025001282010-09-23023 September 2010
Relief Request ANO2-ISI-005 to Extend the Inservice Inspection Interval for the Visual Examination of Accessible Interior to Reactor Vessel Attachment Weld, for Fourth 10-Year Interval
ML1024506542010-09-21021 September 2010
Relief Request ANO2-ISI-004 to Extend Third Inservice Inspection Interval from 10 to 20 Years for Reactor Vessel Weld Examinations
ML1009103502010-08-19019 August 2010
Request for Relief PRR-ANO2-2010-1, Relief from the Requirements of Operation and Maintenance Code Section ISTB-5221 and ITSB-5223 for the Service Water Pumps
ML1011701272010-06-0202 June 2010
Request for Alternative ANO1-ISI-014, to Implement a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
ML1011701192010-05-0505 May 2010
Request for Relief Nos. ANO1-ISI-015, ANO1-ISI-016, ANO1-ISI-017, ANO1-ISI-018, ANO1-ISI-019, and ANO1-ISI-020, Relief from Requirements of the ASME Code, Section XI
ML1009706592010-04-26026 April 2010
Request for Alternative ANO2-ISI-003 to Use 2001 Edition Through 2003 Addenda in Lieu of the 2004 Edition for Fourth 10-Year Inservice Inspection Interval
2CAN021002, Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps2010-02-17017 February 2010
Request for Relief PRR-ANO2-2010-1 from the Requirements of OM Code Section ISTB-5221 and ISTB-5223 for the Service Water Pumps
2CAN011005, Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-7162010-01-28028 January 2010
Supplement to Request for Alternative Implementation of a Risk-Informed Inservice Inspection Program Based on ASME Code Case N-716
ML0923005512009-08-27027 August 2009
Request for Alternative ANO2-ISI-002 to 10 CFR 50.55a(g)(6)(ii)(D) Examination Requirements, for Remainder of Current 10-Year Inservice Inspection Interval and Fourth ISI Interval Until the Head Is Replaced
2023-05-24
[Table view]
Category:Letter
MONTHYEARML23326A0392024-01-24024 January 2024
Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML24017A1582024-01-17017 January 2024
Submittal of Emergency Plan Revision 50
IR 05000313/20234202024-01-10010 January 2024
Security Baseline Inspection Report 05000313/2023420 and 05000368/2023420
IR 05000313/20234022024-01-0202 January 2024
Security Baseline Inspection Report 05000313/2023402 and 05000368/2023402
ML23354A0022023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23349A1672023-12-21021 December 2023
Request for Withholding Information from Public Disclosure
ML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting
ML23352A0292023-12-13013 December 2023
Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection
ML23340A1592023-12-13013 December 2023
Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment
IR 05000313/20234052023-12-12012 December 2023
Security Baseline Inspection Report 05000313/2023405 and 05000368/2023405
ML23341A0832023-12-11011 December 2023
Material Control and Accounting Program Inspection Report 05000313/368/2023404- Cover Letter
ML23305A0922023-12-0707 December 2023
Summary of Regulatory Audit Regarding License Amendment Request to Revise Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b
ML23333A1362023-11-29029 November 2023
Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
ML23275A2072023-11-28028 November 2023
Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23325A1412023-11-21021 November 2023
Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation
IR 05000313/20230032023-11-21021 November 2023
Revised - ANO Revised Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/ 2023001
ML23243B0452023-11-13013 November 2023
Request for Withholding Information from Public Disclosure
ML23313A0962023-11-13013 November 2023
Integrated Inspection Report 05000313/2023003 and 05000368/2023003 and Independent Spent Fuel Storage Installation Inspection Report 07200013/2023001
ML23311A2082023-11-0909 November 2023
Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV
IR 05000313/20230112023-10-10010 October 2023
Commercial Grade Dedication Inspection Report 05000313/2023011 and 05000368/2023011
IR 05000313/20230052023-08-21021 August 2023
Updated Inspection Plan for Arkansas Nuclear One, Units 1 and 2 (Report 05000313/2023005 and 05000368/2023005) - Mid Cycle
IR 05000313/20243012023-08-14014 August 2023
Notification of NRC Initial Operator Licensing Examination 05000313/2024301
IR 05000313/20230022023-08-11011 August 2023
Integrated Inspection Report 05000313/2023002 and 05000368/2023002 and Notice of Violation
ML23209A6022023-08-0909 August 2023
Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk- Informed Completion Times
IR 05000416/20230022023-08-0808 August 2023
Integrated Inspection Report 05000416/2023002 and Independent Spent Fuel Storage Installation Inspection Report 07200050/2023001
ML23208A2132023-08-0303 August 2023
Regulatory Audit Summary Concerning Review of License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23208A2112023-07-27027 July 2023
Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions
ML23188A1732023-07-12012 July 2023
Request for Withholding Information from Public Disclosure
ML23142A2022023-06-29029 June 2023
Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements
IR 05000313/20234032023-06-28028 June 2023
Security Baseline Inspection Report 05000313/2023403 and 05000368/2023403
ML23178A0892023-06-26026 June 2023
August 2023 Emergency Preparedness Program Inspection-Request for Information
ML23166B0902023-06-21021 June 2023
Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements
ML23180A1082023-06-20020 June 2023
ANO Unit 1 SAR Amendment 31, TRM, TS Bases, 10 CFR 50.59 Report, and Commitment Change Summary Report
IR 05000313/20234012023-06-13013 June 2023
Cyber Security Inspection Report 05000313/2023401 and 05000368/2023401
ML23130A2972023-05-17017 May 2023
Notification of Inspection (NRC Inspection Report 05000313/2023003) and Request for Information
ML23121A3012023-05-10010 May 2023
Regulatory Audit Plan in Support of License Amendment Request to Revise Technical Specifications to Adopt Risk - Informed Completion Times
ML23114A3572023-05-10010 May 2023
Regulatory Audit Summary Concerning Review of Request for Alternative ANO-CISI-002 Regarding Containment Inservice Inspection Frequency
ML23130A2732023-05-10010 May 2023
and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
IR 05000313/20230012023-05-0909 May 2023
Integrated Inspection Report 05000313/2023001 and 05000368/2023001
ML23118A3202023-05-0808 May 2023
Notification of Biennial Problem Identification and Resolution Inspection and Request for Information (05000313;05000368/2023010)
IR 05000368/20233012023-05-0101 May 2023
NRC Examination Report 05000368/2023301
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
ML23108A1362023-04-24024 April 2023
Approval of Request for Half-Nozzle Repair of Reactor Vessel Closure Head Penetration No. 46
ML23110A1122023-04-20020 April 2023
Annual Report for Entergy Quality Assurance Program Manual Changes Under 10 CFR 50.54(a)(3), 10 CFR 71.106, and 10 CFR 72.140(d). Notification of Application of Approved Appendix B to 10 CFR 72 Subpart G
2024-01-24
[Table view]
Category:Safety Evaluation
MONTHYEARML23326A0392024-01-24024 January 2024
Issuance of Amendment No. 281 Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML23275A2072023-11-28028 November 2023
Issuance of Amendment No. 280 Removal of Technical Specification Condition Allowing Two Reactor Coolant Pump Operation
ML23142A2022023-06-29029 June 2023
Issuance of Amendment Nos. 279 and 332 Emergency Plan Staffing Requirements
ML23166B0902023-06-21021 June 2023
Request for Relief ANO1 ISI 036 Regarding Volumetric Examination Requirements
ML23142A1062023-05-24024 May 2023
Authorization and Safety Evaluation for Alternative Request No. ANO1-ISI-035
ML23117A2172023-05-0101 May 2023
Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment
ML22342B1602023-01-10010 January 2023
Requests for Relief ANO2-ISI-023, -024, -025, -026, -027, and -028 to Permit Reduction of Inspection Area Due to Interference (EPIDs L-2022-LLR-0022,-0023, -0024, -0025, -0026, and -0027)
ML22263A1912022-12-0909 December 2022
Issuance of Amendment No. 278 Revision to Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations (EPID L-2021-LLA-0181) - Non-Proprietary
ML22236A5452022-08-26026 August 2022
Correction to Issuance of Amendment No. 331 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors
ML22138A4312022-06-23023 June 2022
Issuance of Amendment No. 277 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components for Nuclear Power Reactors
ML22104A2222022-05-12012 May 2022
Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554
ML22083A1242022-04-28028 April 2022
Arkansas, Units 1 and 2; Grand Gulf Nuclear Station; River Bend Station; and Waterford Steam Electric Station - Issuance of Amendments Revise Technical Specifications to Adopt TSTF-541, Revision 2
ML22039A2822022-03-15015 March 2022
Issuance of Amendment Nos. 274 and 328 One-Time Change to Support Proactive Upgrade of the Emergency Cooling Pond Supply Piping
ML22007A3172022-01-18018 January 2022
1, River Bend Station 1, and Waterford Steam Electric Station 3 - Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI
ML21225A0552021-12-17017 December 2021
Issuance of Amendment No. 327 Addition of Technical Specification Limiting Condition for Operation 3.0.6 and Adoption of Safety Function Determination Program
ML21341B2262021-12-13013 December 2021
Acceptance of Requested Licensing Action License Amendment Request to Revise Technical Specifications 3.4.12 and 3.4.13 Based on Revised Dose Calculations
ML21313A0082021-12-0808 December 2021
Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML21208A4492021-09-20020 September 2021
Issuance of Amendment No. 325 Revise Loss of Voltage Relay Allowable Values and Number of Degraded Voltage Channels
ML21132A2792021-05-19019 May 2021
Request for Approval of Change to the Entergy Quality Assurance Program Manual
ML21088A4332021-04-14014 April 2021
Issuance of Amendment No. 324 Adoption of Technical Specification Task Force Traveler, TSTF-569, Revision 2, Revise Response Time Testing Definition
ML21027A4282021-03-23023 March 2021
Issuance of Amendment No. 272 Replacement of Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent
ML21040A5132021-03-10010 March 2021
Issuance of Amendment No. 271 Revision to Loss of Voltage Relay Allowable Values
ML20351A1532021-02-0808 February 2021
Issuance of Amendment No. 323 Technical Specification Deletions, Additions, and Relocations
ML20288A8242020-11-16016 November 2020
Regulatory Audit Summary Concerning License Amendment Request to Replace the Reactor Building Spray Sodium Hydroxide Additive with a Passive Reactor Building Sump Buffering Agent
NUREG-1432, Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-14322020-10-30030 October 2020
Issuance of Amendment No. 322 Technical Specification Changes Related to Revised Fuel Handling Accident Analysis and Adoption of Technical Specification Improvements Consistent with NUREG-1432
ML20226A2722020-08-18018 August 2020
Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI
ML20160A1472020-06-30030 June 2020
Issuance of Amendment No. 270 to Adopt TSTF 563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program
ML20135H1412020-06-30030 June 2020
Issuance of Amendment Nos. 269 and 321 Request to Incorporate the Tornado Missile Risk Evaluator Into the Licensing Basis
ML20121A1932020-05-0606 May 2020
Alternative Requests for the Fifth 10 Year Interval Inservice Testing of Low Pressure Safety Injection Pumps and Service Water Valves
ML20107J3172020-04-23023 April 2020
Relief Request ANO1-ISI-033 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles
ML20087L8032020-04-0808 April 2020
Issuance of Amendment No. 320 to Revise Control Element Assembly Drop Times
ML20083J9682020-03-26026 March 2020
Approval of Request for Alternative ANO 2-PT-002 End-of-Internal System Leakage Test for Extended Reactor Coolant Pressure Boundary Piping
ML19231A2972020-01-29029 January 2020
Issuance of Amendment No. 318 Addition of Technical Specification Actions to Address Inoperability of the Containment Building Sump
ML19220A9382019-09-27027 September 2019
Issuance of Amendment No. 266 Adoption of Technical Specifications Task Force Traveler TSTF-567, Revision 1, Add Containment Sump TS to Address GSI-191 Issues
ML19254A6032019-09-19019 September 2019
Units 2 and 3; Palisades Nuclear Plant; River Bend; and Waterford Steam Electric Station, Unit 3 - Relief Request No. EN-19-RR-1, Use of ASME Code Case N-831-1
ML19175A0422019-09-11011 September 2019
Arkansas Units 1 and 2; Grand Gulf, Unit 1; Indian Point 2 and 3; Palisades; River Bend, Unit 1; Waterford Unit 3 - Issuance of Amendments to Adopt TSTF-529, Clarify Use and Application Rules
ML19184A5542019-07-15015 July 2019
Request for Relief ANO1-ISI-032 from the ASME Code Section XI Visual Examination Requirements for the Fourth 10-Year Inservice Inspection Interval
ML19156A4002019-06-11011 June 2019
Request for Alternative ANO2-ISI-021 to Permit Continued Application of the 2007 Edition Through the 2008 Addenda of ASME Code
ML19098A9552019-05-22022 May 2019
Issuance of Amendment No. 264 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-425, Revision 3
ML19063B9482019-04-23023 April 2019
Issuance of Amendment No. 315 Adoption of Technical Specification Task Force Traveler TSTF-425, Revision 3
ML18337A2472019-01-17017 January 2019
Issuance of Amendment Nos. 263 and 314 Revision to Emergency Action Level Scheme
ML18346A3142019-01-0707 January 2019
Relief Nos. ANO1-ISI-027, -028, -029, -030, and -031 from ASME Code, Section XI, Examination Requirements for Fourth 10-Year Inservice Inspection Interval (EPID L-2018-LLR-0063, -0064, -0065, -0066, -0067)
ML18317A3822018-12-19019 December 2018
Issuance of Amendment No. 313, Revise Technical Specification 3.3.3.6, Post-Accident Instrumentation
ML18298A0122018-11-27027 November 2018
Issuance of Amendment No. 311 Updating the Reactor Coolant System Pressure Temperature Limits
ML18260A3392018-10-24024 October 2018
Issuance of Amendment No. 261 Revision to Technical Specification Bases Related to Emergency Feedwater Turbine-Driven Pump Steam Supply Valves
ML18192A1042018-08-15015 August 2018
Alternative to Examination of Reactor Pressure Vessel Flange Threads
ML18173A0192018-06-27027 June 2018
Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule (CAC MG0244; EPID L-2017-LLL-0020)
ML18115A2822018-06-19019 June 2018
Issuance of Amendment No. 260 Technical Specification Changes Pursuant to Technical Specifications Task Force (TSTF) Traveler TSTF-412 Revision 3 (CAC No. MG0009; EPID L-2017-LLA-0267)
ML18134A2532018-06-19019 June 2018
Issuance of Amendment No. 310 Technical Specification Changes to Provide Actions for Emergency Feedwater Pump Inoperability Consistent with NUREG-1432, Revision 4 (CAC No. MG0016; EPID L-2017-LLA-0268)
ML18128A0672018-06-0808 June 2018
Arkansas, Units 1 and 2; Grand Gulf, Unit 1; Indian Point Unit Nos. 2 and 3; Palisades; Pilgrim; River Bend Station, Unit 1; and Waterford, Unit-3 Relief Request No. EN-17-RR-1, Alternative to Use ASME Code Case N-513-4
2024-01-24
[Table view] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 September 23, 2010 Vice President, Operations Arkansas Nuclear One Entergy Operations, Inc.
1448 S. R. 333 Russellville, AR 72802 SUB..IECT: ARKANSAS NUCLEAR ONE, UNIT 2 - REQUEST FOR RELIEF AN02-ISI-005, REQUEST TO EXTEND THE INSERVICE INSPECTION INTERVAL FOR THE VISUAL EXAMINATION OF ACCESSIBLE INTERIOR TO REACTOR VESSEL ATTACHMENT WELD (TAC NO. ME2566)
Dear Sir or Madam:
By letter dated November 4,2009, Entergy Operations, Inc. (the licensee), submitted, pursuant to paragraph 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), a request for relief for the Arkansas Nuclear One, Unit 2 (ANO-2), for visual examination of the accessible interior attachment welds within and beyond the beltline region and a visual examination of the accessible core support structure surfaces of the reactor pressure vessel once each 10-year inservice inspection (lSI) interval.
Specifically, the licensee requested permission to extend, from 10 to 20 years, the lSI interval that is required by Examination Categories B-N-2 and B-N-3 of Table IWB-2500-1 of Section XI of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), 2001 Edition, 2003 Addenda for the third 10-year lSI interval for ANO-2. This proposed alternative is applicable to the third 10-year lSI for the examination categories B-N-2 and B-N-3, Items B13.50, B13.60, and B13.70 visual examinations.
The U.S. Nuclear Regulatory Commission (NRC) staff has reviewed the licensee's submittal and determined that compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(ii), the NRC staff authorizes relief request AN02-ISI-005, until the end of the third 1O-year lSI interval for Examination Categories B-N-2 and B-N-3, Items B13.50, B13.60, and B13.70, at ANO-2, which are scheduled to be performed in 2018.
All other requirements of the ASME Code,Section XI for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
-2 The NRC staffs safety evaluation is enclosed. If you have any questions, please contact Kaly Kalyanam at (301) 415-1480 or via e-mail at kaly.kalyanam@nrc.gov.
Sincerely, Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST AN02-ISI-005 REQUEST TO EXTEND B-N-2 AND B-N-3 COMPONENT EXAMINATIONS ENTERGY OPERATIONS, INC.
ARKANSAS NUCLEAR ONE, UNIT 2 DOCKET NO. 50-382
1.0 INTRODUCTION
By letter dated November 4, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093090314), Entergy Operations, Inc. (Entergy, the licensee),
submitted a request to the U.S. Nuclear Regulatory Commission (NRC) for the approval for use of an alternative to the requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code),Section XI, Paragraph IWB-2412, Inspection Program B. The proposed alternative was requested under Title 10 of the Code of Federal Regulations (10 CFR) paragraph 50.55a(a)(3)(ii).
The licensee requested approval for the use of alternative AN02-ISI-005, to extend the inservice inspection (lSI) interval for visual examinations of the Category B-N-2 components (Interior Attachments Within Beltline Region and Interior Attachments Beyond Beltline Region) and B-N-3 components (Core Support Structure), so that the examinations will be performed at the same time as the examinations of the B-A and B-D components (which are scheduled to occur in 2018).
2.0 REGULATORY EVALUATION
In accordance with 10 CFR 50.55a(g)(4), the licensee is required to perform lSI of ASME Code Class 1, 2, and 3 components and system pressure tests during the first 1O-year interval and subsequent 1O-year intervals that comply with the requirements in the latest edition and addenda of Section XI of the ASME Code, incorporated by reference in 10 CFR 50.55a(b),
subject to the limitations and modifications listed therein.
The ANO-2 Code of record for the inspection of ASME Code Class 1, 2, and 3 components is the 2001 Edition through 2003 Addenda of the ASME Code,Section XI. The regulations in 10 CFR 50.55a(a)(3) state, in part, that the Director of the Office of Nuclear Reactor Regulation may authorize an alternative to the requirements of 10 CFR 50.55a(g). For an alternative to be authorized, as per 10 CFR 50.55a(a)(3)(ii), the licensee must show that following the ASfVlE Enclosure
-2 Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
2.1 Background The visual inspection of Category B-N-2 and B-N-3 components to discover whether flaws have initiated, whether pre-existing flaws have extended, and whether pre-existing flaws may have been missed in prior examinations has always been done at the same time as the visual and ultrasonic lSI of Category B-A and B-D components. The licensee submitted a request (Request for Alternative AN02-ISI-004) to extend the lSI of the Category B-A and B-D components from 10 to 20 years by separate letter dated October 29, 2009 (ADAMS Accession No. ML093030136). By letter dated September 21, 2010 (ADAMS Accession No. ML102450654), the NRC staff authorized Request for Alternative AN02-ISI-004. The examinations of Category B-A and B-D components are required to be performed at regular intervals, as defined in Section XI of the ASME Code. Performing all of these inspections at the same time reduces the number of times that the unit's full core and internals must be moved to gain access for the examinations, in addition to significant savings in dose and outage duration.
3.0 TECHNICAL EVALUATION
3.1 Description of Proposed Alternatives In AN02-ISI-005, the licensee proposes the interval for Category B-N-2 and B-N-3 inspections be the same as that for Category B-A and B-D inspections.
3.2 Components for Which Relief is Requested Examination Category Item Number Description B-N-2 B13.50 Interior Attachments Within Beltline Region B-N-2 B13.60 Interior Attachments Beyond Beltline Region B-N-3 B13.70 Core Support Structure 3.3 Basis for Proposed Alternatives The basis for the alternative is that performing the visual inspections of the B-N-2 and B-N-3 components on a different schedule than the Category B-A and B-D components would result in significant hardship without a compensating increase in safety. The licensee indicates that the Category B-N-2 and B-N-3 components have been inspected regularly in the past and no significant indications were noted. Likewise, a review of the same Category B-N-2 and B-N-3 inspections at other, similar nuclear power plants have been performed many times without finding a significant indication.
Furthermore, in its letter dated November 4, 2009, the licensee notes that:
The reactor vessel would undergo, as a minimum, the Section XI Examination Category B-P pressure tests and visual examination conducted at the end of
-3 each refueling before plant start-up, as well as leak tests with visual examinations that precede each start-up following maintenance or repair activities.
3.4 NRC Staff Evaluation The NRC staff notes that the inspection of B-N-2 and B-N-3 components can only be done after the fuel and internals are removed from the reactor pressure vessel (RPV), and is usually only done at the same time as the lSI of Category B-A and B-D components. In addition, the licensee's request is consistent with the industry practice of performing the Category B-N-2 and B-N-3 on the same schedule for the lSI for Category B-A and B-D welds.
The licensee's request for alternative, AN02-ISI-004, to perform the B-A and B-D welds on a 20-year interval instead of a Code-required 10-year interval (i.e., postpone it to until the end of the third interval for Categories B-A and B-D components at ANO-2 on March 25, 2020, with the lSI examinations scheduled to occur in 2018) was reviewed by the NRC staff and by letter dated September 21, 2010 (ADAMS Accession No. ML102450654), the staff authorized the request.
The current relief request, AN02-ISI-005, to extend the lSI interval that is required by Examination Categories B-N-2 and B-N-3, is consistent with the industry practice stated in the previous paragraph.
The radiation exposure to establish the conditions for and perform the ASME examination categories B-N-2 and B-N-3 examinations would essentially double if the subject examinations were performed in an outage different from the RPV shell, lower head, and nozzle weld examinations. Additionally, the NRC staff notes that an unnecessary risk is created by the removal of the core barrel to perform a visual examination without a compensating increase in quality or safety.
Finally, all of the previous inspections of Category B-N-2 and B-N-3 components at ANO-2 have not found any significant indications of cracking or any other problems. No evidence of service induced degradation has been noted in the same inspections at other similar nuclear power plants. Additionally, the NRC staff notes that the change in interval for the inspections does not impact the defense-in-depth philosophy.
Based on the above, the NRC staff concludes that performing the examination of the RPV interior attachments and core support structure in an outage different from the RPV shell, head, and nozzle welds inspections would result in hardship or unusual difficulty without a compensating increase in quality or safety. Therefore, the proposed alternative is acceptable under the provisions of 10 CFR 50.55a(a)(3)(ii) until the end of the third interval, March 25, 2020.
4.0 CONCLUSION
The NRC staff has completed its review of the submittal for AN02-ISI-005 regarding ANO-2.
The staff concludes that performing the lSI of Category B-N-2 and B-N-3 components every 10 years as required by Section XI of the ASME Code would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety. The staff concludes
-4 that the Category B-N-2 and B-N-3 inspections may be performed as proposed and the alternative is authorized according to the provisions of 10 CFR 50.55a(a)(3)(ii) until the end of the third interval for Categories B-N-2 and B-N-3 components at ANO-2, which are scheduled to be performed in 2018.
All other requirements of the ASME Code,Section XI for which relief was not specifically requested and approved in the subject request for relief remain applicable, including third-party review by the Authorized Nuclear Inservice Inspector.
Principal Contributor: C. Fairbanks Date: September 23, 2010
-2 The NRC staffs safety evaluation is enclosed. If you have any questions, please contact Kaly Kalyanam at (301) 415-1480 or via e-mail at kaly.kalyanam@nrc.gov.
Sincerely,
/RA!
Michael T. Markley, Chief Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-368
Enclosure:
Safety Evaluation cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL4 r/f RidsAcrsAcnw_lVIailCTR Resource RidsNrrDciCptb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl4 Resource RidsNrrLAJBurkhardt Resource RidsNrrPMANO Resource RidsOgcRp Resource RidsRgn4MailCenter Resource CFairbanks, NRR/DCINIB ADAMS Accession No. ML102500128 *SE email I OFFICE NRR/LPL4/PM NRR/LPL4/LA NRRIDCI/CPTB NRR/LPL4/BC NAME NKalyanam ...1Burkhardt MMitchell* MMarkley II DATE 9/22/10 9/17/10 8/31/10 9/23/10 OFFICIAL RECORD COpy
