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| | number = ML14267A470 | | | number = ML14267A470 |
| | issue date = 09/24/2014 | | | issue date = 09/24/2014 |
| | title = BVPS Additional Draft RAIs License Amendment Request to Extend Containment Leakage Test Frequency (TAC Nos. MF3985 and MF3986) | | | title = BVPS Additional Draft RAIs License Amendment Request to Extend Containment Leakage Test Frequency |
| | author name = Whited J A | | | author name = Whited J |
| | author affiliation = NRC/NRR/DORL/LPLI-2 | | | author affiliation = NRC/NRR/DORL/LPLI-2 |
| | addressee name = | | | addressee name = |
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| | docket = 05000334, 05000412 | | | docket = 05000334, 05000412 |
| | license number = DPR-066, NPF-073 | | | license number = DPR-066, NPF-073 |
| | contact person = Whited J A | | | contact person = Whited J |
| | case reference number = TAC MF3985, TAC MF3986 | | | case reference number = TAC MF3985, TAC MF3986 |
| | document type = Request for Additional Information (RAI) | | | document type = Request for Additional Information (RAI) |
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| {{#Wiki_filter:DRAFT DRAFT REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO A LICENSE AMENDMENT REQUEST TO EXTEND CONTAINMENT LEAKAGE TEST FREQUENCY BEAVER VALLEY POWER STATION - UNITS 1 AND 2 DOCKET NO. 50-344 AND 50-412 By letter dated April 16, 2014, 1 FirstEnergy Nuclear Operating Company (the licensee) submitted a license amendment request for Beaver Valley Power Station (BVPS) Units 1 and | | {{#Wiki_filter:DRAFT REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO A LICENSE AMENDMENT REQUEST TO EXTEND CONTAINMENT LEAKAGE TEST FREQUENCY BEAVER VALLEY POWER STATION - UNITS 1 AND 2 DOCKET NO. 50-344 AND 50-412 By letter dated April 16, 2014,1 FirstEnergy Nuclear Operating Company (the licensee) submitted a license amendment request for Beaver Valley Power Station (BVPS) Units 1 and |
| : 2. The proposed amendment would modify BVPS Technical Specification 5.5.12, "Containment Leakage Rate Testing Program," Item a, be deleting reference to the BVPS-1 exemption letter dated December 5, 1984, 2 and requiring compliance with Nuclear Energy Institute (NEI) topical report NEI 94-01, Revision 3-A, 3 "Industry Guideline for Implementing Performance-Based Option of [Title 10 to the Code of Federal Regulations] 10 CFR Part 50 Appendix J," instead of Regulatory Guide 1.163, 4 "Performance Based Containment Leak Test Program," including listed exceptions. This change will allow BVPS 1 and 2 to extend the Type A reactor containment test, required by 10 CFR Part 50 Appendix J, test interval from one test in 10 years up to one test in 15 years and extension of the Type C test interval up to 75 months. To | | : 2. The proposed amendment would modify BVPS Technical Specification 5.5.12, Containment Leakage Rate Testing Program, Item a, be deleting reference to the BVPS-1 exemption letter dated December 5, 1984,2 and requiring compliance with Nuclear Energy Institute (NEI) topical report NEI 94-01, Revision 3-A,3 Industry Guideline for Implementing Performance-Based Option of [Title 10 to the Code of Federal Regulations] 10 CFR Part 50 Appendix J, instead of Regulatory Guide 1.163,4 Performance Based Containment Leak Test Program, including listed exceptions. This change will allow BVPS 1 and 2 to extend the Type A reactor containment test, required by 10 CFR Part 50 Appendix J, test interval from one test in 10 years up to one test in 15 years and extension of the Type C test interval up to 75 months. To complete its review, the Nuclear Regulatory Commission (NRC) staff in the Mechanical and Civil Engineering Branch (EMCB) request a response to the questions below. |
| | | EMCB RAI 1 The first five rows in the Scheduled Outage column of the table in Section 3.2.1, Containment Inservice Inspection Program, on page 21 of 54 of the licensees submittal list 1R25, 1R28, 1R30, and the 10th and 11th rows list 2R20, 2R23, 2R24. |
| complete its review, the Nuclear Regulatory Commission (NRC) staff in the Mechanical and Civil Engineering Branch (EMCB) request a response to the questions below. | | : a. Explain why 1R27, 1R29 and 1R31 are not listed for the first five rows and 2R22 is not listed for rows 10 and 11. |
| | | : b. Also, in the same table, 4th column, Exam Method, explain why VT-3 examination is performed once per 10-year interval for 1-CNMT-SPARE-PENE-BOLTING, and 2-CNMT-ELEC-PENE-BOLTING. |
| EMCB RAI 1 The first five rows in the "Scheduled Outage" column of the table in Section 3.2.1, "Containment Inservice Inspection Program", on page 21 of 54 of the licensee's submittal list "1R25, 1R28, 1R30," and the 10 th and 11 th rows list "2R20, 2R23, 2R24." | | EMCB RAI 2 Section 3.1.2, Type B and C Testing and Tables on pages 12 and 13 of 54 of Reference 1, describes Type B and C testing and leak rate summation history for Units 1 and 2 (respectively), which indicated the as-found minimum pathway summations, and the as-left maximum pathway summations, 1 |
| : a. Explain why 1R27, 1R29 and 1R31 are not listed for the first five rows and 2R22 is not listed for rows 10 and 11. | | Agencywide Documents Access and Management System (ADAMS) Accession No. ML14111A291. |
| : b. Also, in the same table, 4 th column, "Exam Method", explain why VT-3 examination is performed once per 10-year interval for 1-CNMT-SPARE-PENE-BOLTING, and 2-CNMT-ELEC-PENE-BOLTING. | |
| EMCB RAI 2 Section 3.1.2, "Type B and C Testing" and Tables on pages 12 and 13 of 54 of Reference 1, describes Type B and C testing and leak rate summation history for Units 1 and 2 (respectively), which indicated the as-found minimum pathway summations, and the as-left maximum pathway summations, 1 Agencywide Documents Access and Management System (ADAMS) Accession No. ML14111A291. | |
| 2 ADAMS Accession No. ML003766713. | | 2 ADAMS Accession No. ML003766713. |
| 3 ADAMS Accession No. ML12221A202. | | 3 ADAMS Accession No. ML12221A202. |
| 4 ADAMS Accession No. ML003740058. | | 4 ADAMS Accession No. ML003740058. |
| representing the effective management of the Containment Leakage Rate Testing Program. In order for the NRC staff to assess the proper and effective implementation of the Type B and Type C local leak rate testing program for each unit, please provide the following:
| | DRAFT |
| : a. For the last two consecutive periodic tests, please provide a table that has (1) the component(s) that have not demonstrated acceptable
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| performance, (2) the as-found value, (3) the acceptable value, (4) the as-left value, (5) the causes of the test failure, (6) the corrective actions taken, and (7) the next test schedule intervals.
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| : b. A discussion of any operating experience and evaluation results, regarding the potential for, or presence of, corrosive conditions at the concrete-to-metal interface at the basement floor of the containment. The discussion should include the potential for stagnant water to be trapped behind a degraded floor seal (moisture barrier) area that could promote
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| pitting corrosion. This item is r equested to be consistent with NRC Information Notice 2004-09, "Corrosion of Steel Containment and Containment Liner."}} | | representing the effective management of the Containment Leakage Rate Testing Program. In order for the NRC staff to assess the proper and effective implementation of the Type B and Type C local leak rate testing program for each unit, please provide the following: |
| | : a. For the last two consecutive periodic tests, please provide a table that has (1) the component(s) that have not demonstrated acceptable performance, (2) the as-found value, (3) the acceptable value, (4) the as-left value, (5) the causes of the test failure, (6) the corrective actions taken, and (7) the next test schedule intervals. |
| | : b. A discussion of any operating experience and evaluation results, regarding the potential for, or presence of, corrosive conditions at the concrete-to-metal interface at the basement floor of the containment. The discussion should include the potential for stagnant water to be trapped behind a degraded floor seal (moisture barrier) area that could promote pitting corrosion. This item is requested to be consistent with NRC Information Notice 2004-09, "Corrosion of Steel Containment and Containment Liner."}} |
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Category:Request for Additional Information (RAI)
MONTHYEARML24204A0012024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports ML24044A1772024-02-14014 February 2024 RAI for 180 Days Steam Generator Report ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23122A0342023-05-0202 May 2023 NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report ML22312A5912022-11-0808 November 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22278A0972022-10-0606 October 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Fire Protection Program Changes ML22178A1322022-06-24024 June 2022 Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage ML22068A1822022-03-0909 March 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 ML22013A7512022-01-13013 January 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010 ML21292A0482021-10-19019 October 2021 Ti 2515/194 Inspection Documentation Request ML21259A1642021-09-16016 September 2021 NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits ML21124A1322021-05-0404 May 2021 Notification of Conduct of a Fire Protection Team Inspection ML21102A1542021-04-0909 April 2021 Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR ML21082A4942021-03-23023 March 2021 Final RAIs for GL 04-02 Closure (Email) ML21068A3502021-03-0909 March 2021 Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing ML21015A5762021-01-14014 January 2021 Final RAIs for Steam Generator 180 Day Tube Inspection Report ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20290B0082020-10-0808 October 2020 Draft Request for Additional Information - Steam Generator Letter ML20127H8672020-05-0606 May 2020 NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements ML20072N0402020-03-12012 March 2020 Request for Additional Information - Control Envelope Habitability LAR ML19192A2222019-07-18018 July 2019 Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19143A0732019-05-29029 May 2019 FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments ML18242A3642018-08-29029 August 2018 Request for Additional Information (Final) -Steam Generator Technical Specification LAR ML18102B0852018-04-12012 April 2018 NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver ML18043A0102018-02-0909 February 2018 NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans ML18024B3642018-01-24024 January 2018 NRR E-mail Capture - Beaver Valley 10 CFR 50.54(f) - NTTF 2.1 SPRA Review ML18019A0722018-01-18018 January 2018 NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule ML17353A1582017-12-19019 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17352B2612017-12-18018 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17303B1582017-11-0707 November 2017 FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information ML17256A2502017-09-13013 September 2017 NRR E-mail Capture - Beaver Valley Power Station Units 1&2: Request for Additional Information for Emergency Plan EAL Change to Adopt NEI 99-01, Rev. 6, ML17220A2342017-08-0808 August 2017 E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request ML17093A7622017-04-10010 April 2017 Request for Additional Information Regarding Emergency Action Level Scheme Change License Amendment Request ML17031A0362017-02-0303 February 2017 Request for Additional Information Regarding Relief Request Numbers PR6 and PR7 ML16333A0162016-12-0202 December 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16147A2842016-06-14014 June 2016 Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections ML16071A1222016-04-0707 April 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16084A8442016-03-30030 March 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16060A0122016-02-29029 February 2016 FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120 ML15320A4132015-11-24024 November 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15280A0742015-10-0909 October 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15279A1252015-10-0505 October 2015 Licensed Operator Positive for Fitness-for-Duty-Test ML15181A2142015-07-14014 July 2015 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 & MF6055) ML15125A4162015-05-11011 May 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 (TAC Nos. MF3301 & MF3302) ML15016A4392015-01-20020 January 2015 Draft Request for Additional Information ML15007A5582015-01-15015 January 2015 Request for Additional Information Steam Generator Inspection Reports 2024-07-17
[Table view] |
Text
DRAFT REQUEST FOR ADDITIONAL INFORMATION OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR ADDITIONAL INFORMATION RELATED TO A LICENSE AMENDMENT REQUEST TO EXTEND CONTAINMENT LEAKAGE TEST FREQUENCY BEAVER VALLEY POWER STATION - UNITS 1 AND 2 DOCKET NO. 50-344 AND 50-412 By letter dated April 16, 2014,1 FirstEnergy Nuclear Operating Company (the licensee) submitted a license amendment request for Beaver Valley Power Station (BVPS) Units 1 and
- 2. The proposed amendment would modify BVPS Technical Specification 5.5.12, Containment Leakage Rate Testing Program, Item a, be deleting reference to the BVPS-1 exemption letter dated December 5, 1984,2 and requiring compliance with Nuclear Energy Institute (NEI) topical report NEI 94-01, Revision 3-A,3 Industry Guideline for Implementing Performance-Based Option of [Title 10 to the Code of Federal Regulations] 10 CFR Part 50 Appendix J, instead of Regulatory Guide 1.163,4 Performance Based Containment Leak Test Program, including listed exceptions. This change will allow BVPS 1 and 2 to extend the Type A reactor containment test, required by 10 CFR Part 50 Appendix J, test interval from one test in 10 years up to one test in 15 years and extension of the Type C test interval up to 75 months. To complete its review, the Nuclear Regulatory Commission (NRC) staff in the Mechanical and Civil Engineering Branch (EMCB) request a response to the questions below.
EMCB RAI 1 The first five rows in the Scheduled Outage column of the table in Section 3.2.1, Containment Inservice Inspection Program, on page 21 of 54 of the licensees submittal list 1R25, 1R28, 1R30, and the 10th and 11th rows list 2R20, 2R23, 2R24.
- a. Explain why 1R27, 1R29 and 1R31 are not listed for the first five rows and 2R22 is not listed for rows 10 and 11.
- b. Also, in the same table, 4th column, Exam Method, explain why VT-3 examination is performed once per 10-year interval for 1-CNMT-SPARE-PENE-BOLTING, and 2-CNMT-ELEC-PENE-BOLTING.
EMCB RAI 2 Section 3.1.2, Type B and C Testing and Tables on pages 12 and 13 of 54 of Reference 1, describes Type B and C testing and leak rate summation history for Units 1 and 2 (respectively), which indicated the as-found minimum pathway summations, and the as-left maximum pathway summations, 1
Agencywide Documents Access and Management System (ADAMS) Accession No. ML14111A291.
2 ADAMS Accession No. ML003766713.
3 ADAMS Accession No. ML12221A202.
4 ADAMS Accession No. ML003740058.
DRAFT
representing the effective management of the Containment Leakage Rate Testing Program. In order for the NRC staff to assess the proper and effective implementation of the Type B and Type C local leak rate testing program for each unit, please provide the following:
- a. For the last two consecutive periodic tests, please provide a table that has (1) the component(s) that have not demonstrated acceptable performance, (2) the as-found value, (3) the acceptable value, (4) the as-left value, (5) the causes of the test failure, (6) the corrective actions taken, and (7) the next test schedule intervals.
- b. A discussion of any operating experience and evaluation results, regarding the potential for, or presence of, corrosive conditions at the concrete-to-metal interface at the basement floor of the containment. The discussion should include the potential for stagnant water to be trapped behind a degraded floor seal (moisture barrier) area that could promote pitting corrosion. This item is requested to be consistent with NRC Information Notice 2004-09, "Corrosion of Steel Containment and Containment Liner."