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Category:Code Relief or Alternative
MONTHYEARML21299A0032021-10-28028 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 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) ML20022A2582020-01-28028 January 2020 Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control ML20002A0202020-01-13013 January 2020 Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System 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 ML19247B1972019-09-0909 September 2019 Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination ML19232A0252019-08-27027 August 2019 Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities W3F1-2019-0052, CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2)2019-07-18018 July 2019 CFR 50.55a Relief Number WF3-RR-19-2, Proposed Alternative to Code Case N-666-1, Weld Overlay of Class 1, 2, and 3 Socket Welded Connections, Section XI, Division 1 in Accordance with 10 CFR 50.55a(z)(2) 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 W3F1-2018-0065, Request for Relief from ASME Section XI Volumetric Examination Requirements - Third 10-Year Interval, W3-ISI-0322018-11-30030 November 2018 Request for Relief from ASME Section XI Volumetric Examination Requirements - Third 10-Year Interval, W3-ISI-032 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 ML17341A1202017-12-11011 December 2017 Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049) ML17328A8822017-11-29029 November 2017 Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47) 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 ML17069A1872017-03-22022 March 2017 Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024 ML16235A2282016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML16182A2702016-07-0606 July 2016 Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program 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 ML14070A0082014-03-26026 March 2014 Request for Alternative W3-ISI-023, ASME Code Case N-770-1 Successive Examinations, Third 10-Year Inservice Inspection Interval ML13192A2222013-08-0202 August 2013 Request for Alternative W3-ISI-021, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval ML13128A1292013-05-31031 May 2013 Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval ML13085A1592013-03-26026 March 2013 Verbal Authorization on 12/18/2012, Request for Alternative W3-ISI-021, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval ML13085A1252013-03-26026 March 2013 Verbal Authorization on 12/18/2012, Revised Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request for the Third 10-Year Inservice Inspection Interval ML12293A3622012-11-0808 November 2012 Relief Request VRR-WF3-2012-1 Associated with Category a Leak Test of Component Cooling Water Check Valve ACC-108B for the Third 10-Year Inservice Inspection Interval W3F1-2012-0085, Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request2012-10-16016 October 2012 Request for Alternative W3-ISI-020, ASME Code Case N-770-1 Baseline Examination Request ML12234A6352012-08-21021 August 2012 Verbal Authorization of Relief Request VRR-WF3-2012-1 ML1133301372012-01-0404 January 2012 Request for Alternative W3-CISI-002 to ASME Code, Section XI, IWE-5221 for Post-repair Testing of Steel Containment Vessel Opening, Third 10-Year Inservice Inspection Interval ML1125701682011-10-14014 October 2011 Request for Alternative W3-ISI-019 from Inservice Inspection Requirements of Reactor Vessel Head In-Core Instrument Nozzles, Third 10-Year Inservice Inspection Interval ML1125702732011-10-14014 October 2011 Request for Alternative W3-ISI-018 from Inservice Inspection Requirements of Reactor Pressure Vessel Head Control Element Drive Mechanism Nozzles, Third 10-Year Inservice Inspection Interval ML1035703922011-01-13013 January 2011 Relief Request No. W3-ISI-017, Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection, for Third 10-Year Inservice Inspection Interval ML1029903712010-11-23023 November 2010 Correction to May 18, 2010 Safety Evaluation for Relief Request No. W3-CISI-001 Regarding Post Repair Testing of the Steel Containment Vessel Opening ML1015905742010-06-30030 June 2010 Relief Request Nos. WF3-ISI-007 to WF3-ISI-014 from ASME Code, Section XI Volumetric Examination Requirements - Second 10-Year Interval ML1008500892010-05-18018 May 2010 Relief Request W3-CISI-001, Request for Alternative to ASME IWE-5521, Post Repair Testing of the Steel Containment Vessel Opening ML1008203552010-03-23023 March 2010 Request for Additional Information Round 2, Relief Request Nos. WF3-ISI-007 to WF3-ISI-014 from ASME Code, Section XI Volumetric Examination Requirements - Second 10-Year Interval W3F1-2010-0018, Request for Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection2010-02-22022 February 2010 Request for Alternative to ASME IWA-5211 Regarding Chemical Volume Control System Pipe Visual Inspection W3F1-2010-0002, Request for NRC Alternative to ASME IWE-5521 Regarding Post Repair Testing of Waterford 3's Steel Containment Vessel-Opening2010-02-0909 February 2010 Request for NRC Alternative to ASME IWE-5521 Regarding Post Repair Testing of Waterford 3's Steel Containment Vessel-Opening 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 ML0931604422009-11-0404 November 2009 Email Verbal Authorization of Request for Alternative W3-ISI-015 - Third 10-year Inservice Inspection Interval ML0930808142009-11-0404 November 2009 Email Verbal Authorization of Request for Alternative - W3-ISI-016 ML0912103752009-06-12012 June 2009 Relief, Request for Alternative W3-ISI-006, from Requirements of ASME Code Section XI, for Second 10-Year Inservice Inspection Interval ML0903708982009-03-0606 March 2009 Unit 3 - Request for Alternative CEP-ISI-012, Use Alternative Requirements in ASME Code Case N-753 CNRO-2009-00001, Relief Requests for Third 120 Month Inservice Inspection Interval2009-01-23023 January 2009 Relief Requests for Third 120 Month Inservice Inspection Interval CNRO-2008-00035, Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 8052008-11-20020 November 2008 Follow-up to Request for Extension of Discretion for the Interim Enforcement Policy for Fire Protection Issues on 10CFR50.48(c), National Fire Protection Association Standard NFPA 805 ML0809801202008-04-28028 April 2008 Request for Alternative W3-ISI-005, Request to Use ASME Code Case N-716 ML0809502732008-04-21021 April 2008 Revised Request for Alternative W3-R&R-006 to ASME Code Requirements for Weld Overlay Repairs for Second 10-Year Inservice Inspection ML0802504912008-02-15015 February 2008 Request for Alternative W3-ISI-003 to ASME Code Requirements to Allow Extension to Second 10-Year Inservice Inspection Interval Beyond That Currently Allowed by ASME Subsection IWA-2340(d) ML0725600262007-09-24024 September 2007 Withdrawal of W3-ISI-002, Request for Alternative CNRO-2007-00027, Request for Alternative W3-ISI-004 Proposed Alternative to Second Interval ISI Examinations2007-08-0707 August 2007 Request for Alternative W3-ISI-004 Proposed Alternative to Second Interval ISI Examinations ML0701200812007-02-0202 February 2007 River Bend Station, & Waterford Steam Electric Station, Unit 3 - Request for Alternative CEP-PT-001, Visual Exam of Vent & Drain Leakage Tests (TAC MD1399, MD1400, MD1401, MD1402, & MD1403) 2021-10-28
[Table view] Category:Safety Evaluation
MONTHYEARML24164A2512024-08-0707 August 2024 Issuance of Amendment No. 271 Technical Specification Change to Revise Surveillance Requirements Included in the Surveillance Frequency Control Program ML24067A1032024-04-25025 April 2024 Closeout of Generic Letter 2004 02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22322A1092023-02-17017 February 2023 Issuance of Amendment No. 270 Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b ML22300A2082022-11-30030 November 2022 Issuance of Amendment No. 269 Adoption of 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML22194A9012022-07-20020 July 2022 Issuance of Amendment No. 268 Adoption of Technical Specification Task Forcetraveler TSTF-569, Revise Response Time Testing Definition, Revision 2 ML22153A4452022-07-0808 July 2022 Issuance of Amendment No. 267 for Reactor Coolant System Pressure/Temperature Limits and Low Temperature Overpressure Setpoints Applicable for 55 Effective Full Power Years ML22145A0152022-05-27027 May 2022 Issuance of Amendment No. 266 to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program ML22104A2222022-05-12012 May 2022 Issuance of Amendments Revise Technical Specifications to Adopt TSTF 554 ML22075A1022022-04-29029 April 2022 Issuance of Amendment No. 264 to Relocate Chemical Detection System Technical Specifications to Technical Requirements Manual 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 ML22061A2172022-03-15015 March 2022 Revision of the Reactor Vessel Material Surveillance Capsule Withdrawal Schedule 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 ML21313A0082021-12-0808 December 2021 Issuance of Amendments to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections ML21166A1832021-09-15015 September 2021 Issuance of Amendment No. 261 Regarding Removal and Relocation of Boration System Technical Specifications ML21131A2432021-08-24024 August 2021 Issuance of Amendment No. 260 Digital Upgrade to the Core Protection and Control Element Assembly Calculator System ML21082A3022021-05-19019 May 2021 Issuance of Amendment No. 259 to Revise Emergency Action Levels to a Scheme Based on NEI 99-01, Revision 6, Development of Emergency Action Levels for Non-Passive Reactors ML20280A3292020-10-20020 October 2020 Issuance of Amendment No. 258 Regarding Technical Specification 3/4.8.1 Surveillance Requirements ML20205L5742020-08-25025 August 2020 Issuance of Amendment No. 257 Control Room Air Condition System Technical Specifications ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML20022A2582020-01-28028 January 2020 Re-Issuance of Approval of Relief Request WF3-RR-19 2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control ML20002A0202020-01-13013 January 2020 Approval of Relief Request WF3-RR-19-2, Relief from the Requirements of Asme Code Section XI Regarding Alternate Repair of Degraded Drain Line of Chemical and Volume Control System ML19275D4382019-10-24024 October 2019 Redacted - Issuance of Amendment No. 256 for Use of the Tranflow Code for Determining Pressure Drops Across the Steam Generator Secondary Side Internal Components ML19282D8922019-10-15015 October 2019 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule 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 ML19247B1972019-09-0909 September 2019 Approval of Relief Request W3-ISI-032,Relief from the Requirements of ASME Code Section XI Regarding Volumetric Examination ML19232A0252019-08-27027 August 2019 Authorization of Proposed Alternative to ASME Code Section XI, IWA-4000, Repair/Replacement Activities ML19164A0012019-06-28028 June 2019 Issuance of Amendment No. 254 Regarding Revision of Technical Specification 3/4.7.4, Ultimate Heat Sink, ML19157A3162019-06-12012 June 2019 Authorization of Proposed Alternative to ASME Code Case N-770-2 ML19022A3372019-02-13013 February 2019 Issuance of Amendment No. 253 to Revise Section 15.4.3.1 of the Updated Final Safety Analysis Report to Account for Fuel Misload ML18282A0302018-10-18018 October 2018 Proposed Alternative to ASME Code, Section XI, Regarding Charging Pipe Visual Inspection ML18180A2982018-07-23023 July 2018 Issuance of Amendment No. 252 Adoption of the Raptor-M3G Code for Neutron Fluence Calculations 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 ML18026B0532018-04-26026 April 2018 Issuance of Amendment No. 251 Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control,(Cac No. MF9537; EPID L-2017-LLA-0205) ML17341A1202017-12-11011 December 2017 Relief Request PRR-WF3-2017-3, Request for Alternative to ASME OM Code Requirements for Comprehensive Testing of High Pressure Safety Injection Pump AB (CAC No. MF9875; EPID L-2017-LLR-0049) ML17328A8822017-11-29029 November 2017 Requests for Relief GRR-1, PRR-1 and PRR-2, Alternatives to ASME OM Code Requirements for Inservice Testing for the Fourth 10-Year Program Interval (CAC Nos. MF9869, 9870, and 9871; EPID L-2017-LRM-0045-47) ML17192A0072017-07-27027 July 2017 Issuance of Amendment No. 250 Adoption of Technical Specifications Task Force Traveler TSTF 545, Revision 3 ML17069A1872017-03-22022 March 2017 Request for Alternative to 10 CFR 50.55a(c) ASME Code Section III Code Case 1361-1, Relief Request W3-ISI-024 ML17045A1482017-03-0303 March 2017 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 ML16235A2282016-12-0909 December 2016 Request for Alternative Test Plan to American Society of Mechanical Engineers Code for Operation and Maintenance of Nuclear Power Plants ML16278A0172016-10-19019 October 2016 Entergy Fleet Relief Request RR-EN-ISI-15-1, Alternative to Maintain Inservice Inspection Related to Activities to the 2001 Edition/2003 Addendum of ASME Section XI Code ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16159A4192016-07-26026 July 2016 Issuance of Amendment No. 249 Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control ML16182A2702016-07-0606 July 2016 Relief Request PRR-WF3-2016-1, Alternative to the Inservice Testing Program ML16126A0332016-06-27027 June 2016 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) 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 ML16093A0282016-05-31031 May 2016 Entergy Services, Inc., Proposed Alternative to Utilize ASME Code Case N-789-1, Relief Request RR-EN-15-1, Revision 1 ML16077A2702016-05-10010 May 2016 Issuance of Amendment No. 247 Regarding Cyber Security Plan Milestone 8 Full Implementation Schedule ML15289A1432015-11-13013 November 2015 Redacted - Issuance of Amendment No. 246 Changes to Technical Specification 3.1.3.4 Regarding Control Element Assembly Drop Times 2024-08-07
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Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 6, 2016 Site Vice President Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
SUBJECT:
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - RELIEF REQUEST PRR-WF3-2016-1, ALTERNATIVE TO THE INSERVICE TESTING PROGRAM (CAC NO. MF7485)
Dear Sir:
By letter dated March 17, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16077A376), as supplemented by letter dated May 26, 2016, (ADAMS Accession No. ML16154A115), Entergy Operations, Inc. (the licensee), submitted Relief Request PRR-WF3-2016-1, which proposed an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), Section ISTB-6200, associated with pump inservice testing at Waterford Steam Electric Station, Unit 3 (Waterford 3).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.55a(z)(2), the licensee requested authorization for the alternative in Relief Request PRR-WF3-2016-1 on the basis that the ASME OM Code requirements present an undue hardship without a compensating increase in the level of quality and safety.
The NRC staff has reviewed the subject request and has determined, as set forth in the enclosed safety evaluation, that compliance with the ASME OM Code corrective action requirement of ISTB-6200(a) would result in hardship or unusual difficulty without increase in the level of quality and safety, and that the alternative proposed in Relief Request PRR-WF3-2016-1 provides reasonable assurance that the High-Pressure Safety Injection Pump AB (Sl-MPMP-0002AB) is operationally ready.
Accordingly, the U.S. Nuclear Regulatory Commission (NRC) staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2) for this proposed alternative. Therefore, the NRC staff authorizes the use of the alternative in Relief Request PRR-WF3-2016-1 for Waterford 3 until the end of Operating Cycle 21, which began in December 2015 and is scheduled to last for approximately 18 months.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request remain applicable.
If you have any questions, please contact the Project Manager, April Pulvirenti at 301-415-1390 or via e-mail at April.Pulvirenti@nrc.gov.
Sincerely,
/~
Shaun M. Anderson, Acting Chief Plant Licensing 4-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
Safety Evaluation cc w/encl: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELIEF REQUEST PRR-WF3-2016-1 ALTERNATIVE TO THE INSERVICE TESTING PROGRAM ENTERGY OPERATIONS. INC.
WATERFORD STEAM ELECTRIC STATION. UNIT 3 DOCKET NO. 50-382
1.0 INTRODUCTION
By letter dated March 17, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16077A376), as supplemented by letter dated May 26, 2016 (ADAMS Accession No. ML16154A115), Entergy Operations, Inc. (the licensee), submitted an alternative to the requirements of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code), associated with pump inservice testing (IST) at Waterford Steam Electric Station, Unit 3 (Waterford 3).
Specifically, pursuant to Title 10 of the Code of Federal Regulations (10 CFR),
Section 50.55a(z)(2), the licensee requested authorization for the alternative in Relief Request PRR-WF3-2016-1 on the basis that the ASME OM Code requirements present an undue hardship without a compensating increase in the level of quality and safety.
2.0 REGULATORY EVALUATION
The regulation in 10 CFR 50.55a, "Codes and standards," paragraph (f), "lnservice testing requirements," states, in part, that IST of certain ASME Code Class 1, 2, and 3 pumps and valves be performed in accordance with the specified ASME OM Code and applicable addenda incorporated by reference in the regulations.
Section 50.55a(z) of 10 CFR states, in part, that alternatives to the requirements of 10 CFR 50.55a(f) may be used, when authorized by the U.S. Nuclear Regulatory Commission (NRC), if the licensee demonstrates (1) the proposed alternatives would provide an acceptable level of quality and safety or (2) compliance with the specified requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety.
Based on the above, and subject to the following technical evaluation, the NRC staff finds that regulatory authority exists for the licensee to request and the Commission to authorize the alternatives requested by the licensee.
Enclosure
3.0 TECHNICAL EVALUATION
=
Applicable Code Edition and Addenda===
The applicable ASME OM Code edition and addenda for the Waterford 3 third 10-year IST program interval is the 2001 Edition through the 2003 Addenda.
Applicable Code Requirements
- ISTB-3300, "Reference Values," (e)(1 ), states, "Reference values shall be established within +/-20% of pump design flow rate for the comprehensive test."
- ISTB-3300(e)(2), states, "Reference values shall be established within +/-20% of pump design flow for the Group A and Group B tests, if practicable. If not practicable, the reference point flow rate shall be established at the highest practicable flow rate."
- ISTB-3400, "Frequency of lnservice Tests," states, "An inservice test shall be run on each pump as specified in Table ISTB-3400-1."
- Table ISTB-3400-1, "lnservice Test Frequency," requires Group A and Group B tests to be performed quarterly, and Comprehensive tests to be performed biennially.
- Table ISTB-3500-1, "Required Instrument Accuracy," specifies the instrument accuracies for Group A, Group B, Comprehensive, and Preservice tests.
- Table ISTB-5100-1, "Centrifugal Pump Test Acceptance Criteria," defines the required acceptance criteria for Group A, Group B, and Comprehensive tests for centrifugal pumps.
- ISTB-6200, "Corrective Action," (a), "Alert Range," states, "If the measured test parameter values fall within the alert range of Table ISTB-5100-1, Table ISTB-5200-1, Table ISTB-5300-1, or Table ISTB-5300-2, as applicable, the frequency of testing specified in ISTB-3400 shall be doubled until the cause of the deviation is determined and the condition is corrected."
Reason for Request
During refueling outages, a comprehensive pump test (CPT) is performed on High-Pressure Safety Injection (HPSI) Pump AB. The pump flow rate is approximately 405 gallons per minute (gpm), and inboard and outboard pump bearing vibration and pump differential pressure (DP) data are verified to be within the acceptable range criteria in Table ISTB-5100-1.
On November 3, 2015, a CPT was performed on HPSI Pump AB, and two of the vibration readings were in the alert range. The licensee also performed a vibration frequency spectrum analysis. Based on the current pump vendor's (Flowserve) recommendation, the licensee realigned the pump and motor and inspected the pump foundations for voids. On November 23, 2015, a post-maintenance CPT was performed and elevated vibration levels were detected.
The same two vibration readings were in the alert range. Per ISTB-6200(a), "Alert Range," the
frequency of the CPT shall be doubled until the cause of the high vibration readings is determined and the condition is corrected.
The licensee performed a cause evaluation and determined that the pump is in the beginning stages of end of life. In order to avoid further pump wear, the licensee is utilizing the following recommendations to the extent practical: (1) avoid using the pump for non-accident, non-surveillance scenarios/tasks that can be accomplished with other pumps, (2) use HPSI Pump A (which has an upgraded rotating assembly), as the preferred pump, (3) minimize the pump stop/start cycles as much as possible, and (4) minimize the pump operation above 120 percent of the best efficiency point.
In its letter dated March 17, 2016, the licensee stated that the following information demonstrates that the HPSI AB Pump is capable of performing its safety function:
- Bearing vibrations do not improve or worsen with higher flow rates and longer periods of operation [approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> on November 23, 2015);
- Pump discharge flow has consistently achieved TS [Technical Specification] 4.5.2(h) flow requirements during each refueling outage;
- Pump differential pressure has achieved TS 4.5.2(f)(1) DP requirements during each quarterly surveillance during Operating Cycle 20 prior to RF [Refueling Outage) 20;
- The pump has [remained] within IST Comprehensive [pump] test differential pressure acceptance criteria with no degrading trend in pump hydraulic performance.
The licensee provided data from CPTs performed since RF16 on October 28, 2009. Using the DP value from the CPT performed on October 28, 2009, as the reference value, the data shows that the DP has consistently been in the acceptable range for the five CPTs performed since the test during RF16, and there has been no evidence of a degrading trend on pump hydraulic performance.
Proposed Alternative The Waterford 3 third 10-year IST program interval began on December 1, 2007 and is scheduled to end on November 30, 2017.
The licensee requested to use an alternative to the applicable ASME OM Code requirements for HPSI Pump AB (Sl-MPMP-0002AB). The licensee requested to not double the CPT test frequency as per ISTB-6200(a), because in order to perform an additional CPT, a mid-cycle shutdown is required and the reactor pressure vessel head must be removed.
In lieu of the additional CPT, the licensee proposes to perform Group A tests during Operating Cycle 21 using the pre-October 2013 HPSI Pump AB quarterly test flow rate and flow path. The pre-October 2013 HPSI Pump AB quarterly test flow rate was approximately 250 gpm, and the flow path was the hot leg injection line back to the refueling water storage pool (RWSP). The 250 gpm flow rate is approximately 62 percent of the HPSI Pump AB comprehensive pump test flow rate, which is the highest practicable flow rate for online testing. The 250 gpm flow rate is
located on a sloped portion of the pump curve where pump degradation can be detected. The test data will be compared to the Group A vibration and DP acceptance criteria that were established when the pump was known to be operating acceptably prior to the third IST interval, and analyzed to ensure there are no indications of unacceptable pump performance.
ISTB-6200 shall remain applicable to the Group A quarterly tests. The vibration, flow, and pressure instrumentation used during the Group A tests shall meet the instrumentation accuracy requirements stated in Table ISTB-3500-1.
The licensee states that this proposed alternative is a one-time request until pump refurbishment is performed during RF21. Therefore, the duration of the proposed alternative is for Operating Cycle 21, which began in December 2015 and will continue until RF21. RF21 is scheduled to begin in April 2017.
3.2 NRC Staff Evaluation The licensee requests an alternative to the ASME OM Code corrective action requirement of ISTB-6200(a) for the HPSI Pump AB, which is classified as a Group B pump. ISTB-6200(a) requires that if a measured test parameter falls within the alert range, the frequency of testing shall be doubled until the cause of the deviation is determined and the condition is corrected.
Vibration measurements at two locations were in the alert range when a CPT was performed on HPSI Pump AB on November 3, 2015. The pump and motor were realigned, and a CPT was performed again on November 23, 2015, and the vibration measurements at the same two locations were still in the alert range. Doubling the frequency of the CPT would require a mid-cycle shutdown and removal of the reactor pressure vessel head, which is a hardship. In lieu of doubling the frequency of the CPT, the licensee proposes to perform Group A quarterly tests on the pump instead of Group B quarterly tests until RF 21, which is when the pump will be repaired. The differences between Group A and Group B tests are that the Group A test is performed at a higher flow rate (approximately 250 gpm versus approximately 30 gpm), and vibration measurements are required for a Group A test and not for a Group B test. The flow path will be the hot leg injection line to the RWSP, which will allow for the higher flow rate of 250 gpm. The 250 gpm flow rate is located on a sloped portion of the pump curve, which will allow the monitoring of pump degradation.
The licensee determined that HPSI Pump AB is in the beginning stages of end of life, and is limiting operation of the pump, to the extent practical, in order to avoid further wear on the pump. The licensee avoids using the pump for non-accident, non-surveillance scenarios/tasks that can be accomplished with other pumps, uses HPSI Pump A as the preferred pump, minimizes the pump stop/start cycles as much as possible, and minimizes the operation of the pump above 120 percent of the best efficiency point.
The licensee provided CPT and TS surveillance data back to 2009 that indicates that HPSI Pump AB has not shown any degradation in flow or differential pressure since that time. Also, bearing vibrations do not improve or worsen with higher flow rates and longer periods of pump operation (approximately 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.)
Based on the above, the NRC staff finds that the proposed alternative provides reasonable assurance that HPSI Pump AB will remain operationally ready until RF 21.
4.0 CONCLUSION
As set forth above, the NRC staff determines that compliance with the ASME OM Code corrective action requirement of ISTB-6200(a) would result in hardship or unusual difficulty without increase in the level of quality and safety, and that the alternative proposed in Relief Request PRR-WF3-2016-1 provides reasonable assurance that the HPSI Pump AB (Sl-MPMP-0002AB) is operationally ready.
Accordingly, the NRC staff concludes that the licensee has adequately addressed all of the regulatory requirements set forth in 10 CFR 50.55a(z)(2) for this proposed alternative.
Therefore, the NRC staff authorizes the use of the alternative in Relief Request PRR-WF3-2016-1 at Waterford 3 until the end of Operating Cycle 21, which began in December 2015. The Operating Cycle 21 duration is approximately 18 months.
All other ASME OM Code requirements for which relief was not specifically requested and approved in the subject request remain applicable.
Principal Contributor: R.Wolfgang Date: July 6, 2016
If you have any questions, please contact the Project Manager, April Pulvirenti at 301-415-1390 or via e-mail at April.Pulvirenti@nrc.gov.
Sincerely, IRA/
Shaun M. Anderson, Acting Chief Plant Licensing 4-2 and Decommissioning Transition Branch Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382
Enclosure:
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PUBLIC LPL4-2 R/F RidsACRS_MailCTR Resource RidsNrrDorlDpr Resource RidsNrrDorllpl4-2 Resource RidsNrrDeEpnb Resource RidsNrrLAPBlechmanResource RidsNrrPMWaterford Resource RidsRgn4MailCenter Resource JBowen, EDO RIV ADAMS Access1on No. ML16182A270 *b1yema1*1 d ate d OFFICE DORL/LPL4-2/PM DORL/LPL4-2/LA NRR/DE/EPNB NAME APulvirenti PBlechman DAiiey*
DATE 7/1/16 7/1/16 06/12/2016 OFFICE DORL/LPL4-2/BC(A)
NAME SAnderson DATE 7/6/16 OFFICIAL RECORD COPY