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Category:Letter
MONTHYEARML24022A1172024-01-23023 January 2024 Acceptance of Requested Licensing Action Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations ML24012A2422024-01-16016 January 2024 Acceptance of Requested Licensing Action License Transfer Request ML23236A0042023-12-27027 December 2023 Issuance of Amendment 274 Re Changes to Perm Defueled Emergency Plan and Perm Defueled Emergency Action Level Scheme ML23355A1242023-12-26026 December 2023 Withdrawal of an Amendment Request Re License Amendment Request to Revise License Condition to Eliminate Cyber Security Plan Requirements ML23192A0772023-12-26026 December 2023 Letter Exemption from the Requirements of 10 CFR 140.11(a)(4) Concerning Offsite Primary and Secondary Liability Insurance ML23191A5222023-12-22022 December 2023 Exemption Letter from the Requirements of 10 CFR 50.54(W)(1) Concerning Onsite Property Damage Insurance (EPID - L-2022-LLE-0032) ML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23354A2602023-12-21021 December 2023 Reference Simulator Inspection Request for Information L-23-019, Proof of Financial Protection 10 CFR 140.152023-12-18018 December 2023 Proof of Financial Protection 10 CFR 140.15 PNP 2023-030, License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations2023-12-14014 December 2023 License Amendment Request to Revise Renewed Facility Operating License and Permanently Defueled Technical Specifications to Support Resumption of Power Operations PNP 2023-035, Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements2023-12-12012 December 2023 Withdrawal of License Amendment Request - Revise License Condition to Eliminate Cyber Security Plan Requirements PNP 2023-028, Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments2023-12-0606 December 2023 Application for Order Consenting to Transfer of Control of License and Approving Conforming License Amendments L-23-012, Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point2023-11-13013 November 2023 Master Decommissioning Trust Agreement Changes for Indian Point Nuclear Generating Units 1, 2 and 3, Pilgrim Nuclear Power Station, Palisades Nuclear Plant and the Non-Qualified Trust for Big Rock Point ML23291A4402023-11-0303 November 2023 Acceptance of Requested Licensing Action Request for Exemption from 10 CFR 50.82(a)(2) to Support Reauthorization of Power Operations IR 05000255/20230032023-10-0404 October 2023 NRC Inspection Report No. 05000255/2023003(DRSS)-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23275A0012023-10-0202 October 2023 Request for Withholding Information from Public Disclosure for Palisades Nuclear Plant PNP 2023-025, Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.822023-09-28028 September 2023 Request for Exemption from Certain Termination of License Requirements of 10 CFR 50.82 PNP 2023-026, Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations2023-09-28028 September 2023 Pre-Submittal Meeting Presentation - Palisades Nuclear Plant License Transfer Application to Support Resumption of Power Operations PNP 2023-023, Special Report High Range Noble Gas Monitor Inoperable2023-08-0909 August 2023 Special Report High Range Noble Gas Monitor Inoperable ML23215A2302023-08-0303 August 2023 Notice of Organization Change - Chief Nuclear Officer IR 05000255/20230022023-07-19019 July 2023 NRC Inspection Report 05000255/2023002 DRSS-Holtec Decommissioning International, LLC, Palisades Nuclear Plant ML23087A0362023-05-0202 May 2023 PSDAR Review Letter ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment PNP 2023-018, 2022 Annual Non-Radiological Environmental Operating Report2023-04-25025 April 2023 2022 Annual Non-Radiological Environmental Operating Report L-23-004, HDI Annual Occupational Radiation Exposure Data Reports - 20222023-04-24024 April 2023 HDI Annual Occupational Radiation Exposure Data Reports - 2022 PNP 2023-007, and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports2023-04-19019 April 2023 and Big Rock Point, 2022 Annual Radioactive Effluent Release and Waste Disposal Reports PNP 2023-008, 2022 Radiological Environmental Operating Report2023-04-18018 April 2023 2022 Radiological Environmental Operating Report L-23-003, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-31031 March 2023 Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations PNP 2023-002, 6 to Updated Final Safety Analysis Report2023-03-31031 March 2023 6 to Updated Final Safety Analysis Report ML23088A0382023-03-29029 March 2023 Stations 1, 2, & 3, Palisades Nuclear Plant, and Big Rock Point - Nuclear Onsite Property Damage Insurance PNP 2023-006, Report of Changes to Security Plan, Revision 202023-03-29029 March 2023 Report of Changes to Security Plan, Revision 20 PNP 2023-012, Presentation on Regulatory Path to Reauthorize Power Operations2023-03-16016 March 2023 Presentation on Regulatory Path to Reauthorize Power Operations ML23038A0982023-03-15015 March 2023 Request for Withholding Information from Public Disclosure ML23095A0642023-03-14014 March 2023 American Nuclear Insurers, Notice of Cancellation Rescinded PNP 2023-001, Regulatory Path to Reauthorize Power Operations2023-03-13013 March 2023 Regulatory Path to Reauthorize Power Operations PNP 2023-004, Report of Changes to Palisades Nuclear Plant Technical Specification Bases2023-03-0808 March 2023 Report of Changes to Palisades Nuclear Plant Technical Specification Bases PNP 2023-005, Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report2023-03-0101 March 2023 Response to Palisades Nuclear Plant - Request for Additional Information Related to the Post-Shutdown Decommissioning Activities Report ML22361A1022023-02-24024 February 2023 Reactor Decommissioning Branch Project Management Changes for Some Decommissioning Facilities and Establishment of Backup Project Manager for All Decommissioning Facilities ML23052A1092023-02-17017 February 2023 FEMA Letter to NRC, Proposed Commission Paper Language for Palisades Nuclear Plant Emergency Plan Decommissioning Exemption Request ML23032A3992023-02-0101 February 2023 Regulatory Path to Reauthorize Power Operations IR 05000255/20220032022-12-28028 December 2022 NRC Inspection Report No. 05000255/2022003(DRSS); 07200007/2022001 (Drss) Holtec Decommissioning International, LLC, Palisades Nuclear Plant L-22-042, Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.152022-12-14014 December 2022 Oyster, Pilgrim, Indian Point, Palisades and Big Rock Point - Proof of Financial Protection 10 CFR 140.15 PNP 2022-037, Report of Changes to Security Plan, Revision 192022-12-14014 December 2022 Report of Changes to Security Plan, Revision 19 ML22321A2852022-11-17017 November 2022 LLC Master Decommissioning Trust Agreement for Palisades Nuclear Plant IR 05000255/20224012022-11-0909 November 2022 Decommissioning Palisades Nuclear Plant - Decommissioning Security Inspection Report 05000255/2022401 PNP 2022-036, Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme2022-11-0808 November 2022 Response to Request for Additional Information Regarding License Amendment Request for Proposed Permanently Defueled Emergency Plan and Permanently Defueled Emergency Action Level Scheme PNP 2022-035, International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations2022-11-0202 November 2022 International - Notification of Commitment Cancellations for Remaining Activities Related to Beyond-Design-Basis Seismic Hazard Reevaluations PNP 2022-024, Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 140.11(a)(4) Concerning Primary and Secondary Liability Insurance PNP 2022-026, Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance2022-10-26026 October 2022 Request for Exemption from 10 CFR 50.54(w)(1) Concerning Onsite Property Damage Insurance ML22292A2572022-10-25025 October 2022 Permanently Defueled Emergency Plan License Amendment RAI Letter 2024-01-23
[Table view] Category:Safety Evaluation
MONTHYEARML23263A9772023-12-22022 December 2023 Exemption from Certain Emergency Planning Requirements and Related Safety Evaluation ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML22039A1982022-05-13013 May 2022 Issuance of Amendment No. 272 Permanently Defueled Technical Specifications ML21292A1482021-12-13013 December 2021 Safety Evaluation Related to Request for Direct and Indirect Transfers of Control of Facility Operating License DPR-6 for Big Rock Point and Renewed Facility Operating License DPR-20 for Palisades Nuclear Plant and ISFSI (EPID L-2020-LLM-00 ML21292A1472021-12-13013 December 2021 Draft Conforming License Amendments - Palisades Nuclear Plant Renewed Facility Operating License DPR-20 and ISFSI and Big Rock Point Facility Operating License DPR-6 and ISFSI (EPID L-2020-LLM-0003) (Enclosure 2) ML20365A0012021-01-19019 January 2021 Relief Request 5-8 Related to ASME Code Case N-729-4 Supplemental Examination Requirements of Reactor Vessel Closure Head Penetration Nozzles ML20226A2722020-08-18018 August 2020 Request to Use a Provision of a Later Edition of the ASME BPV Code, Section XI ML19317D8552019-12-30030 December 2019 Issuance of Amendment No. 271 Regarding Adoption of TSTF-425, Relocate Surveillance Frequencies to Licensee Control - RITSTF Initiative 5B ML19318E3942019-12-0202 December 2019 Reactor Vessel Material 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 ML19198A0802019-08-20020 August 2019 Issuance of Amendments No. 269 Regarding Changes to NFPA 805 Modifications and Change to Full Compliance Implementation Date for the Fire Protection Program (Epids L-2018-LLA-0296 and L-2019-LLA-0049) ML19135A0502019-05-21021 May 2019 Correction to Safety Evaluation for Amendment No.268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement ML19107A0532019-05-13013 May 2019 Issuance of Amendment No. 268 Regarding Revision to Diesel Generator Undervoltage Start Surveillance Requirement ML19112A3172019-04-26026 April 2019 Approval of Alternative for Repair of Reactor Pressure Vessel Head Penetrations ML18170A2192018-09-24024 September 2018 Issuance of Amendment Changes to the Emergency Plan for Permanently Defueled Condition (CAC No. MG0198; EPID L-2017-LLA-0305) 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 ML18114A4102018-06-0404 June 2018 Issuance of Amendment Regarding Administrative Controls for Permanently Defueled Condition (CAC No. MG0021; EPID L-2017-LLA-0266) ML18135A2632018-05-21021 May 2018 Relief Request No. RR 5-6 Alternate to the Reexamination Frequency for a Relevant Condition ML18039A2442018-02-27027 February 2018 Issuance of Amendment License Amendment Request to Change the Full Compliance Implementation Date for the Fire Protection Program Transition License Condition for Required Modifications ML17328B0332017-12-15015 December 2017 Issuance of Amendment Cyber Security Plan Implementation Schedule (CAC No. MF9523; EPID L-2017-LLA-0199) ML21067A4982017-09-0707 September 2017 Relief Request No. RR 5-4 Proposed Alternative, Weld Reference System ML17151A3502017-08-21021 August 2017 Approval of Certified Fuel Handler Training and Retraining Program ML17194A8072017-08-14014 August 2017 Relief Request No. RR 4-25 Limited Coverage Examinations During the Fourth 10-Year Inservice Inspection Interval ML17137A0282017-06-29029 June 2017 Relief Request Number RR 5; 5 Proposed Alternative, Under-Vessel Leakage Examination ML17121A5102017-06-0808 June 2017 Issuance of Amendment License Amendment Request for Editorial and Administrative Changes to Technical Specifications ML17082A4652017-05-30030 May 2017 Issuance of Amendment Application to Revise Technical Specifications to Adopt TSTF 545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML16300A0302016-12-19019 December 2016 Issuance of Amendment Revision to the Requirements for Steam Generator Tube Inspections and Repair Criteria in the Cold Leg Tube Sheet Region ML16281A4982016-10-28028 October 2016 Issuance of Amendment No. 260, Revise License Condition 2.C.(4) and Technical Specifications Related to Control Rod Drive Exercise Surveillance ML16251A6202016-09-13013 September 2016 Entergy Fleet Request for Approval of Change to the Entergy Quality Assurance Program Manual (CAC Nos. MF7086 - MF7097) ML16014A3182016-08-22022 August 2016 Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 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 ML16078A0682016-05-0202 May 2016 Issuance of Amendment Cyber Security Plan Implementation Schedule ML16043A4852016-03-14014 March 2016 Relief Request Number RR 4-24 - Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML16022A1072016-02-0101 February 2016 Relief Request Number RR 4-23- Proposed Alternative Concerning ASME Code Depth Sizing Requirement ML15334A3072015-12-22022 December 2015 Relief Request Numbers RR 5-2 and 5-3, Proposed Alternative to the Requirements of the ASME OM Code for the Fifth 10-Year Inservice Test Interval ML15320A2442015-11-25025 November 2015 Relief Request Number 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-Year ISI Interval for ISI Related Activities ML15103A0592015-05-18018 May 2015 Issuance of Amendment Adoption of TSTF-426, Revision 5, Revise or Add Actions to Preclude Entry Into Limiting Condition for Operation 3.0.3 - RITSTF Initiatives 6B and 6C. ML15055A1062015-04-22022 April 2015 Issuance of Amendment License Amendment Request to Revise Emergency Response Organization Staff Augmentation Response Times ML15007A1912015-02-27027 February 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) ML14237A1442014-12-0808 December 2014 Issuance of Amendment Cyber Security Plan Implementation Schedule ML14283A2872014-10-22022 October 2014 Issuance of Amendment Application for Technical Specification Change (TSTF-427) to Add Limiting Condition for Operation 3.0.9 Regarding the Unavailability of Barriers Using the Consolidated Line Item Improvement Process ML14223B2262014-09-0404 September 2014 Proposed Alternative, Use of Alternate ASME Code Case N-770-1 Baseline Examination ML14199A5572014-08-13013 August 2014 Relief Request Number RR-4-19, Proposed Alternative to the Requirements of ASME Code Case N-638-4 ML14210A2662014-08-0808 August 2014 Arkansas, Units 1 & 2, Big Rock Point, James A. Fitzpatrick, Grand Gulf, Unit 1, Indian Point, Units 1, 2 & 3, Palisades, Pilgrim, River Bend, Unit 1, Vermont Yankee, Waterford, Safety Evaluation Quality Assurance Program Manual, Rev. 24 & ML13312A4232013-11-26026 November 2013 Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation ML13129A2192013-05-29029 May 2013 Staff Assessment in Response to Recommendation 9.3 of the Near-Term Task Force Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident ML13025A3062013-03-14014 March 2013 ANO 1 & 2, Big Rock, FitzPatrick, GGNS, Indian Point 1, 2 & 3, Palisades, Pilgrim, RBS, Vermont Yankee, and Waterford - Correction to Amendments Issued on 12/28/12, Revise QA Program Manual and Staff Qualification Technical Specifications ML13056A5142013-02-28028 February 2013 Non-Proprietary Issuance of Amendment Regarding Replacement of Spent Fuel Pool Region 1 Storage Racks 2023-05-01
[Table view] |
Text
March 1, 2002 Mr. Douglas E. Cooper Site Vice President Palisades Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530
SUBJECT:
PALISADES PLANT - RELIEF REQUEST RR-V-33a TO IMPLEMENT CHECK VALVE CONDITION MONITORING PROGRAM (TAC NO. MB3228)
Dear Mr. Cooper:
By letter dated October 17, 2001, the Nuclear Management Company, LLC (the licensee),
submitted Relief Request RR-V-33a requesting approval from the U.S. Nuclear Regulatory Commission (NRC) to implement the check valve portion of the American Society of Mechanical Engineers (ASME) Code for the Operation and Maintenance of Nuclear Power Plants, 1995 edition, 1996 addenda (OMa-1996 Code), including Appendix II, Check Valve Condition Monitoring Program, at the Palisades Nuclear Plant. The licensee proposes to implement the ASME OMa-1996 Code and Appendix II in phases for all check valves at Palisades, with full implementation of the ASME OMa-1996 Code by December 31, 2003. The licensee requested relief to implement the alternative on a phased-in schedule pursuant to Title 10 of the Code of Federal Regulations, Part 50, Section 50.55a(a)(3)(i).
The NRC staff has evaluated the licensees request for approval to implement the check valve portion of the OMa-1996 Code, including the Appendix II Condition Monitoring Program, at Palisades. The NRC staffs safety evaluation is enclosed. The NRC staff finds the licensees request to use the check valve portion of the OMa-1996 Code and related regulatory requirements with regard to implementation of Appendix II to be acceptable and it is, therefore, approved pursuant to 10 CFR 50.55a(f)(4)(iv). The NRC staff also finds the licensees proposed phased-in implementation of the OMa-1996 Code and Appendix II requirements at Palisades to be acceptable and it is authorized pursuant to 10 CFR 50.55a(a)(3)(i) on the basis that the proposed alternative provides an acceptable level of quality and safety.
If you have any questions concerning this action, please call Mr. Darl Hood of my staff at (301) 415-3049.
Sincerely,
/RA/
William D. Reckley, Acting Chief, Section 1 Project Directorate III Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-255
Enclosure:
Safety Evaluation cc w/encl: See next page
ML020430003 Palisades Plant cc:
Mr. Robert A. Fenech, Senior Vice President Michigan Department of Attorney General Nuclear, Fossil, and Hydro Operations Special Litigation Division Consumers Energy Company 630 Law Building 212 West Michigan Avenue P.O. Box 30212 Jackson, MI 49201 Lansing, MI 48909 Arunas T. Udrys, Esquire Mr. Roy A. Anderson Consumers Energy Company Executive Vice President and 212 West Michigan Avenue Chief Nuclear Officer Jackson, MI 49201 Nuclear Management Company, LLC 700 First Street Regional Administrator, Region III Hudson, WI 54016 U.S. Nuclear Regulatory Commission 801 Warrenville Road Laurie A. Lahti Lisle, IL 60532-4351 Manager - Licensing Nuclear Management Company, LLC Supervisor 27780 Blue Star Memorial Highway Covert Township Covert, MI 49043 P. O. Box 35 Covert, MI 49043 Steven T. Wawro Nuclear Asset Director Office of the Governor Consumers Energy Company P. O. Box 30013 Palisades Plant Lansing, MI 48909 27780 Blue Star Memorial Highway Covert, MI 49043 U.S. Nuclear Regulatory Commission Resident Inspector's Office Mr. John Paul Cowan Palisades Plant Senior Vice President 27782 Blue Star Memorial Highway Palisades Plant Covert, MI 49043 Nuclear Management Company, LLC 27780 Blue Star Memorial Highway Drinking Water and Radiological Covert, MI 49043 Protection Division Michigan Department of Environmental Quality 3423 N. Martin Luther King Jr Blvd P. O. Box 30630 CPH Mailroom Lansing, MI 48909-8130 November 2001
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO THE INSERVICE TESTING PROGRAM RELIEF REQUEST RR-V-33a PALISADES NUCLEAR PLANT DOCKET NO. 50-255
1.0 INTRODUCTION
Title 10 of the Code of Federal Regulations, Section 50.55a (10 CFR 50.50a), requires that inservice testing (IST) of certain American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 pumps and valves be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code (the ASME B&PV Code) and applicable addenda, except where alternatives have been authorized or relief has been requested by the licensee and granted by the Commission pursuant to 10 CFR 50.55a(a)(3)(i), 10 CFR 50.55a(a)(3)(ii), or 10 CFR 50.55a(f)(6)(i). In proposing alternatives or requesting relief, the licensee must demonstrate that: (1) the alternatives would provide an acceptable level of quality and safety, (2) compliance would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety, or (3) conformance would be impractical for its facility. The regulation at 10 CFR 50.55a authorizes the Commission to approve alternatives and to grant relief from ASME Code requirements upon making the necessary findings. The regulation at 10 CFR 50.55a(f)(4)(iv) states that IST of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in paragraph (b),
subject to Commission approval. Portions of editions or addenda may be used provided that all related requirements of the respective editions and addenda are met.
By letter dated October 17, 2001, the Nuclear Management Company, LLC (NMC), submitted Relief Request RR-V-33a requesting the U.S. Nuclear Regulatory Commissions (NRCs) approval to implement the check valve portion of the ASME Code for the Operation and Maintenance of Nuclear Power Plants, 1995 edition, 1996 addenda (OMa-1996 Code),
including Appendix II, Check Valve Condition Monitoring Program, at the Palisades Nuclear Plant. NMC proposed that implementation of the ASME OMa-1996 Code and Appendix II be phased-in for all check valves at Palisades. NMC committed to the full implementation of the ASME OMa-1996 Code by December 31, 2003. NMC requested relief to implement the alternative on the proposed implementation phased-in schedule pursuant to 10 CFR 50.55a(a)(3)(i).
ENCLOSURE
The current Code of record for the Palisades IST check valve program is the ASME B&PV Code,Section XI, 1989 edition, which references the requirements of ASME/ANSI OMa-1988, Part 10.
The NRC staffs findings with respect to NMCs request to use the check valve portion of the OMa-1996 Code and related regulatory requirements, including the implementation of the Appendix II alternative, and NMCs proposed phased-in implementation of the OMa-1996 Code and Appendix II requirements at Palisades, are contained in this safety evaluation.
2.0 NMCS RELIEF REQUEST NMC requested relief from the requirements of ASME/ANSI OMa-1988, Part 10, to implement the check valve portion of the ASME OMa-1996 Code including the Appendix II, Check Valve Condition Monitoring Program, at Palisades. NMC requested approval in order to support the scheduled IST of check valves during the refueling outage of 2003. NMC proposed that the implementation of the ASME OMa-1996 Code and Appendix II be phased-in for all check valves at the Palisades Nuclear Plant. Relief was requested for the implementation on a phased-in schedule, pursuant to 10 CFR 50.55a(a)(3)(i). The phased-in implementation period requested is 2 years and extends to December 31, 2003. This code update for check valves is 3 years in advance of the required 10-year IST program code update. NMC commits to the full implementation of the ASME OMa-1996 Code by December 31, 2003.
2.1 NMCS Basis for Relief NMCs reason for the relief request is to establish a Condition Monitoring Program for the IST of certain check valves in preparation for Palisades required 10-year IST program code update.
NMC proposes to take advantage of the ASME/NRC OM Code improvement efforts in developing a performance-based code, because it allows a period of time for implementing bi-directional testing of check valves that are not currently tested in their IST program. NMCs Relief Request RR-V-33a referenced the NRCs 10 CFR 50.55a rule amendment that was published in the Federal Register (64 FR 51370, September 22, 1999). In this final rule, the NRC staff stated its expectations with regard to requests by licensees to apply Appendix II under 10 CFR 50.55a(f)(4)(iv) in advance of incorporating the ASME OMa-1996 Code as its Code of record.
The proposed implementation schedule allows a period of time (one refueling cycle) to test and phase valves into the program, particularly those not currently bi-directionally tested. This schedule also allows sufficient time to establish the process and prepare procedures and valve groupings required to implement the Appendix II Condition Monitoring Program.
At Palisades, there are 23 check valves that are not currently tested in both the open and closed direction. These check valves will be bi-directionally tested under this requested relief.
Bi-directional testing improves the capability to detect valve degradation prior to failure. The initial check valve implementation evaluations performed will include those valves not currently bi-directionally tested.
The proposed implementation of the requirements of the check valve portion of the ASME OMa-1996 Code, including Appendix II, will be phased-in for all check valves at Palisades.
NMC considers that the proposed alternative to phase-in the check valves, subject to the requirements of the OMa-1996 Code and related regulations, pursuant to 10 CFR 50.55a(a)(3)(i), provides an acceptable level of quality and safety.
3.0 NRC STAFFS EVALUATION NMC indicates that the testing and examination of the check valves will be managed by the condition monitoring approach by adopting the requirements of Appendix II contained in the OMa-1996 Code, subject to the three modifications identified in 10 CFR 50.55a(b)(3)(iv). NMC also indicates that the initial Appendix II implementation and evaluation activities performed will include those valves not currently bi-directional tested, and if the Condition Monitoring Program is discontinued for a valve or group of valves during the implementation process, the requirements of all applicable check valve portions of OMa-1996 Code will be implemented.
As part of its amendment to 10 CFR 50.55a, the NRC incorporated by reference the OM Code 1995 edition through the 1996 addenda, with certain modifications required when implementing Appendix II, as stated in 10 CFR 50.55a(b)(3)(iv). The amendment stated, The NRC staff will favorably consider a request by a licensee under §50.55a(f)(4)(iv) to apply Appendix II, in advance of incorporating the 1995 Edition with 1996 Addenda of the ASME OM Code as its Code of record, if the licensee justifies the following in its submitted request: (1) The modifications to Appendix II contained in the rule have been satisfied; and (2) All portions of the 1995 Edition with the 1996 Addenda of the OM Code that apply to check valves are implemented for the remaining check valves not included in the Appendix II program.
Two significant changes were introduced in the OMa-1996 Code that (1) requires bi-directional IST of the check valve disc movement, and (2) provides the Check Valve Condition Monitoring Program as an alternative to IST exercise testing for certain check valves. This integral two-part improvement to the Code provides interrelated requirements. Bi-directional testing improves the IST capability of detecting valve degradation prior to valve failure. The Condition Monitoring Program alternative allows the licensee certain IST flexibility in establishing the types of test, examination, and preventive maintenance activities and their associated intervals, when justified based on the valves performance and operating condition. These Code changes were developed and published such that licensees who elect not to implement condition monitoring in their IST programs would be required to bi-directionally test check valves as a default set of testing and examination requirements.
The NRC staff considers the Condition Monitoring Program approach of OMa-1996 Code, Appendix II, for check valve IST with the modifications in 10 CFR 50.55a(b)(3)(iv), to be an improvement over present Code requirements, and encourages licensees to implement the condition monitoring alternative. The use of the alternative IST program provides the licensee with knowledge of the valves operating condition, informed and verified expectations of the valves performance over extended intervals, and a process to reduce the burden of unnecessary IST.
NMC stated that it would implement its Condition Monitoring Program on an extended schedule (approximately 2 years). As previously noted, the NRCs amendment to 10 CFR 50.50a stated that the licensee should justify that all portions of the 1995 edition with the 1996 addenda of the OM Code that apply to check valves are implemented for the remaining check valves not included in the Appendix II program. For those check valves not currently bi-directionally tested, this extended period would allow the licensee to establish the process, procedures, and valve groupings to implement Appendix II requirements. Thus, there will be a period when certain check valves not currently tested in a bi-directional manner might not meet all testing requirements in the 1995 edition with the 1996 addenda. For these check valves, NMC will meet testing requirements of its Code of record (i.e., 1989 ASME Code,Section XI) until the Appendix II program is fully implemented. At that time, all ASME Code Class 1, 2, and 3 check valves in the IST program will be included in the Appendix II program or will meet the check valve requirements in the 1995 edition with the 1996 addenda for those check valves not included in the Appendix II program. On the basis that during the phased-in implementation period, those check valves that are not bi-directionally tested will meet the IST requirements of the current Code of record, the NRC staff finds that the alternative provides an acceptable level of quality and safety.
Therefore, the NRC staff finds that NMCs request to use the check valve portion of the OMa-1996 Code and to apply Appendix II in advance of incorporating the 1995 edition with 1996 addenda of the ASME OM Code as its Code of record at the Palisades Nuclear Plant, as described in its letter dated October 17, 2001, is acceptable and, therefore, it is approved pursuant to 10 CFR 50.55a(f)(4)(iv). The NRC staff further finds that NMCs proposed implementation sequence to phase-in its Condition Monitoring Program over a 2-year period, in order to establish the process, prepare procedures and valve groupings, and obtain performance data, is acceptable and is authorized pursuant to 10 CFR 50.55a(a)(3)(i), on the basis that the proposed alternative provides an acceptable level of quality and safety.
4.0 CONCLUSION
The NRC staff concludes that NMCs request to use the check valve portion of the OMa-1996 Code, including Appendix II, and the related regulatory requirements is approved pursuant to 10 CFR 50.55a(f)(4)(iv). In addition, the NRC staff finds that NMCs proposed phased-in implementation of OMa-1996 Code, including Appendix II requirements, at Palisades is authorized pursuant to 10 CFR 50.55a(a)(3)(i) on the basis that the proposed alternative provides an acceptable level of quality and safety.
Principal Contributor: F. Grubelich Date: March 1, 2002