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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARU-604792, Post-Outage 120-Day Inservice Inspection (ISI) Summary Report2024-02-0101 February 2024 Post-Outage 120-Day Inservice Inspection (ISI) Summary Report U-604788, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 32023-12-12012 December 2023 Fourth Ten-Year Interval Inservice Testing Program Plan Revision 3 U-604703, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 22022-04-14014 April 2022 Fourth Ten-Year Interval Inservice Testing Program Plan Revision 2 U-604687, Post-Outage 90-Day Inservice Inspection (Isi) Summary Report2022-01-21021 January 2022 Post-Outage 90-Day Inservice Inspection (Isi) Summary Report U-604633, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 12021-05-23023 May 2021 Fourth Ten-Year Interval Inservice Testing Program Plan Revision 1 U-604555, Fourth Ten-Year Interval Inservice Testing Program Plan Revision 02020-07-13013 July 2020 Fourth Ten-Year Interval Inservice Testing Program Plan Revision 0 U-604527, Post Outage 90-Day Lnservice Inspection (ISI) Summary Report2020-01-15015 January 2020 Post Outage 90-Day Lnservice Inspection (ISI) Summary Report NMP2L2711, Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-8792019-10-16016 October 2019 Byron Station; Calvert Cliffs; Clinton Power Station; LaSalle County Station; Limerick Generating Station; and Nine Mile Point Nuclear Station - Proposed Alternative to Utilize Code Case N-879 NMP2L2700, Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants2019-04-30030 April 2019 Co. - Submittal of Proposed Alternative to Utilize Code Case N-879 for Plants U-604457, Third Ten-Year Interval Inservice Testing Program Plan Revision 92018-11-21021 November 2018 Third Ten-Year Interval Inservice Testing Program Plan Revision 9 U-604438, Post Outage 90-Day Lnservice Inspection (ISI) Summary Report2018-08-17017 August 2018 Post Outage 90-Day Lnservice Inspection (ISI) Summary Report ML18233A3982018-08-17017 August 2018 Submittal of Post Outage 90-Day Inservice Inspection (ISI) Summary Report U-604359, Third Ten-Year Interval Lnservice Testing Program Plan, Revision 82017-07-20020 July 2017 Third Ten-Year Interval Lnservice Testing Program Plan, Revision 8 U-604326, Third Ten-Year Interval Inservice Testing Program Plan Revision 72017-03-0808 March 2017 Third Ten-Year Interval Inservice Testing Program Plan Revision 7 U-604303, Post-Outage 90-Day Inservice Inspection Summary Report2016-08-19019 August 2016 Post-Outage 90-Day Inservice Inspection Summary Report U-604262, Third Ten-Year Interval Inservice Testing Program Plan, Revision 62016-02-15015 February 2016 Third Ten-Year Interval Inservice Testing Program Plan, Revision 6 U-604237, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report2015-08-14014 August 2015 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report U-604203, Correction to C1R14 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report2015-03-23023 March 2015 Correction to C1R14 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report ML14031A2222014-01-28028 January 2014 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report U-604060, Post-Outage 90-Day Inservice Inspection (ISI) Summary Report2012-03-21021 March 2012 Post-Outage 90-Day Inservice Inspection (ISI) Summary Report ML11269A0182010-10-12012 October 2010 ISI Program Plan Third Ten-Year Inspection Interval U-603967, Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval2010-07-12012 July 2010 Submittal of Inservice Testing Program Plan for the Third Ten-Year Interval U-603958, Post-Outage 90-Day Inservice Inspection Summary Report2010-05-0606 May 2010 Post-Outage 90-Day Inservice Inspection Summary Report U-603907, Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection Plan2009-07-31031 July 2009 Submittal of Program for the Second 10-Year Interval Containment Inservice Inspection Plan U-603857, 90-Day Post-Outage Inservice Inspection (ISI) Summary Report2008-05-0505 May 2008 90-Day Post-Outage Inservice Inspection (ISI) Summary Report RS-07-058, Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements2007-04-19019 April 2007 Amergen/Exelon Nuclear - Request for Relief - Use of the Boiling Water Reactor Vessel and Internals Project (BWRVIP) Guidelines in Lieu of Specific ASME Code Requirements U-603774, 90-Day Post-Outage Inservice Inspection (SI) Summary Report2006-05-26026 May 2006 90-Day Post-Outage Inservice Inspection (SI) Summary Report U-603676, Day Post-Outage Inservice Inspection (ISI) Summary Report2004-05-27027 May 2004 Day Post-Outage Inservice Inspection (ISI) Summary Report ML0335802082003-12-24024 December 2003 Ltr Dated 12/24/03 Re Clinton Station Concerning Notification of Baseline Inspection and Request for Information RS-03-188, Supplemental Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program2003-10-0202 October 2003 Supplemental Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program U-603571, Day Post-Outage Inservice Inspection (ISI) Summary Report2002-08-0202 August 2002 Day Post-Outage Inservice Inspection (ISI) Summary Report 2024-02-01
[Table view] Category:Letter type:RS
MONTHYEARRS-24-093, Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-10-10010 October 2024 Response to Request for Additional Information - Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-087, Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2024-09-0909 September 2024 Annual 10 CFR 50.46 Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-24-061, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations2024-06-14014 June 2024 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2024-01, Preparation and Scheduling of Operator Licensing Examinations RS-24-055, 2023 Corporate Regulatory Commitment Change Summary Report2024-05-17017 May 2024 2023 Corporate Regulatory Commitment Change Summary Report RS-24-050, Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2024-05-0909 May 2024 Additional Information Supporting Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-24-041, Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests2024-04-30030 April 2024 Alternative Request to Utilize Code Case OMN-32, Alternative Requirements for Range and Accuracy of Pressure, Flow, and Differential Pressure Instruments Used in Pump Tests RS-24-002, Constellation Energy Generation, LLC - Annual Property Insurance Status Report2024-04-0101 April 2024 Constellation Energy Generation, LLC - Annual Property Insurance Status Report RS-24-023, Report on Status of Decommissioning Funding.2024-03-22022 March 2024 Report on Status of Decommissioning Funding. RS-24-005, Additional Information Supporting Request for Partial Site Release2024-02-0808 February 2024 Additional Information Supporting Request for Partial Site Release RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023 Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans RS-23-090, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2023-09-0707 September 2023 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023 Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs RS-23-081, Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation2023-08-21021 August 2023 Request for License Amendment to Revise Technical Specifications Related to Reactor Water Cleanup Isolation Instrumentation RS-23-085, Supplemental Information Related to Request for Partial Site Release2023-08-0303 August 2023 Supplemental Information Related to Request for Partial Site Release RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations RS-23-073, Request for Partial Site Release2023-06-0707 June 2023 Request for Partial Site Release RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023 Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling RS-23-049, Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations2023-03-23023 March 2023 Constellation Energy Generation, LLC, Report on Status of Decommissioning Funding for Reactors and Independent Spent Fuel Storage Installations RS-23-039, Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air2023-03-0101 March 2023 Request for License Amendment to Revise Technical Specifications Section 3.8.3, Diesel Fuel Oil, Lube Oil, and Starting Air RS-23-045, Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.2032023-02-28028 February 2023 Constellation Energy Generation, LLC Submittal of Fitness for Duty Performance Data Reports for 2022 Per 10 CFR 26.717(c) & 10 CFR 26.203 RS-23-003, Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-102023-01-31031 January 2023 Constellation Energy Generation, LLC, Summary of Changes to Quality Assurance Topical Report, NO-AA-10, and Decommissioning Quality Assurance Program, NO-DC-10 RS-23-002, Application to Adopt TSTF-332, ECCS Response Time Testing2023-01-13013 January 2023 Application to Adopt TSTF-332, ECCS Response Time Testing RS-22-126, Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2022-11-30030 November 2022 Constellation Energy Generation, LLC - Request to Use Provisions of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI RS-22-121, Notice of Intent to Pursue Subsequent License Renewal Applications2022-11-0909 November 2022 Notice of Intent to Pursue Subsequent License Renewal Applications RS-22-092, Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration2022-10-0303 October 2022 Nine and Quad Cities - Application to Revise Primary Containment Isolation Instrumentation Technical Specifications in Accordance with TSTF-306, Revision 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration RS-22-107, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station2022-09-29029 September 2022 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors for Clinton Power Station RS-22-093, Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans2022-08-18018 August 2022 Advisement of Leadership Changes for Constellation Energy Generation, LLC and Submittal of Updated Standard Practice Procedures Plans RS-22-089, Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-07-25025 July 2022 Additional Information Supporting Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-060, Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling RS-22-061, Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves2022-05-24024 May 2022 Request for License Amendment to Adopt TSTF-269, Revision 2, Allow Administrative Means of Position Verification for Locked or Sealed Valves RS-22-067, Constellation Radiological Emergency Plan Addendum and Procedure Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum and Procedure Revision RS-22-068, Constellation Radiological Emergency Plan Addendum Revision2022-05-19019 May 2022 Constellation Radiological Emergency Plan Addendum Revision RS-22-055, Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan2022-04-18018 April 2022 Submittal of Preliminary Decommissioning Cost Estimate and Spent Fuel Management Plan RS-22-051, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-04-12012 April 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-020, Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock2022-04-0707 April 2022 Request for License Amendment to Revise the Secondary Containment Design Basis to Credit the Fuel Building Railroad Airlock RS-22-049, Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for V2022-04-0404 April 2022 Constellation Energy Generation, LLC, Supplemental Information to Correct Typographical Errors in Constellations Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Va RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations RS-22-027, Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated2022-02-23023 February 2022 Constellation, Response to Request for Additional Information Regarding Application to Revise Technical Specifications to Adopt TSTF-541 Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated P RS-22-023, Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement2022-02-23023 February 2022 Constellation Energy Generation, LLC, Executed Trust Fund Agreement Amendment and Subordinate Trust Agreement RS-22-019, Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists2022-02-16016 February 2022 Constellation Energy Generation, LLC - Update to Correspondence Addressees and Service Lists RS-22-013, Request to Transfer 10 CFR Part 71 Quality Assurance Program Approval for Radioactive Material Packages Under the Common Exelon Quality Assurance Program Approval No. 71-0008, to the Common Constellation Quality Assurance Program Approval2022-02-0909 February 2022 Request to Transfer 10 CFR Part 71 Quality Assurance Program Approval for Radioactive Material Packages Under the Common Exelon Quality Assurance Program Approval No. 71-0008, to the Common Constellation Quality Assurance Program Approval N RS-22-015, Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC2022-02-0101 February 2022 Notification of Completion of License Transfer and Request to Continue Processing Pending NRC Actions Previously Requested by Exelon Generation Company, LLC RS-22-004, Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-01-0404 January 2022 Supplement to Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements RS-21-121, Proposed Changes to Decommissioning Trust Agreements and Master Terms2021-12-15015 December 2021 Proposed Changes to Decommissioning Trust Agreements and Master Terms RS-21-102, Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors2021-09-29029 September 2021 Annual Report of Emergency Core Cooling System Evaluation Model Changes and Errors RS-21-091, Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes2021-09-13013 September 2021 Implementation of Insider Threat Program Requirements Associated with the Voluntary Security Clearance Program and Advisement of Leadership Changes RS-21-087, Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values2021-08-31031 August 2021 Additional Information Supporting Request for License Amendment to Revise Degraded Voltage Relay Allowable Values RS-21-078, Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel2021-08-19019 August 2021 Response to Request for Additional Information for Application to Revise Technical Specification to Adopt TSTF-582, Reactor Pressure Vessel Water Inventory Control (RPV WIC) Enhancements, and TSTF-583-T, TSTF-582 Diesel RS-21-076, Application to Adopt TSTF-273, Safety Function Determination Program Clarifications2021-07-30030 July 2021 Application to Adopt TSTF-273, Safety Function Determination Program Clarifications RS-21-063, Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2021-06-30030 June 2021 Application to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements 2024-09-09
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AmerGen Energy Company, LLC AmerGen An Exelon/British Energy Company Clinton Power Station R.R. 3 Box 228 Clinton, IL 61727-9351 RS-03-188 October 2, 2003 10 CFR 50.55a U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Clinton Power Station, Unit I Facility Operating License No. NPF-62 NRC Docket No. 50 461
Subject:
Supplemental Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program
References:
(1) Letter from K. R. Jury (AmerGen Energy Company, LLC) to U.S. NRC, "Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program," dated February 14, 2003 (2) Letter from K. R. Jury (AmerGen Energy Company, LLC) to U.S. NRC, uAdditional Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program," dated July 17, 2003 In Reference 1, AmerGen Energy Company (AmerGen), LLC submitted a request for a proposed alternative to the requirements of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, Rules for Inservice Inspection of Nuclear Power Plant Components," ASME/ANSI OMa-1988, "Operations and Maintenance of Nuclear Power Plants," 1987 Edition through the 1988 Addenda, Part 10, Sections 4.2.1.1 and 4.2.1.2 for Clinton Power Station (CPS).
ASME/ANSI OMa-1988, Part 10, Section 4.2.1.1, requires Category A and B valves to be tested nominally every three months (i.e., quarterly), unless the conditions specified by Section 4.2.1.2 are used to justify an alternate testing frequency. This request proposed allowing testing of Shutdown Service Water (SX) system valves without restriction on plant operating mode, while maintaining an 18-month testing frequency. This will optimize the availability and maintenance of the SX system by performing the full-stroke tests of these valves once per fuel cycle during scheduled work windows for this system. The proposed alternative testing will provide an equivalent level of quality and safety. 04 ?
'Z October 2, 2003 U. S. Nuclear Regulatory Commission Page 2 Reference 2 provided requested additional information in support of the NRC review of the proposed relief request.
Subsequent to the NRC's review of References 1 and 2, the NRC has identified that additional information be provided to support justification of the proposed alternative valve testing requirements for valves 1SX01 2A, 1SX01 2B, 1SX062A, and 1SX062B. The attachment to this letter provides the NRC requested information.
Should you have any questions related to this information, please contact Mr. Timothy A. Byam at (630) 657-2804.
Sincerely, Patrick R. Simpson Manager - Licensing
Attachment:
Supplemental Information Supporting the Proposed Altemative Testing-Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program cc: Regional Administrator - NRC Region Ill NRC Senior Resident Inspector - Clinton Power Station
ATTACHMENT Supplemental Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program The following details provide furtherjustfication for changing the testing frequency from the current cold shutdown to once per cycle, without restriction on plant operating mode.
Non-Refueling Outage Cold Shutdown Testing Cold shutdowns, other than those associated with refueling outages, are infrequent and typically prompted by emergent equipment issues. Resources and scheduled activities during a cold shutdown are primarily devoted to recovery from the shutdown and expeditiously returning the unit to power. In order to stroke the Shutdown Service Water (SX) system valves SX012A, SX012B, SX062A, and SX062B, it is necessary to realign the Component Cooling Water (CC) system to the Fuel Pool Cooling and Cleanup (FC) system heat exchangers. The time required to restore the heat exchangers to a cleanliness level necessary to support this activity may delay the unit's-return to power, making it impractical to perform the stroke time testing during cold shutdown. Historically, the time it takes to drain and refill the heat exchangers is approximately 16 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This time could be increased if additional flushing is required. Extending the unit shutdown for the purpose of stroking the valves would not have a corresponding safety benefit and would not be consistent with the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code, Section Xl, "Rules for Inservice Inspection of Nuclear Power Plant Components," ASME /American National Standards Institute (ANSI) OMa-1988, "Operations and Maintenance of Nuclear Power Plants," Section 4.2.1.2(g), which states: "...(it) is not the intent of this Part to keep the plant in cold shutdown in order to complete cold shutdown testing."
It should be noted that over the past two operating cycles (i.e., since restart from the seventh refueling outage), Clinton Power Station (CPS) has not experienced any entries into Mode 4, Cold Shutdown," except as part of a refueling outage sequence.
Refueling Outage Testing During Mode 4 and Mode 5, "Refueling," the amount of time and resources necessary to stroke the valves and restore the heat exchangers to acceptable cleanliness levels would detract from expeditious transition into the refueling activity. Availability of the FC system is vital to maintaining acceptable fuel pool temperatures with recently discharged fuel assemblies present. Additionally, these activities may detract from efficient refueling outage execution. It is necessary to maintain the FC system in service to provide acceptable water quality to ensure water clarity in the upper containment fuel pools.
Also, the FC system is used to remove radioactive contaminants from the pool water in order to minimize the radiation level in the vicinity of the pool and the release of radioisotopes from the pool water into the air. Performing the required testing after refueling activities are complete could put this testing on critical path and could delay startup. Therefore, it would be preferable to schedule this testing with other work activities that would not impact plant startup, whether it be performed during a refueling outage or during an on-line system outage.
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ATTACHMENT Supplemental Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program Component Reliability Valves SX01 2A, 1SX01 2B, SX062A, and 1SX062B each have had a very good performance history, having never failed an Inservice Testing Program test. The valves are normally closed and seldom operated, except for the performance of surveillance testing. As stated above, the valves are stroked on a Cold Shutdown frequency, and given their on-line performance history and the fact that CPS does not routinely enter Cold Shutdown testing for an extended period (i.e., other than during refueling), the valves are, in effect, only stroked once each refueling outage to satisfy surveillance requirements. The valves are in a raw water system that is susceptible to silting. Due to the concerns associated with untreated lake water, the piping in which the valves are located is included in the CPS Generic Letter 89-13 program. These valves are located at the interface of raw lake water and clean demineralized water. Currently, the lines are scheduled for non-destructive examination (i.e., radiography) on a 10-year frequency.
The valves are maintained in a standby condition during unit operation. The only routine operational evolution performed that requires these valves to be exercised is the flow balance testing performed every 4 years. Following approval of the proposed relief request, the flow balance testing will be scheduled in conjunction with the subject code required valve stroking. There are no other SX system surveillances that require cycling of the subject valves. As discussed in ASME Code Case OMN-1, Alternative Rules for Preservice and Inservice Testing of Certain Electric Motor-Operated Valve Assemblies in Light-Water Reactor Power Plants," motor-operated valves shall be exercised on an interval not to exceed once per refueling cycle. This request does not seek additional relaxation beyond this requirement.
Motor Ooerated Valve MOV) Testing Program The 1SX012AB and 1SX062AIB valves have an inherently robust design. They are standard design code valves utilizing Limitorque SMB-000 type motor operators.
Operating experience with these MOV's has been exceptionally good, with the likelihood of valve failure being statistically extremely low. The actuators have approximately a 30% margin per Generic Letter 89-10 program calculations.
The valves are identified as low risk components in the CPS MOV testing program. The valves are well maintained through periodic inspection, lubrication and Valve Operator Testing Evaluation System (VOTES) testing. The VOTES testing provides an excellent analytical tool for monitoring valve degradation. These MOV's are currently on a 3-year clean and inspect periodicity and a 5-year thrust verification testing periodicity.
Conclusion The above discussion identifies why it is an acceptable alternative to allow testing of the subject SX valves as proposed and why it is undesirable to restrict stroking the Page 2 of 3
-I ATTACHMENT Supplemental Information Supporting the Proposed Alternative Testing Requirements for Shutdown Service Water System Valves for the Second 10-Year Inservice Testing Program ISX012A, SX012B, ISX062A, and ISX062B valves solely during a cold shutdown or refueling outage due to conflicting work activities and schedule constraints. However, there may be instances when stroking the valves may be feasible during a cold shutdown or refueling outage based on the scheduled work scope. Therefore, as requested in the referenced letter, CPS proposes to allow testing of the SXO1 2A, 1SXO12B, 1SX062A, SX062B valves, without restriction on plant operating mode, while maintaining a once per refueling cycle testing frequency.
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