|
---|
Category:Letter type:HNP
MONTHYEARHNP-18-050, Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date2018-09-17017 September 2018 Request to Extend Reactor Vessel Surveillance Capsule Report Submission Date HNP-18-004, License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme2018-08-13013 August 2018 License Amendment Request to Change Shearon Harris Nuclear Power Plant, Unit 1, Emergency Plan Emergency Action Level Scheme HNP-18-035, Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval2018-06-0404 June 2018 Relief Request I3R-18, Alternative Repair and Replacement Testing Requirements for the Containment Building Equipment Hatch Sleeve Weld, Lnservice Inspection Program for Containment, Third Ten-Year Interval HNP-18-049, Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 192018-05-0303 May 2018 Submittal of 1 0 CFR 50.54(q) Evaluation Form of Changes to Procedure EMP-420, Emergency Program Maintenance, Revision 19 HNP-18-023, Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes2018-05-0202 May 2018 Report of Changes Pursuant to 10 CFR 50.59 and Summary of Commitment Changes HNP-18-042, Annual Environmental (Non-radiological) Operating Report2018-04-30030 April 2018 Annual Environmental (Non-radiological) Operating Report HNP-18-032, Annual Radiological Environmental Operating Report2018-04-25025 April 2018 Annual Radiological Environmental Operating Report HNP-18-031, Annual Radioactive Effluent Release Report2018-04-25025 April 2018 Annual Radioactive Effluent Release Report HNP-18-047, Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation2018-04-20020 April 2018 Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval, Non-Proprietary Version of Calculation HNP-18-045, Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval2018-04-18018 April 2018 Submittal of Relief Request I4R-18, Reactor Vessel Closure Head Nozzle Repair Technique, Inservice Inspection Program, Fourth Ten-Year Interval HNP-18-044, Cycle 22 Core Operating Limits Report, Revision O2018-04-16016 April 2018 Cycle 22 Core Operating Limits Report, Revision O HNP-18-039, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2018-04-13013 April 2018 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-18-021, Annual Report in Accordance with Technical Specification 6.9.1.22018-02-19019 February 2018 Annual Report in Accordance with Technical Specification 6.9.1.2 HNP-18-020, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-02-16016 February 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-019, Cycle 21 Core Operating Limits Report, Revision 12018-02-14014 February 2018 Cycle 21 Core Operating Limits Report, Revision 1 HNP-18-017, CFR 50.54(q) Evaluations2018-02-0505 February 2018 CFR 50.54(q) Evaluations HNP-18-001, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors.2018-02-0101 February 2018 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems, and Components (Sscs) for Nuclear Power Reactors. HNP-18-002, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2018-01-22022 January 2018 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-18-003, Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses2018-01-18018 January 2018 Response to Request for Additional Information Regarding License Amendment Request for Spent Fuel Storage Pool Criticality Analyses HNP-18-007, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations2018-01-11011 January 2018 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis - Supplement Regarding De Minimis Penetrations HNP-18-006, Submittal of 14-Day Special Report for Accident Radiation Monitors2018-01-0404 January 2018 Submittal of 14-Day Special Report for Accident Radiation Monitors HNP-17-093, Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 32017-11-29029 November 2017 Supplement to License Amendment Request Proposing a New Set of Fission Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3 HNP-17-078, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-11-27027 November 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-082, Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In..2017-10-30030 October 2017 Response to Request for Additional Information Regarding License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Limit Detailed In.. HNP-17-084, Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements2017-10-30030 October 2017 Response to Request for Additional Information Regarding a License Amendment Request Proposing Changes to Emergency Diesel Generator Technical Specifications Surveillance Requirements HNP-17-025, Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan2017-10-23023 October 2017 Fourth Interval Lnservice Inspection Plan, Third Interval Containment Lnservice Inspection Plan, and Fourth Interval Lnservice Inspection Pressure Test Plan HNP-17-072, License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis2017-10-19019 October 2017 License Amendment Request to Incorporate Tornado Missile Risk Evaluator Into Licensing Basis HNP-17-077, License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications2017-10-10010 October 2017 License Amendment Request Regarding Rod Control Movable Assemblies Technical Specifications HNP-17-076, Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements.2017-10-0202 October 2017 Supplement to License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Duplicate Reporting Requirements. HNP-17-073, Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-09-14014 September 2017 Supplemental Information for License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-062, Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal2017-09-13013 September 2017 Response to March 12, 2012, Request for Information Enclosure 2, Recommendation 2.1, Flooding, Required Response 3, Flooding Focused Evaluation Summary Submittal HNP-17-061, Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-07-20020 July 2017 Supplement to License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-008, License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses2017-06-28028 June 2017 License Amendment Request Regarding Spent Fuel Storage Pool Criticality Analyses HNP-17-003, License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection2017-06-0505 June 2017 License Amendment Request for Emergency Diesel Generator Surveillance Requirements Regarding Voltage and Frequency Limits and the Voltage Limit for Emergency Diesel Generator Load Rejection HNP-17-040, Snubber Program Plan2017-06-0101 June 2017 Snubber Program Plan HNP-17-051, 10 CFR 50.54(q) Evaluation2017-05-24024 May 2017 10 CFR 50.54(q) Evaluation HNP-17-050, Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center2017-05-24024 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation for Revision 21 to PEP-250, Activation and Operation of the Joint Information Center HNP-17-041, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete2017-05-22022 May 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106, and Delete Du HNP-17-033, License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 112017-05-22022 May 2017 License Amendment Request Proposing a New Set of Fission Gas Gap Release Fractions for High Burnup Fuel Rods That Exceed the Linear Heat Generation Rate Limit Detailed in Regulatory Guide 1.183, Table 3, Footnote 11 HNP-17-049, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 26 to PEP-110, Emergency Classification and Protective Action Recommendations. HNP-17-047, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-048, Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations.2017-05-18018 May 2017 Transmittal of 10 CFR 50.54(q) Evaluation and Revision 28 to PEP-230, Control Room Operations. HNP-17-046, 10 CFR 50.54(q) Evaluation2017-05-18018 May 2017 10 CFR 50.54(q) Evaluation HNP-17-024, Annual Environmental (Nonradiological) Operating Report2017-04-28028 April 2017 Annual Environmental (Nonradiological) Operating Report HNP-17-023, Annual Radioactive Effluent Release Report2017-04-28028 April 2017 Annual Radioactive Effluent Release Report HNP-17-034, Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106..2017-04-25025 April 2017 Response to Request for Additional Information Regarding License Amendment Request to Relocate Technical Specification Cycle-Specific Parameters to the Core Operating Limits Report, Delete Reference to Plant Procedure PLP-106.. HNP-17-035, Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator2017-04-12012 April 2017 Request for Pilot Plant Status and Fee Waiver to Implement Tornado Missile Risk Evaluator HNP-17-045, 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation2017-03-30030 March 2017 10 CFR 50.54(q) Evaluation of Change in Emergency Plan Implementation Procedure PEP-241, Revision 7, Technical Support Center (TSC) Emergency Ventilation System Operation HNP-17-014, Annual Report in Accordance with Technical Specifications, Section 6.9.1.22017-02-16016 February 2017 Annual Report in Accordance with Technical Specifications, Section 6.9.1.2 HNP-17-015, Summary of 10 CFR 50.54(q) Evaluation2017-02-15015 February 2017 Summary of 10 CFR 50.54(q) Evaluation 2018-09-17
[Table view] |
Text
C WW-AJRobert J. Duncan, 11 Progress Energy ViceRbr Nuclear Harris JPresidentDna,l Plant Progress Energy Carolinas, Inc.
FEB 2 7 2007 Serial: HNP-07-026 U.S. Nuclear Regulatory Commission ATTENTION: Document Control Desk Washington, DC 20555 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 INSPECTION AND MITIGATION OF ALLOY 82/182 PRESSURIZER BUTT WELDS Ladies and Gentlemen:
By letter dated January 31, 2007, Carolina Power and Light Company (CP&L) doing business as Progress Energy Carolinas, Inc., notified the NRC of actions taken or planned at the Harris Nuclear Plant (HNP) for inspecting or mitigating Alloy 82/182 butt welds on the pressurizer spray, surge and relief lines. By a phone call with the NRC on February 20, 2007, HNP discussed the previous letter and the NRC's expectations for mitigation of the pressurizer Alloy 82/182 butt welds and enhanced unidentified RCS leakage monitoring.
During this phone call, HNP confirmed its previous commitment to mitigate the subject welds by installing full structural weld overlays by the end of refueling outage 14 (RFO-14) scheduled in the fall 2007, and to continue performing daily unidentified RCS leakage monitoring. By a follow-up phone call with the NRC on February 22, 2007, HNP committed to implement enhanced unidentified RCS leakage monitoring in Modes 1-3 until the subject welds are mitigated in the fall 2007. The enhanced unidentified RCS leakage monitoring will be in effect by March 6, 2007.
Attachment 1 provides HNP's response to the NRC's expectations for mitigation of the pressurizer Alloy 82/182 butt welds and enhanced unidentified RCS leakage monitoring, which supersedes the HNP response contained in the letter dated January 31, 2007.
Attachment 2 provides the commitments to this letter, which includes the original commitment as documented in the letter dated January 31, 2007, as well as new or revised regulatory commitments.
HNP will notify the NRC prior to any revisions to the commitments contained in this letter.
P.O.Box 165 New Hill, NC 27562 T> 919.362.2502 F> 919.362.2095
I,> ~)
HNP-07-026 Page 2 Our staff is available to meet with the NRC to discuss any of the information in this letter. Please refer any questions regarding this submittal to Dave Corlett at (919) 362-3137.
J. Duncan, II Vice President Harris Nuclear Plant RJD/jpy Attachments:
- 1. HNP's Response to the NRC's Expectations for Mitigation of Pressurizer Alloy 82/182 Butt Welds and Enhanced RCS Leakage Monitoring
- 2. Commitments c:
Mr. P. B. O'Bryan, NRC Senior Resident Inspector Mr. C. P. Patel, NRC Project Manager Dr. W. D. Travers, NRC Regional Administrator
Attachment 1 to SERIAL: HNP-07-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 HNP'S RESPONSE TO THE NRC EXPECTATIONS FOR MITIGATION OF PRESSURIZER ALLOY 82/182 BUTT WELDS AND ENHANCED REACTOR COOLANT SYSTEM LEAKAGE MONITORING Expectation 1: Mitigation Date The licensee should confirm its commitment to mitigate the pressurizerAlloy 82/182 butt welds in 2007.
Response 1:
HNP will comply with Expectation 1.
The Harris Nuclear Plant (HNP) confirms its commitment, as discussed in the letter dated January 31, 2007, to mitigate the pressurizer Alloy 82/182 butt welds by installing full structural weld overlays on these welds and to inspect post-overlay during refueling outage 14 (RFO-14) in the fall 2007.
Page Al-1 of 5
Attachment 1 to SERIAL: HNP-07-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 HNP'S RESPONSE TO THE NRC EXPECTATIONS FOR MITIGATION OF PRESSURIZER ALLOY 82/182 BUTT WELDS AND ENHANCED REACTOR COOLANT SYSTEM LEAKAGE MONITORING Expectation 2: RCS Leakage Monitoring Frequency The licensee should confirm its commitment to monitor RCS leakage daily while the plant is in Modes 1-3.
Response 2:
HNP will comply with Expectation 2.
HNP confirms its commitment, as discussed in the letter dated January 31, 2007, to continue monitoring unidentified RCS leakage daily while the plant is in Modes 1-3 during stable plant conditions until mitigation of the pressurizer Alloy 82/182 butt welds scheduled in RFO-14 (fall 2007).
As discussed during the phone call on February 20, 2007, HNP may extend the monitoring frequency within the 25% allowance for daily surveillance intervals provided by the Technical Specifications (TS) at HNP. In addition, HNP may extend the monitoring frequency during transient plant conditions such as power ascension.
Page A1-2 of 5
Attachment 1 to SERIAL: HNP-07-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 HNP'S RESPONSE TO THE NRC EXPECTATIONS FOR MITIGATION OF PRESSURIZER ALLOY 82/182 BUTT WELDS AND ENHANCED REACTOR COOLANT SYSTEM LEAKAGE MONITORING Expectation 3: RCS Leakage Monitoring Action Levels The action levels for RCS leakage monitoring should include the following two parts:
- 1. A 0. 1 gpm change from one day to the next sustainedfor 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with at least 0. 1 gpm not confirmed from sources other than the pressurizernozzle welds.
- 2. A 0. 25 gpm above the baseline sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with at least 0. 25 gpm not confirmed from sources other than the pressurizernozzle welds.
For Part 2, the baseline is established using unidentified RCS leakrate information collected during the first seven (7) days of Mode I full power operationsafter the most recent bare metal visual inspection of the pressurizernozzle welds.
Response 3:
HNP will comply with Expectation 3.
As discussed during the phone call on February 20, 2007, HNP will implement the two unidentified RCS leakage monitoring actions levels as follows:
- 1. A 0.1 gpm increase in the daily measurement to the mean, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with at least 0.1 gpm not confirmed from sources other than the pressurizer nozzle welds.
- 2. A 0.25 gpm above the baseline, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with at least 0.25 gpm not confirmed from sources other than the pressurizer nozzle welds.
For Part 1, the mean has been established in accordance with standard statistical analysis methodologies and is updated periodically.
For Part 2, the baseline was established using unidentified RCS leakrate information collected during the first seven (7) days of Mode 1 full power operations after the most recent bare metal visual inspection of the pressurizer nozzle welds.
For both Parts 1 and 2, any leakage that is confirmed to be from sources other than the pressurizer nozzle welds is not required to meet the Technical Specifications' definition of identified leakage.
Page A1-3 of 5
a Attachment 1 to SERIAL: HNP-07-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 HNP'S RESPONSE TO THE NRC EXPECTATIONS FOR MITIGATION OF PRESSURIZER ALLOY 82/182 BUTT WELDS AND ENHANCED REACTOR COOLANT SYSTEM LEAKAGE MONITORING Expectation 4: RCS Leakage Monitoring Actions Once the 72-hour sustainedperiod is complete and the leak rate is still elevated, place the unit in Mode 3 within six (6) hours and Mode 5 within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and perform bare metal visual inspection of the unmitigatedpressurizersurge, spray, safety, and relief nozzle butt welds and safe end butt welds containingAlloy 82/182 material.
Response 4:
HNP will comply with Expectation 4.
This monitoring action applies to both Parts 1 and 2 of the RCS Leakage Monitoring Action Levels discussed in Response 3 above, and these actions will be implemented by HNP procedure, OPT-9002T, Temporary Test for Pressurizer Dissimilar Weld Enhanced Leakage Monitoring, Daily Interval, Modes 1,2, 3, Expires 10/30/07, which will be in effect by March 6, 2007.
As discussed during the phone call on February 20, 2007, a positive determination that the unidentified RCS leakage came from a source other than the pressurizer Alloy 82/182 butt welds will terminate the required actions, conditioned upon finding the source and quantifying the leak. In addition, whenever unidentified RCS leakage is reduced to less than the action levels in Response 3 above, then the actions may be terminated.
Page A1-4 of 5
Attachment 1 to SERIAL: HNP-07-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 HNP'S RESPONSE TO THE NRC EXPECTATIONS FOR MITIGATION OF PRESSURIZER ALLOY 82/182 BUTT WELDS AND ENHANCED REACTOR COOLANT SYSTEM LEAKAGE MONITORING Expectation 5: Reporting
- 1. Report details of any corrective or mitigative actions taken within 60 days of unit restart.
- 2. Report bare metal visual inspection results within 60 days of unit restart.
Response 5:
HNP will comply with Expectation 5.
As discussed during the phone call on February 20, 2007, HNP will implement the reporting as follows:
- 1. HNP will report information of any corrective or mitigative actions taken within 60 days of unit restart.
- 2. If HNP shuts down due to unidentified RCS leakage (i.e., the action of Response 4 above), then HNP will report bare metal visual inspection results within 60 days of unit restart.
For Report 1, the details of the mitigation actions will be contained in the associated relief request, so this report will provide information confirming completion of the mitigation actions and post-mitigation inspection results.
For Report 2, this reporting is conditioned upon a shutdown due to the action of Response 4 above for unidentified RCS leakage, and it does not add a requirement to perform a pre-mitigation inspection.
Page A1-5 of 5
J.-. .'-..
Attachment 2 to SERIAL: HNP-07-026 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-400/LICENSE NO. NPF-63 INSPECTION AND MITIGATION OF ALLOY 82/182 PRESSURIZER BUTT WELDS COMMITMENTS Scheduled.
SCorrCmmitment(s) Completion, Date
- 1. HNP will mitigate the pressurizer Alloy 82/182 butt welds by installing full structural weld overlays on these welds and will End of RFO-14 inspect post-overlay during refueling outage 14 (RFO-14) in (fall 2007) the fall 2007.
- 2. HNP will monitor unidentified RCS leakage daily while the Beginning on plant is in Modes 1-3 during stable plant conditions until March 6, 2007 until mitigation of the pressurizer Alloy 82/182 butt welds mitigation of the scheduled in RFO-14 (fall 2007). pressurizer Alloy 82/182 butt welds
- 3. If unidentified RCS leakage should increase by 0.1 gpm in the daily measurement to the mean, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with at least 0.1 gpm not confirmed from sources other than Beginning on the pressurizer nozzle welds, then the unit will be placed in March 6, 2007 until Mode 3 within six (6) hours and Mode 5 within the next 36 mitigation of the hours, and a bare metal visual inspection of the unmitigated pressurizer Alloy pressurizer surge, spray, safety, and relief nozzle butt welds 82/182 butt welds and safe end butt welds containing Alloy 82/182 material will be performed.
- 4. If unidentified RCS leakage should increase by 0.25 gpm above the baseline, sustained for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> with at least 0.25 gpm not confirmed from sources other than the pressurizer Beginning on nozzle welds, then the unit will be placed in Mode 3 within March 6, 2007 until six (6) hours and Mode 5 within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, and a mitigation of the bare metal visual inspection of the unmitigated pressurizer pressurizer Alloy surge, spray, safety, and relief nozzle butt welds and safe 82/182 butt welds end butt welds containing Alloy 82/182 material will be performed.
- 5. HNP will report information of any corrective or mitigative actions taken, and if HNP shuts down due to unidentified Within 60 days of RCS leakage (i.e., the action of Response 4 of this letter), unit restart then HNP will report bare metal visual inspection results.
Page A2-1 of 1