Letter Sequence Response to RAI |
|---|
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MONTHYEARML0233004652002-11-26026 November 2002
Review of Relief Requests Associated with the Fourth Interval Inservice Testing Program Plan Submittal Dated November 22, 2002
Project stage: Approval
ML0308200022003-03-21021 March 2003
3/21/2003, Monticello, RAI, the Fourth 10-Year Interval Inservice Testing Program
Project stage: RAI
L-MT-03-023, Response to Request for Additional Information Regarding Fourth 10-Year Interval Inservice Testing Program Relief Request Number No.VR-012003-04-29029 April 2003
Response to Request for Additional Information Regarding Fourth 10-Year Interval Inservice Testing Program Relief Request Number No.VR-01
Project stage: Response to RAI
L-MT-03-040, Response to Request for Additional Information on the Fourth 10-Year Inservice Testing Interval Relief Request No. Pr 032003-05-15015 May 2003
Response to Request for Additional Information on the Fourth 10-Year Inservice Testing Interval Relief Request No. Pr 03
Project stage: Response to RAI
L-MT-03-044, Response to Request for Additional Information Regarding Relief Request No. PR-042003-05-30030 May 2003
Response to Request for Additional Information Regarding Relief Request No. PR-04
Project stage: Response to RAI
ML0317002092003-07-17017 July 2003
Relief Request, Nos. PR-01, PR-02, PR-03, PR-04, PR-05, and VR-02 Related to the Fourth 10-Year Interval Inservice Testing Program
Project stage: Acceptance Review
2003-04-29
[Table View] |
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARL-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023
2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
L-MT-23-024, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Inspection (ISI) Interval, RR-002 (L-MT-23-024)2023-07-11011 July 2023
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Inspection (ISI) Interval, RR-002 (L-MT-23-024)
L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022
Sixth Interval Inservice Testing (1ST) Plan
ML22067A0842022-03-0707 March 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-28 (LMT-22-007)
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
L-MT-21-051, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-22 (L-MT-21-051)2021-12-23023 December 2021
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-22 (L-MT-21-051)
ML21305A0672021-11-0101 November 2021
Clone of 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing (IST) Ten-Year Interval PR-02 (L-MT-21-054)
ML21278A1852021-10-0505 October 2021
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-02 (LMT-21-049)
L-MT-21-041, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-05 (L-MT-21-041)2021-08-31031 August 2021
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval VR-05 (L-MT-21-041)
L-MT-21-038, 2021 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2021-08-17017 August 2021
2021 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
L-MT-20-004, 10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2020-02-14014 February 2020
10 CFR 50.55a Request: Request RR-016 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval
L-MT-20-001, 10 CFR 50.55a(z)(1) Request Vr 05: Request for Approval of an Alternative for Pressure Isolation Valve Testing2020-01-16016 January 2020
10 CFR 50.55a(z)(1) Request Vr 05: Request for Approval of an Alternative for Pressure Isolation Valve Testing
L-MT-19-028, 2019 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report; Second Steam Dryer Inspection Summary2019-08-0909 August 2019
2019 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report; Second Steam Dryer Inspection Summary
L-MT-17-059, 2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report2017-08-0909 August 2017
2017 Refueling Outage 90-Day Lnservice Inspection (ISI) Summary Report
L-MT-15-064, Cycle 27 Inservice Inspection Summary Report2015-08-26026 August 2015
Cycle 27 Inservice Inspection Summary Report
ML14212A0712014-07-30030 July 2014
10 CFR 50.55a Request No. Vr 05: Proposed Alternative to Lnservice Testing Requirements Pursuant to 10 CFR 50.55a(a)(3)(ii)
L-MT-14-037, CFR 50.55a Request No. 009: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fifth Ten-Year Lnservice Inspection Interval2014-06-0606 June 2014
CFR 50.55a Request No. 009: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fifth Ten-Year Lnservice Inspection Interval
L-MT-14-021, Proposed Alternative in Accordance with 10 CFR 50.55a Request RR-008 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval2014-02-28028 February 2014
Proposed Alternative in Accordance with 10 CFR 50.55a Request RR-008 Associated with the Fifth Ten-Year Inservice Inspection (ISI) Interval
ML13308B2192013-10-11011 October 2013
Enclosure 3 - MNGP Evaluation EC-22537 - 2013 H8-H9 Shroud Support Structure Indications Update
ML13308B2182013-10-0808 October 2013
Enclosure 2- BWRVIP Inspection Summary Report
ML13308B2172013-10-0808 October 2013
Enclosure 1 - Cycle No. 26 and 1R26 2013 Refueling Outage Inservice Inspection: Interval 4, Period 3 and Interval 5, Period 1, Owner'S Activity Report (OAR-1)
L-MT-13-060, Response to Request for Additional Information Regarding Fifth 10-Year Inservice Inspection Program Plan Review2013-07-17017 July 2013
Response to Request for Additional Information Regarding Fifth 10-Year Inservice Inspection Program Plan Review
L-MT-12-094, In-service Testing (IST) Program Plan for Safety Related Seismic Restraints (Snubbers) for the Fifth 10-Year Interval2012-11-30030 November 2012
In-service Testing (IST) Program Plan for Safety Related Seismic Restraints (Snubbers) for the Fifth 10-Year Interval
L-MT-12-019, CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval2012-02-28028 February 2012
CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Testing Interval
L-MT-12-017, CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Inspection Interval2012-02-28028 February 2012
CFR 50.55a Requests Associated with the Fifth Ten-Year Inservice Inspection Interval
L-MT-12-020, Fifth Ten-Year Lnservice Testing Plan2012-02-28028 February 2012
Fifth Ten-Year Lnservice Testing Plan
L-MT-12-018, Fifth Ten-Year Lnservice Inspection Plan2012-02-28028 February 2012
Fifth Ten-Year Lnservice Inspection Plan
L-MT-12-011, Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals2012-02-15015 February 2012
Supplement to 10CFR50.55a Requests Associated with the Fourth and Fifth Lnservice Lnspection Ten-Year Intervals
L-MT-11-046, Cycle 25 Inservice Inspection Summary Report2011-08-23023 August 2011
Cycle 25 Inservice Inspection Summary Report
L-MT-09-078, Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements2009-08-0707 August 2009
Submittal of Cycle No. 24 Inservice Inspection Summary Report for Inservice Inspection and ASME Section Xl Repairs and Replacements
L-MT-07-058, Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements2007-07-27027 July 2007
Cycle No. 23 Lnservice Inspection Summary Report for Lnservice Inspection and ASME Section XI Repairs and Replacements
L-MT-05-088, 10 CFR 50.55a Request No. 13: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Inservice Inspection Interval2005-09-27027 September 2005
10 CFR 50.55a Request No. 13: Relief from Impractical Examination Coverage Requirements Pursuant to 10 CFR 50.55a(g)(5)(iii) for the Fourth Ten-Year Inservice Inspection Interval
L-MT-05-078, Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements2005-07-12012 July 2005
Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements
L-MT-05-039, Fourth Interval Inservice Inspection Examination Plan. Revision 32005-04-26026 April 2005
Fourth Interval Inservice Inspection Examination Plan. Revision 3
L-MT-04-050, Fourth Interval Inservice Inspection Examination Plan, Revision 22004-09-16016 September 2004
Fourth Interval Inservice Inspection Examination Plan, Revision 2
L-MT-03-056, Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements2003-08-25025 August 2003
Summary Report for Inservice Inspections and ASME Section XI Repairs and Replacements
L-MT-03-023, Response to Request for Additional Information Regarding Fourth 10-Year Interval Inservice Testing Program Relief Request Number No.VR-012003-04-29029 April 2003
Response to Request for Additional Information Regarding Fourth 10-Year Interval Inservice Testing Program Relief Request Number No.VR-01
ML0235205912002-12-0606 December 2002
to Engineering Work Instruction EWI-09.04.01, Inservice Testing Program.
ML0233806832002-11-22022 November 2002
Part 2 of 2, Monticello, Request for Review and Approval of Relief Request Associated with Fourth 10-Year Interval Inservice Testing Program Plan Submittal
ML0233701072002-11-22022 November 2002
Part 1 of 2, Monticello, Request for Review and Approval of Relief Request Associated with Fourth 10-Year Interval Inservice Testing Program Plan Submittal
ML0217102272002-06-0606 June 2002
Inservice Testing Program for Engineering Work Instruction, Revision 8
ML0211905312002-04-0101 April 2002
Revision 7 to EWI-09.04.01, Inservice Testing Program.
ML0208603482002-03-12012 March 2002
Part 1 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements
ML0208605512002-03-12012 March 2002
Part 2 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613
ML0208606762002-03-12012 March 2002
Part 3 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613
ML0208606932002-03-12012 March 2002
Part 4 of 4, Monticello Nuclear Generating Plant, Summary Report for Inservice Inspections & ASME Section XI Repairs & Replacements, Owner'S Report for Repairs or Replacements - Form NIS-2, Revision 4 to 3613
ML0203203662002-01-11011 January 2002
Inservice Inspection Plan Submittal of Relief Request Number 14 for the Third Ten Year Interval
2023-07-31
[Table view]
Category:Letter type:L
MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024
Subsequent License Renewal Application Supplement 8
L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023
License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data
L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2
L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023
2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023
Subsequent License Renewal Application Supplement 7
L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023
Update to the Technical Specification Bases
L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023
Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1
L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023
10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09
L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023
License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6
L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023
Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1
L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023
Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2
L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 3
L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6
L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023
Subsequent License Renewal Application Supplement 5
L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023
Subsequent License Renewal Application Response to Request for Additional Information Set 1
L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023
2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report
L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023
10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11
L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023
Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1
L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023
Subsequent License Renewal Application Supplement 3
L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023
Subsequent License Renewal Application Supplement 2
L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023
Submittal of 2022 Annual Radiological Environmental Operating Report
L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023
Submittal of 2022 Annual Radioactive Effluent Release Report
L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023
Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32
L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023
2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)
L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023
Subsequent License Renewal Application Supplement 1
L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023
Core Operating Limits Report (COLR) for Cycle 31, Revision 3
L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023
Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2
L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023
10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)
L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023
CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program
L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023
Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)
L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022
Industry Groundwater Protection Initiative Special Report
L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022
L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative
L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022
2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46
L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022
Update to the Monticello Technical Specification Bases
L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022
Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022
Letter Submitting Post-Exam Package
L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022
Sixth Interval Inservice Testing (1ST) Plan
L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022
Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022
Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)
L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022
Changes to the Emergency Plan
L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022
Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies
L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022
Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency
L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022
2021 Annual Radiological Environmental Operating Report
L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022
2021 Annual Radioactive Effluent Release Report
L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022
2021 Annual Report of Individual Monitoring
L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022
Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval
L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022
License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency
L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022
Special Report for the Bypass of the Offgas Treatment Storage System
L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)
L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022
10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)
2024-01-11
[Table view] |
Text
i .Monticello Nuclear Generating Plant Committed to Nuclear Excelence Operated by Nuclear Management Company, LLC April 29, 2003 L-MT-03-023 10 CFR Part 50 Section 50.55a(a)(3)
US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 LICENSE No. DPR-22 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION REGARDING FOURTH 10-YEAR INTERVAL INSERVICE TESTING PROGRAM RELIEF REQUEST NUMBER NO. VR-01 (TAC No. MB6807)
Reference 1: NMC Letter to NRC, "Request for Review and Approval of Relief Requests Associated with Fourth 10-Year Interval Inservice Testing Program Plan Submittal," dated November 22, 2002 Reference 2: NRC Letter to NMC, "Monticello Nuclear Generating Plant - Request for Additional Information (RAI) Related To the Fourth 10-Year Interval Inservice Testing (IST) Program (TAC No. MB6807)," dated March 21, 2003 In Reference 1 Nuclear Management Company, LLC (NMC) requested NRC approval of the Monticello Nuclear Generating Plant (MNGP) Inservice Testing (IST) Fourth Ten-Year Interval relief requests (RR). One of the new relief request provided was Valve Relief (VR)-01, "Control Rod Drive-1 14 Closure Testing." VR-01 was requested based on code edition and addenda changes in the IST Program Plan.
Reference 2 requested the NMC to provide additional information regarding the grouping of 121 check valves into a single group for sampling purposes.
While determining the response to questions raised in Reference 2, additional information became available that indicated that the current relief request could be revised to provide an enhanced relief request. Therefore, on 4/21/03 NMC held a conference call with the NRC to discuss the revised approach for the relief request.
Subsequent to the conference call between NMC and the NRC, NMC has decided to withdraw the initial issue of the relief request contained in Reference 1 and supercede it with the relief request enclosed in Attachment A to this letter. Because of the revised approach, the questions/information requested by the NRC in Reference 2 are no longer applicable and are not discussed further.
2807 West County Road 75
- Monticello, Minnesota 55362-9637 Telephone: 763-295-5151
USNRC Nuclear Management Company, LLC Page 2 This letter makes no new commitments.
If you have any questions regarding this submittal, please contact John Fields, Senior Licensing Engineer at (763) 295-1663.
David L.Wilson Site Vice President Monticello Nuclear Generating Plant cc: Regional Administrator-lIl, NRC NRR Project Manager, NRC Sr. NRC Resident Inspector, NRC State of Minnesota Boiler Inspector Hartford Insurance Attachment A - RELIEF REQUEST VR-01, Rev. 1
Attachment A NUCLEAR MANAGEMENT COMPANY, LLC MONTICELLO NUCLEAR GENERATING PLANT DOCKET 50-263 April 29, 2003 VALVE RELIEF REQUEST VR-01, Rev. 1 3 pages follow A-1
Attachment A MONTICELLO NUCLEAR GENERATING STATION VALVE RELIEF REQUEST NUMBER: VR-01 (Page 1 of 3)
COMPONENT IDENTIFICATION Code Classes: 2
References:
ISTC 4.5.2 "Exercising Requirements" Examination Categories: C Item Numbers: N/A
==
Description:==
Control Rod Drive Hydraulics Component Numbers: CRD-114 (total 121)
CODE REQUIREMENT American Society of Mechanical Engineers (ASME) OMa Code 1996, ISTC 4.5 "Inservice Exercising Test for Category C Check Valves" includes a requirement under 4.5.2 "Exercising Requirements" which states, "Each check valve test shall include open and close tests."
ISTC 4.5.2(c) states, "If exercising is not practicable during plant operation and cold shutdowns, it shall be performed during refueling outages."
BASIS FOR RELIEF The subject check valves, CRD-1 14 (scram discharge header check valves), are simple ball-check design. There are no internal parts in the check valves that are susceptible to rapid degradation and sudden failure. In addition, the control rods are infrequently scrammed and these valves are thus subjected to few stress/wear cycles.
It is not practical to perform the close exercise test on-line, since the testing could result in the rapid insertion of one or more control rods, and cause rapid reactivity transients. Additionally, performing the close test on all 121 valves each refueling outage is a hardship that is not offset by a compensating increase in the level of quality and safety. The volume of testing results in a substantial burden on plant resources via the expenditure of person-hours and person-REM to perform the associated system filling, venting and testing tasks.
Furthermore, the valves are welded into the line and it is not practicable to perform a disassembly and inspection of each valve in accordance with ISTC 4.5.4(c). Due to the piping configuration of hydraulic control unit a disassembly and inspection of the check valve presents a hardship. To access the check valve an additional valve requires disassembly and then the welded piping may be removed. There is no provision for routine access for direct visual A-2
- + v -
Attachment A examination of the ball and body seats or for indirect examination of internals using remote viewing aides such as a boroscope.
Generic Letter (GL) 89-04, "Guidance on Developing Acceptable Inservice Testing Programs," provides staff approved alternatives in Attachment 1, Positions 1, 2, 6, 7, 9, and 10. Position 7 provides an approved alternative "Testing Individual Control Rod Scram Valves in Boiling Water Reactors (BWRs)." The position requires that those ASME Code Class valves that must change position to provide the scram function should be included in the IST Program and be tested in accordance with the requirements of Section Xl except where relief has been granted in a previously issued Safety Evaluation Report or as discussed in Position 7.
GL 89-04 Position 7 states:
"The control rod drive system valves that perform an active safety function in scramming the reactor are the scram discharge volume vent and drain valves, the scram inlet and outlet valves, the scram discharge header check valves, the charging water header check valves, and the cooling water header check valves. With the exception of the scram discharge volume vent and drain valves, exercising the other valves quarterly during power operations could result in the rapid insertion of one or more control rods more frequently than desired."
-.for those control rod drive system valves where testing could result in the rapid insertion of one or more control rods, the rod scram test frequency identified in the facility TS may be used as the valve testing frequency to minimize rapid reactivity transients and wear of the control rod drive mechanisms. The alternate test frequency should be clearly stated and documented in the IST Program."
The proper operation of the check valves is demonstrated during scram time testing. During scram time testing, scram insertion time is measured for each Control Rod Drive (CRD). Monticello Technical Specification No. 3.3.C provides scram insertion times for the CRD. If a particular CRD scram insertion time is acceptable per the Monticello Technical Specifications requirement, the CRD-114 check valves are functioning properly. Monticello Technical Specification 4.3.C requires:
"During each Operating Cycle, each operable control rod shall be subjected to scram time tests from the fully withdrawn position. If testing is not accomplished during reactorpower operation, the measured scram insertion times shall be extrapolated to the reactor power operation condition utilizing previously determined correlations."
The Scram Discharge Header Check Valves have a safety function to open. This valve must open to provide a flow path from the overpiston area of the control rod A-3
Attachment A drive to the scram discharge header during a scram. This check valve closed function is to prevent backflow from the scram discharge volume (SDV) to the overpiston area of the drive when a Scram is reset. Flow from the CRD to the SDV occurs throughout the entire scram stroke of the control rod and continues until volume pressure equals reactor vessel pressure. There would normally be no demand for check valve closure until after the rod is fully inserted and latched.
PROPOSED ALTERNATE PROVISIONS Pursuant to 10CFR50.55a(a)(3)(i), NMC proposes to perform testing of the CRD scram discharge header check valves consistent with the alternative testing provided in GL 89-04. This would mean that the closed function would not be tested as required by ISTC 4.5.2.
CONCLUSION In summary, the proposed NMC alternative uses an already approved alternative contained in Position 7 of GL 89-04. The closed function of the valve is not required in order to perform the safety function for the control rod to insert during a scram. The closed function would not be performed per ISTC 4.5.2.
PERIOD FOR WHICH RELIEF IS REQUESTED Relief is requested for the Fourth Ten-year interval of the Inservice Testing Program.
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