Letter Sequence Request |
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EPID:L-2020-LLR-0007, Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-01) (Withdrawn, Closed) |
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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARML23229A5262023-08-17017 August 2023 Inservice Inspection Summary Report - 1 RE24, ML23221A3002023-08-0909 August 2023 RE22 Inspection Summary Report for Steam Generator Tubinq, Rev. 1 (Epld L-2023-LRO-0029) ML23044A6192023-02-13013 February 2023 Summary Report for Inservice Inspection (2RE22) Completed in November 2022 ML22033A5442022-02-0202 February 2022 Inservice Inspection Summary Report -1RE23 NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 ML21196A4922021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval ML21144A1092021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval ML20303A2602020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing ML20281A8542020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing ML20191A2702020-07-0909 July 2020 Inservice Inspection Summary Report -1RE22 NOC-AE-20003700, Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-01)2020-01-22022 January 2020 Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-01) NOC-AE-20003703, Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-04)2020-01-22022 January 2020 Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-04) NOC-AE-19003696, Supplemental Information for Proposed Alternative to ASME Code Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) EPID: L 2019-LLR-0096)2019-11-26026 November 2019 Supplemental Information for Proposed Alternative to ASME Code Requirements for the Repair/Replacement of Essential Cooling Water System Class 3 Buried Piping (Relief Request RR-ENG-3-24) EPID: L 2019-LLR-0096) NOC-AE-19003620, Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23)2019-02-28028 February 2019 Proposed Alternative for Extension of Volumetric Examination Interval for Reactor Vessel Closure Head with Alloy 690 Nozzles in Accordance with 10 CFR 50.55a(z)(1) (Relief Request RR-ENG-3-23) NOC-AE-19003624, Inservice Inspection Summary Report- 1RE212019-02-0707 February 2019 Inservice Inspection Summary Report- 1RE21 NOC-AE-18003603, Transmittal of 2RE19 Inspection Summary Report for Steam Generator Tubing2018-10-18018 October 2018 Transmittal of 2RE19 Inspection Summary Report for Steam Generator Tubing NOC-AE-18003587, Inservice Inspection Summary Report -2RE192018-07-25025 July 2018 Inservice Inspection Summary Report -2RE19 NOC-AE-17003503, Inservice Inspection Summary Report - 1 RE202017-07-20020 July 2017 Inservice Inspection Summary Report - 1 RE20 NOC-AE-17003440, Inservice Inspection Summary Report -2RE18 Completed in November 20162017-02-0808 February 2017 Inservice Inspection Summary Report -2RE18 Completed in November 2016 NOC-AE-16003364, 1RE19 Inspection Summary Report for Steam Generator Tubing2016-04-25025 April 2016 1RE19 Inspection Summary Report for Steam Generator Tubing NOC-AE-16003355, Inservice Inspection Summary Report, 1RE192016-03-24024 March 2016 Inservice Inspection Summary Report, 1RE19 NOC-AE-15003282, Inservice Inspection Summary Report -2E172015-08-0606 August 2015 Inservice Inspection Summary Report -2E17 NOC-AE-14003170, Inservice Inspection Summary Report - 1 RE182014-08-26026 August 2014 Inservice Inspection Summary Report - 1 RE18 NOC-AE-14003139, RE16 Inspection Summary Report for Steam Generator Tubing2014-05-22022 May 2014 RE16 Inspection Summary Report for Steam Generator Tubing NOC-AE-14003112, Inservice Inspection Summary Report - 2RE162014-03-24024 March 2014 Inservice Inspection Summary Report - 2RE16 NOC-AE-13002968, Inservice Inspection Summary Report - 1RE172013-02-21021 February 2013 Inservice Inspection Summary Report - 1RE17 NOC-AE-12002803, Inservice Inspection Summary Report - 2RE152012-02-20020 February 2012 Inservice Inspection Summary Report - 2RE15 NOC-AE-11002722, RE16 Inspection Summary Report for Steam Generator Tubing2011-09-21021 September 2011 RE16 Inspection Summary Report for Steam Generator Tubing NOC-AE-11002706, Inservice Inspection Summary Report - 1RE162011-07-28028 July 2011 Inservice Inspection Summary Report - 1RE16 NOC-AE-11002651, Inservice Testing Program Description: Safety-Related Seismic Restraints (Snubbers) for the Third 10-Year Interval2011-03-14014 March 2011 Inservice Testing Program Description: Safety-Related Seismic Restraints (Snubbers) for the Third 10-Year Interval NOC-AE-10002585, Inservice Inspection Summary Report - 2RE142010-08-0202 August 2010 Inservice Inspection Summary Report - 2RE14 NOC-AE-10002577, Notification of Upgrading of the Inservice Inspection Program for the Third Inspection Interval2010-07-29029 July 2010 Notification of Upgrading of the Inservice Inspection Program for the Third Inspection Interval NOC-AE-10002565, Inservice Testing Program Description: Safety-Related Seismic Restraints (Snubbers) for the Third 10-Year Interval2010-07-13013 July 2010 Inservice Testing Program Description: Safety-Related Seismic Restraints (Snubbers) for the Third 10-Year Interval NOC-AE-11002684, Categorization of Risk-Informed Piping2010-06-20020 June 2010 Categorization of Risk-Informed Piping ML1006401202010-02-22022 February 2010 Inservice Testing Program Description for the Third 10-Year Interval NOC-AE-10002522, Inservice Inspection Summary Report - 1RE152010-02-16016 February 2010 Inservice Inspection Summary Report - 1RE15 NOC-AE-09002408, Transmittal of 2RE13 Inspection Summary Report for Steam Generator Tubing2009-03-24024 March 2009 Transmittal of 2RE13 Inspection Summary Report for Steam Generator Tubing NOC-AE-09002381, Inservice Inspection Summary Report - 2RE132009-01-20020 January 2009 Inservice Inspection Summary Report - 2RE13 NOC-AE-08002318, Inservice Inspection Summary Report - 1RE142008-06-23023 June 2008 Inservice Inspection Summary Report - 1RE14 NOC-AE-07002195, Inservice Inspection Summary Report - 2RE122007-07-25025 July 2007 Inservice Inspection Summary Report - 2RE12 NOC-AE-07002143, 1RE13 Inservice Inspection Summary Report for Steam Generator Tubing2007-04-16016 April 2007 1RE13 Inservice Inspection Summary Report for Steam Generator Tubing ML0701602012007-01-0808 January 2007 Inservice Inspection Summary Report - IRE13 NOC-AE-06001960, Inservice Inspection Summary Report2006-01-19019 January 2006 Inservice Inspection Summary Report NOC-AE-05001938, Refueling Outage Inservice Inspection Results for Steam Generator Tubing2005-10-12012 October 2005 Refueling Outage Inservice Inspection Results for Steam Generator Tubing NOC-AE-05001910, Inservice Inspection Summary Report - 1RE122005-07-15015 July 2005 Inservice Inspection Summary Report - 1RE12 NOC-AE-05001853, Revised Steam Generator Tube Inservice Inspection Plan for the Second Inspection Interval at Plant2005-03-0303 March 2005 Revised Steam Generator Tube Inservice Inspection Plan for the Second Inspection Interval at Plant NOC-AE-04001763, Inservice Inspection Summary Report for Welds and Component Supports - 2RE102004-07-22022 July 2004 Inservice Inspection Summary Report for Welds and Component Supports - 2RE10 2023-08-09
[Table view] Category:Letter type:NOC
MONTHYEARNOC-AE-230040, Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06)2023-12-14014 December 2023 Supplement to Proposed Alternate Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (Relief Request RR-ENG-4-06) NOC-AE-230039, Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/20230032023-12-12012 December 2023 Docket Nos. Stn 50-498, Stn 50-499 - Reply to a Notice of Violation, NRC Inspection Report 05000498/2023003 and 05000499/2023003 NOC-AE-230039, Submittal of Update Foreign Ownership, Control or Influence (FOCI)2023-07-11011 July 2023 Submittal of Update Foreign Ownership, Control or Influence (FOCI) NOC-AE-220039, Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 252023-02-0606 February 2023 Physical Security Plan, Training and Qualification Plan, Safeguards Contingency Plan, and Independent Spent Fuel Storage Installation Security Program Revision 25 NOC-AE-220038, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2022-06-23023 June 2022 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask NOC-AE-210038, Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 252022-01-0404 January 2022 Submittal of Operations Quality Assurance Plan Changes QA-089, QA-091, and Revision 25 NOC-AE-21003858, 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes2021-12-0606 December 2021 10 CFR 50.46 Thirty-Day Report of Significant ECCS Model Changes NOC-AE-21003853, Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-12-0303 December 2021 Revised Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003848, Unit 1 Cycle 24 Core Operating Limits Report2021-11-18018 November 2021 Unit 1 Cycle 24 Core Operating Limits Report NOC-AE-21003846, Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material2021-11-0404 November 2021 Response to End of Enforcement Discretion and Request for Approval of Alternate Disposal Procedures for Very Low-Level Radioactive Material NOC-AE-21003842, 10 CFR 50.59 Summary Report2021-09-23023 September 2021 10 CFR 50.59 Summary Report NOC-AE-21003841, Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25)2021-09-23023 September 2021 Request for Relief from ASME Section Xl Code Requirements for Weld Examinations (Relief Request RR-ENG-3-25) NOC-AE-21003832, Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-09-0909 September 2021 Supplement to License Amendment Request to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003812, Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections2021-08-10010 August 2021 Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections NOC-AE-21003825, Update of Foreign Ownership, Control, or Influence Information (FOCI)2021-08-0505 August 2021 Update of Foreign Ownership, Control, or Influence Information (FOCI) NOC-AE-21003824, Update Foreign Ownership, Control, or Influence (FOCI)2021-07-29029 July 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003823, Update Foreign Ownership Control or Influence (FOCI)2021-07-28028 July 2021 Update Foreign Ownership Control or Influence (FOCI) NOC-AE-21003820, Nuclear Insurance Protection2021-07-20020 July 2021 Nuclear Insurance Protection NOC-AE-21003819, Inservice Inspection Summary Report - 2RE212021-07-15015 July 2021 Inservice Inspection Summary Report - 2RE21 NOC-AE-21003816, Commitment Change Summary Report2021-06-30030 June 2021 Commitment Change Summary Report NOC-AE-21003814, Technical Specification Bases Control Program2021-06-24024 June 2021 Technical Specification Bases Control Program NOC-AE-21003810, Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- CPS Energy NOC-AE-21003811, Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy2021-06-17017 June 2021 Update Foreign Ownership, Control, or Influence (FOCI)- Nrg Energy NOC-AE-21003806, Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval2021-05-20020 May 2021 Inservice Inspection Program Plan and Inservice Testing Program Snubber Inservice Test Plan for the Fourth Ten-Year Interval NOC-AE-21003801, Annual Dose Report for 20202021-04-26026 April 2021 Annual Dose Report for 2020 NOC-AE-21003802, 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report2021-04-26026 April 2021 2020 South Texas Project Electric Generating Station Annual Environmental Operating Report NOC-AE-21003804, Operator Licensing Examination Schedule2021-04-21021 April 2021 Operator Licensing Examination Schedule NOC-AE-21003800, Radioactive Effluent Release Report2021-04-19019 April 2021 Radioactive Effluent Release Report NOC-AE-21003799, Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan2021-04-15015 April 2021 Changes to South Texas Project Electric Generating Station (STPEGS) Emergency Plan NOC-AE-21003795, Cycle 22 Core Operating Limits Report2021-04-15015 April 2021 Cycle 22 Core Operating Limits Report NOC-AE-21003796, Update Foreign Ownership, Control, or Influence (FOCI)2021-04-15015 April 2021 Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-21003791, Financial Assurance for Decommissioning - 2021 Update2021-03-31031 March 2021 Financial Assurance for Decommissioning - 2021 Update NOC-AE-21003790, Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter)2021-03-31031 March 2021 Response to Apparent Violations in NRC Inspection Report 05000498/2020401 and 05000499/2020401: (EA-20-122) (Letter) NOC-AE-210037, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-21003792, STP Fire Hazards Analysis Report, Amendment 26 (Redacted)2021-03-30030 March 2021 STP Fire Hazards Analysis Report, Amendment 26 (Redacted) NOC-AE-200037, License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications2021-03-11011 March 2021 License Amendment Request to Revise Technical Specification 3.6.3 to Append a Note and Remove the Index from Technical Specifications NOC-AE-21003784, Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing2021-03-0808 March 2021 Response to Request for Additional Information Regarding 1RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-21003786, Annual Fitness for Duty Performance Report for 20202021-03-0101 March 2021 Annual Fitness for Duty Performance Report for 2020 NOC-AE-21003785, Evidence of Financial Protection2021-02-23023 February 2021 Evidence of Financial Protection NOC-AE-21003781, Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts2021-01-27027 January 2021 Notice Regarding Withdrawal of Funds from Nuclear Decommissioning Trust Subaccounts NOC-AE-21003780, Submittal of Update Foreign Ownership, Control, or Influence (FOCI)2021-01-0707 January 2021 Submittal of Update Foreign Ownership, Control, or Influence (FOCI) NOC-AE-20003778, Changes to South Texas Project Electric Generating Station Emergency Plan2020-12-17017 December 2020 Changes to South Texas Project Electric Generating Station Emergency Plan NOC-AE-20003777, STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency2020-12-10010 December 2020 STPNOC Concerns Regarding the Proposed Change to the Evaluated Force-on-Force Inspection Guidance During the COVID-19 Public Health Emergency NOC-AE-20003766, Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan2020-12-0202 December 2020 Supplement to Change Implementation Date for License Amendment Request to Revise the STPEGS Emergency Plan NOC-AE-20003767, Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic2020-11-16016 November 2020 Request for a One-Time Exemption from 10 CFR 73, Appendix 8, Section VI, Subsection C.3.(1)(1) Regarding Annual Force-on-Force (FOF) Exercises, Due to Covid 19 Pandemic NOC-AE-20003765, Inservice Testing Program Description for the Fourth Ten-Year Interval2020-10-28028 October 2020 Inservice Testing Program Description for the Fourth Ten-Year Interval NOC-AE-20003764, 1 RE22 Inspection Summary Report for Steam Generator Tubing2020-10-0707 October 2020 1 RE22 Inspection Summary Report for Steam Generator Tubing NOC-AE-20003762, Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen2020-09-22022 September 2020 Supplement to License Amendment Request to Revise Technical Specifications to Adopt TSTF-374, Revision 0, Revision to TS 5.5.13 and Associated TS Bases for Diesel Fuel Oil Using the Consolidated Line Item Improvemen NOC-AE-20003761, Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic2020-09-10010 September 2020 Supplement to Exemption Request from 10 CFR 50 Appendix E Due to COVID-19 Pandemic NOC-AE-20003760, Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal2020-09-0808 September 2020 Update Foreign Ownership. Control. or Influence(FOCI)- Transmittal 2023-07-11
[Table view] |
Text
Nuclear Operating Company South Texas Project Electric Generating Station P.O. Box 289 Wadsworth, Texas 77483 January 22,2020 NOC-AE-20003703 10CFR50.55a(z)
STI:34969739 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001 South Texas Project Units 1 & 2 Docket Nos. STN 50-498, STN 50-499 Proposed Alternatives to ASME OM Code 2012 Edition for the Fourth Inservice Test Interval (Relief Request PRR-04)
Pursuant to 10 CFR 50.55a(z), STP Nuclear Operating Company (STPNOC) hereby requests an alternative to the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 2012 Edition for use during the fourth ten-year Inservice Test (1ST) interval at South Texas Project. The details of the request are attached.
STPNOC requests approval of the alternatives by September 1, 2020 to support the fourth ten-year interval starting on September 25,2020.
There are no new commitments in this letter.
If there are any questions regarding this request, please contact N. Boehmisch at 361-972-8172 or me at 361-972-7743.
l^oCM<X2^S>'t<'l 85
^2-:
-^r Roland Dunn General Manager, Engineering
Attachment:
Relief Request PRR-04, Use of Code Case OMN-22 ec:
Regional Administrator, Region IV U.S. Nuclear Regulatory Commission 1600 East Lamar Boulevard Arlington, TX 76011-4511
Attachment NOC-AE-20003703 Page 1 of 4 Attachment Relief Request PRR-04, Use of Code Case OMN-22
- 1. ASME Code Component(s) Affected All pumps in the 1ST Program with vibration reference (Vr) values of < 0.05 inches per second (ips). See Table 1 for the initial list of these pumps. The 0.05 ips value will be applied to individual vibration locations for listed pumps whose measured reference value is less than 0.05 ips. When new reference values are established, the measured parameters would be evaluated for each location to determine if the minimum value for Vr would apply.
The Table 1 pumps are required to perform a specific function in shutting down the reactor to a safe shutdown condition, maintaining a safe shutdown condition or mitigating the consequences of an accident.
2. Applicable Code Edition and Addenda
American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code) 2012 Edition.
3. Applicable Code Requirement
ISTB-3300(a), "Reference Values". Initial reference values shall be determined from the results of testing meeting the requirements to ISTB-3100, "Preservice Testing", or from the results of the first 1ST.
Table ISTB-5121-1, "Centrifugal Pump Test Acceptance Criteria", Alert Range and Required Action Range.
Table ISTB-5221-1, "Vertical Line Shaft Centrifugal Pump Test Acceptance Criteria", Alert Range and Required Action Range.
Table ISTB-5321-1, "Positive Displacement Pump (Except Reciprocating) Test Acceptance Criteria", Alert Range and Required Action Range.
Table ISTB-5321-2, "Reciprocating Positive Displacement Pump Test Acceptance Criteria", Alert Range and Required Action Range.
4. Reason for Request
TheASME Code committees have approved Code Case OMN-22, "Smooth Running Pumps" and is scheduled to be published with the 2020 Edition of the OM Code. This Code Case has not been approved for use in Regulatory Guide 1.192.
Code Case OMN-22 allows for alternative requirements for use with smooth running pumps in lieu of use of vibration values obtained in the reference value tests. For very low reference values, hydraulic noise and instrument accuracy can represent a significant portion of the reading and affect the repeatability of subsequent measurements. A smooth running pump could be subject to unnecessary increased testing if the measured vibration parameter exceeds an acceptable range based on these very low reference values.
Attachment NOC-AE-20003703 Page 2 of 4 Smooth running pumps have a much lower reference value for stable operation and the ranges for acceptable range and higher levels listed in the Alert Range do not allow for adequate vibration monitoring techniques to be applied to smooth running pumps. Guidelines set forth in Code Case OMN-22 allow for a very low baseline vibration value with a pump vibration velocity of ^ 0.050 in/sec when establishing the vibration reference value, which allows for trending of the pump vibration on a much lower scale than what is currently allowed.
ASME OM Code Case OMN-22, "Smooth Running Pumps" has not been approved by the NRC and a relief request is required for use of this Code Case.
- 5. Proposed Alternative and Basis for Use STPNOC proposes to utilize the provisions of Code Case OMN-22, "Smooth Running Pumps".
For those pumps with very low vibration values, the following vibration velocity criteria shall be applied to any vibration test points qualifying for the use of the "minimum reference" value:
Acceptable Range: ^0.125 in/sec Alert Range: > 0.125 in/sec to 0.300 in/sec Required Action Range: > 0.300 in/sec Supplemental Monitorincj:
Pumps that will use the "minimum reference" value for one or more vibration points will be maintained in STPNOC's Predictive Maintenance (PdM) program. The PdM program will apply predictive monitoring techniques and perform vibration analysis beyond the trending of vibration levels specified in the ASME OM Code to provide early identification of pump performance issues.
At a minimum, STPNOC will perform spectral analysis of measured vibration of the applicable pumps. STPNOC will document the conclusion of the PdM performance analysis on the pump test record prior to the subsequent test with a conclusion of acceptable, degrading but acceptable, or unacceptable. Corrective action will be initiated when an unacceptable trend in performance is identified.
Corrective Action:
If a measured pump vibration parameter falls within the alert range or the required action range specified above, STPNOC will follow the required actions within the edition/addenda of the applicable Code (for example, ISTB-6200 for the 2012 Edition of the ASME OM Code). The alert and required action ranges would be established in accordance with Code Case OMN-22 rather than the requirements of ISTB-3300, ISTB-5100, ISTB-5200 and the associated tables.
If a PdM Supplemental Monitoring activity identifies a parameter outside the normal operating range or identifies a trend toward an unacceptable degraded state, action will be taken to (1) identify and document the condition in the Corrective Action Program, (2) increase monitoring to establish the rate of change of the monitored parameter, (3) review component-specific information to identify the degradation cause, (4) develop a plan to remove the pump from service to perform maintenance prior to significant performance degradation, and (5) address potential common cause issues applicable to other pumps based on the results of the analysis of the specific pump performance.
Using the provisions of this relief request as an alternative to the requirements of ISTB-3300 provides a reasonable alternative to the ASME OM Code requirements. Based on this determination, the proposed alternative provides an acceptable level of quality and safety.
Attachment NOC-AE-20003703 Page 3 of 4 Conclusion; In summary, STPNOC proposes to test the pumps listed in Table 1 of this request by implementing the requirements ofASME OM Code Case OMN-22 and requests NRC approval to implement this change because Code Case OMN-22 is not listed in Regulatory Guide 1.192.
Using the provisions of this request would provide adequate detection of component degradation and would continue to provide reasonable assurance of the operational readiness of affected components. Therefore, compliance with the requirements ofASME OM Code Case OMN-22 would result in an acceptable level of quality and safety pursuant to 10 CFR 50.55a(z)(1).
- 6. Duration of Proposed Alternative The proposed alternative, if approved, would be implemented from the end of the Third Interval (September 25, 2020) until the end of the Fourth Interval (September 25, 2030).
- 7. Precedent NRC approval of Millstone Power Station Units 2 and 3 relief requests P-02 and P-03 for smooth running pumps with measured reference values below 0.05 ips (Reference 2).
NRC approval of James A. Fitzpatrick Nuclear Power Plant relief request PRR-02 for smooth running pumps with measured reference values below 0.05 ips (Reference 3).
- 8. Reference
- 1. ASME OM Code-2012, Code Case OMN-22, "Smooth Running Pumps"
- 2. Letter from J.G. Danna, NRC, to D.G. Stoddard, Dominion Energy, "Millstone Power Station, Unit Nos. 2 and 3 - Alternative Requests Related to the Fifth and Fourth 10-year Interval Pump, Valve, and Snubber Inservice Testing Programs, Respectively (EPID L-2018-LLR-0012-Through EPiD L-2018-LLR-0022)", November 13, 2018, ML18290A602
- 3. Letter from J.G. Danna, NRC, to B.C. Hanson, Exelon Generation Company, "James A.
Fitzpatrick Nuclear Power Plant - Issuance of Relief Requests for Alternatives to Certain ASME OM Code Requirements", April 13, 2018, ML18044A993
Attachment NOC-AE-20003703 Page 4 of 4 Table 1: Initial Scope of PRR-04*
Pump Description TPNS Unit ASME Class Centrifugal Charging Pump 1A 2R171NPA101A 1 2 Centrifugal Charging Pump 1B 2R171NPA101B 1 2 Centrifugal Charging Pump 2A 2R172NPA201A 2 2 Essential Chilled Water Pump 1 1A 3V111VPA004 1 3 Essential Chilled Water Pump 1 1 B 3V111VPA005 1 3 Essential Chilled Water Pump 11C 3V111VPA006 1 3 Essential Chilled Water Pump 21A 3V112VPA004 2 3 Essential Chilled Water Pump 21 B 3V112VPA005 2 3 Essential Chilled Water Pump 21 C 3V112VPA006 2 3 Essential Cooling Water Pump 1A 3R281NPA101A 1 3 Essential Cooling Water Pump 1B 3R281NPA101B 1 3 Essential Cooling Water Pump 1C 3R281NPA101C 1 3 Essential Cooling Water Pump 2A 3R282NPA201A 2 3 Essential Cooling Water Pump 2B 3R282NPA201B 2 3 Essential Cooling Water Pump 2C 3R282NPA201C 2 3 Low Head Safety Injection Pump 1A 2N121NPA102A 1 2 Low Head Safety Injection Pump 1B 2N121NPA102B 1 2 Low Head Safety Injection Pump 1C 2N121NPA102C 1 2 Low Head Safety Injection Pump 2A 2N122NPA202A 2 2 Low Head Safety Injection Pump 2B 2N122NPA202B 2 2 Low Head Safety Injection Pump 2C 2N122NPA202C 2 2 Motor Driven Aux Feedwater Pump No. 11 3S141MPA01 1 3 Motor Driven Aux Feedwater Pump No. 22 3S142MPA02 2 3 Motor Driven Aux Feedwater Pump No. 23 3S142MPA03 2 3 Turbine Driven Aux Feedwater Pump No. 14 3S141MPA04 1 3 Residual Heat Removal Pump 1A 2R161NPA101A 1 2 Residual Heat Removal Pump 1B 2R161NPA101B 1 2 Residual Heat Removal Pump 1C 2R161NPA101C 1 2 Residual Heat Removal Pump 2A 2R162NPA201A 2 2 Residual Heat Removal Pump 2B 2R162NPA201B 2 2 Residual Heat Removal Pump 2C 2R162NPA201C 2 2 Spent Fuel Cooling Pump 1A 3R211NPA101A 1 3 Spent Fuel Cooling Pump 1B 3R211NPA101B 1 3 Spent Fuel Cooling Pump 2A 3R212NPA201A 2 3 Spent Fuel Cooling Pump 2B 3R212NPA201B 2 3
- Scope may change based on future reference values tests. When new reference values are established, the measured parameters would be evaluated for each location to determine if the minimum value for Vr would apply.