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Category:Report
MONTHYEARML24103A2482024-04-12012 April 2024 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for 2023 ML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 1R24 ML23325A1612023-10-26026 October 2023 Relief Request 70 - Proposed Alternatives in Accordance with 10 CFR 50.55a(z)(1) for Pressurizer Lower Shell Temperature Nozzle ML22308A1662022-11-0404 November 2022 23rd Refueling Outage Steam Generator Tube Inspection Report ML22091A3072022-04-0101 April 2022 Independent Spent Fuel Storage Installation (Isfsi), Evacuation Time Estimate Study ML21077A2562021-03-18018 March 2021 El Paso Electric Co., Application for Approval of Indirect Transfer of Control of Licenses Pursuant to 10 C.F.R. 50.80 and 72.50 ML21005A2712020-12-29029 December 2020 102-08208 PVNGS Communication Required by Confirmatory Order EA-20-054 ML19136A4092019-05-16016 May 2019 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2018 ML19046A3512019-02-15015 February 2019 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R21 ML18187A4172018-07-0606 July 2018 License Amendment Request and Exemption Request to Support the Implementation of Framatome High Thermal Performance Fuel ML17181A5152017-06-29029 June 2017 Flooding Focused Evaluation Summary ML17248A5262017-05-30030 May 2017 3INT-ISI-3, Revision 4, Third Inspection Interval Inservice Inspection Program Summary Manual, Unit 3, Enclosure 3 to 102-07551-MDD/MSC ML17006A2172017-01-0505 January 2017 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U3R19 ML16306A4442016-11-14014 November 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML16321A0032016-10-31031 October 2016 WCAP-18030-NP, Revision 1, Criticality Safety Analysis for Palo Verde Nuclear Generating Station Units 1, 2, and 3. ML16221A6042016-09-13013 September 2016 Staff Assessment of Information Provided Under Title 10 of Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of Near-Term Task Force Review of Insights from . ML16120A3892016-04-28028 April 2016 1-SR-2016-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional ML15336A0842015-11-30030 November 2015 NET-300047-07 Revision 1, Material Qualification Report of Maxus for Spent Fuel Storage. ML15188A0492015-06-30030 June 2015 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U3R18 ML15111A4302015-04-17017 April 2015 Attachments 2 & 3: Flaw Fracture Mechanics, Corrosion & Loose Parts Evaluations for One Cycle Relief (DAR-MRCDA-15-6-NP) and APS Response to NRC Request for Additional Information Dated April 14, 2015 ML15076A0732015-03-10010 March 2015 Seismic Hazard and Screening Report ML15012A4462015-01-0606 January 2015 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U1R18 ML15027A1222014-12-19019 December 2014 Technical Specification (TS) Bases Revision 61 ML14184B3822014-06-27027 June 2014 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R18 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14126A6362014-04-30030 April 2014 APS Supplement to the Seismic Walkdown Report Requested by the NRC Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.1, 2.3, and 9.3 of the Near-Term Task Force. ML14087A1882014-04-11011 April 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident ML14034A1472014-01-24024 January 2014 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U3R17 ML13329A0382013-08-31031 August 2013 WCAP-17787-NP, Rev 0, Palo Verde Nuclear Generating Station STAR Program Implementation Report. ML13252A1112013-08-31031 August 2013 WCAP-17680-NP, Supplement 1, Rev. 0, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2 - Supplemental Information. CY-12-009, Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance2013-05-16016 May 2013 Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance ML13120A5032013-04-10010 April 2013 Technical Requirements Manual, Revision 57 ML1307003422013-02-28028 February 2013 APS Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML13022A4072013-01-14014 January 2013 Third 10-Year Interval, Second Period: Owner'S Activity Report for Unit 2 Refueling Outage 17 (U2R17) ML12355A7482012-12-31031 December 2012 Evacuation Time Estimate Study; Cover Through Section 4 ML12355A7512012-12-14014 December 2012 Evacuation Time Estimate Study; Section 5 Through 12 ML12355A7522012-12-14014 December 2012 Evacuation Time Estimate Study; Appendix a Through H ML12278A1002012-09-0707 September 2012 Pressurized Water Reactor (PWR) Internals Aging Management Program Plan ML12229A1192012-08-0303 August 2012 Attachment 4, PVNGS Engineering Study 13-ES-A037, Revision 0, Fault Tree Analysis and Reliability Evaluation for Low Pressure Safety Injection (LPSI) Pump Trip at the Recirculation Actuation Signal (RAS) ML12229A1202012-08-0303 August 2012 Attachment 5, PVNGS Engineering Study 13-NS-C089, Revision 0, PRA Evaluation of LPSI Pump Failing to Trip on RAS 2024-04-12
[Table view] Category:Miscellaneous
MONTHYEARML24019A2012024-01-19019 January 2024 Fourth 10-Year Interval, Second Period Owner’S Activity Report Number 1R24 ML21077A2562021-03-18018 March 2021 El Paso Electric Co., Application for Approval of Indirect Transfer of Control of Licenses Pursuant to 10 C.F.R. 50.80 and 72.50 ML19136A4092019-05-16016 May 2019 Emergency Core Cooling System Performance Evaluation Models, 10 CFR 50.46(a)(3)(ii) Annual Report for Calendar Year 2018 ML19046A3512019-02-15015 February 2019 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R21 ML17181A5152017-06-29029 June 2017 Flooding Focused Evaluation Summary ML17006A2172017-01-0505 January 2017 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U3R19 ML16306A4442016-11-14014 November 2016 Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation ML16221A6042016-09-13013 September 2016 Staff Assessment of Information Provided Under Title 10 of Code of Federal Regulations Part 50, Section 50.54(F), Seismic Hazard Reevaluations for Recommendation 2.1 of Near-Term Task Force Review of Insights from . ML16120A3892016-04-28028 April 2016 1-SR-2016-001-00, Fuel Building Ventilation System High Range Radioactive Gaseous Effluent Monitor Nonfunctional ML15188A0492015-06-30030 June 2015 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U3R18 ML15111A4302015-04-17017 April 2015 Attachments 2 & 3: Flaw Fracture Mechanics, Corrosion & Loose Parts Evaluations for One Cycle Relief (DAR-MRCDA-15-6-NP) and APS Response to NRC Request for Additional Information Dated April 14, 2015 ML15012A4462015-01-0606 January 2015 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U1R18 ML14184B3822014-06-27027 June 2014 Third 10-Year Interval, Third Period: Owner'S Activity Report Number U2R18 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14034A1472014-01-24024 January 2014 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U3R17 ML13252A1112013-08-31031 August 2013 WCAP-17680-NP, Supplement 1, Rev. 0, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Submittal Report for Palo Verde Nuclear Generating Station Unit 2 - Supplemental Information. CY-12-009, Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance2013-05-16016 May 2013 Closure Options for Generic Safety Issue (GSI) - 191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance ML1307003422013-02-28028 February 2013 APS Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML13022A4072013-01-14014 January 2013 Third 10-Year Interval, Second Period: Owner'S Activity Report for Unit 2 Refueling Outage 17 (U2R17) ML12200A0312012-06-26026 June 2012 Third 10-Year Interval, First Period: Owner'S Activity Report Number U3R16 ML11195A0172011-07-0606 July 2011 Third 10-Year Interval, Second Period: Owner'S Activity Report Number U2R16 ML11189A0952011-06-29029 June 2011 Independent Spent Fuel Storage Installation (ISFSI) - Submittal of 10 CFR 50.59, 10 CFR 72.48, and Commitment Change Reports (January 2010 - December 2010) ML1103107342011-01-19019 January 2011 Third 10-Year Interval, First Period, Second Outage: Owner'S Activity Report Number U3R15 ML1024400382010-08-20020 August 2010 Third 10-Year Interval, First Period, Second Outage: Owner'S Activity Report Number 1R15 ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1013103942010-04-30030 April 2010 Submittal of Steam Generator Tube Inspection Report ML1006805162010-03-0202 March 2010 Third 10-Year Interval, First Period, Second Outage: Owner'S Activity Report Number 2R15 ML1015302192009-12-16016 December 2009 APS 2004 Pump Installation Completion Report for PVNGS Firing Range Well. Filed with Adwr on Aug. 3, 2004 (PV-406) PVNGS ML0933104422009-11-18018 November 2009 Steam Generator Tube Inspection Report ML0932401312009-11-12012 November 2009 Special Report 2-SR-2009-001-00 ML0923801522009-08-18018 August 2009 Third 10-Year Interval, First Outage of the First Period, Owner'S Activity Report - 3R14 ML0920202692009-07-16016 July 2009 Revised Steam Generator Tube Inspection Report ML1015907552009-06-12012 June 2009 Final Corrective Action Plan Report for 80-Acre Wsr, Submitted to Adeq June 12, 2009 ML0910304182009-03-31031 March 2009 2008 Decommissioning Funding Status Report ML0905801982009-02-17017 February 2009 Third 10-Year Interval, First Outage of the First Period, Owner'S Activity Report - U1R14 ML0825504022008-09-0303 September 2008 Third 10-Year Interval - Fourteenth Refueling Outage - Owner'S Activity Report ML1015503122008-05-15015 May 2008 APS 2008 PVNGS 2007 Annual Monitoring and Compliance Report App No. P-100388 ML0810102292008-04-10010 April 2008 Lesson Learned Inputs for the Reactor Oversight Program Safety Culture Evaluation for Use at 4/17/08 Public Meeting ML0807400502008-03-0505 March 2008 Response to Request for Additional Information Related to 2006 Steam Generator Tube Inspections ML0803702332008-01-24024 January 2008 Radioactive Waste Shipment Delay Special Report 1-SR-2008-001-00 ML0800901932008-01-0202 January 2008 Steam Generator Tube Inspection Report 2024-01-19
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Item: 2715731 - CRDR Problem Identification WMCRFORM Item No X 2715731 Unit 1 Classification : SPEC EVAL Statua : RECLASSIFY Type/Sub z CRDR Source Type/Item : Report Date : 6/14/2004 Title (U-1) SHORTLY AFTER PLACING AFN-POl IN SERVICE, AN AREA OPERATOR REPORTED A WATERHNMMER CONDITION ON THE FEEDWATER LINES ON THE 120' OF THE TURBINE BUILDING.
Identified By : GAFFNEY*TIMOTHY J Due Date : 06/30/2004 Eval Due Date t 6/30/2004 Reasp Group a 9734 SYS ENG MECHANICAL B Reap Org t SYS ENG MECHANICAL BOP Assigned TO X Discovery Date/Time : 06/15/2004 15:00 Need Date : Control Rm Review : N Source Doc./ Type : Legacy Item / Type : Attachments : Y Description z Shortly after placing AFN-P01 in service, an Area Operator reported a waterhammer condition on the feedwater lines on the 120 Ft of the Turbine Building. The waterhammer lasted approximately 5 minutes. Systems Engineering (Jones) was notified of the condition and walked down the affected piping. Engineering found no visible signs of damage from the waterhammer. This CRDR is being initiated to document the condition for Engineering's evaluation.
Initiators Suggested Disposition Added On Added By Comment Text 6/15/2004 GAFFNEY*TIMOTHY J Engineering to evaluate the cause of the condition and recommend corrective action to prevent recurrance.
Requirement(s) Violated Added Oa Added By Comment Text 6/15/2004 GAFFNEY*TIMOTHY J None.
Recommend Closure: NO Report Date: 07/02/2004 ll:QS Page of 44 Page 1I of Report Date: 07/02/2004 11:06
Item: 2715731 - CRDR Problem Identification WMCRFORM Leaders Review Added By Added On Type Comment Text GAFFNEY*TIMOTHY J 6/15/2004 LDRS CAUSE Placing AFN-PO1 in service appears to be the cause of the waterhammer.
GAFFNEY*TIMOTHY J 6/15/2004 LDRS SUG Agree with suggested disposition. Recommend classification of ADVERSE and assignment to DISPOSITION Systems Engineering for evaluation. Recommend initial cause code of SPP.
GAFFNEY*TIMOT1IY J 6/15/2004 LDRS Potentially transportable.
TRANSPORTABILITY Design Components ID Name Q ASME EQ T.S. Bldg Room Slev lMAFNPOl**PUMPXX AUXILIARY FEED WATER PUMP OA N N 7 ? 7 103 Unit/Systems I"144 0 System Name S .-4 4
p4 1-AF-SYS AUXILIARY FEEDWATER Pf
('1 L~I Action Taken I-
- a Date/Time Action Taken By Action Taken Summary
(.4 6/15/2004 15:14 GAFFNEY*TINOTHY J Notified the UDL, Site Manager, Engineering, and NRC Resident of the condition.
6/18/2004 8:39 MIYAHARA*HELMUT R Performed engineering post-water hammer walkdown identified rotated clamp pipe support 01-AF-025-H-004 6/18/2004 8:41 MIYA=ARA*HELMUT R Performed piping system stress analysis for identified rotated clamp. Determined to be acceptable when cosidering all systemdesign loadings.
6/18/2004 8:43 MIYAHARA*HELMUT R Initiated CM to re-work clamp position to drawing 01-AF-025-H-004. Recommend work to be performed U1R12.
Report Date: 07/02/2004 11:06 Page of 44 Page 22 of Report Date: 07/02/2004 11:06
Item: 2715731 - CRDR Problem Identification WMCRFORM CRC/NRA Requested Action Added On Added By Comment Text 6/16/2004 DUTTON*EDWIN C Criteria 12 (Van Dop)
Determine if the condition constitutes a Maintenance Rule Functional Failure.
-Include determination basis If the condition is a Maintenance Rule Functional Failure, Evaluate the Significance per the following:
- 1. Is the MRFF a repeat Functional Failure?
- 2. Does the failure cause a MRule SSC performance criteria or goal to be exceeded?
- 3. Is the MRFF an indicator of a clearly Declining Trend?
Reference procedure 70DP-OMR01 for specific requirements and complete SWMS CRDR 0003 Form.
Criteria 9 to 2 (Brutcher)
Determine impact of water hammer.
Special Evaluation Added On Added By Comment Text 6/17/2004 MIYAHARA*IIELMUT R NSSS/pipe stress engineering performed a walk-down of the Aux Feedwater sytem Line AF-025-DCDA-60 and its pipe supports. Visual inspection identified 13-AF-025-fl-004 Pipe Clamp rotated on the pipe. The pipe clamp supports a vertical strut.
We have performed a computer analysis (SMNM ILMS625, dated 06/17/04) simulating this identified condition of the rotated pipe clamp. Review of the analysis shows that all resulting pipe stresslevels and pipe support loadings meet ASME Code allowable values.
Therefore this situation is acceptable for all design loadings and will perform as designed.
This analyisis/evaluation will be documented in Calculation 13-MC-AF-504 Volume 3.
Engineering recommends the pipe clamp to be restored to the drawing during UlR12.
Further recomends downgrade to ADVERSE and assign for evaluation of system operating condition to Mark Van eU Dop.
U Attached Forms Description Document ID Rev. Created By Created Date Attached Step MRule FF Review.ROOO.pdf (Media Id: 1105683) CRDR-0003 000 LANDSTROM*CARL E 06/29/2004 MRule Eval Report Date: 07/02/2004 11:06 Page 3 Page of 4 3 of 4 Report Date: 07/02/2004 11:06
Item: 2715731 - CRDR Problem Identification WMCRFORM Item: 2715731 - CRDR Problem Identification WMCRFORH Workflow History Details From --------
Person Work Assignment Action/Status Date Coment VAN DOP*MARK W 9734 SYS ENG MECHANICAL B MRULE EVAL 07/02/2004 <no comment provided>
LANDSTROM*CARL E 9734 SYS ENG MECHANICAL B Returned 06/29/2004 Pot Sig Eval Complete. Not a MRule Functional Failure MIYAHARA*HELMUT R 9711 DESIGN MECHANICAL NS POT SIG 06/18/2004 Performed piping aytem.walk-down and stresss evaluation.
BUSTO*ROBERT E 9734 SYS ENG MECHANICAL B Referred 06/16/2004 Perform MRFF Eval w
14 MITCHELL*LORNA S CRDR GROUP CLASSIFY 06/16/2004 <no comment provided>
0 an MITCHELL*LORNA S CRDR GROUP CLASSIFY 06/16/2004 <no comment provided>
oU
-4 MITCHELL*LORNA S CRDR GROUP CLASSIFY 06/16/2004 <no comment provided>
cs)
'-4 I-Cl GAFFNEY*TIMOTHY J 8225 SHIFT TECH ADVISORS LDR REVIEW 06/15/2004 <no comment provided>
84 GAFFNEY*TIMOTHY J 8225 SHIFT TECH ADVISORS IDENTIFY 06/15/2004 <no comment provided>
GAFFNEY*TIMOTHY J REPORT 06/14/2004 <no comment provided>
Report Date: 07/02/2004 11:06 Page 4 of 44 Report Date: 07/02/2004 11:06
Maintenance Rule Functional Failure Review Is this Condition a Maintenance Rule - No fYes g Unknown Functional Failure? U L If yes:
Is this condition a repeat functional D No Yes Unknown failure?
Does this failure cause a M-Rule SSC D No Yes D Unknown performance criteria to be exceeded?
Is this condition an indicator of a clearly C No E Yes 2 Unknown declining trend?
Comments The intended function of the N Train AF pump is to be the normal source of SG feedwater during startups and shutdowns. This function is successful if 500 gpm can be delivered to either SG within 20 minutes of initiation of a manual demand. In this event, the pump started and delivered the desired flow to support plant operation. Following the described water hammer, the piping was inspected. No damage was found which would make the system incapable of performing its function for an indefinite period of time. Therefore, this event is not a MRule Functional Failure.
System Engineering recommends that this CRDR be classified as REVIEW and assigned to System Engineering for followup review of the event.
General Guidance for MRFF Determinations Definitions:
Maintenance Rule Functional Failure (MRFF) is the failure of an SSC within the scope of the Maintenance Rule that, if not corrected, could or did cause the affected system, train or component to be unable to accomplish or support its key safety function(s). Failures occurring during post maintenance testing are not considered MRFFs if they occur prior to returning the SSC to service and are caused by the maintenance for which the post maintenance testing is performed. An MRFF of low risk significant SSCs monitored at the plant level occurs only when plant level performance criteria is effected or an unplanned safety system actuation results (i.e., when the failure results in a plant trip, unplanned capacity loss or safety system actuation).
Support SSC: A system, subsystem, or component which provides support required by supported SSC(s) to perform their Maintenance Rule Key Safety Function(s). Essential Cooling Water (EW) is considered a support SSC for Essential Chilled Water (EC) and Shutdown Cooling (SDC).
Supported SSC: A system, subsystem, or component that depends upon one or more support SSCs to perform its Maintenance Rule Key Safety Function(s). The IPSI Pump is supported by the Essential Room Cooler, which is supplied by Essential Chilled Water (EC). Therefore the HPSI Pump is considered an SSC supported by EC.
General Rules for MRFF Determinations I. General Rule for LRS SSCs Monitored at The Plant Level
- 1. For normally operating low risk significant key safety functions monitored at the plant level an MRFF occurs only when a component, train or system failure causes a plant trip, unplanned capacity loss or safety system actuation I. General Rules for Post Maintenance Testing and Troubleshooting Activities
- 2. SSC failures detected during post maintenance retest prior to declaring the equipment available for service will not be counted as a maintenance rule functional failure unless the failure is unrelated to the maintenance performed.
- 3. Following an MRFF, all demands that are placed on the SSC as part of the troubleshooting and verification of corrective maintenance following the MIRFF should be considered invalid (no demand and no failure) regardless of their success or failure. Normal accounting of SSC demands should resume upon the final retest of the SSC, which will be counted as a demand.
- m. General Rules for Trips or Malfunctions of Equipment Bypassed in Emergencv Mode
- 4. Spurious operation of a trip that would be bypassed while the SSC was performing its key safety function will not be counted as a MRFF providing the bypass feature is periodically verified functional.
- 5. A malfunction of equipment that prevents the successful completion of a test will not be counted as an MRFF provided that the equipment is not used by the SSC for the fulfillment of its key safety function.
IV. General Rules for Human Performance Errors by Operations, Maintenance and Others
- 6. Human performance errors (such as valve mispositioning events) can result in Maintenance Rule Functional Failures even when there is no damage to, malfunction of, or degraded condition of the effected SSC.
- An operator error made during support of a maintenance activity (i.e.,
corrective, preventative, predictive'or testing) that unexpectedly caused an SSC to be incapable of accomplishing the key safety function(s) for which it was included in the Scope of the Maintenance Rule would typically be considered an MRFF.
- Any error made during routine operations resulting in a latent failure of a Maintenance Rule SSC is typically considered an MRFF. A latent failure is a condition that is not detected and corrected prior to declaring the SSC available for service and that could (or does) cause a failure of the key safety function(s).
- Minor equipment problems or operating errors will not be considered MRFFs provided the following criteria are satisfied: 1) the problem is detected and corrected during the evolution; 2) the problem is diagnosed and corrected without corrective maintenance (e.g., turn a switch or reset a breaker); and 3) these actions can be completed within the time limits assumed by the safety analysis and PRA.
V. General Rules for Support and Supported SSCs
- 7. Typically, a Maintenance Rule Functional Failure (MRFF) of a support SSC will not be counted as an MRFF of the supported SSC for Maintenance Rule reliability monitoring purposes even if the failure renders the supported SSC unable to perform its Maintenance Rule key safety function(s).
Maintenance Rule System Performance Criteria/Scoping Basis information in the Maintenance Rule Performance Criteria Database for exceptions related to combining systems for monitoring purposes .
- 8. The risk ranking and monitoring criteria for support systems was established based on "at power" system functions, therefore some support systems for outage related key safety functions may not be independently monitored during outage periods. When this occurs, an SSC failure resulting in the loss of a key safety function that is high risk significant only during outage periods may need to be considered an MRFF of the supported system even when the failure occurs within the formal boundary of a support system.
- 9. Support components such as supply breakers, relays and other components (e.g., the turbine driven AF pump steam admission valves) designed to supply energy, an actuation signal or cooling for a single supported SSC (i.e., the support component supports only one SSC not multiple SSCs) are considered to be within the scope of the Maintenance Rule SSC they support unless otherwise documented in the applicable system basis documents. Therefore, any failures of these components resulting in the inability of the supported SSC to perform its Maintenance Rule Key
Safety Function(s) will be counted as an MRFF of the supported SSC, but will not be counted as an MRFF of the support system. See Rules 10 and 11 for additional guidance regarding MRFF determinations for these types of components.
- 10. When there are redundant support components designed to supply energy, an actuation signal or cooling for a single supported SSC the failure of either support SSC should be counted as an MRFF, unless a documented evaluation or special accounting rule justifies an alternate approach. This justification should consider whether either the PRA or the plant Safety Analysis Report take credit for the redundant support SSC.
VII General Rule for Redundant SSCs within a Redundant Train
- 11. Special accounting rules should be developed and documented to address failures of redundant components within a single train that are both capable of independently supporting a key safety function (e.g., two check valves in a single line). Unless the PRA or plant Safety Analysis specifically takes credit for such redundancy, the special accounting rule can stipulate that the failure of only one of the redundant components need not be counted as an MRFF.