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Category:Report
MONTHYEARNLS2024065, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2024-10-0707 October 2024 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2024055, Data from Metamic Coupon Sampling Program2024-07-29029 July 2024 Data from Metamic Coupon Sampling Program ML23129A2792023-04-20020 April 2023 1 to Updated Safety Analysis Report, Plant Unique Analysis Report Mark I Containment Program NLS2023010, Inservice Inspection OAR-1 Owners Activity Report for Cooper Nuclear Station2023-02-0909 February 2023 Inservice Inspection OAR-1 Owners Activity Report for Cooper Nuclear Station NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022050, Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library2022-11-0909 November 2022 Notification of Revision to Cooper Nuclear Station Emergency Response Data System Data Point Library NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021 ML19262G9042019-11-0808 November 2019 Staff Assessment of Flood Hazard Integrated Assessment (Public) NLS2019040, 3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary)2019-08-0707 August 2019 3-EN-DC-147, Rev. 5C1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 54 Effective Full-Power Years (Efpy). (Non-proprietary) NLS2019028, Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 02018-10-24024 October 2018 Enclosure 2 - Calculation Package, File No. 1801303.301, Cooper Nuclear Station Core Shroud H3 Weld Evaluation - 2018, Revision 0 ML18184A2732018-07-18018 July 2018 Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter (CAC No. MF7819; EPID L-2016-JLD-0006) NLS2018024, Report 004N7680-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Coo(Er Nuclear Station Cycle 31.2018-04-30030 April 2018 Report 004N7680-R1-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR, Coo(Er Nuclear Station Cycle 31. NLS2018003, Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20172018-01-15015 January 2018 Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2017 NLS2017070, Seismic Mitigating Strategies Assessment Report for the Reevaluated Seismic Hazard Information2017-08-24024 August 2017 Seismic Mitigating Strategies Assessment Report for the Reevaluated Seismic Hazard Information ML17244A2812017-05-0808 May 2017 16C4384-RPT-005, Rev 005, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation. NLS2016070, Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events2017-01-0404 January 2017 Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events NLS2016066, Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation2016-12-20020 December 2016 Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation ML16351A2472016-12-12012 December 2016 Review of SIA Calculation 1601004.301, Cooper High Pressure RHRSW Thinning Evaluation Per Code Case N-513 ML17018A1522016-11-0101 November 2016 Pressure and Temperature Limits Report, Revision 1 NLS2016058, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/20162016-10-0707 October 2016 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/2016 ML16351A2512016-09-15015 September 2016 SW-E-3-2851-3, Ultrasonic Thickness Measurement System. ML16351A2502016-09-13013 September 2016 SW-Z4-2851-7, Altrasonic Thickness Measurement System. NLS2016021, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary)2016-04-21021 April 2016 Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary) ML16084A1832016-03-0202 March 2016 Er 15-019, Rev. 1, Cooper Nuclear Station Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary Version of Er 15-015). NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015 Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al NLS2015073, Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 22015-08-0606 August 2015 Er 15-019, Rev. 0, Pressure and Temperature Limits Report (PTLR) for 32 Effective Full-Power Years (EFPY) (Non-Proprietary), Enclosure 2 NLS2015091, 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-07-28028 July 2015 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 NLS2015043, Expedited Seismic Evaluation Process Report2015-04-29029 April 2015 Expedited Seismic Evaluation Process Report ML15006A2342015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) ML17018A1532014-12-31031 December 2014 BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program Data Source Book and Plant Evaluations NLS2016014, Er 15-019, Supplement 1, BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations.2014-12-31031 December 2014 Er 15-019, Supplement 1, BWRVIP-135, Revision 3: BWR Vessel and Internals Project, Integrated Surveillance Program (ISP) Data Source Book and Plant Evaluations. NLS2014074, Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 92332014-07-30030 July 2014 Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 9233 ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 NLS2014044, and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.2102014-05-13013 May 2014 and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210 NLS2014027, Enclosure - Seismic Hazard Evaluation and Screening Report for Cooper Nuclear Station2014-03-20020 March 2014 Enclosure - Seismic Hazard Evaluation and Screening Report for Cooper Nuclear Station ML14007A6502014-02-11011 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14037A1672014-02-10010 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Cooper Nuclear Station, TAC No.: MF0972 NLS2012130, Problem Identification and Resolution P. 1(c) Substantive Cross-Cutting Issue2012-12-13013 December 2012 Problem Identification and Resolution P. 1(c) Substantive Cross-Cutting Issue ML12340A2752012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment E Through J ML12340A2732012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment D - Area Walk-By Checklists ML12340A2692012-11-27027 November 2012 Engineering Evaluation 12-E18, Revision 0, Attachment C - Page 76 of 322 ML12340A2682012-11-27027 November 2012 CNS Memo DED12-0003 Response to 10 CFR 50.54(f) Section 2.3 Seismic, Enclosing Engineering Evaluation 12-E18, Revision 0 NLS2012124, Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report2012-11-26026 November 2012 Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report NLS2012085, CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 20122012-10-10010 October 2012 CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 2012 NLS2012089, Submittal of Nuclear Material Transaction Report2012-08-29029 August 2012 Submittal of Nuclear Material Transaction Report ML1216000292012-06-11011 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident NLS2012040, Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 282012-05-30030 May 2012 Enclosure 2, Gnf S-0000-0140-2518-R0-NP, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Cycle 28 NLS2012006, Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c)2012-04-24024 April 2012 Nebraska Public Power District - Cooper Nuclear Station, License Amendment Request to Revise the Fire Protection Licensing Basis to NFPA 805 Per 10 CFR 50.48(c) 2024-07-29
[Table view] Category:Miscellaneous
MONTHYEARNLS2024065, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2024-10-0707 October 2024 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2024055, Data from Metamic Coupon Sampling Program2024-07-29029 July 2024 Data from Metamic Coupon Sampling Program NLS2023005, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20222023-01-19019 January 2023 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2022 NLS2022042, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report2022-10-0707 October 2022 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report NLS2022003, Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20212022-01-20020 January 2022 Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2021 ML19262G9042019-11-0808 November 2019 Staff Assessment of Flood Hazard Integrated Assessment (Public) ML18184A2732018-07-18018 July 2018 Staff Review of Mitigation Strategies Assessment Report of the Impact of the Reevaluated Seismic Hazard Developed in Response to the March 12, 2012, 50.54(f) Letter (CAC No. MF7819; EPID L-2016-JLD-0006) NLS2018003, Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 20172018-01-15015 January 2018 Submittal of Annual Report of Changes and Errors in Emergency Core Cooling System Evaluation Models for 2017 ML17244A2812017-05-0808 May 2017 16C4384-RPT-005, Rev 005, 50.54(f) NTTF 2.1 Seismic High Frequency Confirmation. NLS2016070, Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events2017-01-0404 January 2017 Completion of Required Action by NRC Order EA-12-049 - Mitigation Strategies for Beyond-Design-Basis External Events NLS2016066, Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation2016-12-20020 December 2016 Completion of Required Action by NRC Order EA-12-051 - Reliable Spent Fuel Pool Instrumentation ML16351A2472016-12-12012 December 2016 Review of SIA Calculation 1601004.301, Cooper High Pressure RHRSW Thinning Evaluation Per Code Case N-513 NLS2016058, 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/20162016-10-0707 October 2016 10 CFR 50.59(d)(2) and 10 CFR 72.48(d)(2) Summary Report of Evaluations for 08/01/2014 - 07/31/2016 NLS2016021, Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary)2016-04-21021 April 2016 Gnf Additional Information Regarding the Requested Changes to the Technical Specification SLMCPR - Cooper Nuclear Station Cycle 30 (Non-Proprietary) NLS2015128, Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 91682015-10-29029 October 2015 Submittal of 10 CFR 71.95 Report Involving Energysolutions Certificate of Compliance No. 9168 ML15259A3422015-08-24024 August 2015 10 CFR 71.95 Report Evaluation Form; Submitted by Fenok, Erwin Resin Solutions, North Anna Power Stations, Et Al ML15006A2342015-02-11011 February 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) NLS2014074, Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 92332014-07-30030 July 2014 Submittal of 10 CFR 71.95 Report Involving Areva Certificate of Compliance No. 9233 NLS2014044, and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.2102014-05-13013 May 2014 and ISFSI - Thirty-Day Notification Pursuant to 10 CFR 72.212, Conditions of General License Issued Under Section 72.210 NLS2012124, Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report2012-11-26026 November 2012 Enclosure to NLS2012124, Cooper Nuclear Station Flooding Walkdown Report NLS2012085, CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 20122012-10-10010 October 2012 CFR 50.59(d)(2) Summary Report Covering Time Period from August 1, 2012 to July 31, 2012 NLS2012089, Submittal of Nuclear Material Transaction Report2012-08-29029 August 2012 Submittal of Nuclear Material Transaction Report ML1216000292012-06-11011 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants NLS2009099, SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application2009-12-0707 December 2009 SAMA Meteorological Anomaly Related to the Cooper Nuclear Station License Renewal Application NLS2008106, Submittal of Program for Maintenance of Irradiated Fuel2008-12-23023 December 2008 Submittal of Program for Maintenance of Irradiated Fuel NLS2008096, Corrected Semiannual Fitness for Duty Program Performance Report for the Period of January 1, 2008 Through June 30, 20082008-10-22022 October 2008 Corrected Semiannual Fitness for Duty Program Performance Report for the Period of January 1, 2008 Through June 30, 2008 NLS2008059, Submittal of Revised Root Cause Investigation - Diesel Generator Amphenol Connector2008-07-21021 July 2008 Submittal of Revised Root Cause Investigation - Diesel Generator Amphenol Connector NLS2008033, Response to Request for Additional Information for Question I.2 Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-03-12012 March 2008 Response to Request for Additional Information for Question I.2 Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate NLS2008019, Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate2008-03-0606 March 2008 Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specifications - Appendix K Measurement Uncertainty Recapture Power Uprate ML0917502992008-01-0101 January 2008 Lr - NPPD 2008 Integrated Resource Plan NLS2006090, Core Operating Limits Report, Cycle 24, Revision 02006-11-0505 November 2006 Core Operating Limits Report, Cycle 24, Revision 0 NLS2006084, CFR 50.59(d)(2) Summary Report2006-10-12012 October 2006 CFR 50.59(d)(2) Summary Report NLS2005107, Reporting of Changes and Errors in ECCS Evaluation Models Cooper Nuclear Station2005-12-28028 December 2005 Reporting of Changes and Errors in ECCS Evaluation Models Cooper Nuclear Station ML0520901582005-08-0202 August 2005 2004 External Stakeholder Response; 2004 Reactor Oversight Process External Survey - Attachment ML0522700732005-04-18018 April 2005 Event Notification Report for April 18, 2005 ML0727008492005-01-31031 January 2005 Caldon Experience in Nuclear Feedwater Flow Measurement NLS2004117, 1OCFR50.59(d)(2) Summary Report2004-10-14014 October 2004 1OCFR50.59(d)(2) Summary Report NLS2004105, Initial Actions Summary Report and Response to NRC Generic Letter 2003-01, Control Room Habitability.2004-09-30030 September 2004 Initial Actions Summary Report and Response to NRC Generic Letter 2003-01, Control Room Habitability. ML0619802152004-08-0606 August 2004 CNS Assessment of Survivability of the Service Water Pumps When Gland Waste Water Was Lost ML0622205762004-07-27027 July 2004 Johnston Pump Company Letter to Mr. Kent Sutton ML0619801532004-07-16016 July 2004 Excerpts from Historic Work Orders ML0532204612004-06-14014 June 2004 Power Reactor Status Report for 6/14/04 ML0618607342004-05-11011 May 2004 Comments Concerning Loss of Gland Water to the Service Water Pumps at Cooper Nuclear Station ML0618607312004-05-0606 May 2004 Comments Concerning Loss of Gland Water to the Service Water Pumps at Cooper Nuclear Station ML0618701942004-04-30030 April 2004 Excerpt from Missouri Nuclear Accident Plan ML0619801092004-03-17017 March 2004 CNS Roots Cause Investigation - Service Water Gland Water Valve Mis-positioning Event, SCR 2004-0077 ML0619801012004-03-10010 March 2004 CNS Clearance Order, Section SWB-1-4324147 SW-STNR-B ML0626304082004-03-0101 March 2004 PSEG Nuclear, LLC Salem/Hope Creek Safety Culture Assessment ML0619800892004-02-18018 February 2004 CNS Notification 10294449 2024-07-29
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UZ/18/ZU04 iIIPP : Notification overview 1 Lp, lV, VI L'upy 2 Page I Notification: 10294449 "Not*,icdtion 310294449 Notification tyt CR Description SW GLAND WATER (A) AND (B) TROUBLE ALARM Condition Report Reported by JRWEISS 17:25:07 NotifictnDate 02/08/2004 Start date 02/08/2004 End date 02/12/2004 Start time 17,;:25 :07 End time 16:30:00 Priority CM FunctLocaiion CNS-SW SERVICE WATER SORT SW Equipment Order Assembly MaintPlanGroup PED Plant. Engineering Tel.
Malf. Start Date Malf. End date Malf. Start time 00:00:00 Malf. End lime 00:00:00
021T87T2 004 NPPD: Notification overview 1 SCSCHWI Copy 2 Page,2 Notification: 10294449 02/08/2004 17:25:07 btcuser (BTCUSER)
DESCRIPTION OF CONDITION:
Received Annunciator ANN -ANN - (A-4/E-6)i SW GLAND WTR SUPPLY SYS A TROUBLE, 'and ANN -ANN -(B-3/E-6), SW GLAND WTR SUPPLY SYS B TROUBLE, Bldg operator reported that the alarms were due to Low Pressure and they were both clear. The following parameters were-noted:
A/C Gland water pressure 18#
SWP A Gland water flow 5.4gpm SWP C Gland water flow- 7.8gpm B/D Gland water pressure 16.5#
SWP B Gland water flow 7.6gpm SWP D Gland water flow 6.3gpm No adjustments were made to the system, no other alarm were received.
REQUIREMENT NOT MET:
- SW GLAND WATER LOW PRESSURE ALARMS
- METHOD OF DISCOVERY:
CONTROL ROOM ALARM IMMEDIATE ACTIONS TAKEN:
DISPATCHED BLDG OPERATOR PER THEALARM RESPONSE PROCEDURE.
.RECOMMENDATIONS:
DETERMINE AND CORRECT CAUSE OF ALARM.
LOCATION !OF EVIDENCE:
IS-903-SWP ROOM FUNCTIONAL LOCATION (IF KNOWN);:
SW GLAND WATER PRESSURE
- EQUIPMENT (IF KNOWN):
SW GLAND WATERSYSTEM REPORTED BY:
JRWEISS WORK CENTER:
OPS SUBMITTED BY:
j rweiss
02118/2004 NPPD: Notification overview 1 opy Notification: 10294449
'SUPERVISOR:
BRIAN MURPHY DEFICIENCY TAG:
IS THIS AN EQUIPMENT ISSUE?
(X] YES, CONTACT THE SENIOR REACTOR OPERATOR (SRO) IN THE WORK CONTROL CENTER (WCC) OR. THE:CONTROL ROOM.
[ ] NO.
IF THE :CONDITION IS EXPECTED TO 'BE INCLUDED IN THE CORRECTIVE ACTION PROGRAM, INDICATE IF YOU WOULD LIKE TO EVALUATE THE ACTIONS TO BE TAKEN FOR THE CONDITION?
( I YES
[X] NO ADDITIONAL COMMENTS:
02/08/.2004 23.:341:05 Rod L. Penfield (RLPENFI) Phone .402-825-5413 The following parameters were noted upon investigation:
A/C Gland water pressure 18#
SWP A Gland water flow 5.4gpm SWP C Gland water flow 7.8gpm BiD Gland water pressure 16.5#..
SWP B Gland Water flow -7.6gpm SWP D Gland Water flow 6.3gpm Sufficient :gland water to ýpumps was always maintained greater than 1.5 gpm. SW Operability not affected by the condition identified.
THIS IS THE ONLY ALARM THAT 'HAS BEEN RECEIVED ON THE SERIVE WATER GLAND WATER SYSTEM'. GLAND WATER FLOWS WERE MAINTAINED GREATER THAN 1.5 GPM AT ALL TIMES. MOST LIKELY THE CAUSE OF THIS 'ALARM WAS SYSTEM LOADING .DUE TO DEMANDS ON THE SCREEN' WASH AND SPARGER SYSTEMS. RECOMMEND SYSTEM ENGINEER TREND THIS CONDITIONI.
-Task ACTIVITY TAGD N/A Partner
.System Status TSCO Task REVIEW OPRV Partner System Status TSCO 02/08/2004 '18:19:07 Steve Wheeler (SCWHEEL)
OPERATIONS REVIEW OF NOTIFICATION Is the condition an immediate nuclear or personnel safety concern?
[ I YES - Immediately notify Shift Manager
uZI IO/[UU'+ iarrLu: IlTOITIcaTI!n overview 1 bUbuVV L 4 rage 4 Notification: 10294449
- Is the condition reportable or potentially reportable per 10CFR20, 10CFR26.73, 10CFR50.72, 10CFR50.73, or 10CFR73.71 (reference Procedure 2.0.5
- and NUREG 1022)?
[ ] YES - Immediately notify Shift Manager CXX] NO Does the condition affect or potentially affect -any of the *SSC(s) described in Attachment 4? Also consider generic concerns and common mode failures, when applicable. For significant programmatic issues, determine if a basis for Reasonable Assurance of Safety per Procedure 0.5.BCO is required. h E XX I YES - Immediately notify Shift Manager
[ ] NO - NOT IN SCOPE Does the condition call the SSC(s) performance into question?
[ XX ] NO - Basis: SW HEADER PRESSURE DROPPED APPROXIMATELY 3-4 PSIG WHEN THE LOW PRESSURE ALARMS .CAME IN., BELIEVED DUE TO GLAND WATER PRESSURES CLOSE TO ALARM 'SETPOINT 'OF 14 PSIG AND `SEQUENCING OF SW LOADS IN INTAKE (A/B ZURN BLOWN DOWN, zSPARGERS SWAPPING). "ALARM CONDITION -HAS CLEARED. ADEQUATE 'GLAND WATER FLOW WAS NOTED'BY THE STATION OPERATOR.
[ -] YES - Declare SSC(s) inoperable and document a basis 'for Reasonable Assurance of Safety if TRM or ODAM LCO 3.0.3 'is entered
[ I 'YES - Document !a reasonable :expectation of OPERABILITY on the Notificationh AND Perform INFORMATION' GATHERING Does the condition call the SSC(s) qualification into question?
I XX ] NO - Basis:SW HEADER PRESSURE DROPPED APPROXIMATELY 3-4 PSIG WHEN 'THE LOW PRESSURE ALARMS CAME IN., BELIEVED 'DUE TO GLAND WATER PRESSURES, CLOSE TO ALARM SETPOINT OF 14 PSIG AND SEQUENCING OF SW LOADS IN INTAKE (A/B ZURN BLOWN DOWN, SPARGERS SWAPPING). ALARM CONDITION HAS CLEARED. ADEQUATE GLAND WATER FLOW WAS NOTED BY THE STATION OPERATOR.
[ ] YES - Declare SSC(s) inoperable and document a basis 'for Reasonable Assurance of _Safety if TRM or ODAM LCO 3.0.3 is entered
[ ] YES -'Document a reasonable expectation of OPERABILITY on the Notificationh AND Perform 'INFORMATION' GATHERING Does 'the condition describe .an existing but previously unanalyzed condition or accident?
[XX] NO
[ ] YES - Declare SsC (s) inoperable and document a basis for Reasonable Assurance of Safety if TRM or ODAM :LCO 3.0.3 is "entered
[ ] YES -Document a reasonable expectatibn of OPERABILITY on the Notificationh AND Perform INFORMATION GATHERING 02/08/2004 23:22:37 Rod L. Penfield (RLPENFI) Phone 402-825-5413
02118/2004 NPPD: Notification overview *;bubtI'IM ~LJLJMVI opy z~ Page *,
Nptification: 10294449 I
Task .REVIEW'WCCR I CONCUR WITH THE OPS REVIEW Partner System Status TSCO Task REVIEW CAP TREND- OPS Partner System Status TSCO 02/10/2004 11:25:32 David Hockenborne (DWHOCKE)
TREND- OPS Task REVIEW SCRN TREND PED Partner System Status TSCO Task REVIEW .LIC NOT REPORTABLE Partner System Status TSCO 02/10/2004'15:19442 Coy L. Blair (CLBLAIR)
NO OPERABILITY IMPACT Task REVIEW.MRUL EXPORTCIC=SW-PS-387
.Partner System .,Status TSCO TSSC Task ACTIVITY TAGR N/A Partner Systemn Status TSCO item detail 0001 Text Object part MI01 :ANNUNCIATORS Damage Cause of damage Cause text SW Assembly Error class End of report