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Category:Report
MONTHYEARL-24-233, Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-12-18018 December 2024 Proposed Alternative Request to Defer ASME Code Section XI Inservice Inspection Examinations for Pressurizer and Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles L-23-214, Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements2024-06-0505 June 2024 Submittal of Relief Request for Impractical American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI Examination Requirements L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-22-253, Submittal of Pressure and Temperature Limits Report, Revision 52023-01-10010 January 2023 Submittal of Pressure and Temperature Limits Report, Revision 5 L-22-211, Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report2022-09-29029 September 2022 Technical Specification 5.6.6 Steam Generator Tube Inspection 180-Day Report L-22-216, Submittal of Pressure and Temperature Limits Report. Revision 42022-09-27027 September 2022 Submittal of Pressure and Temperature Limits Report. Revision 4 L-22-149, Post Accident Monitoring Report2022-06-23023 June 2022 Post Accident Monitoring Report ML22202A4362022-04-0808 April 2022 Enclosure F: Updated Inputs to 52 EFPY P-T Operating Curves ML22202A4372022-03-0202 March 2022 Enclosure G: Framatome Inc. Document 86-9344713-000, Davis-Besse Reactor Vessel Embrittlement Fluence Reconciliation Through 60 Years IR 05000346/20210902021-12-16016 December 2021 Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding ML21322A2892021-12-0909 December 2021 Approval of Plant-Specific Analysis of Certain Reactor Vessel Internal Components in Accordance with License Renewal Commitment No. 53 ML20302A3022020-09-25025 September 2020 1 to Technical Requirements Manual ML19255H0992019-10-10010 October 2019 Staff Assessment of Flooding Focused Evaluation L-19-189, 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension2019-07-29029 July 2019 54010-CALC-01, Davis-Besse Nuclear Power Station: Evaluation of Risk Significance of Permanent ILRT Extension ML22262A1522019-05-0101 May 2019 Framatome Inc., Document ANP-2718NP, Revision 007, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station ML22202A4332019-04-30030 April 2019 Enclosure C: Framatome ANP-2718NP, Rev. 7, Appendix G Pressure-Temperature Limits for 52 EFPY for the Davis-Besse Nuclear Power Station L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile..2018-04-12012 April 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile.. ML18053A0232018-02-22022 February 2018 Compilation of Industry Provided Information on Anchor Darling Double Disc Gate Valve Population Affected by Flowserve, Part 21 Issue of Wedge Pin Failure on an Anchor Darling Double Disc Gate Valve in Report Format with Valve Count ML18149A2812018-02-16016 February 2018 2017 ATI Environmental Inc. Midwest Laboratory Radiological Environmental Monitoring Program L-17-270, Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.462017-09-0101 September 2017 Notification of Emergency Core Cooling System (ECCS) Evaluation Model Change Pursuant to 10 CFR 50.46 ML17086A0322017-03-31031 March 2017 Enclosure B to L-17-105, Areva Report ANP-3542NP, Revision 1, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility at 60 Years L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments ML17026A0082016-12-31031 December 2016 Areva Report ANP-3542NP, Time-Limited Aging Analysis (TLAA) Regarding Reactor Vessel Internals Loss of Ductility for Davis-Besse Nuclear Power Station, Unit No. 1 at 60 Years (Non Proprietary) L-16-229, Submittal of Pressure and Temperature Limits Report, Revision 32016-07-28028 July 2016 Submittal of Pressure and Temperature Limits Report, Revision 3 L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016 Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue) L-15-288, Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-10-0202 October 2015 Response to NRC Letter. Request for Information, Per 10 CFR 50.54(f) Regarding Recommendations 2.1. 2.3. and 9.3. of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML15230A2892015-08-25025 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML14353A0592014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of in L-14-401, 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station2014-11-0303 November 2014 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station L-14-289, Pressure and Temperature Limits Report. Revision 22014-09-22022 September 2014 Pressure and Temperature Limits Report. Revision 2 L-14-259, Firstenergy Nuclear Operating Companys (Fenocs) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Companys (Fenocs) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14141A5252014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014 Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 ML14134A5172014-05-30030 May 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-148, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2014-05-19019 May 2014 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models ML14112A3152014-04-21021 April 2014 Review of Draft Plant-Specific Supplement 52 to the Generic Environmental Impact Statement for License Renewal of Nuclear Plants Regarding L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014 Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML14007A6702014-02-21021 February 2014 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14042A2942014-02-19019 February 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Davis-Besse Nuclear Power Station, TAC No.: MF0961 ML13340A1592013-11-26026 November 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1472013-11-26026 November 2013 & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0159) ML13340A1632013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G ML13340A1622013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1602013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1582013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 L-13-154, CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models2013-05-28028 May 2013 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling System Evaluation Models L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan ML13009A3752012-12-12012 December 2012 Enclosure B to L-12-444, Calculation No. 32-9195651-000, Equivalent Margins Assessment of Davis-Besse Transition Welds for 52 EFPY - Non-Proprietary L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident L-12-283, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 364 of 461 Through Appendix C, Area Walk-By Checklists, Sheet 20 of 1392012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 364 of 461 Through Appendix C, Area Walk-By Checklists, Sheet 20 of 139 2024-06-05
[Table view] Category:Miscellaneous
MONTHYEARL-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000346/20210902021-12-16016 December 2021 Reissue Davis-Besse NRC Inspection Report (05000346/2021090) Preliminary White Finding L-18-108, Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile..2018-04-12012 April 2018 Request to Extend Enforcement Discretion Provided in Enforcement Guidance Memorandum 15-002 for Tornado-Generated Missile Protection Non-Conformance Identified in Response to Regulatory Issue Summary 2015-06, Tornado Missile.. ML18053A0232018-02-22022 February 2018 Compilation of Industry Provided Information on Anchor Darling Double Disc Gate Valve Population Affected by Flowserve, Part 21 Issue of Wedge Pin Failure on an Anchor Darling Double Disc Gate Valve in Report Format with Valve Count L-17-088, Independent Spent Fuel Storage Installation Changes, Tests and Experiments2017-03-27027 March 2017 Independent Spent Fuel Storage Installation Changes, Tests and Experiments L-16-148, Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue)2016-04-21021 April 2016 Fatigue Monitoring Program Evaluation of Reactor Coolant Pressure Boundary Components for Effects of the Reactor Coolant Environment on Fatigue Usage (I.E., Environmentally-Assisted Fatigue) ML15230A2892015-08-25025 August 2015 Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review ML14353A0592014-12-19019 December 2014 First Energy Nuclear Operating Company (FENOC) Expedited Seismic Evaluation Process (ESEP) Reports Response to NRC Request for Information Pursuant to 10 CFR50.54(f) Regarding Recommendation.1 of the Near-Term Task Force (NTTF) Review of in L-14-401, 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station2014-11-0303 November 2014 2734296-R-010, Rev. 0, Expedited Seismic Evaluation Process (ESEP) Report Davis-Besse Nuclear Power Station L-14-259, Firstenergy Nuclear Operating Companys (Fenocs) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051)2014-08-28028 August 2014 Firstenergy Nuclear Operating Companys (Fenocs) Third Six-Month Status Report in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order Number EA-12-051) ML14141A5252014-06-30030 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima DAI-ICHI Nuclear Power Plant Accident L-14-167, Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 20142014-06-18018 June 2014 Report of Facility Changes, Tests and Experiments for the Period Ending May 26, 2014 L-14-104, Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2014-03-11011 March 2014 Firstenergy Nuclear Operating Co. Response to NRC Request for Information Pursuant to 10 CFR 50.54 (F) Regarding the Flooding Aspects of Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident ML13340A1592013-11-26026 November 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix a ML13340A1472013-11-26026 November 2013 & Perry Nuclear Power Plant - Response to RAI Associated with Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident (TAC Nos. MF0116 & MF0159) ML13340A1632013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix C to Appendix G ML13340A1622013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (2 of 2) ML13340A1602013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1, Appendix B (1 of 2) ML13340A1582013-10-0909 October 2013 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report Revision 1 L-13-157, Generic Safety Issue 191 Resolution Plan2013-05-15015 May 2013 Generic Safety Issue 191 Resolution Plan L-12-347, FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2012-11-27027 November 2012 FENOC Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Flooding Aspects of Recommendation 2.3 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident ML13008A0642012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 244 of 461 Through Sheet 363 of 461 ML13008A0312012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Appendix a, Resumes and Qualifications, Page A-39 ML13008A0622012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Page B-1 Through Sheet 120 of 416 ML13008A0632012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 121 of 461 Through Sheet 243 of 461 L-12-283, Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 364 of 461 Through Appendix C, Area Walk-By Checklists, Sheet 20 of 1392012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B, Seismic Walk-Down Checklists, Sheet 364 of 461 Through Appendix C, Area Walk-By Checklists, Sheet 20 of 139 ML13135A2432012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix a - Resumes and Qualifications ML13135A2422012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Cover Through Page 176 ML13135A2442012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 1 of 379 Through Sheet 201 of 379 ML13135A2452012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix B - Seismic Walkdown Checklists (Swcs), Sheet 202 of 379 Through Sheet 379 of 379 ML13135A2462012-08-10010 August 2012 Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report, Appendix C - Area Walk-by Checklists (Awcs) Through End ML12213A3372012-07-27027 July 2012 SB-00-20: CR-2011-03346 Evaluation ML12213A3352012-07-27027 July 2012 Review of Technical Assessment Report No. 25539-200 COR-0000-00001 ML12138A0492012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 2 ML12138A0582012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 3 ML12138A0672012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 4 ML12138A0732012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 5 L-12-196, FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 72012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 7 ML12138A0372012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1, Submittal of Contractor Root Cause Assessment Report-Section 1 ML12138A0812012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 6 L-12-071, 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model2012-03-16016 March 2012 10 CFR 50.46 Report of Significant Changes or Errors in the Loss of Coolant Accident Evaluation Model ML12200A2122011-11-21021 November 2011 Containment Shield Building Issue ML12200A2102011-11-17017 November 2011 Containment System Primary Steel Containment an Shield Building ML12213A3482011-10-28028 October 2011 Table of Contents to Isolated Crack Indication Identified by Impulse Response Testing of the Shield Building L-11-319, Pressure and Temperature Limits Report2011-10-27027 October 2011 Pressure and Temperature Limits Report ML11301A2302011-06-0101 June 2011 Reference: State Energy Consumption Estimates 1960 Through 2009 ML1101007582011-01-10010 January 2011 Pressure Temperature Limits Report Attachment ML11301A2232010-07-31031 July 2010 Chp Regional Application Centers: Activities and Selected Results for Fiscal Year 2009 ML1015201162010-05-26026 May 2010 Field Report Control Rod Drive Mechanism Number 4 Ultrasonic Results ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants 2023-08-07
[Table view] |
Text
L NOP-LP-2001-01 CONDITION REPORT TITLE: BORON BUILD UP ON REACTOR VESSEL HEAD CR Number 02-00685 0
R I
G I
N A
T I
0 N
P L
A N
T 0
P E
R A
T I
0 N
S RPA I
UPV I
ARB I
DISCOVERY DATE TIME EVENT DATE ~
TIME
~ SYSTEM I ASSET#
2/21/2002 11:oo 2/21/02 11:oo 062-01 Tl*RC
_ _ _ _ _ ~
EQUIPMENT DESCRIPTION REACTOR VESSEL HEAD DESCRIPTION OF CONDITION and PROBABLE CAUSE (if known) Summarize any attachments. Identify what, when, where, why, how.
~
~
~
As part of FTl's reactor vessel head work it was identified that there was loose boron 1-2" deep 75% around the circumference of the flange. On the other 25% from stud 16 to 30 (clockwise), the boron was hard baked 3-4" thick on southeast quadrant (x-y axis). The large boron accumulation is in the same region as seen in 12RF0, but not as deep.
SUPV COMMENTS I IMMEDIATE ACTIONS TAKEN (Discuss CORRECTIVE ACTIONS completed, basis for closure.)
FTI CONTACT: Jim Harris ATTACHMENTS N/A
[ U E v a l Required 1
Other NIA COMMENTS Notified the Boric Acid Control Coordinator and Outage Engineering Manager per NG-EN-00324, Boric Acid Corrosion Control. Will track as a Mode 4 restraint.
Current Mode - Unit 1 Power Level - Unit 1 ' Current Mode - Unit 2 SRO - UNIT 1 SRO - UNIT 2
~ DATE Power Level - Unit 2 i
5 0
1 I
Steenbergen, C Ploeger, T 2/22/2002
- ATEGORY I EVAL ASSIGNED ORGANIZATION DUE DATE I
CA PE 4/7/2002 TREND CODES Comp Type I ID Resp Process I Activity I Cause Code(s)
(If Cause Or w, Org NONE
~~~
HDW 0575 NA
~~
~~~
~~
1 REPORTABLE?
O Y e s No LERNo.
Y '
02/22/02 i
~~~
INVESTIGATION OPTIONS CLOSED BY DATE 0
Generic Implications 0 Part 21 0 Maint.Rule D O E Evaluation Page 1 of 1
NOP-LP-2001-05 CR Category:
Action Type:
Schedule Type:
CA
( B ) REVIEW
( A ) Normal Work Management CORRECTIVE ACTION CA Number:
1 CR Number:
02-00685 Corrective Action Type:
( OT ) Other 0
R I
G I
N A
T 0
R 4cc EPT -
LUAL ITY I
M P
L E
M E
N T
I N
G 0
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2 v J E 4 R I
I F
( E R
r i Cause Code:
Resp Org:
( NA ) Not Applicable PE Completed By:
NOWICKI, K Organization:
Date:
Phone:
Attachments:
RA 2/22/2002 8590 0
Yes El NO Corrective Action Implementation Date:
3/4/2002 j
Signature indicates Corrective Action complete:
Completed By:
SIEMASZKO, A Date:
2/28/2002 If a Refueling Outage is required, Enter the Refueling Outage number:
2~
N/A 0
1R Signature indicates verification for SCAQ CRs:
Implementing Organization Supervisor:
Date:
Implementing Organization Approval:
CUNNINGS, J Date:
3/4/2002 a Enter Name and Sign:
Zomments:
Other Tracking #
Corrective Action Due Date:
NIA 3/5/2002 4pproval:
Date:
Approval: (Enter Name and Sign)
MCALLISTER, A Page 1 of 3 Section:
Date:
PE 2/22/2002 Quality Organization Approval:
Date:
NOP-LP-2001-05 CR Category:
CA CORRECTIVE ACTION Action Type:
Schedule Type:
CA Number:
( J ) ROLL-OVER
( A ) Normal Work Management 2
CR Number:
02 -0 0 685 Corrective Action Type:
( OT ) Other 0
R I
G I
N A
T 0
R Cause Code:
Resp Org:
( NA ) Not Applicable PE 4cc EPT Completed By:
NOWICKI. K LUAL ITY I
M P
L E
M E
N T
I N
G 0
R G
3 v J E 4 R L
I I F V E R
r i Organization:
Date:
Phone:
Attachments:
RA 311 512002 8590 0
Yes NO If a Refueling Outage is required, Enter the Refueling Outage number: 0 2~
N/A 0
1R
~~
Other Tracking #
Corrective Action Due Date:
NIA 311 512002 Approval: (Enter Name and Sign)
Cunnings, J. for Rogers Corrective Action Implementation Date:
311 512002 Signature indicates Corrective Action complete:
Completed Bv:
NOWICKI. K Date:
311 512002 Section:
Date:
PE 312512002 Signature indicates verification for SCAQ CRs:
Implementing Organization Supervisor:
Date:
ImDlementina Oraanization Amroval:
CUNNINGS. J Date:
3/26/2002 1
Enter Name and Sign:
Comments:
Approval:
Date:
Page 2 of 3
I NOP-LP-2001-05 CR Category:
CA CORRECTIVE ACTION Action Type:
Schedule Type:
CA Number:
( W ) ANI REVIEW
( A ) Normal Work Management 3
CR Number:
02-00685 Corrective Action Type:
Cause Code:
( OT ) Other
( NA ) Not Applicable Resp Org:
AN I
==
Description:==
ANI Review Completed By:
SIEMASZKO. A Organization:
Date:
Phone:
Attachments:
PE 311 512002 7341 0
Yes lid NO If a Refueling Outage is required, Enter the Refueling Outage number:
0 2~
N/A 0
1R
Response
CR 02-00685 has been reviewed and accepted by T. Laps ANI1 on 03/15/02.
~
~~
Other Tracking #
Corrective Action Due Date:
NIA 311 512002 Corrective Action Implementation Date:
3/15/2002 A Signature indicates Corrective Action complete:
J Signature indicates verification for SCAQ CRs:
J Enter Name and Sign:
Completed By:
LAPS, T Date:
311 512002 Implementing Organization Supervisor:
Date:
Implementing Organization Approval:
LAPS, T Date:
311 512002 Comments:
Approval: (Enter Name and Sign)
LAPS, T Approval:
Section:
Date:
AN I 311 512002 Date:
Quality Organization Approval:
Page 3 of 3 Date:
I CRNumber SIEMASZKO, A 02-00685 CAUSE ANALYSIS NOP-LP-2001-03 311 512002 Condition Description and Cause Basis:
1 Hardware I Degraded Condition Resolution Required?
This CR is being rolled into CR 02-00891.
Process Code HDW Activity Code 0575 Category I Eva1 Code: CA 0 Yes 0 NO If Yes, select one Repair 0
Scrap 0
Rework Use-As-Is Trend Codes Cause Code (If causeisT or W )
Component Code Type ID#
Resp Org NONE None
~
~
~
Primary NA Not Applicable Secondary Tertiary
~-
~~
Completed By:
I Date:
Page 1 of 1
NOP-LP-2001-06 2
INVESTIGATION SUM MARY A
1 OT 1
NA 1
PE 1 Cunnings, J. for Rogers 1
3/25/02 I 3/15/2002 I 311 512002 CR Number:
02 -00 685 3
Category I Eval: CA Assigned Organization: PE Quality Followup Req'd: 0 Yes W NO 4 Acceptance of the CR Investigation signifies acceptance of the following items, as applicable:
A OT NA ANI 1 LAPS,T Yes 0 No Corrective Actions ( listed below )
Yes 0 No Cause Analysis Originator Identification Date (listed below, if any)
(listed below, if any)
SIEMASZKO, A 311 512002 c]
Yes No Generic Implications 0
Yes W No 10 CFR 21 Decision Checklist Acceptance of Investigation:
Cunnings, J. for Rogers Date:
Quality Approval:
3/25/2002 Date:
Closure Comments:
Quality Comments:
CORRECTIVE ACTIONS Resp CA Sched CA Cause Org.
Number:
Type:
Type:
Code:
codes:
CA Acceptance:
1 1
A
/ O T I N A 1
PE I MCALLISTER,A Accept Due Completed Date:
Date:
Date:
I 2/22/02 I
3/5/2002 1
3/4/2002 Page 1 of 1