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MONTHYEARML22034A3992022-02-16016 February 2022 Enclosure 1 - IP 71130.03 Cy 2021 - IR 8 Baseline Inspection Completion ML22034A3972022-02-16016 February 2022 Enclosure 2 - IP 92707 CY2021 - IR 8 Baseline Inspection Completion ML22034A3952022-02-16016 February 2022 Enclosure 3 - IP 96001 CY2021 - IR 8 Baseline Inspection Completion ML16285A3202016-10-12012 October 2016 ROP PI Frequently Asked Questions (Faqs): 13-04 ML16159A4002016-06-16016 June 2016 Iepra Ror for Point Beach SE Section 3.4 ML16159A4022016-06-16016 June 2016 Fpra Ror for Point Beach SE Section 3.4 ML15261A7492015-09-14014 September 2015 NRC Supplement to NRC Letter - Notification of NRC Inspection and Request for Information Dated May 1, 2015 - NextEra Energy Point Beach Nuclear Plant (Msh) ML16072A0362015-06-0303 June 2015 Receipt of Cd Containing Revised I/O Files from NextEra Point Beach Nuclear Plant Flood Hazard Re-Evaluation Report ML15014A1602015-01-14014 January 2015 Attachment 2 - NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML15014A1532015-01-14014 January 2015 Attachment 1- NEI Comments on NRC Working Group Recommendations to Revise the Substantive Cross-Cutting Issue Process ML14314A5122014-11-13013 November 2014 Enclosure 2 - Frequently Asked Questions (Faqs) Discussed During the October 22 2014 Reactor Oversight Process Public Meeting ML14147A0112014-06-20020 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 ML14149A1532014-05-0101 May 2014 FOIA/PA-2014-0074 - Resp 4 - Partial. Group F (Records Already Publicly Available) ML12056A0522012-03-12012 March 2012 Enclosure 6 - List of Power Reactor Licensees and Holders of Construction Permits in Active or Deferred Status ML1017301232010-06-0909 June 2010 Green Ticket Tritium Releases ML0806704192008-03-0707 March 2008 CDBI Findings ML0732400242007-10-25025 October 2007 Examples of Max Thermal Power License Conditions ML0726203022007-09-28028 September 2007 Amendment to Indemnity Agreement No. B-41, Amendment No. 14 ML0726303192007-09-14014 September 2007 P. Paquin Ltr Amendment to Certificate of Compliance No. 6574 for the Model No. 3-82B Package (TAC L24116)/ Register User List ML0635404332006-12-20020 December 2006 Enclosure 2 - Consent and Hearing Waiver Form - the Nuclear Management Company, LLC ML0634705992006-12-14014 December 2006 Plant Service List ML0627903812006-09-29029 September 2006 Exhibit 26 to Case No. 2-2002-004, Interview Report ML0626801502006-09-22022 September 2006 Escort Ratio for Visitors ML0626503122006-09-0101 September 2006 Liquid Radiation Release Lessons Learned Task Force Final Report (Enclosure) ML0626504142005-11-0303 November 2005 RIII-2005-A-0062 Closure ML0626802782005-08-29029 August 2005 3rd ARB Action Plan RIII-05-A-0062 (Point Beach) ML0626802752005-08-22022 August 2005 2nd ARB Action Plan, RIII-05-A-0062 (Point Beach) ML0626504072005-07-19019 July 2005 Action Request - Corrective Action Program (CAP) ML0626802642005-07-18018 July 2005 Initial ARB Action Plan RIII-05-A-0062 (Point Beach) ML0518603982005-07-15015 July 2005 NRC Actions Under the Reactor Oversight Process for the Point Beach Nuclear Plant, Units 1 and 2 ML0518903972005-07-0101 July 2005 Log Entries Report ML0518903962005-07-0101 July 2005 U1R28 Outage Risk Plan Ppg Outage Management ML0518903952005-07-0101 July 2005 U1R28 Add/Delete Log ML0626504032005-06-22022 June 2005 Action Request - Corrective Action Program (CAP) (CAP065250) ML0626503992005-06-10010 June 2005 Action Request - Corrective Action Program (CAP) (CAP065041) ML0626504012005-06-10010 June 2005 Action Request - Corrective Action Program (CAP) (CAP065035) ML0515202282005-05-24024 May 2005 EP FFD Questions Not Asked ML0514700842005-05-24024 May 2005 COLR 28 Replaced with COLR 29 Prior to Vessel Removal. Attach: 04/14/2004 Condition Evaluation 013784. Attach: 04/12/2004 CAP 055612. Attach: Undated Bullet Nose Disconnected & Removed with Head ML0515202262005-05-24024 May 2005 2SI-825B Not Full Open with Handwritten Notations ML0515202242005-05-24024 May 2005 Phone Line Through Containment Hatch While Fuel Movement in Progress ML0515202232005-05-24024 May 2005 Loss of SFP Cooling Due to Breaker Miss Alignment ML0515202212005-05-24024 May 2005 2SI-825B Not Full Open with Handwritten Notations ML0515202192005-05-24024 May 2005 U1R28 Interim Exit Meeting Notes ML0515202182005-05-24024 May 2005 Tsac Not Entered When Source Range Audible Count Rate Removed from Service ML0515202072005-05-24024 May 2005 Questions for Followup Based on Last Outage ISI Summary Report ML0514700772005-05-24024 May 2005 Refuel Outage 1R28 Resident Inspector Coverage ML0514700822005-05-24024 May 2005 Mikes 2004-03 IR Section Write Ups, 2T-34A Accumulator Level Indication ML0515201472005-05-24024 May 2005 Phone Line Through Containment Hatch While Fuel Movement in Progress ML0515202132005-05-24024 May 2005 Inservice Inspection Document Request ML0515201492005-05-24024 May 2005 Transient Combustible Materials in Containment & Turbine Building Without Administrative Controls 2022-02-16
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-NMC-Comirrned lo Nuclear Excellence Point Beach Refueling Outage Edition
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CONTACT INFORMATION Control Room Emergency - x2911 Work Control Center - x6703 OCC - x 7190 - Option I I) Lessons Learned - x7190 - Option 2 Plant Status - x7190 - Option 3 Accomplishments
. Completed RCS Fill & Vent Activities IAW OP-4A
. 1P-1A Reactor Coolant Pump Balance Weight Move
. Restored Containment Upper Hatch Interlocks
. Post Fill and Vent Valve Line Up a Started I P-1A Reactor Coolant Pump
. Started 1W-3B Control Rod Drive Shroud Fan
. Silica Dilution and Heat Up RCS to 1650 F Personnel Last 24 Hours Outage to . IT-3B Low Head Safety Injection Valve Safety Date . Start 1P-1 B Reactor Coolant Pump Recordable - 0 Recordable- I' I Disabling - 0 Disabling - 0
- OSHA Recordable - Back strain. Schedule Focus AreaslPriorities
. Continue Containment Purge Work
. TS-30 High & Low Head SI Check Valve Test
. Heatup RCS to 190OF
. Cold Rod Functional Testing V- (0I Inrormabon inths record was d Wd inaccordance with th Froieom of htrmf Act, exempt s, ;i..
Ni, 0 ea a;z-dom
'! I: I 1.
". ' . June 1, 2004 OUTAGE GOALS NUCLEAR SAFETY GOAL ACTUAL HUMAN PERFORMANCE GOAL ACTUAL PERFORMANCE GOA_ ACUA Unplanned orangelred paths None None Security Violations X l12 loggable events 3 Reactor trips (either unit) None 1 Station human performance dock l None 4 Safeguards actuation (either unit) None None Rework _ __ _% l On Goal Loss of shutdown cooling None None SCHEDULE PERFORMANCE Outage Duration Loss of Rx vessel level control None None (excludes extensions due to s 30 days Off Goal extended head or BMI Inspections)
INDUSTRIAL SAFETY Mod Implementation 100% of Rev 0 On Goal PERFORMANCE
> 85% schedule Lost time accidents None None Schedule Compliance compliance with Off Goal outage milestone Personnel injuries (OSHA recordable) None 1 Emergent work (during s2%late additions On Goal Implementation) s 5%Emergent RADIOLOGICAL PERFORMANCE Scope Complete 2 95% of On Goal
____ ____ ____ __ .Rev 0 scope Radiation exposure (Excludes additional 100% of Scheduled dose from any head or BMI repair s 92 R 85.325 R Operator Burdens Operator Burdens On Goal contingencies) complete Personnel contaminations 5K CPMWI I1 Post Outage availability Bcontinuous ct150 days of operation Available alater dateat Radiological events (defined as unplanned uptake w/assigned dose >10 mrem or s1 event 1 BUDET ERFRMACE Within -2%to 0%of Seriously BUGTPRFR AC outage budget Challenged dose event based on ED alarms Radmaterial event (defined as any rad <1 event 0 material outside RCA ! 100 CPM)
Operating Experience OE1 8340 - A HHSI pump Flushing Line Isolation Valve outside the Containment Was Found Partially Open On March 26, 2004 during performance of High Head Safety Injection (HHSI) Pump I B Inservice Test in Unit 1, HHSI pump 18 flushing line isolation valve (SI-0120B) was found partially open. If this valve were to be open during a postulated Loss Of Coolant Accident (LOCA), the resulting release from the Safety Injection (SI) System would cause the General Design Criterion (GDC) number 19 (Control Room Operator Dose Limits) and the 10CFR100 offsite dose limits to be exceeded.
Lessons Learned: The importance of personnel exercising caution around plant equipment to avoid accidental mispositioning that could result In exceeding the Control Room Operator and the IOCFR100 offsite dose limits during a postulated LOCA.
Human Performance Seek first to understand:
An individual was preparing to attend atraining class when he got a call from another NMC plant requesting assistance with a problem. Missed training had been a problem in his department but helping another site was also a high priority. The PBNP employee decided to get the information that the other site needed and showed up 24 minutes late for training (a department HU clock reset). He should have used the Stop When Unsure tool and contacted his supervisor for direction.
Training can be missed with appropriate management approvals.
Safety Snippet If your backfield is in motion, use a zone defense Contract electrician was pulling wire for a conduit through ajunction box for the security upgrade project. While bending over to retrieve a pull string, the wind caught the junction box door. It swung and struck the employee in the back.