ML112440117
| ML112440117 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 09/01/2011 |
| From: | Eugene Dipaolo NRC/RGN-I/DRP/PB6 |
| To: | Pacilio M Exelon Nuclear, Exelon Generation Co |
| dipaolo, em | |
| References | |
| IR-11-006 | |
| Download: ML112440117 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PENNSYLVANIA 19406.1415 Septennber L, 2OI1, Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer (CNO), Exelon Nuclear 4300 Winfield Rd.
Warrenville, lL 60555
SUBJECT:
MID-CYCLE LETTER FOR OYSTER CREEK NUCLEAR GENERATING STATION (REPORT 0500021 9/201 1 006)
Dear Mr. Pacilio:
On August 9,2011, the NRC completed its mid-cycle performance review of the Oyster Creek Nuclear Generating Station. The NRC reviewed the most recent quarterly performance indicators (Pls) in addition to inspection results and enforcement actions from July 1,2010 through June 30, 2011. This letter informs you of the NRC's assessment of your facility during this period and its plans for future inspections at your facility. This performance review and enclosed inspection plan do not include security information. A separate letter will include the NRC's assessment of your performance in the Security Cornerstone and its security-related inspection plan.
The NRC determined the performance at Oyster Creek during the most recent quarter was within the Licensee Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix because all inspection findings had very low (i.e., green) safety significance, and all Pls indicated that your performance was within the nominal, expected range (i.e., green).
Therefore, the NRC plans to conduct ROP baseline inspections at your facility.
The NRC evaluates cross-cutting themes to determine whether a substantive cross-cutting issue exists in a particular area and to encourage licensees to take appropriate actions before more significant performance issues emerge. Regarding Oyster Creek, the staff identified that there were five Green findings for the current twelve month assessment period with a documented cross-cutting aspect in the Human Performance cross-cutting area, and that there was a common cross-cutting theme associated with these findings. Specifically, the theme was associated with procedure adequacy, which was the most significant contributor to the five Green findings H.2(c).
In evaluating the scope of efforts and progress in addressing the cross-cutting theme, the NRC staff determined that Exelon has recognized the cross-cutting theme and has initiated action to develop an improvement plan. Therefore, the staff has determined that a substantive cross-cutting issue in the Human Performance cross-cutting area does not exist at this time. We will monitor your progress in the Human Performance cross-cutting area through the baseline inspection program, including a focused review of your proposed corrective action plan.
M. Pacilio 2
The enclosed inspection plan lists the inspections scheduled through December 31,2012. ln addition to baseline inspections, we also plan to conduct lnspection procedure (lp) 60g55.1, Operation of an ISFSI lndependent Fuel Storage lnstallation at Operating Plants in November 2012' Routine inspections performed by resident inspectors are not included in the inspection plan' The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle pbrformance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.
ln the days following the Fukushima Daiichi nuclear accident in Japan, the Commission directed the staff to establish a senior-level agency task force to conduct a methodical and systematic review of the NRC's processes and regulations to determine whether the agency should make additional improvements to its regulatory system. The NRC has since comptete-O Temporary lnstruction (Tl) 183, "Follow-up to Fukushima Daiichi Nuclear Station Fuel Damage Event," ind T-l-]_8_1 "Availability and Readiness Inspection of Severe Accident Management Guidelines (sAMGs)" at your facility. Results of these inspections can be found here:
hltp://WyYw.Irc.gov/iapan/iapan-activities.html.
Additionally, on May 1 1,2011, the agency issued NRC Bulletin 2011-01, "Mitigating Strategies," to confirm compliance with Order en-OZ-026, subsequently imposed license conditions, and 10 CFR 50.54(hhx2), and to determine the status of licensee mitigating strategies programs. On July 12, 2011, the NRC's Task Force made its recommendations to the Commission in its report, "Recommendations for Enhancing fe.actol Safety in the 21't Century: The Near-Term Task Force Review of lnsights from the Fukushima DaiichiAccident." The NRC is currently reviewing the Task Forceb recommendations to determine what additional actions may be warranted.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at hitp:/iwww.nrc.sov/readins-rm/adams.html (the Public Electronic Reading Room).
Please contact me at 610-337-5046 with any questions you have regarding this letter.
Sincerely, q^/il4. /t/v Eugene M. DiPaolo, Acting Chief Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-219 License Nos: DPR-16
Enclosure:
Inspection Plan cc w/encl: Distribution via ListServ
M. Pacilio The enclosed inspection plan lists the inspections scheduled through December 31,2012. ln addition to baseline inspections, we also plan to conduct lnspection Procedure (lP) 60855.1, Operation of an ISFSI Independent Fuel Storage Installation at Operating Plants in November 2012. Routine inspections performed by resident inspectors are not included in the inspection plan. The inspections listed during the last nine months of the inspection plan are tentative and may be revised at the end-of-cycle performance review. The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnel availability issues. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.
In the days following the Fukushima Daiichi nuclear accident in Japan, the Commission directed the staff to establish a senior-level agency task force to conduct a methodical and systematic review of the NRC's processes and regulations to determine whether the agency should make additional improvements to its regulatory system. The NRC has since completed Temporary lnstruction (Tl) 183, "Follow-up to Fukushima Daiichi Nuclear Station Fuel Damage Event," and Tl-184, "Availability and Readiness lnspection of Severe Accident Management Guidelines (SAMGs)" at your facility. Results of these inspections can be found here:
http://www.nrc.qov/iapan/iapan-activities.html. Additionally, on May 1 1,2011, the agency issued NRC Bulletin 2011-01, "Mitigating Strategies," to confirm compliance with Order EA 026, subsequently imposed license conditions, and 10 CFR 50.54(hhx2), and to determine the status of licensee mitigating strategies programs. On July 12,2011, the NRC's Task Force made its recommendations to the Commission in its report, "Recommendations for Enhancing Reactor Safety in the 21st Century: The Near-Term Task Force Review of lnsights from the Fukushima DaiichiAccident." The NRC is currently reviewing the Task Force's recommendations to determine what additional actions may be warranted.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be made available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRC's document system (ADAMS). ADAMS is accessible from the NRC Web site at http:i/wurw.nrc.qov/readinq-rm/adams.html (the Public Electronic Reading Room).
Please contact me at 610-337-5046 with any questions you have regarding this letter.
Sincerely,
/RA/
Eugene M. DiPaolo, Acting Chief Projects Branch 6 Division of Reactor Projects Docket Nos.: 50-219 License Nos: DPR-16
Enclosure:
Inspection Plan cc w/encl: Distribution via ListServ Distribution: See attached page SUNSI Review Complete: CWN (Reviewer's Initials)
DOCUMENT NAME:S:\\ROP-12 MID-CYCLE REVIEMBMNCH 6\\OC\\OC ROP-12 MC COVER LTR.DOCX After declaring this document "An Official Agency Record" it will be released to the Public.
ML112440117 in the box: "C" = Coov without attachmenvenclosure "E" =
OFFICE mmt RI/DRP RI/DRP NAME CNewporUCWN EMDiPaolo/ EMD DATE 08t31 t11 09t01 t11
.N. = No copy
M. Pacilio Distribution Wencl:
W. Dean, RA D. Lew, DRA D. Roberts, DRP J. Clifford, DRP C. Miller, DRS P. Wilson, DRS R. Bellamy, DRP G. Barber, DRP C. Newport, DRP N. Lafferty, DRP A. Dugandzic, DRP J. McHale, Rl OEDO J. Kulp, DRP, SRI J. Ambrosini, DRP, Rl J. DeVries, DRP, OA DRS Branch Chiefs (6)
N. McNamara, Rl, SLO D. Tifft, Rl, SLO D. Screnci, Rl, PAO N. Sheehan, Rl, PAO R. Barkley, Rl, ORA RidsNrrPMOysterCreek Resource Rids N rrDorlLpll -2 Resou rce ROPreports Resources RidsNrrDirsl pab Resource ROPassessment Resource
Page 1 of 2 08/03/2011 08:38:41 Report 22 Oyster Creek Inspection / Activity Plan 07t0'1t2011 - 12t31t2012 No. of Staff on Site 07 t11t2011 07 t2012011 O7l11EXM. OPERATOR LICENSING INITIAL EXAMS U01831 FY11-OYSTER CREEK, INITIAL OL EXAM HP.71'124. INSTRUMENTS/REMP/ISFSI lP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants lP 71124.05 Radiation Monitoring Instrumentation lP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment lP 71124.07 Radiological Environmental Monitoring Program T1.177
. MANAGING GAS ACCUMULATION IN ECCS lP 2515t177 Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal & Containment Spray System EP EX
. EP EXERCISE EVALUATION lP 7111401 Exercise Evaluation lP 7111404 Emergency Action Level and Emergency Plan Changes lP 7'l 151-EP01 Drill/Exercise Performance lP 71151-EP02 ERO Drill Particioation lP 71151-EP03 Alert & Notification System HP.7 1 124. ACCESS/ALARA/AIR/DOSE/INSTRU MENTS/PI lP 71124.01 Radiological Hazard Assessment and Exposure Controls lP 71124.02 Occupational ALARA planning and Controls lP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation lP 71124.04 Occupational Dose Assessment lP 71124.05 Radiation Monitoring Instrumentation lP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation lP 71 151-OR01 Occupational Exposure Control Effectiveness lP 71 151-PR01 RETS/ODCM Radiological Effluent 5/14EXAM. OYSTER CREEK INITIAL OL EXAM U01848 FY12-OYSTER CREEK INITIAL OPERATOR LICENSING EXAM U01848 FY12-OYSTER CREEK INITIAL OPERATOR LICENSING EXAM 7111117. PERMANENT PLANT MODS lP 7111117T Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications lP 71'11117f Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications 7111107T. TRIENNIAL HEAT SINK lP 7111107f Heat Sink Performance INSP
. ACCESS/ALARA/AIRBORNE/DOSE ASSESS lP 2515t175 Emergency Response Organization, Drill/Exercise Performance lndicator, Program Review 1
1 1
1 1
1 1
1 1
07 t11t2011 07 t11t2011 07t11t20'11 07t11t2011 09t12t2011 0912612011 09t26t2011 09t26t2011 09t26t2011 09t26t2011 10t17t2011 10t17t2011 10t17 t2011 10t17t2011 10t1712011 10t17 t2011 10t17 t2011 10t17t2011 04t16t2012 05t14t2012 01123t2012 02t06t2012 07t1512011 07 t1512011 07 t'1512011 07t15t2011 09t16t2011 09t3012011 09t30t2011 09t30t2011 0913012011 09t3012011 10t21t2011 10t21t2011 10t21t2011 10t21t2011 10t2112011 10t21t2011 10t21t2011 10t21t2011 04t20t2012 05t18t2012 01t27t2012 02t10t2012 1
1 1
1 4I 1
1 1
02t27t2012 0310212012 03t12t2012 0311612012 flhis report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.
Page 2 oi 2 OBl03l2O11 08:38:41 Report 22 Oyster Creek Inspection / Activity Plan 0710112011 - 12t3112012 I unit h l-P{anned lHumuer$ Start DateJ i No. of Staff b End E lnsptction Actinitt b T
on Site B 1
1 1
1 1
1 1
I 03t12t2012 03t12t2012 03t12t2012 03t12t2012 07t1612012 07t1612012 0711612012 07t16t2012 08t1312012 0812712012 08t27t2012 0812712012 08t27t2012 08t27t2012 0s110t2012 09t10t2012 09110t2012 10t22t2012 11112t2012 11t12t2012 11t12t2012 11t12t2012 11t12t2012 11t12t2012 Comments:
03t16t2012 03t16t2012 03t16t2012 03t16t2012 07t20t2012 07t20t2012 07t20t2012 07t20t2012 08t17t2012 0813112012 08t31t2012 08t31t2012 08t31t2012 08t31t2012 Osh4t2012 09t14t2012 09t14t2012 10t2612012 11t16t2012 11t1612012 11t16t2012 11t16t2012 11t16t2012 11t16t2012 INSP tP 71',t24.01 lP 71124.02 lP 71124.03 lP 71124.04 INSP lP 71124.01 lP 71124.02 lP 71124.05 tP 71124.06 711528 lP 711528 lP 711528 EP PROGR.
lP 7111402 lP 7111403 lP 7111404 lP 7111405 INSP lP 71124.01 tP 71124.05 tP 71124.06 71 1 1 108G tP 71 11108G INSP lP 60855.1 tP 71124.01 lP 71124.02 tP 71124.03 tP 71124.05 lP 71151-PR01 ACCESS/ALARA/AIRBORNE/DOSE ASSESS Radiological Hazard Assessment and Exposure Controls Occupational ALAM Planning and Controls In-Plant Airborne Radioactivity Control and Mitigation Occuoational Dose Assessment ACCESSIALARA/I NST/EFF LU ENTS Radiological Hazard Assessment and Exposure Controls Occupational ALAM Planning and Controls Radiation Monitoring Instrumentation Radioactive Gaseous and Liquid Effluent Treatment PI&R Problem ldentification and Resolution Problem ldentification and Resolution EP PROGRAM INSPECTION Alert and Notification System Testing Emergency Preparedness Organization Stafiing and Augmentation System Emergency Action Level and Emergency Plan Changes Correction of Emergency Preparedness Weaknesses and Deficiencies ACCESS/INST/EFFLUENTS Radiological Hazard Assessment and Exposure Controls Radiation Monitoring Instrumentation Radioactive Gaseous and Liquid Effluent Treatment INSERVICE INSPECTION Inserviie Inspection Activities - BWR ACC ESS/ALARA/AIR/I NST/ISFSIIPI VERIF Operation of an Independent Spent Fuel Storage Installation at Operating Plants Radiological Hazard Assessment and Exposure Controls Occupational ALARA Planning and Controls In-Plant Airborne Radioactivity Control and Mitigation Radiation Monitoring Instrumentation RETS/ODCM Radiological Effluent 1
1 1
1 1
1 1
ifhis report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.