ML112411354
| ML112411354 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 09/01/2011 |
| From: | Paul Krohn Reactor Projects Region 1 Branch 4 |
| To: | Pacilio M Exelon Nuclear, Exelon Generation Co |
| KROHN PG | |
| References | |
| IR-11-006 | |
| Download: ML112411354 (6) | |
Text
UNITED STATES N UCLEAR REGU LATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA. PA 19406-1415 September 1, ZOLI Mr. Michael J. Pacilio Senior Vice President, Exelon Generation Company, LLC President and Chief Nuclear Officer. Exelon Nuclear 4300 Winfield Rd.
Warrenville, lL 60555
SUBJECT:
MID-CYCLE LETTER FOR LIMERICK GENERATING STATION (05000352 t201 1006 and 05000353t2011 006)
Dear Mr. Pacilio:
On August 9,2011, the U.S. Nuclear Regulatory Commission (NRC) NRC completed its mid-cycle performance review of the Limerick Generating Station Units 1 and2. 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 performan@ 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 Limerick Units 1 and2 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 enclosed inspection plan lists the inspections scheduled through December 31,2012.
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. In addition to the baseline inspection program, we plan to conduct Inspection Procedure (lP) 60855, "Operation of an lSFSli' lP 71002, "Licensee Renewal Inspection;" and Temporary Instruction (Tl) Tl-177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)." From July 1, 2010, to June 30, 2011, the NRC issued one severity level lV (SLIV) traditional enforcement non-cited violation associated with impeding the regulatory process (ML10357012q.1 Therefore, the NRC also plans to conduct lP 92702 to follow-up on this violation. The NRC will contact you as soon as possible to discuss changes to the inspection plan should circumstances warrant any changes.
' Designation in parenthesis refers to an ADAMS accession number. Documents referenced in this letter are publicly available using the accession number in ADAMS.
M. Pacilio 2
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 Inspection of Severe Accident Management Guidelines (SAMGs)," at your facility. Results of these inspections can be found here:
http://www.nrc.qov/iapan/iapan-ac!_v-ities.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 Insights from the Fukushima Daiichi Accident." The NRC is currently reviewing the Task Force's recommendations to determine what additional actions may be warranted.
ln accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be 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 httpl//www.nrc.qov/readino-rm/adams.hlml (the Public Electronic Reading Room).
Please contact me at (610) 337-5120 with any questions you have regarding this letter.
Sincerely,fr/-* ru Paul G. Krohn, Chief Division of Reactor Projects Projects Branch 4 Docket Nos. 50-352, 50-353 License Nos. NPF-39, NPF-85
Enclosure:
lnspection Plan cc w/encl: Distribution via ListServ
M. Pacilio 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 Instruction (Tl) 183, "Follow-up to Fukushima Daiichi Nuclear Station Fuel Damage Event," and Tl-184, "Availability and Readiness Inspection of Severe Accident Management Guidelines (SAMGs)," at your facility. Results of these inspections can be found here:
http://www.nrc.qoviiapan/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 will be 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/wvn4r.nrc.qovlreadinq-rm/adams.html (the Pubtic Electronic Reading Room).
Please contact me at (610) 337-5120 with any questions you have regarding this letter.
Sincerely,
/RA/
Paul G. Krohn, Chief Division of Reactor Projects Projects Branch 4 Docket Nos. 50-352, 50-353 License Nos. NPF-39. NPF-85
Enclosure:
lnspection Plan cc w/encl: Distribution via ListServ Distribution: See attached page SUNSI REVIEW COMPLETE: AAR (Reviewer's Initials)
DOCUMENT NAME: S:\\ROP-12 MID-CYCLE REVIEMBRANCH 4\\LIM\\LIMERICK MID-CYCLE ASSESSMENT LETTER.DOCX After declaring this document "An Official Agency Record" it will be released to the Public.
To receive a copy of this document, indicate in box:"C" = Copy w/o attachment/enclosure, E' = Copy M attachmenl/enclosure"N"=No copy
)FFICE mmt RI/DRP 1I/DRP
?/DRP
{AME iDiPaolo/ AAR for*
MRosebroold AAR*
rGKrohn/ PGK
)ATE
,115t11 08t15t11
)8t18t11
- See Previous Concurrence OFFICIAL RECORD COPY ML112411354
M. Pacilio Distribution w/encl:
W. Dean, RA (RIORAMAIL Resource)
D. Lew, DRA (RIORAMAIL Resource)
D. Roberts, DRP (RIDRPMAIL Resource)
J. Clifford, DRP (RIDRPMAIL Resource)
C. Miller, DRP (RlDRSMail Resource)
P. Wilson, DRS (RlDRSMail Resource)
P. Krohn, DRP A. Rosebrook. DRP R. Montgomery, DRP S. lbarrola, DRP E. DiPaolo, DRP, SRI N. Sieller, DRP, Rl N. Esch, DRP, Admin Asst.
J. McHale, Rl, OEDO DRS Branch Chiefs (6)
N. McNamara, Rl, SLO D. Tifft, RI. SLO D. Screnci, Rl, PAO N. Sheehan, Rl, PAO R. Barkley, Rl, ORA RidsNrrPMLimerick Resource RidsNrrDorlLpll -2 Resource ROPreports Resource RidsNrrDirslpab Resource ROPassessment Resource
Page 1 ol 2 081171201'1 15:17:16 Report 22 Limerick Inspection / Activity Plan 0710112011 - 1213112012 No. of Staff on Site Unit Number 1.2 1,2 1,2 1,2 07t18t2011 08/08/201 1 09t12t2011 09t19t2011 09t26t2011 10t17t2011 10t31t2011 10t31t2011 11t1412011 11t14t2011 11t14t2011 11t14t2011 11t14t2011 11t14t2011 01t09t2012 01t09t2012 01t09t2012 02127t2012 03t05t2012 0310512012 03t05t2012 o9t30t2011 10t21t2011 11t04t2011 11t04t2011 11t18t201'l 11t18t2011 11t18t2011 11t18t20',t1 11t18t2011 1111812011 01t13t2012 o1t13t2012 o1t'13t2012 0310212012 03t09t2012 03t09t2012 03togt2012 lP 7111401 tP 7111404 tP 71 151-EP01 tP 71151-EP02 tP 71151-EP03 60855.1.ISFSIOPERATIONINSPECTION 07t23t2011 lp 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants TI-177
. MANAGING GAS ACCUMULATION IN ECCS Ogl12t21.l1 lp 2515t177 Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal & Containment Spray System 92702
. FOLLOW.UP FOR UFSAR SLIV NCV 09t1412011 lp 92TOZ Followup On Conective Actions For Violations And Deviations 7111107T - TRIENNIAL HEAT SINK 0912312011 lP 71111071 Heat Sink Performance 71124
. REMP tP 71124.07 Radiological Environmental Monitoring Program 7111117. PERMANENT PLANT MODIFICATIONS lp 71111171 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications lp 7111117T Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications 71124
. EFFLUENTS lP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment EP EX
. EP EXERGISE EVALUATION Exercise Evaluation Emergency Action Level and Emergency Plan Changes Drill/Exercise Performance ERO Drill Participation Alert & Notification System 1,2 1,2 1,2 I,Z 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1
1,2 1,2 1,2
. OCC RAD SAFEW - INSTRUMENTS Radiation Monitoring I nstrumentation
- OCC RAD SAFETY Radiological Hazard Assessment and Exposure Controls Occupational ALARA Planning and Controls Occuoational Dose Assessment 7111108G - TNSERVTCE INSPECTION Inservice Inspection Activities - BWR
. ACCESS/ALARA/AI RBORNE RADIOACTIVITY Radiological Hazard Assessment and Exposure Controls Occupational ALARA Planning and Controls In-Plant Airborne Radioactivity Control and Mitigation 71124 tP 71124.05 71124 tP 71124.01 lP 71124.02 lP 71124.04 tP 7111108G 71124 tP 71124.01 lP 71124.02 tP 71124.03 fhis report does not include INPO and oUTAGE activities.
This report shows only on-site and announced inspection procedures.
Page 2 ol 2 0811712011 15:17:16 Report 22 Limerick Inspection / Activity Plan 07t0112011 - 1213112012 No. of Staff on Site Unit Number 1,2 1,2 1
1 1,2 I,Z 1,2 1,2 1,2 1,2 I,Z 1,2 1,2 1,2 1,2
't,2 71002
- LR TNSPECTION OBlO4l2O12 0610812012 lP 71002 License Renewal lnspection 0611812012 0612212012 lP 71002 License Renewal Inspection 1O/O8EXM. LIMERICK INITIAL EXAM o9t1ot2o12 09t14t2012 U01858 FY13-LTMERICK lNlTlAL OPERATOR LICENSING EXAM 1OtO8t2O12 10t19t2012 U01858 FY13-LIMERICK lNlTlAL OPERATOR LICENSING EXAM 71124
-RW 06111t2012 O6t1St2O12 lP 71'124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 7111121 - CDBI 0812712012 0813112012 lP 7111121 Component Design Bases lnspection 0911012012 Ogl14l2!12 lP 7111121 Component Design Bases lnspection Ogt24l2,12 0912812012 lP 7111'121 Component Design Bases Inspection 71111118. LIMERICK ON-SITE RQL INSP WIP/F RESULTS 1Ol2Sl2O12 1110212012 lP 71111118 Licensed Operator Requalification Program 711528 - Pt&R 10t22120'12 1012612012 lP 711528 Problem ldentification and Resolution 11t0512012 1110912012 lP 711528 Problem ldentification and Resolution EP PROGR. EP PROGRAM INSPECTION
'l2lj3l2\\12 1210712012 lP 7111402 Alert and Notification System Testing 1210312012 12t0712012 lP 7111403 Emergency Preparedness Organization Staffing and Augmentation System 12t0312012 1210712012 lP 7111404 Emergency Action Level and Emergency Plan Changes 12103t2012 12t0712012 lP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 71124
. OCC RAD SAFETY 12t1012O12 12114t2012 lP 71124.01 Radiological Hazard Assessment and Exposure Controls
'his report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.