ML112420788

Mid-Cycle Performance Review and Inspection Plan 2011 - R. E. Ginna Nuclear Power Plant

ML112420788
Person / Time
Site:	Ginna
Issue date:	09/01/2011
From:	Darrell Roberts Division Reactor Projects I
To:	Joseph Pacher Ginna
References
IR-11-006
Download: ML112420788 (5)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PA 19406-1415 September 1, 2OIl Mr. Joseph E. Pacher, Vice President R. E. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519

SUBJECT:

MID.CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN -

R. E. ctNNA NUCLEAR POWER PLANT (REPORT 05AA024412011006)

Dear Mr. Pacher:

On August 10,2011, the U.S. Nuclear Regulatory dommission (NRC) completed its mid-cycle perforriance review of R. E. Ginna Nuclear Power Flant (Ginna). The NRC reviewed the most iecent quarterly performance indicators (Pls) in adQition to inspection results and enforcement actions irom .tuty 1,2010, through June 30, 2011. llhis letter informs you of the NRC's assessment of your facility during this period and itE plans for future inspections at your facility.

This performante review and enclosed inspection plan do not include security information' A separate letter will include the NRC's assessment 0f your performance in the Security Cornerstone and its security-related inspection plart.

The NRC determined the performance at Ginna during the most recent quarter was within the Regulatory Response Column of the NRC's ReactQr Oversight Process (ROP) Action Matrix bejause att inspection findings had very low (i.e., green) safety significance, and there was one White pl in the Mitigating Systems Cornerstone. The White Pl was related to exceeding the White significance t-nresnod for the Mitigating Systems Performance Index (MSPI)' Heat RemovaT Systems pl, since the third quarter2Oog, due to reliability issues associated with the auxiliary feedwater (AFW) system, specifically the turbine-driven (TD) AFW pump. Becau.se the White Fl *as inspected usin'g lp 95002, the NRC determined that no additional agency follow-up beyond the baseline inspection program is necessary. The plant will remain in the plans to R'egulatory Response Column untilthe White Pl returns to Green. Therefore, the NRC conduct ROP baseline inspections at your facility.

The enclosed inspection plan lists the inspections scheduled through December 31,2012.

plan.

Routine inspections performed by resident inspectors are not included in the inspection The inspeciions listed during the last nine months of the inspection plan are tentative and may plan to_

be revised at the end-of-cycle performance review. The NRC provides the inspection allow for the resolution of iny 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 establisli a senior-level agency task fofce to conduct a methodical and systematic review of the NRC's processes and regulations tordetermine whether the agency should make additional improvements to its regulatory system.The NRC has since completed Temporary lnstruction (TI) 1g3, "Follow-up tJfutuinima Daiichi Nuclear Station Fuel Damage Event," and

J. Pacher 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.oov/iapan/japan-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 it$ report, "Recommendations for Enhancing Reactor Safety in the 21't Century: The Near-Term Task Force Review of Insights 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://www.hrc.qov/readinq-rm/adams.html (the Public Electronic Reading Room).

Pfease contact Glenn Dentel at (610) 337-5233 with any questions you have regarding this letter.

Darrell J. R . Director Docket No. 50-244 License No. DPR-18

Enclosure:

Ginna lnspection / Activity Plan cc Mencl: Distribution via ListServ

J. Pacher 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-activities.html. Additionally, on May 11,2011, the agency issued NRC Bulletin2011-01, "Mitigating Strategiesi" 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 21't Century: The Near-Term Task Force Review of Insights from the Fukushima DaiichiAccident." The NRC is currently reviewing the Task Force's recommendations to determine what additionalactions 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://www.rtrc.qov/readins-rm/adams.html (the Public Electronic Reading Room).

Please contact Glenn Dentel at (610) 337-5233 with any questions you have regarding this letter.

Sincerely, IRAI Darrell J. Roberts, Director Division of Reactor Projects Docket No. 50-244 License No. DPR-18

Enclosure:

Ginna Inspection / Activity Plan Distribution dencl: (via E-mail)

W. Dean, RA N. Perry, DRP N. Sheehan, PAO D. Lew, DRA J. Hawkins, DRP R. Barkley, OM D. Roberts. DRP K. Cronk, DRP N. McNamara, SLO J. Clifford, DRP N. Floyd, DRP D. Tift, SLO C. Miller. DRS G. Hunegs, DRP, SRI ROPassessment Resource P. Wilson, DRS D. Dodson, DRP Rl RidsNrrDirslpabResource J. McHale, Rl OEDO M. Rose, DRP, OA RidsNrrPMREGlnna Resource G. Dentel. DRP DRS Branch Chiefs (6) RidsNrrDorlLpll -1 Resource D. Screnci, PAO ROPreportsResource@nrc.gov SUNSI Review Gomplete: GTD (Reviewer's Initials) MLl12420788 DOCUMENT NAME: S:\ROP-l2 Mid-Cycle Review\Branch l\GlN MC LTR 2011.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 the box: "C" = Copy without attachmenuenclosure "E" = Copy with attachmenuenclosure "N" = No coPY CFFICE /hp RI/DRP IN tI/DRP RI/DRP NAME NSPerry/NSP 3TDentel/GTD DJRoberts/DJR

)ATE Jgt18t11 )8t18t11 18/30/1 1 OFFICIAL R :CORD COPY

Page 1 of 2 Ginna AA29l2Af 15:30:59 Inspection / Activity Plan Report 22 07101t2011 - 1213112012 Unit No. of Staff Number on Site 1124.06 - RETS 71124.06 1 09t12t2011 09t16t2011 tP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants 1 a9n212011 0911612011 tP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment 1 09t12t2011 09/16/2011 rP 71151-OR01 Occupational Exposure Conhol Effectiveness I 09t12t2011 09/16/201 1 lP 71151-PRo1 RETS/ODCM Radiological Effluent 7'111107T - TRIENNIAL HEAT SINK 09t26t2011 09/30/2011 tP 71111077 Heat Sink Performance 7111117 - PERMANENT PLANT MODIFICATIONS 10t03t2011 10t0712011 lP 71111177 Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications 10t17t2011 10t2112011 lP 711111TT Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications EP EX . EP EXERCISE EVALUATION I 1012412011 1012812011 lP 71'11401 Exercise Evaluation 1 1012412011 1012812011 lp 7111404 Emergency Action Level and Emergency Plan changes I 1012412011 1Ol2Bl2O11 lP 71 151-EP01 Drill/Exercise Performance 1 1012412011 1012812011 lP 71151-EP02 ERO Drill Pa(icipation I 1012412011 1012812011 lP 71151-EP03 Alert & Notification System 7't124 - RADTATION SAFEW INSPECTIoN 1 02113t2012 02t17t2012 tP 71124.02 occupational ALARA Planning and controls I 0211312012 02t17t2012 lp 71124.03 In-Plant Airborne Radioactivity control and Mitigation I 0211312012 Ail1712012 lP 71124.04 occupational Dose Assessment T1.177 - MANAGING GAS ACGUMULATION IN ECCS 02113t2012 0211712012 lp 2s1st177 Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal & Containment Spray System 711528 - Pl&R O4tO9l2O12 04t13t2012 lP 711528 Problem ldentification and Resolution 0412312012 0412712012 lP 711528 Problem ldentification and Resolution lO/lEXM . GINNA INITIAL EXAM OgIOgI2Ol2 O}IO7I2O12 U01857 FY13-GINNA INITIAL OPERATOR LICENSING EXAM 1OIO1I2O12 1OIO5I2O12 U01857 FY13-GINNA INITIAL OPERATOR LICENSING EXAM TRI FI - TRIENNIAL FIRE PROTECTION INSPECTION Aglfilz112 Ogl14l2112 lp 7'l111OSp Fire Protection-NFPA 805 Transition Period [Triennial]

Ogt24l2O1Z Ogl2BlZOl2 tp 71111g5p Fire Protection-NFPA 805 Transition Period [Triennial]

EP PROGR - EP PROGRAM INSPECTION Ogt17t2\12 Ogt21t2}12 lP 7111402 Alert and Notification System Testing ogt17l2o12 ogl21l2o12 lp 71 11403 Ernergency Preparedness organization Staffing and Augmentation System this report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection proceclures.

Page 2 ot 2 Ginna 0812912011 15:30:59 Inspection / Activity Plan Report 22 07t01t2011 - 1213112012 Unit No. of Staff Number on Site EP PROGR . EP PROGRAM INSPECTION 0911712012 0912112012 tP 7111404 Emergency Action Level and Emergency Plan Changes 09t1712012 0912112012 tP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 71111118 - GINNA ON-SITE RQL INSP w/ P/F RESULTS 11t12t2012 1111612012 tP 71111118 Licensed Operator Requalification Program fhis report does not include INPO and OUTAGE activities.

This report shows only on-site and announced inspection procedures.