ML112430469
| ML112430469 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 09/01/2011 |
| From: | Bill Dean Region 1 Administrator |
| To: | Rausch T Susquehanna |
| krohn, pg | |
| References | |
| IR-11-006 | |
| Download: ML112430469 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 4TSALLENDALE ROAD KING OF PRUSSIA, PENNSYLVANIA 19406.1415 September L, 20LL Mr. Timothy S. Rausch Senior Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Boulevard Beruvick, PA 18603-0467
SUBJECT:
MID-CYCLE LETTER FOR SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (REPORT 0500038712011006 and 05000388/2011006)
Dear Mr. Rausch:
On August 9,2011, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Susquehanna Steam Electric Station (Susquehanna) Units 1 and 2. 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 NRCs 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 NRCs assessment of your performance in the Security Cornerstone and its security-related inspection plan.
The NRC determined the performance at Susquehanna Unit 1 during the most recent quarter was within the Degraded Cornerstone Column of the NRC's Reactor Oversight Process (ROP)
Action Matrix because of one finding having low to moderate safety significance (i.e., white) and one performance indicator (Pl) having low to moderate safety significance (i.e., white), both associated with the Initiating Events Cornerstone. The White finding was related to an internal flooding event on July 16,2010, which required the operators to insert a manual scram and isolate the normal heat sink. The White Pl was related to the 1't quarter 2011 Unplanned Scrams per 7000 Critical Hours Pl. Specifically, Unit 1 crossed the green-to-white threshold following the unplanned scrams on April 22, May 14, and July 16, 2010, and January 25, 2011.
Although the 2no quarter 2011 Unplanned Scrams Pl returned to Green from White, Susquehanna Unit 1 will remain in the Degraded Cornerstone Column of the NRC Action Matrix until the associated supplemental inspection is completed satisfactorily.
Therefore, in addition to ROP baseline inspections, we plan to schedule and perform a supplemental inspection for Unit 1 using Inspection Procedure (lP) 95002, "lnspection for One Degraded Cornerstone or Any Three White Inputs in a Strategic Performance Areai'when your staff has notified us of your readiness for this inspection as discussed in the 2010 Annual Assessment letter dated March 4,2011.
The NRC determined the performance at Susquehanna Unit 2 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 safety significance (i.e., green), 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 unit 2.
The NRC evaluates cross-cutting themes to determine whether a substantive cross-cutting issue (SCCI) exists in a particular area and to encourage licensees to take appropriate actions before more significant performance issues emerge. Regarding Susquehanna, the NRC identified an SCCI in the Corrective Action Program (CAP) component of the Problem ldentification and Resolution (Pl&R) cross-cutting area. Specifically, there were five findings with a Pl&R cross-cutting aspect of P.1(c) - Evaluation of ldentified Problems - during this assessment period, one of which was the White finding related to the July 16, 2010, internal flooding event. The same theme was identified in the 2010 Annual Assessment letter, however, an SCCI was not assigned at that time since a reasonable duration had not passed to evaluate the effectiveness of PPls corrective actions. For the current assessment period, the NRC has a concern with your progress in addressing and substantially mitigating this issue given that a reasonable duration of time has since passed, findings with the same cross-cutting aspect continue to be identified, and implementation of some corrective actions has been delayed. The Pl&R P.1(c) SCCIwill remain open until PPL has demonstrated sustainable performance improvement as evidenced by effective implementation of an appropriate corrective action plan that results in no safety significant findings and a notable reduction in the overall number of inspection findings with the same cross-cutting aspect.
The NRC also identified a cross-cutting theme in the Resources component of the Human Performance cross-cutting area. Specifically, PPL had four findings with a Human Performance cross-cutting aspect of H.2(c) - Documentation, Procedures, and Component Labeling, which included a green finding in each of the four quarters of the assessment period. The NRC determined that an SCCI associated with H.2(c) does not exist because the NRC does not, at this time, have a concern with your staffs scope of effort and progress in addressing the cross-cutting theme. Specifically, PPL recognized the H.2(c) potentialtheme in the first and second quarters of 2011 and had ongoing analyses, including a root cause investigation, at the end of this assessment period. Notwithstanding, the NRC will continue to closely monitor your staffs progress in addressing the H.2(c)theme.
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. In addition to the inspections discussed above, the NRC plans to conduct NRC lP 60855,ISFSl Campaign Loading Inspectionl'and Temporary lnstruction (Tl) Tl-177, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems (NRC Generic Letter 2008-01)l' The NRC provides the inspection plan to allow for the resolution of any scheduling conflicts and personnelavailability 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 NRCs 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 Eventj'and
T. Rausch Tl-184,'Availability and Readiness lnspection of Severe Accident Management Guidelines (SAMGS) j'at your facility. Results of these inspections can be found here:
http://www.nrc.gov/iapan/iapan-activities.html. Additionally, on May 1 1,2011, the agency issued NRC Bulletin 201 1-01,.Mitigating Strategiesi'to confirm compliance with Order EA-02-026, 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 NRCs 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 DaiichiAccidentl' The NRC is currently reviewing the Task Forces 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.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Please contact Mr. Paul G. Krohn at (610) 337-5120 with any questions you have regarding this letter.
Sincerely, 3
tfueL*"
William M. Dean Regional Administrator Docket Nos. 50-387; 50-388 License Nos. NPF-14, NPF-22
Enclosure:
Inspection Plan cc w/encl: Distribution via ListServ
T. Rausch 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 1 1,2011, the agency issued NRC Bulletin2011-01, "Mitigating Strategies," to confirm compliance with Order EA-02-026, subsequently imposed license conditions, and 10 CFR 50.54(hh)(2), 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.
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.nrc.qov/readins-rm/adams.html (the Public Electronic Reading Room).
Please contact Mr. Paul G. Krohn at (610) 337-5120 with any questions you have regarding this letter.
Sincerely,
/RA by David C. Lew Acting For/
William M. Dean Reg ional Adm inistrator Docket Nos. 50-387; 50-388 License Nos. NPF-14, NPF-22
Enclosure:
Inspection Plan cc w/encl: Distribution via ListServ Distribution dencl: (via e-mail)
W. Dean. RA D. Lew, DRA P. Krohn, DRP P. Finney, DRP, SRI J. McHale, RIOEDO D. Tifft, RI, SLO R. Barkley, Rl, ORA RidsN nPMSusquehanna Resource C. Miller, DRS P. Wilson, DRS R. Montgomery, DRP J. Greives, DRP, Rl DRS Branch Chiefs (6)
D. Screnci, Rl, PAO RidsNrrDorlLpll -1 Resource RidsNrrDirslpab Resou rce D. Roberts, DRP A. Rosebrook, DRP S. lbarrola, DRP S. Farrell, DRP, OA N. McNamara, Rl, SLO N. Sheehan, Rl, PAO ROPreports Resource ROPassessment Resource ML112430469 SUNSI REVIEW COMPLETE: AAR {Reviewer's lnitials)
DOC: S:\\ROP-12 MID-CYCLE REVIEMBRANCH 4\\SUS\\SUSQUEHANNA MID-CYCLE ASSESSMENT LETTER REV6.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 attachmenUenclosure, E" = Copy w/ attacht.4&ncloslt N"=No copl
Page 1 of2 081'1712011 14:51:38 Report 22 Susquehanna Inspection / Activity Plan 07t0112011 - 1213112012 1
1 1
1,2 11t14t2011 12t12t2011 01116t2012 08t29t2011 1112812011 10t10t2011 10110t2011 10110t2011 10110t2011 10110t2011 10t10t2011 10110t2011 10117t2011 1011712011 1011712011 1011712011 o'U3012012 0211312012 02t20t2012 0212012012 02120t2012 03t05t2012 04to2t2012 04102t2012 1111812011 12t16t2011 01t20t2012 0910212011 12t0212011 10t14t2011 1011412011 1011412011 1011412011 1011412011 10t14t2011 10t14t2011 10t21t2011 10t21t2011 10t2112011 10t21t2011 0ac312012 0211712012 0212412012 o2124t2012 o2t24t2012 0310912012 04to6t2012 o41o6t2012 l'gEXAM. SUSOUEHANNA INITIAL OL EXAM U01842 FY12-SUSQ INITIAL OPERATOR LICENSING EXAM U01842 FY12-SUSQ INITIAL OPERATOR LICENSING EXAM U01842 FY12-SUSQ INITIAL OPEMTOR LICENSING EXAM T1.177
. MANAGING GAS ACCUMULATION IN ECCS lP 25151177 Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal & Containment Spray System 7111118. SUSQ REQUAL INSP W' PIF RESULTS lP 71111118 Licensed Operator Requalification Program EP PROGR - EP PROGRAM INSPECTION lP 7111402 Alert and Notification System Testing lP 7111403 Emergency Preparedness Organization Staffing and Augmentation System lP 71 1 1404 Emergency Action Level and Emergency Plan Changes lP 7111405 Conection of Emergency Preparedness Weaknesses and Deficiencies lP 71 151-EP01 Drill/Exercise Performance lP 71151-EPO2 ERO Drill Particioation lP 71151-EP03 Alert & Notification System 71124
- HP lP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants 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 71't528 - Pt&R lP 711528 Problem ldentification and Resolution lP 711528 Problem ldentification and Resolution 71124
- OCC RAD SAFETY lP 71124.01 Radiological Hazard Assessment and Exposure Controls lP 71124.02 Occupational ALARA Planning and Controls lP 71124.03 ln-Plant Airbome Radioactivity Control and Mitigation 7111107T. TRIENNIAL HEAT SINK lP 7111107T Heat Sink Performance 7111108G - TNSERVTCE TNSPECTTON lP 71 1 1 108G Inservice lnspection Activities - BWR 71124
-OCCRADSAFEW lP 71124.01 Radiological Hazard Assessment and Exposure Controls 1,2 1,2 1,2 1,2 1,2 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 Unit Number No. of Staff on Site s report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.
Page 2 of 2 081171201'1 14:51:3E Report 22 Susquehanna Inspection / Activity Plan 07t01t2011 - 1213112012 Unit Number Planned Dates Start End 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1,2 1,2 I,z o4to212012 06t0112012 08t2012012 08t2012012 08t20t2012 08t20t2012 1012212012 10t2212012 11t2612012 12t1012012 11t26t2012 11t2612012 1112612012 04t0612012 0913012012 o&t24t2012 08t2412012 08t24t2012 08t24t2012 10t2612012 10t2612012 11t3012012 12t1412012 11t30t2012 1113012012 1113012012 71124
- OCC RAD SAFEW lP 71124.02 Occupational ALARA Planning and Controls 60855
.ISFSICAMPAINGLOADINGINSPECTION lP 60855 Operation Of An ISFSI 71124
. RAD SAFETY & ISFSI lP 60855.1 Operation of an Independent Spent Fuel Storage Installation at Operating Plants lP 71124.01 Radiological Hazard Assessment and Exposure Controls lP 71124.02 Occupational ALAM Planning and Controls lP 71124.04 Occupational Dose Assessment EP EX
. EP EXERGISE EVALUATION lP 7'111401 Exercise Evaluation lP 7111404 Emergency Action Level and Emergency Plan Changes MODS
. PERMANENT PLANT MODIFICATIONS lp 7111117f Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications lp 7111117T Evaluations of Changes, Tests, or Experiments and Permanent Plant Modifications 71124.08. RADWASTE lP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation lP 71'151-OR01 OccupationalExposureControlEffectiveness lP 71151-PR01 RETS/ODCM Radiological Effluent fhis report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.