ML112440012

Mid-Cycle Performance Review and Inspection Plan 2011 - Millstone Power Station Unit 2 and Unit 3

ML112440012
Person / Time
Site:	Millstone
Issue date:	09/01/2011
From:	Darrell Roberts Division Reactor Projects I
To:	Heacock D Dominion Resources
Bellamy R Rgn-I/DRP/Br6/610-337-5200
References
IR-11-006
Download: ML112440012 (6)

Text

UNITED STATES so"en* NUCLEAR REGU LATORY COMMISSION REGION I

{e +**ti 475 ALLENDALE ROAD KING OF PRUSSIA. PENNSYLVANIA 19406-1415 SepLember 1, 20ll Mr. David Heacock Sr. Vice President and Chief Nuclear Officer Dominion Resources 500 Dominion Boulevard Glenn Allen, VA 23060-6711

SUBJECT:

MID-CYCLE PERFORMANCE REVIEW AND INSPECTION PLAN -

MILLSTONE POWER STATION UNIT 2 AND UNIT 3 (REPORT 05000336/201 1 006 AND 0500042312011 006)

Dear Mr. Heacock:

On August 10, 2011, the U.S. Nuclear Regulatory Commission (NRC) completed its mid-cycle performance review of Millstone Power Station Unit 2 and Unit 3. 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 Millstone Power Station Unit 2 during the most recent quarter was within the Regulatory Response Column of the NRC's Reactor Oversight Process (ROP) Action Matrix based on one finding having low to moderate safety significance (White) in the Initiating Events Cornerstone. The finding is associated with a performance deflciency involving the failure of Unit 2 Millstone personnel to carry out their assigned roles and responsibilities and inadequate reactivity management during main turbine control valve testing, which contributed to an unintended eight percent reactor power transient (88 percent to 96 percent) during the performance of quarterly main turbine control valve testing on February 12,2011.

The NRC determined the performance at Millstone Power Station Unit 3 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 (Green) safety significance, and all Pls indicated that your performance was within the nominal, expected range (Green).

As a result of our review of Millstone Power Station performance, we plan to conduct a supplemental inspection for Unit 2 using Inspection Procedure 95001, "lnspection for One or Two White lnputs in a Strategic Performance Area," when your staff has notified us of your readiness for this inspection. This inspection procedure is conducted to provide assurance that the root cause and contributing causes of risk significant performance issues are understood,

D. Heacock the extent of condition is identified, and the corrective actions are sufficient to prevent recurrence.

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 Millstone Power Station, the staff identified that there were four Green findings for the current twelve month assessment period with a documented cross-cutting aspect in the Problem ldentification and Resolution cross-cutting area, and that there was a common cross-cutting theme associated with these findings.

The theme was associated with the timeliness of corrective actions, which was the most significant contributor to the four Green findings IP.1(d)1.

ln evaluating the scope of efforts and progress in addressing the cross-cutting theme, the NRC staff determined that Dominion 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 Problem ldentification and Resolution cross-cutting area does not exist at this time. We will monitor your progress in the Problem ldentification and Resolution cross-cutting area through the baseline inspection program, including a focused review of your proposed corrective action plan.

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. 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 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:/r4rww.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 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"tCentury: The Near-Term Task Force Review of Insights from the Fukushima DaiichiAccident." The NRC is cunently 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 http://www.nrc.qov/readinq-rm/adams.html (the Public Electronic Reading Room).

D. Heacock Please feelfree to contact Dr. Ronald R. Bellamy at (610)337-5200 with any questions you have regarding this letter.

Sincerely, DarrellJ, Docket Nos. 50-336, 50-423 License No. DPR-65, NPF-49

Enclosure:

Millstone Inspection/Activity Plan cc w/encl: Distribution via ListServ

D. HeacocX 3 please feel free to contact Dr. Ronald R. Bellamy at (610) 337-5200 with any questions you have regarding this letter.

Sincerely, IRAI Darrell J. Roberts, Director Division of Reactor Projects Docket Nos. 50-336, 50-423 License No. DPR-65, NPF-49

Enclosure:

Millstone Inspection/Activity Plan cc dencl: Distribution via ListServ Distribution w/encl: (via email)

W. Dean, RA K. Dunham. DRP R. Barkley, ORA D. Lew, DRA S. Shaffer, DRP, SRI ROPassessment Resource D. Roberts. DRP B. Haagensen, Rl RidsNnDirslpabResource J. Clifford, DRP J. Krafty, DRP, Rl RidsNRRPM Millstone Resource C. Miller, DRS C. Kowalyshyn, OA RidsNRRDorlLPl 1 -2 Resource P. Wilson. DRS DRS Branch Chiefs (6) ROPreportsResource J. McHale, RIOEDO N. McNamara, SLO R. Bellamy, DRP D. Tift, SLO T. Setzer, DRP D. Screnci, PAO, E. Keighley, DRP N. Sheehan, PAO suNsl Review Gomplete: TCS (Reviewer',s Initials)

DOCUMENT NAME: S:\ROP-l2 Mid-Gycle Review\Branch S\MS\MS Mid-Cycle Letter 2011rev2.docx After declaring this document "An Official Agency Record" it will be released to the Public.

"E" = Copy To receive a copy of this document, indicate in the box: "C" = Copy without attachmenUenclosure with attachmenUenclosure "N" = No copy ML1124/j0012 08t31111

Page 1 of2 Millstone 0813112011 13:49t41 Inspection / Activity Plan 07r01t2011 - 12t31t2012 Report 22 O7l11EXM - OPERATOR LICENSING INITIAL EXAMS 07 tl1t2011 07t20t2011 U01832 FY11- MILLSTONE 3, INITIAL OL EXAM 3/14EXM - INITIAL OPERATOR LICENSING U2 EXAMS 09t07t2011 09t09t2011 U01834 FY11- MILLSTONE 2, INITIAL OL EXAM 10t03t2011 10t14t2011 U01834 FY11- MILLSTONE 2, INITIAL OL EXAM 7111118 - MS3 REQUAL INSP WIPIF RESULTS 2,3 08t29/2411 09102t2011 lP 71 1 11 1 18 Licensed Operator Requalification Program EP PROGR . EP PROGRAM INSPECTION 2,3 o8t01t2011 08to5l201'l lP 7111402 Alert and Notification System Testing 2,3 08t01t2011 o8lo5t20't'l lP 7111403 Emergency Preparedness Organization Staffing and Augmentation System 2,3 08t01t201'l 08105t2011 lP 7111404 Emergency Action Level and Emergency Plan Changes 2,3 08t01t20't1 08t05t2011 lP 7111405 Correction of Emergency Preparedness Weaknesses and Deficiencies 2,3 oSto'U2011 0810512011 lP 7115'l-EP02 ERO Drill Participation 2,3 08t01t2011 o8l05l20't1 lP 71 151-EP03 Alert & Notification System 2,3 08/01/201 1 08107t2011 lP 71 151-EP01 DrilVExercise Performance 71124 - PUB RADSAFEry. REMP 2,3 08t22t20't'l 08126t2011 lP 71124.07 Radiological Environmental Monitoring Program 71124 -OCC RADSAFETY 2,3 10t17t2011 10121t201',l lP 7'1124.0'l Radiological Hazard Assessment and Exposure Controls 2,3 10t17t24fi 10121t2011 lP 71124.02 Occupational ALAM Planning and Controls 2,3 10t17t201'l 'tol2'U2011 lP 71124.04 Occupational Dose Assessment 7111108P . U3INSERVICE INSPECTION 3 't0t17t2011 10t2812011 lP 7111109P lnservice Inspection Activities - PWR TI-177 - MANAGING GAS ACCUMULATION IN ECCS 2,3 01t30t2012 02t03t2012 lP 25151177 Managing Gas Accumulation In Emergency Core Cooling, Decay Heat Removal & Gontainment Spray System 71124 -OCC RADSAFETY 2,3 02t27t2012 03102t2012 lP 71124.01 Radiological Hazard Assessment and Exposure Controls 2,3 o2t27t2012 o3102t2012 lP 71'124.02 Occupational ALARA Planning and Controls 2,3 02t27t2012 03toa20e lP 7'1124.04 Occupational Dose Assessment 7111121 - CDBI 2,3 04t16t2012 04120t2012 lP 7111'121 Component Design Bases Inspection 2,3 04t30t2012 05t04t2012 lP 7111121 Component Design Bases Inspection 2,3 05t47t2012 o5111t2012 lP 7111121 Component Design Bases Inspection fhis report does not include INPO and OUTAGE activities.

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

Page 2 ot 2 llllillstone 0913112011 13:49:41 Inspection / Activity Plan 07to1t2011 - 1z31t2012 Report 22 EP EX . EP EXERCISE EVALUATION 2,3 08t05t2012 08t11t2012 tP 711140'l Exercise Evaluation 2,3 08t05t2012 o8rt1n012 tP 7111404 Emergency Action Level and Emergency Plan Changes 711528 . PI&R 2,3 07116t2012 07t20t20't2 tP 711528 Problem ldentification and Resolution 2 07t30t2012 08t03t2012 tP 7't1528 Problem ldentification and Resolution 71111118 . MS2 ONITE REQUAL INSP w/ P'F RESULTS 2,3 09t17t20't2 o9t2112012 lP 71111118 Licensed Operator Requalification Program 71124 . RMS 2,3 08t13t2012 08t17t2012 tP 71124.05 Radiation Monitoring Instrumentation 71124 -RW 2,3 09t10t2012 09t1412012 tP 7't124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation 7111108P . UNIT 2INSERVICE INSPECTION 2 10t15t2012 't0t26t2012 tP 7111108P Inservice Inspection Activities - PWR 71124 - OCC RAD SAFETY 2,3 11t04t2012 11tO912012 tP 71124.01 Radiological Hazard Assessment and Exposure Controls 2,3 't1tMt2012 1110912012 tP 71124.02 Occupational ALARA Planning and Controls 2,3 11104t20't2 1'vo912012 tP 71124.03 ln-Plant Airborne Radioactivity Control and Mitigation 2,3 11t04t2012 11t0912012 tP 7't124.04 Occupational Dose Assessment lhis report does not include INPO and OUTAGE activities.

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