ML070610464
| ML070610464 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 03/02/2007 |
| From: | David Lew Division Reactor Projects I |
| To: | Christian D Dominion Resources |
| Krohn P, RI/DRP/PB6/610-337-5120 | |
| References | |
| IR-07-001 | |
| Download: ML070610464 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 475 ALLENDALE ROAD KING OF PRUSSIA, PENNSYLVANIA 19406-1415 March 2, 2007 Mr. David A. Christian Sr. Vice President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glenn Allen, VA 23060-6711
SUBJECT:
ANNUAL ASSESSMENT LETTER - MILLSTONE POW ER STATION (REPORTS 05000336/2007001 AND 05000423/2007001)
Dear Mr. Christian:
On February 13, 2007, the U.S. Nuclear Regulatory Commission (NRC) staff completed its performance review of the Millstone Power Station (Millstone). Our technical staff reviewed performance indicators (PIs) for the most recent quarter and inspection results for the period from January 1 through December 31, 2006. The purpose of this letter is to inform you of our assessment of your safety performance during this period and our plans for future inspections at your facility.
This performance review and enclosed inspection plan do not include physical protection information. A separate letter designated and marked as "Exempt from Public Disclosure in accordance with 10 CFR 2.390" will include the physical protection review and resultant inspection plan.
Overall, Millstone Units 2 and 3 operated in a manner that preserved public health and safety and fully met all cornerstone objectives. Plant performance for the most recent quarter for Units 2 and 3, was within the Licensee Response column of the NRCs Action Matrix, based on all inspection findings being classified as having very low safety significance (Green) and all PIs indicating performance at a level requiring no additional NRC oversight (Green). Therefore, we plan to conduct reactor oversight process (ROP) baseline inspections at your facility.
W hile Unit 2 performance for the most recent quarter was within the Licensee Response column of the Action Matrix, Unit 2 was within the Regulatory Response column for the first three quarters of the assessment cycle due to one W hite (low to moderate safety significance) PI.
Specifically, Unit 2 had a W hite PI in Scrams with Loss of Normal Heat Removal (LONHR). On February 23, 2006, Unit 2 was manually tripped from 100 percent power due to a loss of both main feedwater pumps following a partial loss of instrument air. This was the third scram with LONHR and caused the PI to cross the Green/W hite threshold. Millstone staff performed a root cause evaluation for the contributing events and the NRC completed a supplemental inspection of the scrams associated with the PI in September 2006. The PI returned to a level requiring no additional oversight (Green) with the reporting of the 4th quarter 2006 data.
D. Christian 2
Additionally, the staff identified that there were five Green findings for the current twelve month assessment period with documented cross-cutting aspects in the area of problem identification and resolution, and there was a cross-cutting theme associated with these findings. The theme was a failure to thoroughly evaluate problems through the implementation of the operability determination process and engineering support evaluation of degraded equipment conditions.
In evaluating the scope of efforts and progress in addressing the cross-cutting theme, NRC staff determined that Millstone appropriately recognized the cross-cutting theme; scheduled and took actions to address the theme based on when the issues occurred; and took a range of corrective actions which have been implemented and are judged, at this point, to be effective in mitigating the cross-cutting theme. Therefore, the staff has determined that a substantive cross-cutting issue in problem identification and resolution does not exist at this time.
The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through June 30, 2008. In addition to baseline inspections, we plan on conducting an independent spent fuel storage facility inspection. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last nine months of the inspection plan are tentative and may be revised at the mid-cycle review.
In accordance with 10 CFR 2.390 of the NRCs "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 W eb site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible. Please contact Paul Krohn at 610-337-5120 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
David C. Lew, Director Division of Reactor Projects Docket Nos. 50-336, 50-423 License Nos. DPR-65, NPF-49
Enclosure:
Millstone Inspection / Activity Plan
D. Christian 3
cc w/encl:
J. A. Price, Site Vice President, Millstone Station C. L. Funderburk, Director, Nuclear Licensing and Operations Support D. W. Dodson, Supervisor, Station Licensing L. M. Cuoco, Senior Counsel C. Brinkman, Manager, W ashington Nuclear Operations J. Roy, Director of Operations, Massachusetts Municipal W holesale Electric Company First Selectmen, Town of W aterford B. Sheehan, Co-Chair, NEAC E. W oollacott, Co-Chair, NEAC E. W ilds, Director, State of Connecticut SLO Designee J. Buckingham, Department of Public Utility Control G. Proios, Suffolk County Planning Dept.
R. Shadis, New England Coalition Staff G. W inslow, Citizens Regulatory Commission (CRC)
S. Comley, We The People D. Katz, Citizens Awareness Network (CAN)
R. Bassilakis, CAN J. M. Block, Attorney, CAN P. Eddy, Electric Division, Department of Public Service, State of New York P. Smith, President, New York State Energy Research and Development Authority J. Spath, SLO Designee, New York State Energy Research and Development Authority
Millstone Inspection / Activity Plan 01/01/2007 - 06/30/2008 Inspection Type Inspection Activity Planned Dates Start End No. of Staff on Site Title Unit Number Page 1 of 2 03/02/2007 07:58:35 Report 22 3
3/12 EXM
- U3 OPERATOR LICENSING INITIAL EXAMS Not Applicable 02/12/2007 02/16/2007 3
U01638 MILLSTONE 3 INITIAL EXAM (FY07)
Not Applicable 03/12/2007 03/16/2007 3
U01638 MILLSTONE 3 INITIAL EXAM (FY07) 1 7111107
- U3 BIENNIAL HEAT SINK INSP Baseline Inspections 01/08/2007 01/12/2007 3
7111107B IP Heat Sink Performance 1
7112101
- OCC RAD SAFETY Baseline Inspections 02/12/2007 02/16/2007 2, 3 7112101 IP Access Control to Radiologically Significant Areas 1
SAFSTOR
- SAFSTOR INSPECTION Other Routine 03/19/2007 03/23/2007 1
40801 IP Self-Assessment, Auditing, And Corrective Action At Permanently Shutdown Reactors Other Routine 03/19/2007 03/23/2007 1
60801 IP Spent Fuel Pool Safety At Permanently Shutdown Reactors Other Routine 03/19/2007 03/23/2007 1
62801 IP Maintenance And Surveillance At Permanenly Shutdown Reactors Other Routine 03/19/2007 03/23/2007 1
71801 IP Decommissioning Performance And Status Revierw At Permanently Suhutdown Reactors Other Routine 03/19/2007 03/23/2007 1
83750 IP Occupational Radiation Exposure 1
7111108P
- U3 IN-SERVICE INSPECTION Baseline Inspections 04/09/2007 04/20/2007 3
7111108P IP Inservice Inspection Activities - PWR 1
7112102
- OCC RAD SAFETY - ALARA Baseline Inspections 04/23/2007 04/27/2007 2, 3 7112102 IP ALARA Planning and Controls 1
TI-166
- CONTAINMENT SUMP MODIFICATIONS - UNIT 3 Safety Issues 04/23/2007 04/27/2007 3
2515/166 IP Pressurized Water Reactor Containment Sump Blockage [NRC GENERIC LETTER 2004-02]
1 7112201
- PUB RAD SAFETY - RETS Baseline Inspections 06/04/2007 06/08/2007 2, 3 7112201 IP Radioactive Gaseous and Liquid Effluent Treatment and Monitoring Systems 3
7111111B
- L.O. REQUAL.PROG.(FOCUS U3)+P/F RVW Baseline Inspections 09/10/2007 09/14/2007 2, 3 7111111B IP Licensed Operator Requalification Program 1
71114
- EP PRGM INSP Baseline Inspections 09/10/2007 09/14/2007 2, 3 7111402 IP Alert and Notification System Testing Baseline Inspections 09/10/2007 09/14/2007 2, 3 7111403 IP Emergency Response Organization Augmentation Testing Baseline Inspections 09/10/2007 09/14/2007 2, 3 7111404 IP Emergency Action Level and Emergency Plan Changes Baseline Inspections 09/10/2007 09/14/2007 2, 3 7111405 IP Correction of Emergency Preparedness Weaknesses and Deficiencies Baseline Inspections 09/10/2007 09/14/2007 2, 3 71151-EP01 IP Drill/Exercise Performance Baseline Inspections 09/10/2007 09/14/2007 2, 3 71151-EP02 IP ERO Drill Participation Baseline Inspections 09/10/2007 09/14/2007 2, 3 71151-EP03 IP Alert & Notification System 3
TRI FIRE
- TRIENNIAL FIRE PROTECTION INSPECTION Baseline Inspections 09/17/2007 09/21/2007 3
7111105T IP Fire Protection [Triennial]
Baseline Inspections 10/01/2007 10/05/2007 3
7111105T IP Fire Protection [Triennial]
This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.
Millstone Inspection / Activity Plan 01/01/2007 - 06/30/2008 Inspection Type Inspection Activity Planned Dates Start End No. of Staff on Site Title Unit Number Page 2 of 2 03/02/2007 07:58:35 Report 22 1
7112103
- OCC RAD SAFETY - INSTRUMENTS Baseline Inspections 09/24/2007 09/28/2007 2, 3 7112103 IP Radiation Monitoring Instrumentation and Protective Equipment 1
- ISFSI INSPECTIONS Other Routine 10/01/2007 12/31/2007 2, 3 60854.1 IP Preoperational Testing of Independent Spent Fuel Storage Facility Installation at Operating Plants 1
7112203
- PUB RAD SAFETY - REMP Baseline Inspections 10/29/2007 11/02/2007 2, 3 7112203 IP Radiological Environmental Monitoring Program (REMP) And Radioactive Material Control Program 3
7111117B
- MODS AND 50.59 Baseline Inspections 11/05/2007 11/09/2007 2, 3 7111102 IP Evaluation of Changes, Tests, or Experiments Baseline Inspections 11/05/2007 11/09/2007 2, 3 7111117B IP Permanent Plant Modifications 4
2/11EXAM
- U2 OPERATOR LICENSING INITIAL EXAMS Not Applicable 03/11/2008 03/14/2008 2
U01634 MILLSTONE 2 INITIAL EXAM (FY08)
Not Applicable 04/07/2008 04/11/2008 2
U01634 MILLSTONE 2 INITIAL EXAM (FY08) 3 TRI FIRE
- TRIENNIAL FIRE PROTECTION INSPECTION Baseline Inspections 01/14/2008 01/18/2008 2
7111105T IP Fire Protection [Triennial]
Baseline Inspections 01/28/2008 02/01/2008 2
7111105T IP Fire Protection [Triennial]
1 7112101
- OCC RAD SAFETY - ACCESS Baseline Inspections 02/11/2008 02/15/2008 2, 3 7112101 IP Access Control to Radiologically Significant Areas 4
- PI&R Baseline Inspections 02/11/2008 02/15/2008 2, 3 71152B IP Identification and Resolution of Problems Baseline Inspections 02/25/2008 02/29/2008 2, 3 71152B IP Identification and Resolution of Problems 1
7111108P
- U2 INSERVICE INSPECTION Baseline Inspections 04/07/2008 04/11/2008 2
7111108P IP Inservice Inspection Activities - PWR Baseline Inspections 04/21/2008 04/25/2008 2
7111108P IP Inservice Inspection Activities - PWR 7
7111121
- CDBI Baseline Inspections 06/23/2008 06/27/2008 2, 3 7111121 IP Component Design Bases Inspection This report does not include INPO and OUTAGE activities.
This report shows only on-site and announced inspection procedures.
D. Christian 2
Additionally, the staff identified that there were five Green findings for the current twelve month assessment period with documented cross-cutting aspects in the area of problem identification and resolution, and there was a cross-cutting theme associated with these findings. The theme was a failure to thoroughly evaluate problems through the implementation of the operability determination process and engineering support evaluation of degraded equipment conditions. In evaluating the scope of efforts and progress in addressing the cross-cutting theme, NRC staff determined that Millstone appropriately recognized the cross-cutting theme; scheduled and took actions to address the theme based on when the issues occurred; and took a range of corrective actions which have been implemented and are judged, at this point, to be effective in mitigating the cross-cutting theme. Therefore, the staff has determined that a substantive cross-cutting issue in problem identification and resolution does not exist at this time.
The enclosed inspection plan details the inspections, less those related to physical protection, scheduled through June 30, 2008. In addition to baseline inspections, we plan on conducting an independent spent fuel storage facility inspection. The inspection plan is provided to allow for the resolution of any scheduling conflicts and personnel availability issues well in advance of inspector arrival onsite. Routine resident inspections are not listed due to their ongoing and continuous nature. The inspections in the last nine months of the inspection plan are tentative and may be revised at the mid-cycle review.
In accordance with 10 CFR 2.390 of the NRCs "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 W eb site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
If circumstances arise which cause us to change this inspection plan, we will contact you to discuss the change as soon as possible.
Please contact Paul Krohn at 610-337-5120 with any questions you may have regarding this letter or the inspection plan.
Sincerely,
/RA/
David C. Lew, Director Division of Reactor Projects Docket Nos.
50-336, 50-423 License Nos.
Enclosure:
Millstone Inspection / Activity Plan Distribution w/encl:
S. Collins, RA D. Lew, DRP M. Dapas, DRA J. Clifford, DRP J. Lamb, RI OEDO A. Blough, DRS A. Kock, OEDO M. Gamberoni, DRS H. Chernoff, NRR J. Trapp, DRS J. Lubinski, NRR J. W hite, DRS M. Kowal, NRR R. Conte, DRS V. Nerses, NRR, PM L. Doerflein, DRS E. Miller, NRR J. Rogge, DRS S. Schneider, Senior Resident Inspector M. Sykes, DRS E. Bartels, Resident OA D. Screnci, PAO P. Krohn, DRP RidsNrrDirslpab B. Norris, DRP Institute of Nuclear Power Operations (INPO)
Region I Docket Room (with concurrences)
SUNSI Review Complete: PGK (Reviewers Initials)
DOCUMENT NAME: S:\\ROP-7 EOC Review\\2006 ROP-7 Annual Assessment Letters\\PDF Merged files\\2006 EOC Millstone Assessment Letter.wpd 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 attachment/enclosure "E" = Copy with attachment/enclosure "N" = No copy OFFICE RI/DRP RI/DRP RI/DRP NAME B. Norris/BSN PKrohn/PGK DLew/DCL DATE 02/27/07 02/27/07 03/02/07 OFFICIAL RECORD COPY