IR 05000336/2010002
| ML101160284 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 04/26/2010 |
| From: | Diane Jackson NRC/RGN-I/DRP/PB5 |
| To: | Heacock D Dominion Resources |
| References | |
| FOIA/PA-2011-0115 IR-10-002 | |
| Download: ML101160284 (28) | |
Text
April 26, 2010
SUBJECT:
MILLSTONE POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000336/2010002 AND 05000423/2010002
Dear Mr. Heacock:
On March 31,2010, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Millstone Power Station Unit 2 and Unit 3. The enclosed inspection report documents the inspection results, which were discussed on April 7, 2010, with Mr. A. J. Jordan and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commission's rules and regulations, and with the conditions of your license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.
Based on the results of this inspection, no findings of significance were identified. However, a licensee-identified violation which was determined to be of very low safety significance is listed in this report. The NRC is treating this violation as non-cited violation (NCV) consistent with Section VI.A.1 of the NRC Enforcement Policy because of the very low safety significance of the violation and because it is entered into your corrective action program. If you contest this NCV in this report, you should provide a response within 30 days of the date of this inspection report, with the basis for your denial, to the Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington DC 20555~0001; with copies to the Regional Administrator, Region I; the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Senior Resident Inspector at Millstone. In addition. if you disagree with the characterization of the cross~cutting aspect of any finding in this report, you should provide a response within 30 days of the date of this inspection report. with the basis for your disagreement, to the Regional Administrator, Region 1 and the NRC Senior Resident Inspector at Millstone. The information you provide will be considered in accordance with Inspection Manual Chapter (IMC) 0305. In accordance with Title 10 of the Code of Federal Regulations (CFR) Part 2.390 of the NRC's qRules of Practice," a copy of this letter, its enclosure, and your response (if any) will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of the 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).
D~c9fL Donald E. Jackson, Chief Projects Branch 5 Division of Reactor Projects Docket Nos.
License Nos.
.
Enclosure:
Inspection Report No. 05 w/Attachment: Supplemental Information 000336/2010002 and 05000423/2010002
REGION I==
50-336, 50-423 DPR-65, NPF-49 05000336/2010002 and 05000423/2010002 Dominion Nuclear Connecticut, Inc.
Millstone Power Station, Units 2 and 3 P. O. Box 128 Waterford, CT 06385 January 1, 2010 through March 31, 2010 S. Shaffer, Senior Resident Inspector, Division of Reactor Projects (DRP)
J. Krafly, Resident Inspector. DRP B. Haagensen, Resident Inspector, DRP D. Dodson, Project Engineer, DRP T. Moslak, Health Physicist. Division of Reactor Safety (DRS)
Donald E Jackson, Chief Projects Branch 5 Division of Reactor Projects Enclosure
Table of Contents
SUMMARY OF FINDINGS
.........................................................................................................3
REPORT DETAILS
..................................................................................................................... 4
1. REACTOR SAFETy........ :................................................,................................................. 4
1R01 Adverse Weather Protection.....................................................................................4 1R04 Equipment Alignment...............................................................................................4 1R05 Fire Protection............................................................_. _........................................... 5 1R07 Heat Sink Performance............................................................................................ 6 1R11 Licensed Operator Requalification Program............................................................. 6 1R12 Maintenance Effectiveness....................................................................................... 7
1R13 Maintenance Risk Assessments and Emergent Work Control.................................. 8
1R15 Operability Evaluations............................................................................................. 9 1R 18 Plant Modifications....................................................................................................9
'IR19 Post-Maintenance Testing...................................................................................... 10 1R20 Refueling and Other Outage Activities........................................_........................... 11 1R22 Surveillance Testing............................................................................................... 12 1EP6 Drill Evaluation....................................................................................................... 13
2. RADIATION SAFETy....................................................................................................... 13
2RS01 Radiological Hazard Assessment and Exposure Controls..................................... 13 2RS02 Occupational ALARA Planning and Controls
OTHER ACTIVITIES
[OA]................................................................................................ 17 40A1 Performance Indicator (PI) Verification................................................................... 17 40A2 Identification and Resolution of Problems.............................................................. 17 40A3 Event Follow-up..................................................................................................... 18 40A6 Meetings, including Exit.................... :..................................................................... 19 40A7 Licensee Identified Violations.................................................................................. 19 ATTACHMENT:
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
................. !.................................................................................... 1
LIST OF ITEMS
OPENED, CLOSED. AND DISCUSSED.......................................................... 2
LIST OF DOCUMENTS REVIEWED
.......................................................................................... 2