IR 05000336/2010003

IR 05000336-10-003, 05000423-10-003 on 04/01/2010 - 06/30/2010 for Millstone Power Station, Unit 2 and 3, Equipment Alignment; Refueling and Other Outage Activities; Identification and Resolution of Problems; Event Follow-up

ML102170013
Person / Time
Site:	Millstone
Issue date:	08/05/2010
From:	Diane Jackson NRC/RGN-I/DRP/PB5
To:	Heacock D Dominion Resources
Jackson D RGN-I/DRP/PB2/610-337-5306
References
FOIA/PA-2011-0115 IR-10-003
Download: ML102170013 (59)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION I

475 ALLENDALE ROAD KING OF PRUSSIA, PA 19406-1415 August 5, 2010 I I

Mr. David Heacock J'

President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glen Allen, VA 23060~6711 I I

SUBJECT: MILLSTONE POWER STATION - NRC INTEGRATED INSPECTION REPORT I'

05000336/2010003 AND 05000423/2010003 II'

Dear Mr,

Heacock:

On June 30,2010, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at I

your Millstone Power Station Unit 2 and Unit 3. The enclosed inspection report documents the inspection results, which were discussed on July 21, 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 I

compliance with the Commission's rules and regulations, and with the conditions of your I license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

This report documents one Severity Level IV non-cited violation (NCV). This report also documents four self-revealing findings of very low safety significance (Green). Two of these findings were determined to involve a violation of NRC requirements. However, because of the very low safety significance and because they have been entered into your corrective action program, the NRC is treating these violations as NCVs, consistent with Section VI.A. 1 of the NRC Enforcement Policy. If you contest any 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 cross-cutting aspect assigned to 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 I, and the NRC Senior Resident Inspector at Millstone. In accordance with Title 10 of the Code of Federal Regulations (CFR) Part 2.390 of the NRC's

"Rules 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).

n~

Donald E. Jackson, Chief Projects Branch 5 Division of Reactor Projects Docket Nos. 50-336,50-423 License Nos. DPR~65. NPF-49

Enclosure:

Inspection Report No. 05000336/2010003 and 05000423/2010003 w/Attachment: Supplemental Information

REGION I==

Docket No.: 50-336, 50-423 License No.: DPR-65, NPF-49 Report No.: 05000336/2010003 and 05000423/2010003 Licensee: Dominion Nuclear Connecticut, Inc.

Facility: Millstone Power Station, Units 2 and 3 Location: P. O. Box 128 Waterford, CT 06385 Dates: April 1. 2010 through June 30,2010 Inspectors: S. Shaffer, Senior Resident Inspector, Division of Reactor Projects (DRP)

J. Krafiy, Resident Inspector, DRP B. Haagensen, Resident Inspector, DRP D. Dodson, Project Engineer, DRP C. Bickett, Senior Project Engineer, DRP T. Moslak, Health Physicist, Division of Reactor Safety (DRS)

P. Kaufman, Senior Reactor Inspector, DRS J. Richmond, Senior Reactor Inspector, DRS J. Rady, Reactor Inspector, DRS Approved by: Donald E. Jackson, Chief Projects Branch 5 Division of Reactor Projects Enclosure

Table of Contents

SUMMARY OF FINDINGS

..........................................................................................................3

REPORT DETAILS

.....................................................................................................................7 1. REACTO,R SAFETy............................................................................................................7 1R01 Adverse Weather Protection ..................................................................................................7 1R04 Equipment Alignment .....................................................................................................,....... 8 1ROS Fire Protection ..................................................................:................................................... 10 1R06 Flood Protection Measures ..................................................................................................11 1R07 Heat Sink Performance ........................................................................................................12 1ROB In-Service Inspection ...........................................................................................................13 1R11 Licensed Operator RequaJification Program ........................................................................ 17 1R12 Maintenance Effectiveness ..................................................................................................17 1R13 Maintenance Risk Assessments and Emergent Work Control ............................................ 18 1R15 Operability Evaluations ........................................................................................................18 1R18 Plant Modifications ...............................................................................................................19 1R19 Post-Maintenance Testing ...................................................................................................20 1R20 Refueling and Other Outage Activities ................................................................................. 21 1R22 Surveillance Testing .............................................................................................................25 1EP6 Drill Evaluation

RADIATION SAFETY

.........................................................................................................27 2RS01 Radiological Hazard Assessment and Exposure Controls ................................................... 27 2RS02 Occupational ALARA Planning and Controls .......................................................................29 2RS03 In-Plant Airborne Radioactivity Control and Mitigation .........................................................31 2RS04 Occupational Dose Assessment

OTHER ACTIVITIES

[OA] .................................................................................................33 40A1 Performance Indicator (PI) Verification ................................................................................. 33 40A2 Identification and Resolution of Problems ............................................................................ 33 40A3 Event Follow-up ....................................................................................................................36 40A5 Other Activities ...................................................................................................................... 39 40A6 Meetings, including Exit ........................................................................................................40 ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

..................................................................................................A-1

LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED

....................................................... A-2

LIST OF DOCUMENTS REVIEWED

...................................................................................... A-2