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=Text=
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{{#Wiki_filter:UNITED NUCLEAR REGULATORY REGION 475 ALLENDALE KING OF PRUSSIA. PENNSYLVANIA April 26, 2010 Mr. David President and Chief Nuclear Dominion 5000 Dominion Glen Allen, VA MILLSTONE POWER STATION -NRC INTEGRATED INSPECTION REPORT 05000336/2010002 AND 05000423/2010002
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION
 
==REGION I==
475 ALLENDALE ROAD KING OF PRUSSIA. PENNSYLVANIA 19406-1415 April 26, 2010 Mr. David Heacock President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glen Allen, VA 23060-6711 SUBJECT: MILLSTONE POWER STATION - NRC INTEGRATED INSPECTION REPORT 05000336/2010002 AND 05000423/2010002


==Dear Mr. Heacock:==
==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.
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.


Based on the results of this inspection, no findings of significance were identified.
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.


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 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.
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).


In addition.
ADAMS is accessible from the NRC Web Site at http://www.nrc.gov/reading-rm/adams.html(the Public Electronic Reading Room).


if you disagree with the characterization of the 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.
D~c9fL Donald E. Jackson, Chief Projects Branch 5 Division of Reactor Projects Docket Nos. 50-336, 50-423 License Nos. DPR-65, NPF-49
 
.  
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).
 
Donald E. Jackson, Chief Projects Branch 5 Division of Reactor Projects Docket Nos. License Nos. 50-336, 50-423 DPR-65, NPF-49 .  


===Enclosure:===
===Enclosure:===
Inspection Report No. 05 w/Attachment:
Inspection Report No. 05000336/2010002 and 05000423/2010002 w/Attachment: Supplemental Information
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.
REGION I==
Docket No.: 50-336, 50-423 License No . : DPR-65, NPF-49 Report No.: 05000336/2010002 and 05000423/2010002 licensee: Dominion Nuclear Connecticut, Inc.


DRP B. Haagensen, Resident Inspector, DRP D. Dodson, Project Engineer, DRP T. Moslak, Health Physicist.
Facility: Millstone Power Station, Units 2 and 3 Location: P. O. Box 128 Waterford, CT 06385 Dates: January 1, 2010 through March 31, 2010 Inspectors: 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)
Approved by: Donald E Jackson, Chief Projects Branch 5 Division of Reactor Projects Enclosure


Division of Reactor Safety (DRS) Donald E Jackson, Chief Projects Branch 5 Division of Reactor Projects Enclosure Table of Contents  
Table of Contents


=SUMMARY OF FINDINGS=
=SUMMARY OF FINDINGS=
.........................................................................................................
......................................................................................................... 3


=REPORT DETAILS=
=REPORT DETAILS=
  ..................................................................................................................... REACTOR SAFETy ........ : ................................................ , ................................................. 1 R01 Adverse Weather Protection  
  ..................................................................................................................... 4
.....................................................................................1 R04 Equipment Alignment  
 
...............................................................................................1 R05 Fire Protection  
REACTOR SAFETy ........ :................................................ ,................................................. 4
............................................................
 
_. _........................................... 1 R07 Heat Sink Performance  
{{a|1R01}}
............................................................................................ 1 R 11 Licensed Operator Requalification Program .............................................................
==1R01 Adverse Weather Protection .....................................................................................4==
 
{{a|1R04}}
==1R04 Equipment Alignment ............................................................................................... 4==
 
{{a|1R05}}
==1R05 Fire Protection ............................................................_. _........................................... 5==
 
{{a|1R07}}
==1R07 Heat Sink Performance ............................................................................................ 6==
 
1R 11 Licensed Operator Requalification Program ............................................................. 6
 
{{a|1R12}}
{{a|1R12}}
==1R12 Maintenance==
==1R12 Maintenance Effectiveness ....................................................................................... 7==
 
{{a|1R13}}
==1R13 Maintenance Risk Assessments and Emergent Work Control .................................. 8==


Effectiveness
....................................................................................... 1 R13 Maintenance Risk Assessments and Emergent Work Control ..................................
{{a|1R15}}
{{a|1R15}}
==1R15 Operability==
==1R15 Operability Evaluations ............................................................................................. 9==


Evaluations
{{a|1R18}}
............................................................................................. 1 R 18 Plant Modifications  
==1R18 Plant Modifications ....................................................................................................9==
....................................................................................................'IR19 Post-Maintenance Testing ...................................................................................... 1 R20 Refueling and Other Outage Activities  
 
........................................
    'IR19 Post-Maintenance Testing ...................................................................................... 10
_........................... 1 R22 Surveillance Testing ............................................................................................... 1 EP6 Drill Evaluation  
 
....................................................................................................... RADIATION SAFETy ....................................................................................................... 2RS01 Radiological Hazard Assessment and Exposure Controls ..................................... 2RS02 Occupational ALARA Planning and Controls
{{a|1R20}}
==1R20 Refueling and Other Outage Activities ........................................_........................... 11==
 
{{a|1R22}}
==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==
==OTHER ACTIVITIES==
[OA] ................................................................................................ 40A1 Performance Indicator (PI) Verification  
[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:  
................................................................... 40A2 Identification and Resolution of Problems .............................................................. 40A3 Event Follow-up  
..................................................................................................... 40A6 Meetings, including Exit ....................  
: ..................................................................... 40A7 Licensee Identified Violations  
.................................................................................. ATTACHMENT:  


=SUPPLEMENTAL
=SUPPLEMENTAL INFORMATION=
INFORMATION=


==KEY POINTS OF CONTACT==
==KEY POINTS OF CONTACT==
  .................  
  ................. ! . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1
! ....................................................................................  
 
==LIST OF ITEMS==
==LIST OF ITEMS==
OPENED, CLOSED. AND DISCUSSED  
OPENED, CLOSED. AND DISCUSSED .......................................................... 2
..........................................................  
==LIST OF DOCUMENTS==


==LIST OF DOCUMENTS REVIEWED==
.......................................................................................... 2
}}
}}

Revision as of 19:31, 13 November 2019

IR 05000336-10-002 and 05000423-10-002; on 01/01/2010 - 03/31/2010; Dominion Nuclear Connecticut Inc.; Millstone Power Station Units 2 and 3, NRC Integrated Inspection Report
ML101160284
Person / Time
Site: Millstone  Dominion icon.png
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)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION

REGION I

475 ALLENDALE ROAD KING OF PRUSSIA. PENNSYLVANIA 19406-1415 April 26, 2010 Mr. David Heacock President and Chief Nuclear Officer Dominion Resources 5000 Dominion Boulevard Glen Allen, VA 23060-6711 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. 50-336, 50-423 License Nos. DPR-65, NPF-49

.

Enclosure:

Inspection Report No. 05000336/2010002 and 05000423/2010002 w/Attachment: Supplemental Information

REGION I==

Docket No.: 50-336, 50-423 License No . : DPR-65, NPF-49 Report No.: 05000336/2010002 and 05000423/2010002 licensee: Dominion Nuclear Connecticut, Inc.

Facility: Millstone Power Station, Units 2 and 3 Location: P. O. Box 128 Waterford, CT 06385 Dates: January 1, 2010 through March 31, 2010 Inspectors: 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)

Approved by: Donald E Jackson, Chief Projects Branch 5 Division of Reactor Projects Enclosure

Table of Contents

SUMMARY OF FINDINGS

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

REPORT DETAILS

..................................................................................................................... 4

REACTOR SAFETy ........ :................................................ ,................................................. 4

1R01 Adverse Weather Protection .....................................................................................4

1R04 Equipment Alignment ............................................................................................... 4

1R05 Fire Protection ............................................................_. _........................................... 5

1R07 Heat Sink Performance ............................................................................................ 6

1R 11 Licensed Operator Requalification Program ............................................................. 6

1R12 Maintenance Effectiveness ....................................................................................... 7

1R13 Maintenance Risk Assessments and Emergent Work Control .................................. 8

1R15 Operability Evaluations ............................................................................................. 9

1R18 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

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