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| number = ML070820079
| number = ML070820079
| issue date = 03/29/2007
| issue date = 03/29/2007
| title = Confirmatory Action Letter (TAC Nos. MD4163 and MD4164)
| title = Confirmatory Action Letter
| author name = Dyer J
| author name = Dyer J
| author affiliation = NRC/NRR
| author affiliation = NRC/NRR
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:March 29, 2007CAL No. NRR-07-021Mr. David A. ChristianSenior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711
{{#Wiki_filter:March 29, 2007 CAL No. NRR-07-021 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711


==SUBJECT:==
==SUBJECT:==
CONFIRMATORY ACTION LETTER - NORTH ANNA POWER STATION, UNITNOS. 1 AND 2 (TAC NOS. MD4163 AND MD4164)
CONFIRMATORY ACTION LETTER - NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2 (TAC NOS. MD4163 AND MD4164)


==Dear Mr. Christian:==
==Dear Mr. Christian:==


This letter confirms commitments by Virginia Electric and Power Company (Dominion)regarding Alloy 82/182 butt welds in the pressurizers at North Anna Power Station, Unit Nos.
This letter confirms commitments by Virginia Electric and Power Company (Dominion) regarding Alloy 82/182 butt welds in the pressurizers at North Anna Power Station, Unit Nos.
1 and 2.
The discovery, in October 2006, of five circumferential indications in three dissimilar metal (DM) welds on the pressurizer at the Wolf Creek Generating Station (Wolf Creek) raised safety concerns based on the size and location of the indications. At Wolf Creek, three indications were in the pressurizer surge nozzle-to-safe end weld, and two separate indications were in the safety and relief nozzle-to-safe end welds. These findings also indicated that significant concerns might exist with the inspection schedules for addressing the pressurizer weld concerns issued by the industry-sponsored Materials Reliability Program (MRP), in Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139).
The Nuclear Regulatory Commission (NRC) is concerned about the pressurizer surge nozzle-to-safe end weld indications, as this is the first time that multiple circumferential primary water stress-corrosion cracking (PWSCC) indications have been identified in a weld. This condition calls into question the degree of safety margin present in past structural integrity evaluations for flawed DM welds susceptible to PWSCC, since multiple stress-corrosion cracking flaws may grow independently and ultimately grow together, significantly reducing the time from flaw initiation to leakage or rupture. The size of the relief nozzle-to-safe end flaw is also of concern, as this flaw has a much larger aspect ratio than those assumed in the estimates used to establish the basis for completing the baseline inspections required by the industry-sponsored MRP. Larger aspect ratios could result in achieving a critical flaw size and rupture before the onset of detectable leakage.
The long-term resolution of this issue is expected to involve changes to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), and will involve changes to the NRC regulations in Title 10 of the Code of Federal Regulations (10 CFR),
Part 50, Section 50.55a, Codes and standards. The development of the NRC regulations, whether the rule adopts the ASME Code standards or defines separate requirements, will likely


1 and 2.
D. Christian                                     benefit from additional operating experience, continuing assessments, and analysis being conducted by the NRC and the MRP.
The discovery, in October 2006, of five circumferential indications in three dissimilar metal (DM)welds on the pressurizer at the Wolf Creek Generating Station (Wolf Creek) raised safetyconcerns based on the size and location of the indications. At Wolf Creek, three indicationswere in the pressurizer surge nozzle-to-safe end weld, and two separate indications were in thesafety and relief nozzle-to-safe end welds. These findings also indicated that significantconcerns might exist with the inspection schedules for addressing the pressurizer weldconcerns issued by the industry-sponsored Materials Reliability Program (MRP), in "PrimarySystem Piping Butt Weld Inspection and Evaluation Guideline (MRP-139)."The Nuclear Regulatory Commission (NRC) is concerned about the pressurizer surge nozzle-to-safe end weld indications, as this is the first time that multiple circumferential primarywater stress-corrosion cracking (PWSCC) indications have been identified in a weld. Thiscondition calls into question the degree of safety margin present in past structural integrityevaluations for flawed DM welds susceptible to PWSCC, since multiple stress-corrosioncracking flaws may grow independently and ultimately grow together, significantly reducing thetime from flaw initiation to leakage or rupture. The size of the relief nozzle-to-safe end flaw isalso of concern, as this flaw has a much larger aspect ratio than those assumed in theestimates used to establish the basis for completing the baseline inspections required by theindustry-sponsored MRP. Larger aspect ratios could result in achieving a critical flaw size andrupture before the onset of detectable leakage. The long-term resolution of this issue is expected to involve changes to the American Society ofMechanical Engineers Boiler and Pressure Vessel Code (ASME Code), and will involvechanges to the NRC regulations in Title 10 of the Code of Federal Regulations (10 CFR),Part 50, Section 50.55a, "Codes and standards."  The development of the NRC regulations,whether the rule adopts the ASME Code standards or defines separate requirements, will likely D. Christian                                                     benefit from additional operating experience, continuing assessments, and analysis beingconducted by the NRC and the MRP.Until NRC regulations are revised, it is necessary to establish a minimum set of enhancedreactor coolant system (RCS) DM butt weld inspection expectations for nickel-basedAlloy 82/182 pressurizer surge, spray, safety, and relief nozzle butt welds, including safe endwelds, to supplement existing inspection and other requirements of the ASME Code and NRCregulations. In addition, enhanced monitoring of RCS leakage is needed to promptly identifyany through-wall flaws in the pressurizer surge, spray, safety, or relief nozzle DM butt welds orsafe end DM butt welds to prevent additional degradation from occurring. The above actionsprovide reasonable assurance that there is no undue risk to the health and safety of the publicwhile the NRC regulations are revised. The NRC communicated the need for near-term enhancements to the industry through publicmeetings held on November 30, 2006, December 20, 2006, and February 2, 2007. Licenseessubmitted letters voluntarily committing to the enhanced inspection and leakage monitoringrequirements. After teleconferences with specific licensees held between February 12 throughFebruary 23, 2007, the licensees submitted supplemental commitment letters addressing theNRC staff's concerns regarding inspection, compensatory actions, and reporting.In your letter dated February 26, 2007 (Agencywide Documents Access & Management System(ADAMS) Accession Number ML070570535), you described actions you will take at North Anna Power Station, Unit Nos. 1 and 2, for the pressurizer dissimilar metal butt welds containing Alloy 82/182 material. These commitments address: 1) completion schedules for inspection/mitigation of the welds; 2) RCS leak monitoring frequency, action levels, and actions; and 3) reporting requirements.The NRC staff has reviewed these actions and commitments and agrees the actions andcommitments are appropriate to address the potential of PWSCC of the applicable pressurizer dissimilar metal butt welds containing Alloy 82/182 material.Pursuant to Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, you are required to:1)Notify me immediately if your understanding differs from that set forth above; 2)Notify me if for any reason you cannot complete the actions and commitments     within the specified schedule and advise me in writing of your modified schedule in advance of the change; and3)Notify me in writing when you have completed the actions and commitments         addressed in this Confirmatory Action Letter.Issuance of this Confirmatory Action Letter does not preclude issuance of an order formalizingthe above commitments or requiring other actions on the part of the licensee; nor does it preclude the NRC from taking enforcement action for violations of NRC requirements that may have prompted the issuance of this letter. In addition, failure to take the actions addressed in this Confirmatory Action Letter may result in enforcement action.In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and D. Christian                                                     your response will be made available electronically for public inspection in the NRC PublicDocument Room or from the NRC's ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should notinclude any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.390(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.Sincerely,/RA/J. E. Dyer, Director Office of Nuclear Reactor RegulationDocket Nos. 50-338 and 50-339License Nos. NPF-4 and NPF-7cc: See next page  
Until NRC regulations are revised, it is necessary to establish a minimum set of enhanced reactor coolant system (RCS) DM butt weld inspection expectations for nickel-based Alloy 82/182 pressurizer surge, spray, safety, and relief nozzle butt welds, including safe end welds, to supplement existing inspection and other requirements of the ASME Code and NRC regulations. In addition, enhanced monitoring of RCS leakage is needed to promptly identify any through-wall flaws in the pressurizer surge, spray, safety, or relief nozzle DM butt welds or safe end DM butt welds to prevent additional degradation from occurring. The above actions provide reasonable assurance that there is no undue risk to the health and safety of the public while the NRC regulations are revised.
The NRC communicated the need for near-term enhancements to the industry through public meetings held on November 30, 2006, December 20, 2006, and February 2, 2007. Licensees submitted letters voluntarily committing to the enhanced inspection and leakage monitoring requirements. After teleconferences with specific licensees held between February 12 through February 23, 2007, the licensees submitted supplemental commitment letters addressing the NRC staffs concerns regarding inspection, compensatory actions, and reporting.
In your letter dated February 26, 2007 (Agencywide Documents Access & Management System (ADAMS) Accession Number ML070570535), you described actions you will take at North Anna Power Station, Unit Nos. 1 and 2, for the pressurizer dissimilar metal butt welds containing Alloy 82/182 material. These commitments address: 1) completion schedules for inspection/mitigation of the welds; 2) RCS leak monitoring frequency, action levels, and actions; and 3) reporting requirements.
The NRC staff has reviewed these actions and commitments and agrees the actions and commitments are appropriate to address the potential of PWSCC of the applicable pressurizer dissimilar metal butt welds containing Alloy 82/182 material.
Pursuant to Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, you are required to:
: 1)     Notify me immediately if your understanding differs from that set forth above;
: 2)     Notify me if for any reason you cannot complete the actions and commitments within the specified schedule and advise me in writing of your modified schedule in advance of the change; and
: 3)     Notify me in writing when you have completed the actions and commitments addressed in this Confirmatory Action Letter.
Issuance of this Confirmatory Action Letter does not preclude issuance of an order formalizing the above commitments or requiring other actions on the part of the licensee; nor does it preclude the NRC from taking enforcement action for violations of NRC requirements that may have prompted the issuance of this letter. In addition, failure to take the actions addressed in this Confirmatory Action Letter may result in enforcement action.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and
 
D. Christian                                     your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.390(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.
Sincerely,
                                                      /RA/
J. E. Dyer, Director Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339 License Nos. NPF-4 and NPF-7 cc: See next page


ML070820079 OFFICECPNBDCILPL2-1PMLPL2-1LALPL2-1/BCTECH EDDIRS/TANAMEKHoffmanESullivanSLingamMO'BrienEMarinosHChangRPascarelliDATE  3/26/073/27/07322/073/22/073/26/07 2/28/073/26/07 OFFICECPNB/BCDRP/D RGN2DORL/DDCI/DAD:DESNRR/D NAMETChanCCastoJlubinski for CHaneyMEvansJGrobeJDyerDATE 3/27073/27/073/27/07   3/28/073/28/073/ 29/07 North Anna Power Station, Units 1 & 2 cc:
ML070820079 OFFICE          CPNB          DCI          LPL2-1PM        LPL2-1LA      LPL2-1/BC        TECH ED      DIRS/TA NAME            KHoffman      ESullivan    SLingam        MOBrien      EMarinos        HChang      RPascarelli DATE              3/26/07      3/27/07      322/07          3/22/07        3/26/07           2/28/07    3/26/07 OFFICE          CPNB/BC        DRP/D RGN2          DORL/D          DCI/D            AD:DES            NRR/D NAME              TChan        CCasto              Jlubinski for   MEvans            JGrobe            JDyer CHaney DATE          3/2707          3/27/07              3/27/07           3/28/07        3/28/07          3/ 29/07 North Anna Power Station, Units 1 & 2 cc:
Mr. David A. ChristianSenior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrooks Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711Mr. C. Lee LintecumCounty Administrator Louisa County Post Office Box 160 Louisa, Virginia 23093Ms. Lillian M. Cuoco, Esq.Senior Counsel Dominion Resources Services, Inc.
Mr. David A. Christian                Senior Resident Inspector Senior Vice President                 North Anna Power Station and Chief Nuclear Officer           U. S. Nuclear Regulatory Commission Virginia Electric and Power Company   P. O. Box 490 Innsbrooks Technical Center           Mineral, Virginia 23117 5000 Dominion Boulevard Glen Allen, VA 23060-6711              Mr. Daniel G. Stoddard Site Vice President Mr. C. Lee Lintecum                    North Anna Power Station County Administrator                   Virginia Electric and Power Company Louisa County                         Post Office Box 402 Post Office Box 160                   Mineral, Virginia 23117-0402 Louisa, Virginia 23093 Dr. Robert B. Stroube, MD, MPH Ms. Lillian M. Cuoco, Esq.             State Health Commissioner Senior Counsel                         Office of the Commissioner Dominion Resources Services, Inc.     Virginia Department of Health Building 475, 5 th floor              Post Office Box 2448 Rope Ferry Road                       Richmond, Virginia 23218 Waterford, Connecticut 06385 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Old Dominion Electric Cooperative 4201 Dominion Blvd.
Building 475, 5 th floorRope Ferry Road Waterford, Connecticut 06385Dr. W. T. LoughVirginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218Old Dominion Electric Cooperative4201 Dominion Blvd.
Glen Allen, Virginia 23060 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.
Glen Allen, Virginia 23060Mr. Chris L. Funderburk, DirectorNuclear Licensing & Operations Support Dominion Resources Services, Inc.
Innsbrook Technical Center 5000 Dominion Blvd.
Innsbrook Technical Center 5000 Dominion Blvd.
Glen Allen, Virginia 23060-6711Office of the Attorney GeneralCommonwealth of Virginia 900 East Main Street Richmond, Virginia 23219Senior Resident InspectorNorth Anna Power Station U. S. Nuclear Regulatory Commission P. O. Box 490 Mineral, Virginia  23117Mr. Daniel G. StoddardSite Vice President North Anna Power Station Virginia Electric and Power Company Post Office Box 402 Mineral, Virginia  23117-0402Dr. Robert B. Stroube, MD, MPHState Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia  23218}}
Glen Allen, Virginia 23060-6711 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219}}

Latest revision as of 21:29, 22 March 2020

Confirmatory Action Letter
ML070820079
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 03/29/2007
From: Dyer J
Office of Nuclear Reactor Regulation
To: Christian D
Virginia Electric & Power Co (VEPCO)
Lingam, Siva NRR/DORL 415-1564
References
TAC MD4163, TAC MD4164, NRR-07-021
Download: ML070820079 (5)


Text

March 29, 2007 CAL No. NRR-07-021 Mr. David A. Christian Senior Vice President and Chief Nuclear Officer Virginia Electric and Power Company Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060-6711

SUBJECT:

CONFIRMATORY ACTION LETTER - NORTH ANNA POWER STATION, UNIT NOS. 1 AND 2 (TAC NOS. MD4163 AND MD4164)

Dear Mr. Christian:

This letter confirms commitments by Virginia Electric and Power Company (Dominion) regarding Alloy 82/182 butt welds in the pressurizers at North Anna Power Station, Unit Nos.

1 and 2.

The discovery, in October 2006, of five circumferential indications in three dissimilar metal (DM) welds on the pressurizer at the Wolf Creek Generating Station (Wolf Creek) raised safety concerns based on the size and location of the indications. At Wolf Creek, three indications were in the pressurizer surge nozzle-to-safe end weld, and two separate indications were in the safety and relief nozzle-to-safe end welds. These findings also indicated that significant concerns might exist with the inspection schedules for addressing the pressurizer weld concerns issued by the industry-sponsored Materials Reliability Program (MRP), in Primary System Piping Butt Weld Inspection and Evaluation Guideline (MRP-139).

The Nuclear Regulatory Commission (NRC) is concerned about the pressurizer surge nozzle-to-safe end weld indications, as this is the first time that multiple circumferential primary water stress-corrosion cracking (PWSCC) indications have been identified in a weld. This condition calls into question the degree of safety margin present in past structural integrity evaluations for flawed DM welds susceptible to PWSCC, since multiple stress-corrosion cracking flaws may grow independently and ultimately grow together, significantly reducing the time from flaw initiation to leakage or rupture. The size of the relief nozzle-to-safe end flaw is also of concern, as this flaw has a much larger aspect ratio than those assumed in the estimates used to establish the basis for completing the baseline inspections required by the industry-sponsored MRP. Larger aspect ratios could result in achieving a critical flaw size and rupture before the onset of detectable leakage.

The long-term resolution of this issue is expected to involve changes to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code), and will involve changes to the NRC regulations in Title 10 of the Code of Federal Regulations (10 CFR),

Part 50, Section 50.55a, Codes and standards. The development of the NRC regulations, whether the rule adopts the ASME Code standards or defines separate requirements, will likely

D. Christian benefit from additional operating experience, continuing assessments, and analysis being conducted by the NRC and the MRP.

Until NRC regulations are revised, it is necessary to establish a minimum set of enhanced reactor coolant system (RCS) DM butt weld inspection expectations for nickel-based Alloy 82/182 pressurizer surge, spray, safety, and relief nozzle butt welds, including safe end welds, to supplement existing inspection and other requirements of the ASME Code and NRC regulations. In addition, enhanced monitoring of RCS leakage is needed to promptly identify any through-wall flaws in the pressurizer surge, spray, safety, or relief nozzle DM butt welds or safe end DM butt welds to prevent additional degradation from occurring. The above actions provide reasonable assurance that there is no undue risk to the health and safety of the public while the NRC regulations are revised.

The NRC communicated the need for near-term enhancements to the industry through public meetings held on November 30, 2006, December 20, 2006, and February 2, 2007. Licensees submitted letters voluntarily committing to the enhanced inspection and leakage monitoring requirements. After teleconferences with specific licensees held between February 12 through February 23, 2007, the licensees submitted supplemental commitment letters addressing the NRC staffs concerns regarding inspection, compensatory actions, and reporting.

In your letter dated February 26, 2007 (Agencywide Documents Access & Management System (ADAMS) Accession Number ML070570535), you described actions you will take at North Anna Power Station, Unit Nos. 1 and 2, for the pressurizer dissimilar metal butt welds containing Alloy 82/182 material. These commitments address: 1) completion schedules for inspection/mitigation of the welds; 2) RCS leak monitoring frequency, action levels, and actions; and 3) reporting requirements.

The NRC staff has reviewed these actions and commitments and agrees the actions and commitments are appropriate to address the potential of PWSCC of the applicable pressurizer dissimilar metal butt welds containing Alloy 82/182 material.

Pursuant to Section 182 of the Atomic Energy Act, 42 U.S.C. 2232, you are required to:

1) Notify me immediately if your understanding differs from that set forth above;
2) Notify me if for any reason you cannot complete the actions and commitments within the specified schedule and advise me in writing of your modified schedule in advance of the change; and
3) Notify me in writing when you have completed the actions and commitments addressed in this Confirmatory Action Letter.

Issuance of this Confirmatory Action Letter does not preclude issuance of an order formalizing the above commitments or requiring other actions on the part of the licensee; nor does it preclude the NRC from taking enforcement action for violations of NRC requirements that may have prompted the issuance of this letter. In addition, failure to take the actions addressed in this Confirmatory Action Letter may result in enforcement action.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and

D. Christian your response will be made available electronically for public inspection in the NRC Public Document Room or from the NRCs ADAMS, accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html. To the extent possible, your response should not include any personal privacy, proprietary, or safeguards information so that it can be made available to the Public without redaction. If personal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you must specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.390(b) to support a request for withholding confidential commercial or financial information). If safeguards information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

Sincerely,

/RA/

J. E. Dyer, Director Office of Nuclear Reactor Regulation Docket Nos. 50-338 and 50-339 License Nos. NPF-4 and NPF-7 cc: See next page

ML070820079 OFFICE CPNB DCI LPL2-1PM LPL2-1LA LPL2-1/BC TECH ED DIRS/TA NAME KHoffman ESullivan SLingam MOBrien EMarinos HChang RPascarelli DATE 3/26/07 3/27/07 322/07 3/22/07 3/26/07 2/28/07 3/26/07 OFFICE CPNB/BC DRP/D RGN2 DORL/D DCI/D AD:DES NRR/D NAME TChan CCasto Jlubinski for MEvans JGrobe JDyer CHaney DATE 3/2707 3/27/07 3/27/07 3/28/07 3/28/07 3/ 29/07 North Anna Power Station, Units 1 & 2 cc:

Mr. David A. Christian Senior Resident Inspector Senior Vice President North Anna Power Station and Chief Nuclear Officer U. S. Nuclear Regulatory Commission Virginia Electric and Power Company P. O. Box 490 Innsbrooks Technical Center Mineral, Virginia 23117 5000 Dominion Boulevard Glen Allen, VA 23060-6711 Mr. Daniel G. Stoddard Site Vice President Mr. C. Lee Lintecum North Anna Power Station County Administrator Virginia Electric and Power Company Louisa County Post Office Box 402 Post Office Box 160 Mineral, Virginia 23117-0402 Louisa, Virginia 23093 Dr. Robert B. Stroube, MD, MPH Ms. Lillian M. Cuoco, Esq. State Health Commissioner Senior Counsel Office of the Commissioner Dominion Resources Services, Inc. Virginia Department of Health Building 475, 5 th floor Post Office Box 2448 Rope Ferry Road Richmond, Virginia 23218 Waterford, Connecticut 06385 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Old Dominion Electric Cooperative 4201 Dominion Blvd.

Glen Allen, Virginia 23060 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Dominion Resources Services, Inc.

Innsbrook Technical Center 5000 Dominion Blvd.

Glen Allen, Virginia 23060-6711 Office of the Attorney General Commonwealth of Virginia 900 East Main Street Richmond, Virginia 23219