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| | number = ML061510365 | | | number = ML061510365 |
| | issue date = 05/31/2006 | | | issue date = 05/31/2006 |
| | title = Surry Unit 1, Relief, Third 10-Year ISI Interval | | | title = Relief, Third 10-Year ISI Interval |
| | author name = Monarque S R | | | author name = Monarque S |
| | author affiliation = NRC/NRR/ADRO/DORL | | | author affiliation = NRC/NRR/ADRO/DORL |
| | addressee name = Christian D A | | | addressee name = Christian D |
| | addressee affiliation = Virginia Electric & Power Co (VEPCO) | | | addressee affiliation = Virginia Electric & Power Co (VEPCO) |
| | docket = 05000280 | | | docket = 05000280 |
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| =Text= | | =Text= |
| {{#Wiki_filter:May 31, 2006Mr. 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 | | {{#Wiki_filter:May 31, 2006 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 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| SURRY POWER STATION, UNIT NO. 1 (SURRY 1 ) - CORRECTION TORELIEF REQUESTS PRT-07 AND PRT-08 (TAC NOS. MC6690 AND MC6707) | | SURRY POWER STATION, UNIT NO. 1 (SURRY 1 ) - CORRECTION TO RELIEF REQUESTS PRT-07 AND PRT-08 (TAC NOS. MC6690 AND MC6707) |
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| ==Dear Mr. Christian:== | | ==Dear Mr. Christian:== |
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| On March 28, 2006, the Nuclear Regulatory Commission (NRC) issued Relief RequestsPRT-07 and PRT-08 for Surry 1. These reliefs were in response to your application dated April 11, 2005. By letter dated April 27, 2006, you informed the NRC that the safety evaluations (SEs) for bothrelief requests contained a discrepancy. Your letter stated that these SEs provided the datesfor the third 10-year inservice inspection interval (ISI) at Surry 2, instead of the dates for the third 10-year ISI at Surry 1. The corrected pages for these SEs are enclosed with this letter. | | On March 28, 2006, the Nuclear Regulatory Commission (NRC) issued Relief Requests PRT-07 and PRT-08 for Surry 1. These reliefs were in response to your application dated April 11, 2005. |
| The revisions to the SEs are identified by lines in the margin.Sincerely,/RA/Stephen R. Monarque, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-280 | | By letter dated April 27, 2006, you informed the NRC that the safety evaluations (SEs) for both relief requests contained a discrepancy. Your letter stated that these SEs provided the dates for the third 10-year inservice inspection interval (ISI) at Surry 2, instead of the dates for the third 10-year ISI at Surry 1. The corrected pages for these SEs are enclosed with this letter. |
| | The revisions to the SEs are identified by lines in the margin. |
| | Sincerely, |
| | /RA/ |
| | Stephen R. Monarque, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-280 |
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| ==Enclosure:== | | ==Enclosure:== |
| Safety Evaluation cc w/encl: See next page | | Safety Evaluation cc w/encl: See next page |
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| ML061510365 NRR-028OFFICENRR/LPL2-1/PMNRR/LPL2-1/LANRR/LPL2-1/BCNAMESMonarque:srmMO'BrienEMarinos DATE5/17/065/18/065/26/06 listed therein. The ASME Code of record for the Surry 1 ISI program is the 1989 edition ofASME Code, Section XI. The licensee requested relief for the third 10-year ISI interval at Surry 1, which began on October 14, 1993, and ended on December 31, 2004. | | ML061510365 NRR-028 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/LPL2-1/BC NAME SMonarque:srm MOBrien EMarinos DATE 5/17/06 5/18/06 5/26/06 listed therein. The ASME Code of record for the Surry 1 ISI program is the 1989 edition of ASME Code, Section XI. The licensee requested relief for the third 10-year ISI interval at Surry 1, which began on October 14, 1993, and ended on December 31, 2004. l |
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| ==3.0TECHNICAL EVALUATION== | | ==3.0 TECHNICAL EVALUATION== |
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| 3.1ASME Code, Section XI Requirement The 1989 edition of ASME Code, Section XI, Article IWB-2500 requires that components beexamined and tested as specified in Table IWB-2500-1. Table IWB-2500-1, examination category B-A, item number B1.11 requires a volumetric examination of the RV circumferential shell welds once each 10-year ISI interval with essentially 100-percent volumetric coverage of the examination volume cross section specified in Figure IWB-2500-1 of ASME Code, Section XI, for essentially 100-percent of the weld length.3.2Component for Which Relief is RequestedCategory Item Description B-A B1.11 RV Circumferential Shell WeldsThe licensee has specifically requested relief for Circumferential Shell Weld 1-04 at Surry 1. This weld adjoins the RV shell with the lower vessel head.3.3Licensee's Basis for Relief Request The ultrasonic examination of the reactor pressure vessel circumferential shellweld is conducted in accordance with techniques qualified by demonstration for Appendix VIII, Supplements 4 and 6 of the 1995-96 Addenda of ASME [Code],Section XI.There are four core support lugs located at 0 degree, 90 degree, 180 degree,and 270 degree [azimuth] positions [at] the vessel inside surface just above the | | 3.1 ASME Code, Section XI Requirement The 1989 edition of ASME Code, Section XI, Article IWB-2500 requires that components be examined and tested as specified in Table IWB-2500-1. Table IWB-2500-1, examination category B-A, item number B1.11 requires a volumetric examination of the RV circumferential shell welds once each 10-year ISI interval with essentially 100-percent volumetric coverage of the examination volume cross section specified in Figure IWB-2500-1 of ASME Code, Section XI, for essentially 100-percent of the weld length. |
| [circumferential shell] weld which restrict[s] complete coverage of the required examination volume. The ultrasonic examination of this weld was performed by scanning the accessible scan surfaces between the support lugs and below the support lugs. Figure 1 [in the licensee's submittal] shows the general configuration of the reactor vessel and location of weld 1-04. Figures 2 and 3 [in the licensee's submittal] show the ultrasonic scanning boundaries for this weld with the restrictions due to the core support lugs. The size of the ultrasonic manipulator end effector limits how close the individual transducers can be positioned to the support lugs while scanning. The proximity of the end effector to the support lugs limits the amount of coverage obtained with each of the qualified transducers. Table 1 [in the licensee's submittal] provides the breakdown of percent [of] coverage of the required examination volume by scan direction and transducer. The achieved coverage of the required examinationvolume applying the qualified techniques is 73.4 [percent]. Relief Request PRT-08 lMay 26, 2006 l subject to the limitations and modifications listed therein. The ASME Code of record for theSurry 1 ISI program is the 1989 edition of ASME Code, Section XI. The licensee requested relief for the third 10-year ISI interval at Surry 1, which began on October 14, 1993, and ended lon December 31, 2004. | | 3.2 Component for Which Relief is Requested Category Item Description B-A B1.11 RV Circumferential Shell Welds The licensee has specifically requested relief for Circumferential Shell Weld 1-04 at Surry 1. |
| l | | This weld adjoins the RV shell with the lower vessel head. |
| | 3.3 Licensees Basis for Relief Request The ultrasonic examination of the reactor pressure vessel circumferential shell weld is conducted in accordance with techniques qualified by demonstration for Appendix VIII, Supplements 4 and 6 of the 1995-96 Addenda of ASME [Code], |
| | Section XI. |
| | There are four core support lugs located at 0 degree, 90 degree, 180 degree, and 270 degree [azimuth] positions [at] the vessel inside surface just above the |
| | [circumferential shell] weld which restrict[s] complete coverage of the required examination volume. The ultrasonic examination of this weld was performed by scanning the accessible scan surfaces between the support lugs and below the support lugs. Figure 1 [in the licensees submittal] shows the general configuration of the reactor vessel and location of weld 1-04. Figures 2 and 3 [in the licensees submittal] show the ultrasonic scanning boundaries for this weld with the restrictions due to the core support lugs. The size of the ultrasonic manipulator end effector limits how close the individual transducers can be positioned to the support lugs while scanning. The proximity of the end effector to the support lugs limits the amount of coverage obtained with each of the qualified transducers. Table 1 [in the licensees submittal] provides the breakdown of percent [of] coverage of the required examination volume by scan direction and transducer. The achieved coverage of the required examination volume applying the qualified techniques is 73.4 [percent]. |
| | Relief Request PRT-08 l May 26, 2006 l |
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| ==3.0TECHNICAL EVALUATION==
| | subject to the limitations and modifications listed therein. The ASME Code of record for the Surry 1 ISI program is the 1989 edition of ASME Code, Section XI. The licensee requested relief for the third 10-year ISI interval at Surry 1, which began on October 14, 1993, and ended l on December 31, 2004. l |
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| 3.1ASME Code, Section XI Requirement The 1989 edition of ASME Code, Section XI, Article IWB-2500, requires that components beexamined and tested as specified in Table IWB-2500-1. Table IWB-2500-1, examination category B-A, Item Number B1.30, requires a volumetric examination of the RV shell-to-flange weld once each 10-year ISI interval, with essentially 100-percent volumetric coverage of the examination volume specified in Figure IWB-2500-4 of ASME Code, Section XI.3.2Component for Which Relief is Requested Category Item Description B-A B1.30 RV Shell-to-Flange Weld 3.3Licensee's Basis for Relief Request The ultrasonic examination of the reactor vessel shell-to-flange weld wasperformed using a combination of manual and remote automated ultrasonic examination techniques. The manual examination was applied from the flange surface with techniques in accordance with the requirements of ASME Section V, Article 4. The remote automated ultrasonic examinations were performed from the vessel shell inside surface using techniques qualified by demonstration for Appendix VIII, Supplements 4 and 6 of the 1995-1996 Addenda of ASME Section XI as allowed by approved relief request SR-030 (NRC letter datedOctober 16, 2004). These automated techniques are noted to produce more accurate, reliable and repeatable procedures of examinations than the standard | | ==3.0 TECHNICAL EVALUATION== |
| [ASME Code] Section V techniques previously used.Figure 1 [of the licensee's submittal] shows the reactor vessel and associatedwelds. Figures 2 and 3 [of the licensee's submittal] illustrate the weld profile andshow scan orientation and directions. Coverage of the examination volume is obtained by combining the manual examination performed from the flange surface with the automated coverage obtained from the vessel shell surface. The examination performed from the flange surface provides examination coverage with the ultrasonic sound beam directed essentially normal to the weld axis. Coverage from the flange provides coverage of the examination volume in one beam direction, perpendicular to the weld axis. The ASME Section XI, Appendix VIII, Supplements 4 and 6 techniques are applied from the vesselinside surface, scanning in four directions to the extent possible. Due to the surface geometry of the flange, the ability to scan the necessary areas to providecomplete coverage of the examination volume in four directions is limited. The examination tool end effector, which holds the ultrasonic transducers, is not able to maintain the necessary surface contact on the non-parallel surface of theRelief Request PRT-07 lMay 26, 2006 l | | |
| Surry Power Station, Units 1 & 2 cc:Ms. Lillian M. Cuoco, Esq.Senior Counsel Dominion Resources Services, Inc. | | 3.1 ASME Code, Section XI Requirement The 1989 edition of ASME Code, Section XI, Article IWB-2500, requires that components be examined and tested as specified in Table IWB-2500-1. Table IWB-2500-1, examination category B-A, Item Number B1.30, requires a volumetric examination of the RV shell-to-flange weld once each 10-year ISI interval, with essentially 100-percent volumetric coverage of the examination volume specified in Figure IWB-2500-4 of ASME Code, Section XI. |
| Building 475, 5th Floor Rope Ferry Road Waterford, Connecticut 06385Mr. Donald E. JerniganSite Vice President Surry Power Station Virginia Electric and Power Company 5570 Hog Island Road Surry, Virginia 23883-0315Senior Resident InspectorSurry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883ChairmanBoard of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683Dr. W. T. LoughVirginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218Dr. Robert B. Stroube, MD, MPHState Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218Office of the Attorney GeneralCommonwealth of Virginia 900 East Main Street Richmond, Virginia 23219Mr. Chris L. Funderburk, DirectorNuclear Licensing & Operations Support Dominion Resources Services, Inc. | | 3.2 Component for Which Relief is Requested Category Item Description B-A B1.30 RV Shell-to-Flange Weld 3.3 Licensees Basis for Relief Request The ultrasonic examination of the reactor vessel shell-to-flange weld was performed using a combination of manual and remote automated ultrasonic examination techniques. The manual examination was applied from the flange surface with techniques in accordance with the requirements of ASME Section V, Article 4. The remote automated ultrasonic examinations were performed from the vessel shell inside surface using techniques qualified by demonstration for Appendix VIII, Supplements 4 and 6 of the 1995-1996 Addenda of ASME Section XI as allowed by approved relief request SR-030 (NRC letter dated October 16, 2004). These automated techniques are noted to produce more accurate, reliable and repeatable procedures of examinations than the standard |
| Innsbrook Technical Center 5000 Dominion Blvd.
| | [ASME Code] Section V techniques previously used. |
| Glen Allen, Virginia 23060-6711}}
| | Figure 1 [of the licensees submittal] shows the reactor vessel and associated welds. Figures 2 and 3 [of the licensees submittal] illustrate the weld profile and show scan orientation and directions. Coverage of the examination volume is obtained by combining the manual examination performed from the flange surface with the automated coverage obtained from the vessel shell surface. |
| | The examination performed from the flange surface provides examination coverage with the ultrasonic sound beam directed essentially normal to the weld axis. Coverage from the flange provides coverage of the examination volume in one beam direction, perpendicular to the weld axis. The ASME Section XI, Appendix VIII, Supplements 4 and 6 techniques are applied from the vessel inside surface, scanning in four directions to the extent possible. Due to the surface geometry of the flange, the ability to scan the necessary areas to provide complete coverage of the examination volume in four directions is limited. The examination tool end effector, which holds the ultrasonic transducers, is not able to maintain the necessary surface contact on the non-parallel surface of the Relief Request PRT-07 l May 26, 2006 l |
| | |
| | Surry Power Station, Units 1 & 2 cc: |
| | Ms. Lillian M. Cuoco, Esq. Office of the Attorney General Senior Counsel Commonwealth of Virginia Dominion Resources Services, Inc. 900 East Main Street Building 475, 5th Floor Richmond, Virginia 23219 Rope Ferry Road Waterford, Connecticut 06385 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Mr. Donald E. Jernigan Dominion Resources Services, Inc. |
| | Site Vice President Innsbrook Technical Center Surry Power Station 5000 Dominion Blvd. |
| | Virginia Electric and Power Company Glen Allen, Virginia 23060-6711 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218}} |
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ML24095A2172024-04-12012 April 2024
– Review of the Spring 2023 Steam Generator Tube Inspection Report
ML24088A2482024-03-26026 March 2024
Inservice Testing Program for Pumps and Valves Sixth Interval Update and Associated Relief and Alternative Requests- Response to Request for Additional Information
ML24087A2082024-03-22022 March 2024
Proposed License Amendment Request Addition of Containment Limiting Condition for Operation and Surveillance Requirements
ML24078A2642024-03-21021 March 2024
– Regulatory Audit in Support of License Amendment Request to Proposed Reclassification of Regulatory Guide 1.97 Variable for Low Head Safety Injection Flow Instrumentation
ML24087A1522024-03-18018 March 2024
Annual Changes, Tests, and Experiments Report Regulatory Commitment Evaluation Report
ML24023A5762024-03-0808 March 2024
Correction to Issuance of Amendment Nos. 315 and 315, Regarding Revised Emergency Plan for Relocation of the Technical Support Center
IR 05000280/20230062024-02-28028 February 2024
Annual Assessment Letter for Surry Power Station, Units 1 and 2 - NRC Inspection Reports 05000280/2023006 and 05000281/2023006
ML24032A4712024-02-20020 February 2024
Exemption from Select Requirements of 10 CFR Part 73 - Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting
ML24051A1782024-02-19019 February 2024
Proposed License Amendment Request - Application to Revise Technical Specifications to Adopt TSTF-577, Revised Frequencies for Steam Generator Tube Inspections
ML24057A0612024-02-19019 February 2024
and Virgil C. Summer Power Nuclear Stations - Nuclear Property Insurance Coverage
IR 05000280/20230042024-02-0909 February 2024
Integrated Inspection Report 05000280/2023004 and 05000281/2023004
IR 05000280/20244012024-02-0606 February 2024
Security Baseline Inspection Report 05000280/2024401, 05000281/2024401 and 07200002/2024401
IR 05000280/20230102024-01-18018 January 2024
– Age Related Degradation Inspection Report 05000280-2023010 and 05000281-2023010
2024-09-03
[Table view] |
Text
May 31, 2006 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:
SURRY POWER STATION, UNIT NO. 1 (SURRY 1 ) - CORRECTION TO RELIEF REQUESTS PRT-07 AND PRT-08 (TAC NOS. MC6690 AND MC6707)
Dear Mr. Christian:
On March 28, 2006, the Nuclear Regulatory Commission (NRC) issued Relief Requests PRT-07 and PRT-08 for Surry 1. These reliefs were in response to your application dated April 11, 2005.
By letter dated April 27, 2006, you informed the NRC that the safety evaluations (SEs) for both relief requests contained a discrepancy. Your letter stated that these SEs provided the dates for the third 10-year inservice inspection interval (ISI) at Surry 2, instead of the dates for the third 10-year ISI at Surry 1. The corrected pages for these SEs are enclosed with this letter.
The revisions to the SEs are identified by lines in the margin.
Sincerely,
/RA/
Stephen R. Monarque, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-280
Enclosure:
Safety Evaluation cc w/encl: See next page
ML061510365 NRR-028 OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/LPL2-1/BC NAME SMonarque:srm MOBrien EMarinos DATE 5/17/06 5/18/06 5/26/06 listed therein. The ASME Code of record for the Surry 1 ISI program is the 1989 edition of ASME Code,Section XI. The licensee requested relief for the third 10-year ISI interval at Surry 1, which began on October 14, 1993, and ended on December 31, 2004. l
3.0 TECHNICAL EVALUATION
3.1 ASME Code,Section XI Requirement The 1989 edition of ASME Code,Section XI, Article IWB-2500 requires that components be examined and tested as specified in Table IWB-2500-1. Table IWB-2500-1, examination category B-A, item number B1.11 requires a volumetric examination of the RV circumferential shell welds once each 10-year ISI interval with essentially 100-percent volumetric coverage of the examination volume cross section specified in Figure IWB-2500-1 of ASME Code,Section XI, for essentially 100-percent of the weld length.
3.2 Component for Which Relief is Requested Category Item Description B-A B1.11 RV Circumferential Shell Welds The licensee has specifically requested relief for Circumferential Shell Weld 1-04 at Surry 1.
This weld adjoins the RV shell with the lower vessel head.
3.3 Licensees Basis for Relief Request The ultrasonic examination of the reactor pressure vessel circumferential shell weld is conducted in accordance with techniques qualified by demonstration for Appendix VIII, Supplements 4 and 6 of the 1995-96 Addenda of ASME [Code],
Section XI.
There are four core support lugs located at 0 degree, 90 degree, 180 degree, and 270 degree [azimuth] positions [at] the vessel inside surface just above the
[circumferential shell] weld which restrict[s] complete coverage of the required examination volume. The ultrasonic examination of this weld was performed by scanning the accessible scan surfaces between the support lugs and below the support lugs. Figure 1 [in the licensees submittal] shows the general configuration of the reactor vessel and location of weld 1-04. Figures 2 and 3 [in the licensees submittal] show the ultrasonic scanning boundaries for this weld with the restrictions due to the core support lugs. The size of the ultrasonic manipulator end effector limits how close the individual transducers can be positioned to the support lugs while scanning. The proximity of the end effector to the support lugs limits the amount of coverage obtained with each of the qualified transducers. Table 1 [in the licensees submittal] provides the breakdown of percent [of] coverage of the required examination volume by scan direction and transducer. The achieved coverage of the required examination volume applying the qualified techniques is 73.4 [percent].
Relief Request PRT-08 l May 26, 2006 l
subject to the limitations and modifications listed therein. The ASME Code of record for the Surry 1 ISI program is the 1989 edition of ASME Code,Section XI. The licensee requested relief for the third 10-year ISI interval at Surry 1, which began on October 14, 1993, and ended l on December 31, 2004. l
3.0 TECHNICAL EVALUATION
3.1 ASME Code,Section XI Requirement The 1989 edition of ASME Code,Section XI, Article IWB-2500, requires that components be examined and tested as specified in Table IWB-2500-1. Table IWB-2500-1, examination category B-A, Item Number B1.30, requires a volumetric examination of the RV shell-to-flange weld once each 10-year ISI interval, with essentially 100-percent volumetric coverage of the examination volume specified in Figure IWB-2500-4 of ASME Code,Section XI.
3.2 Component for Which Relief is Requested Category Item Description B-A B1.30 RV Shell-to-Flange Weld 3.3 Licensees Basis for Relief Request The ultrasonic examination of the reactor vessel shell-to-flange weld was performed using a combination of manual and remote automated ultrasonic examination techniques. The manual examination was applied from the flange surface with techniques in accordance with the requirements of ASME Section V, Article 4. The remote automated ultrasonic examinations were performed from the vessel shell inside surface using techniques qualified by demonstration for Appendix VIII, Supplements 4 and 6 of the 1995-1996 Addenda of ASME Section XI as allowed by approved relief request SR-030 (NRC letter dated October 16, 2004). These automated techniques are noted to produce more accurate, reliable and repeatable procedures of examinations than the standard
[ASME Code] Section V techniques previously used.
Figure 1 [of the licensees submittal] shows the reactor vessel and associated welds. Figures 2 and 3 [of the licensees submittal] illustrate the weld profile and show scan orientation and directions. Coverage of the examination volume is obtained by combining the manual examination performed from the flange surface with the automated coverage obtained from the vessel shell surface.
The examination performed from the flange surface provides examination coverage with the ultrasonic sound beam directed essentially normal to the weld axis. Coverage from the flange provides coverage of the examination volume in one beam direction, perpendicular to the weld axis. The ASME Section XI, Appendix VIII, Supplements 4 and 6 techniques are applied from the vessel inside surface, scanning in four directions to the extent possible. Due to the surface geometry of the flange, the ability to scan the necessary areas to provide complete coverage of the examination volume in four directions is limited. The examination tool end effector, which holds the ultrasonic transducers, is not able to maintain the necessary surface contact on the non-parallel surface of the Relief Request PRT-07 l May 26, 2006 l
Surry Power Station, Units 1 & 2 cc:
Ms. Lillian M. Cuoco, Esq. Office of the Attorney General Senior Counsel Commonwealth of Virginia Dominion Resources Services, Inc. 900 East Main Street Building 475, 5th Floor Richmond, Virginia 23219 Rope Ferry Road Waterford, Connecticut 06385 Mr. Chris L. Funderburk, Director Nuclear Licensing & Operations Support Mr. Donald E. Jernigan Dominion Resources Services, Inc.
Site Vice President Innsbrook Technical Center Surry Power Station 5000 Dominion Blvd.
Virginia Electric and Power Company Glen Allen, Virginia 23060-6711 5570 Hog Island Road Surry, Virginia 23883-0315 Senior Resident Inspector Surry Power Station U. S. Nuclear Regulatory Commission 5850 Hog Island Road Surry, Virginia 23883 Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, Virginia 23683 Dr. W. T. Lough Virginia State Corporation Commission Division of Energy Regulation Post Office Box 1197 Richmond, Virginia 23218 Dr. Robert B. Stroube, MD, MPH State Health Commissioner Office of the Commissioner Virginia Department of Health Post Office Box 2448 Richmond, Virginia 23218
