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MONTHYEARML0515302672005-06-0303 June 2005 6/3/05, Beaver Valley, RAI, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI L-05-123, Response to Request for Additional Information on Generic Letter 2004-022005-07-22022 July 2005 Response to Request for Additional Information on Generic Letter 2004-02 Project stage: Response to RAI ML0603803422006-02-0909 February 2006 Request for Additional Information Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized-Water Reactors TAC Nos. MC4665 and MC4666 Project stage: RAI ML0613802732006-05-18018 May 2006 Request for Scheduler Extension from Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors (TAC No. MC46666) Project stage: Other L-08-054, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions2008-02-14014 February 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Corrective Actions Project stage: Request L-08-035, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors2008-02-29029 February 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized - Water Reactors Project stage: Supplement ML0812301162008-02-29029 February 2008 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors,... Project stage: Other L-08-257, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions2008-08-28028 August 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Request for Extension of Completion Date for Corrective Actions Project stage: Request ML0827402412008-09-30030 September 2008 Extension Request Approval Letter Generic Letter 2004--02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Other L-08-321, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors2008-10-29029 October 2008 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Supplement L-09-056, Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps2009-03-11011 March 2009 Downstream Effects for Recirculation Spray System Pumps and Low Head Safety Injection System Pumps Project stage: Other ML0909001932009-03-31031 March 2009 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Project stage: Other ML0910501002009-04-21021 April 2009 Correction Letter Extension Request Approval to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: Other L-09-131, Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions2009-04-30030 April 2009 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors - Request for Extension of Completion Date for Additional Corrective Actions Project stage: Request ML0912400302009-05-0505 May 2009 Extension Request Approval Letter Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors. Project stage: Other L-09-152, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.2009-06-30030 June 2009 Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Supplement ML1002903182010-02-18018 February 2010 RAI, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors Project stage: RAI ML1008407562010-03-31031 March 2010 Notice of Teleconference Meeting with Firstenergy Nuclear Operating Company Regarding Mutual Understanding of NRR Staff'S Request for Additional Information and to Discuss Generic Letter 2004-02 Project stage: RAI ML1013206652010-05-18018 May 2010 Summary of Category 1 Teleconference with Firstenergy Nuclear Operating Company to Discuss NRC Request for Additional Information Regarding Generic Letter 2004-02 Project stage: RAI L-13-176, Generic Safety Issue 191 Resolution Plan2013-05-16016 May 2013 Generic Safety Issue 191 Resolution Plan Project stage: Other 2009-03-11
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Category:Letter
MONTHYEARIR 05000334/20244032024-11-13013 November 2024 Cybersecurity Problem Identification and Resolution Inspection Report 05000334/2024403 and 05000412/2024403 (Cover Letter Only) IR 05000334/20240032024-11-13013 November 2024 Integrated Inspection Report 05000334/2024003 & 05000412/2024003 IR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-223, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-09-26026 September 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation 05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - 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Text
May 18, 2006 Mr. James H. Lash Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station P. O. Box 4 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 2 (BVPS-2) - REQUEST FOR SCHEDULAR EXTENSION FROM GENERIC LETTER (GL) 2004-02, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY RECIRCULATION DURING DESIGN BASIS ACCIDENTS AT PRESSURIZED WATER REACTORS (TAC NO. MC4666)
Dear Mr. Lash:
By letter dated September 6, 2005, as supplemented by letter dated April 3, 2006, you requested an extension from December 31, 2007, until startup from the spring 2008 refueling outage beginning in March 2008 for implementation of modifications described in GL 2004-02 for BVPS-2. The Nuclear Regulatory Commission (NRC) staff has completed its review of your request and determined that FirstEnergy Nuclear Operating Company (FENOC) has a plan that will result in the installation of final modifications that provide acceptable strainer function with adequate margin for uncertainties. Further, the NRC staff has concluded that FENOC has put mitigation measures in place to adequately reduce risk for the requested short extension period. It is therefore acceptable to extend the completion date for the corrective actions for the issues discussed in GL 2004-02 (specifically, the recirculation spray system pump start signal modification and high pressure safety injection throttle valve gap re-sizing modification) until the completion of the BVPS-2 spring 2008 outage, currently scheduled to begin in March 2008.
Should FENOC elect to begin the outage more than 30 days after March 31, 2008, FENOC will need to provide the NRC additional justification for the further delay in completing the above corrective actions for GL 2004-02.
J. Lash The details of our review are contained in the enclosed evaluation. If you have any questions, please contact me at 301-415-1402.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
Evaluation cc w/encl:
See next page
J. Lash The details of our review are contained in the enclosed evaluation. If you have any questions, please contact me at 301-415-1402.
Sincerely,
/RA/
Timothy G. Colburn, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
Evaluation of Extension Request cc w/encl:
See next page Distribution:
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EVALUATION OF EXTENSION REQUEST GENERIC LETTER 2004-02 FIRSTENERGY NUCLEAR OPERATING COMPANY (FENOC)
BEAVER VALLEY POWER STATION, UNIT NO. 2 (BVPS-2)
DOCKET NO. 50-412 In a September 6, 2005, supplemental response to Nuclear Regulatory Commission (NRC)
Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, dated September 13, 2004, FENOC described its activities for resolution of the Generic Safety Issue (GSI)-191 containment sump issue for BVPS-2. FENOC also stated that in accordance with GL 2004-02, the new containment sump strainer will be installed at BVPS-2 before December 31, 2007. However, FENOC requested an extension for completion of certain actions in response to GL 2004-02 until March 31, 2008 in order to allow adequate time to properly design and install a change to the recirculation spray system (RSS) pumps start signal (which is tied directly to the refueling water storage tank level and designed to ensure the strainer will be submerged during the recirculation phase of all postulated events), and to allow time to prepare and obtain NRC approval of an associated license amendment.
The mitigative measures to improve existing margins that FENOC described in the September 6, 2005 supplemental response to Generic Letter 2004-02 were:
- Increased screen area, filtering capability and structural characteristics of the newly installed multiple-element strainer to be installed in the fall 2006 refueling outage; and
- Bulletin 2003-01 interim compensatory measures would remain in place during the extension period.
In an April 3, 2006, letter to the NRC, FENOC provided additional information related to its request for an extension for completion of actions in response to GL 2004-02. FENOC stated that the high pressure safety injection (HPSI) throttle valves had previously been identified as presenting the limiting downstream opening size for operation with debris-laden fluids. FENOC reported that it has noted that the BVPS-2 valve gap is smaller than the final design opening size of the new sump strainer, an emergent condition necessitating a modification to increase the HPSI throttle valve gap size.
FENOC further stated that it intended to make the HPSI throttle valve modification at BVPS-2 during the spring 2008 refueling outage (2R14), scheduled to begin no later than March 31, 2008, rather than during the fall 2006 outage (2R13) which begins in October 2006. In support of this second extension request, FENOC provided the following new rationales and mitigative actions beyond those provided for the RSS start signal change above:
- The normal one-year processing cycle for a license amendment for the HPSI throttle Enclosure
valve modification would not permit installation of the HPSI throttle valve modification during the 2R13 outage.
- Throttle valve modifications cannot be performed at power because there are no isolation valves between the HPSI throttle valves and the reactor cooling loop piping (FENOC here noted that RSS pump start signal modifications also can not be performed at power because of the need to make wiring changes to the solid state protection system);
- The start date of the 2R13 refueling outage does not allow adequate time for proper design and installation of the HPSI throttle valve modification (as well as associated containment walkdowns, identification of replacement hardware, wear analysis for new components, procurement processes, and (potential) special manufacture of components);
- A previous evaluation had shown that the debris exiting the original strainer and reaching the HPSI throttle valve, although potentially larger than the original HPSI throttle valve gap, would be pushed through the gap;
- The new strainer has openings with a round shape that will lead to a slightly smaller downstream debris size; and
- Operator actions would be taken to manually delay RSS pump start, increasing submerged screen area and enhancing emergency core cooling system pump net positive suction head (later to be accomplished automatically following the RSS pump start signal modification).
The NRC staff has determined that FENOC has a plan that will result in the installation of final GSI-191 modifications that provide acceptable strainer function with adequate margin for uncertainties. Further, the NRC has concluded that FENOC has put mitigation measures in place to adequately reduce risk for the requested short extension period, and it is therefore acceptable to extend the completion date for the corrective actions for the issues discussed in GL 2004-02 (specifically the RSS pump start signal modification and HPSI throttle valve gap re-sizing modification) until the completion of the BVPS-2 2R14 spring 2008 refueling outage, scheduled to begin in March 2008. Should FENOC elect to begin the outage more than 30 days after March 31, 2008, FENOC will need to provide the NRC additional justification for further delay in completing corrective actions for GL 2004-02.
Beaver Valley Power Station, Unit Nos. 1 and 2
cc:
Gary R. Leidich FirstEnergy Nuclear Operating Company President and Chief Nuclear Officer Beaver Valley Power Station FirstEnergy Nuclear Operating Company Mail Stop A-BV-SEB1 Mail Stop A-GO-19 P.O. Box 4, Route 168 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 Lew W. Myers Joseph J. Hagan Executive Vice President, Special Projects Senior Vice President of Operations FirstEnergy Nuclear Operating Company and Chief Operating Officer Beaver Valley Power Station FirstEnergy Nuclear Operating Company Mail Stop A-BV-SGRP Mail Stop A-GO-14 P.O. Box 4, Route 168 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 Manager, Site Regulatory Compliance Danny L. Pace FirstEnergy Nuclear Operating Company Senior Vice President, Fleet Engineering Beaver Valley Power Station FirstEnergy Nuclear Operating Company Mail Stop A-BV-A Mail Stop A-GO-14 P.O. Box 4, Route 168 76 South Main Street Shippingport, PA 15077 Akron, OH 44308 Commissioner James R. Lewis Jeannie M. Rinckel West Virginia Division of Labor Vice President, Fleet Oversight 749-B, Building No. 6 FirstEnergy Nuclear Operating Company Capitol Complex Mail Stop A-GO-14 Charleston, WV 25305 76 South Main Street Akron, OH 44308 Director, Utilities Department Public Utilities Commission David W. Jenkins, Attorney 180 East Broad Street FirstEnergy Corporation Columbus, OH 43266-0573 Mail Stop A-GO-18 76 South Main Street Director, Pennsylvania Emergency Akron, OH 44308 Management Agency 2605 Interstate Dr.
Manager, Fleet Licensing Harrisburg, PA 17110-9364 FirstEnergy Nuclear Operating Company Mail Stop A-GHE-107 Ohio EPA-DERR 395 Ghent Road ATTN: Zack A. Clayton Akron, OH 44333 P.O. Box 1049 Columbus, OH 43266-0149 James H. Lash Vice President
Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc:
Dr. Judith Johnsrud Environmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077