SER Related to Proposed Rev 20 to Northeast Utilities Quality Assurance Program Topical Rept for Millstone Nuclear Power Station,Units 1,2 & 3ML20238F278 |
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08/27/1998 |
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NRC (Affiliation Not Assigned) |
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ML20238F274 |
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NUDOCS 9809030244 |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212A7381999-09-10010 September 1999 Safety Evaluation Supporting Amend 174 to License NPF-49 ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20210U0881999-08-13013 August 1999 Safety Evaluation Supporting Amends 239 & 173 to Licenses DPR-65 & NPF-49,respectively ML20210Q1401999-08-12012 August 1999 Safety Evaluation Supporting Amend 238 to License DPR-65 ML20209G3061999-07-13013 July 1999 Safety Evaluation Supporting Amend 237 to License DPR-65 ML20209D6581999-07-0202 July 1999 Safety Evaluation Supporting Amend 172 to License NPF-49 ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20196H1621999-06-29029 June 1999 Safety Evaluation Supporting Amend 236 to License DPR-65 ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20206M4631999-05-11011 May 1999 Safety Evaluation Supporting Alternative Proposed by Licensee to Perform Ultrasonic Exam on Inner Surface of Nozzle to safe-end Weld ML20206G6221999-05-0404 May 1999 SER Accepting Util Request to Apply leak-before-break Status to Pressurizer Surge Line Piping for Millstone Nuclear Power Station,Unit 2 ML20205S5341999-04-16016 April 1999 Safety Evaluation Supporting Amend 169 to License NPF-49 ML20205N3601999-04-12012 April 1999 Safety Evaluation Supporting Amend 233 to License DPR-65 ML20205G0191999-03-17017 March 1999 Safety Evaluation Supporting Amend 168 to License NPF-49 ML20204H7131999-03-17017 March 1999 Safety Evaluation Concluding That NNECO Provided Adequate Justification for Deviations from RG 1.97,Rev 2, Recommendations,For Instrumentation Monitoring CST Level & Containment Area Radiation at Mnps Unit 2 ML20205G4781999-03-12012 March 1999 Safety Evaluation Supporting Amend 231 to License DPR-65 ML20205G8671999-03-11011 March 1999 Safety Evaluation Supporting Amend 230 to License DPR-65 ML20204C9441999-03-10010 March 1999 Safety Evaluation Denying Licensee Request for License Amend to Revise Frequency of Certain SRs for Electrical Power Sys ML20205G4591999-03-10010 March 1999 Safety Evaluation Supporting Amend 229 to License DPR-65 ML20204E7581999-03-10010 March 1999 Safety Evaluation Supporting Amend 228 to License DPR-65 ML20207L2631999-03-0505 March 1999 Safety Evaluation Supporting Amend 104 to License DPR-21 ML20207L5961999-02-22022 February 1999 Safety Evaluation Concluding That Code Requirements,Which Require 100 Percent Volumetric Exam of RPV flange-to-shell, Impractical to Perform to Extent Required & That Alternative Provide Reasonable Assurance of Structural Integrity ML20203D7601999-02-11011 February 1999 Safety Evaluation Supporting Millstone 1 Certified Fuel Handler Training & Retraining Program ML20203J3191999-02-10010 February 1999 Safety Evaluation Supporting Amend 227 to License DPR-65 ML20199H9181999-01-20020 January 1999 Safety Evaluation Supporting Amend 224 to License DPR-65 ML20198S7801998-12-31031 December 1998 Safety Evaluation Supporting Amend 223 to License DPR-65 ML20198E1471998-12-18018 December 1998 Safety Evaluation Supporting Amend 222 to License DPR-65 ML20198E0571998-12-17017 December 1998 Safety Evaluation Supporting Amend 221 to License DPR-65 ML20196B0501998-11-24024 November 1998 Safety Evaluation Re Licensee 960213 Submittal of 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant,Unit 2 ML20155K1981998-11-0909 November 1998 Safety Evaluation Re Application of leak-before-break Status to Portions of Safety Injection & Shutdown Cooling Sys ML20195B8711998-11-0909 November 1998 Safety Evaluation Approving Revised Evaluation of Primary Cold Leg Piping leak-before-break Analysis for Plant ML20155C3781998-10-30030 October 1998 SER Denying Amend to Allow Changes to Fsar.Nrc Found That NNECO Had Not Considered Diversity Provided by Switch in Control Room That Removes Power to 1 of 2 MOV in SDC Sys Flow Path in Evaluation of High Low Pressure Design ML20155C8441998-10-29029 October 1998 Safety Evaluation Accepting Licensee Proposal to Withdraw ATWS Test Commitment ML20153D8921998-09-23023 September 1998 Safety Evaluation Supporting Amend 163 to License NPF-49 ML20238F2781998-08-27027 August 1998 SER Related to Proposed Rev 20 to Northeast Utilities Quality Assurance Program Topical Rept for Millstone Nuclear Power Station,Units 1,2 & 3 ML20237D4681998-08-21021 August 1998 Safety Evaluation Supporting Amend 219 to License DPR-65 ML20237D5001998-08-20020 August 1998 SER Approving Code Case N-389-1, Alternative Rules for Repairs,Replacements,Or Mods,Section Xi,Div 1 ML20236Y5601998-08-0707 August 1998 Safety Evaluation Supporting Amend 162 to License NPF-49 ML20236U7051998-07-22022 July 1998 Safety Evaluation Granting All Requests for Relief W/Exception of Requests RR-89-17 (Authorized for Class 1 Sys Only) & RR-89-21.Requests RR-13 & RR-14 Will Be Addressed in Separate Evaluation ML20236K3531998-07-0101 July 1998 Safety Evaluation Supporting Amend 218 to License DPR-65 ML20236K6971998-07-0101 July 1998 SER Accepting Third 10-year Interval Inservice Insp Program Plan,Rev 2 & Associated Request for Relief & Proposed Alternatives for Plant,Unit 2 ML20249C2541998-06-24024 June 1998 Safety Evaluation Accepting Proposed Rev 19 to NNECO QAP Topical Rept & Amended Through 980609.Informs That NNECO Exception to Provisions in Paragraph 10.3.5 of Constitutes Temporary & Acceptable Alternative ML20249C0491998-06-22022 June 1998 Safety Evaluation Supporting Amend 217 to License DPR-65 ML20249B0751998-06-16016 June 1998 Safety Evaluation Supporting Amend 216 to License DPR-65 ML20248K9271998-06-0505 June 1998 Safety Evaluation Supporting Amend 161 to License NPF-49 ML20248J0031998-06-0404 June 1998 Safety Evaluation Accepting Millstone Nuclear Power Station Emergency Plan ML20248M2991998-06-0202 June 1998 Safety Evaluation Approving Application Re Restructuring of Central Maine Power Co by Establishment of Holding Company ML20248A8291998-05-27027 May 1998 Safety Evaluation Supporting Amend 160 to License NPF-49 ML20248C4131998-05-26026 May 1998 SER of Individual Plant Exam of External Events Submittal on Millstone Nuclear Power Station,Unit 3 ML20248A3221998-05-26026 May 1998 Safety Evaluation Supporting Amend 215 to License DPR-65 1999-09-10
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program 05000336/LER-1999-012, :on 990917,unrecoverable CEA Misalignment Entry Into TS 3.0.3 Was Noted.Caused by Grounded Coil Wire for Lower Gripper Assembly.Leads Leading to Lower Gripper Coil Were Insulated1999-10-15015 October 1999
- on 990917,unrecoverable CEA Misalignment Entry Into TS 3.0.3 Was Noted.Caused by Grounded Coil Wire for Lower Gripper Assembly.Leads Leading to Lower Gripper Coil Were Insulated
ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 05000336/LER-1999-011, :on 990823,thermal Reactor Power Limit Was Exceeded.Caused by Lack of Conservatism in Procedures & Alarm Setpoints Used to Limit Reactor Power.Revised Operating Procedures1999-09-20020 September 1999
- on 990823,thermal Reactor Power Limit Was Exceeded.Caused by Lack of Conservatism in Procedures & Alarm Setpoints Used to Limit Reactor Power.Revised Operating Procedures
ML20212A7381999-09-10010 September 1999 Safety Evaluation Supporting Amend 174 to License NPF-49 05000245/LER-1999-001-02, :on 990810,discovered That Stack Flow Monitor Four H LCO Action Statement Had Not Been Met.Caused by Personnel Error.Frequency of LCO Action Was Increased & Personnel Involved Received Coaching.With1999-09-0808 September 1999
- on 990810,discovered That Stack Flow Monitor Four H LCO Action Statement Had Not Been Met.Caused by Personnel Error.Frequency of LCO Action Was Increased & Personnel Involved Received Coaching.With
05000336/LER-1999-010, :on 990804,noted Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve.Caused by Inadequate man-machine Interface. Planning Personnel Will Be Briefed on QC Program Indicators1999-09-0202 September 1999
- on 990804,noted Failure to Perform ASME Section XI IST on Pressurizer Relief Line Flow Control Sample Valve.Caused by Inadequate man-machine Interface. Planning Personnel Will Be Briefed on QC Program Indicators
ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20210U0881999-08-13013 August 1999 Safety Evaluation Supporting Amends 239 & 173 to Licenses DPR-65 & NPF-49,respectively ML20210Q1401999-08-12012 August 1999 Safety Evaluation Supporting Amend 238 to License DPR-65 B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 ML20210J0311999-07-21021 July 1999 Rev 20,Change 10 to QAP 1.0, Organization ML20210E5931999-07-19019 July 1999 Revised Page 16 of 21,to App F of Northeast Util QA Program Plan ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr ML20209G3061999-07-13013 July 1999 Safety Evaluation Supporting Amend 237 to License DPR-65 B17814, Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start1999-07-12012 July 1999 Special Rept:On 990612 B Train EDG Failed to Restart within 5 Minutes Following Completion of 18 Month 24 H Endurance Run Required by TS 4.8.1.1.2.g.7.Caused by Procedural inadequacy.Re-performed Hot Restart Via Manual Start ML20209D6581999-07-0202 July 1999 Safety Evaluation Supporting Amend 172 to License NPF-49 ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept B17833, Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Power Station,Unit 1.With ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, ML20196J2191999-06-30030 June 1999 SER Concluding That Licensee USI A-46 Implementation Program,In General,Met Purpose & Intent of Criteria in GIP-2 & Staff Sser 2 for Resolution of USI A-46 ML20211A6751999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level & Operating Data Rept B17830, Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Nuclear Power Station,Unit 3.With ML20196H1621999-06-29029 June 1999 Safety Evaluation Supporting Amend 236 to License DPR-65 05000423/LER-1999-007-01, :on 990518,discharge Filter Associated with Crss Cubicle Sump Pump 3DAS-8A,was Determined to Be Contaminated.Caused by Back Leakage from Contaminated Drains Feeding Into ECCS Pump.Lines Modified.With1999-06-17017 June 1999
- on 990518,discharge Filter Associated with Crss Cubicle Sump Pump 3DAS-8A,was Determined to Be Contaminated.Caused by Back Leakage from Contaminated Drains Feeding Into ECCS Pump.Lines Modified.With
05000423/LER-1999-006-01, :on 990516,both Reactor Plant Aerated Drains SR Air Driven Sump Pumps Failed During TRM Surveillance.Caused by Inadequate Preventive Maint Program Design.Surveillance Procedure Sp 3635B.2 Will Be Conducted Monthly1999-06-15015 June 1999
- on 990516,both Reactor Plant Aerated Drains SR Air Driven Sump Pumps Failed During TRM Surveillance.Caused by Inadequate Preventive Maint Program Design.Surveillance Procedure Sp 3635B.2 Will Be Conducted Monthly
05000423/LER-1999-004-01, :on 990516,ESFA of Numerous Plant Components on Restoration of a Train Sequencer Occurred.Caused by Inadequate Procedure Direction.Issued Brief to Operations Describing Inadvertent Sequencer LOP Event.With1999-06-14014 June 1999
- on 990516,ESFA of Numerous Plant Components on Restoration of a Train Sequencer Occurred.Caused by Inadequate Procedure Direction.Issued Brief to Operations Describing Inadvertent Sequencer LOP Event.With
ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR 05000423/LER-1999-005-01, :on 990510,failure to Perform Surveillance on RCS Pressurizer Heater Penetration Breakers Was Noted.Caused by Lack of Mgt Support.Required Surveillance of Identified Ten Breakers Was Completed1999-06-0808 June 1999
- on 990510,failure to Perform Surveillance on RCS Pressurizer Heater Penetration Breakers Was Noted.Caused by Lack of Mgt Support.Required Surveillance of Identified Ten Breakers Was Completed
05000423/LER-1999-003-01, :on 990505,identified That 18 Month EDG Surveillance Test for LOP with ESF Start Did Not Initiate Test.Caused by Inadequate Understanding of Regulatory Guidance. a & B EDG Returned to Status.With1999-06-0404 June 1999
- on 990505,identified That 18 Month EDG Surveillance Test for LOP with ESF Start Did Not Initiate Test.Caused by Inadequate Understanding of Regulatory Guidance. a & B EDG Returned to Status.With
ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 ML20211B7351999-05-31031 May 1999 Cycle 7 Colr B17804, Monthly Operating Rept for May 1999 for Mnps,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 2.With B17808, Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 3.With 1999-09-08
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4 UNITED STATES g
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO PROPOSED REVISION 20 TO THE NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NUCLEAR POWER STATION. UNITS 1. 2. AND 3 DOCKET NOS. 50-245. 50-336. AND 50-423
1.0 INTRODUCTION
On July 23,1998, Northeast Nuclear Energy Company (NNECO) transmitted proposed Revision 20 to the Northeast Utilities Quality Assurance Program (NUQAP) Topical Report for NRC review and approvalin accordance with 10 CFR 50.54(a)(3).
In its proposed Revision 20 to the NUQAP, NNECO identified several organizational and editorial changes. However, only one minor change (associated with the removal of certain consumables from Appendix A, " Category l Structures, Systems, and Components," to the NUQAP) was identified by the licensee as a reduction in commitment in the NUQAP and thus, subject to NRC approval pursuant to 10 CFR 50.54(a)(3). This reduction in the licensee's quality assurance (QA) program description is the subject of this safety evaluation.
2.0 EVALUATION Appendix A, " Category i Structures, Systems, and Components," Subsection "Consumables,"
of NNECO's NUQAP currently lists specific consumables that when utilized in safety-related systems will be included in the applicable portions of the NUQAP. In Revision 20 to the NUQAP, NNECO proposed to delete bulk nitrogen and hydrogen from this consumable list based on a Material Equipment and Parts List (MEPL) evaluation that concluded that these items are not quality consumables.
Section 17.1," Quality Assurance During The Design and Construction," of NUREG-75/087, "USNRC Standard Review Plan," (SRP), Revision 1, states in Subsection 17.1.2, " Quality Assurance Prooram." subparagraph 2 Aid, that activities related to the quality assurance program are acceptable if the scope of the program includes "[T]he identification of structures, systems, and components and related consumables [ emphasis added] covered by the QA program and controlled measures identifying authorized personnel to approve changes to this list and describing methods controlling its distribution." Accordingly, Section 17.1 of the SRP provides the staff's acceptance criteria on this subject for nuclear power plants in the design and construction phase.
As described in Revision 2 to Section 17.1 of the SRP, subparagraph 2A1a, the provisions related to this area of QA program acceptance were modified as follows: "A commitment that 9009030244 900827 r
PDR ADOCK 05000245 P
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A 2-activities affecting structures, systems, and components important to safety will be subject to the applicable controls of the QA program. The structures, systems, components and related consumables covered by the QA program are identified (QA list)in Section 3.2.1 of the SAR
[ safety analysis report] [ emphasis added)." Thus, Revision 2 to Section 17.1 of the SRP established that the "QA list"information (including consumables) is not required to be included in the QAP description but needs to be identified in Section 3.2.1 of the SAR.
SRP Section 17.2, " Quality Assurance During the Operations Phase," Revision 2 (July 1981) endorses Section 17.1 with respect to QA program acceptance in this area. Since the inclusion in the QAP description of consumables associated with structures, systems, and components subject to the provisions of Appendix B to 10 CFR Part 50 (i.e., safety-related) is not a pre-requisite for QA program acceptance in Section 17.2 of the SRP, NNECO's proposal to remove bulk nitrogen and hydrogen is acceptable.
3.0 CONCLUSION
While NNECO's proposed revision to the NUQAP described above constitutes a reduction in commitments in the QA program description previously approved by the NRC, such exceptions continue to satisfy the provisions of Section 17.2 of the SRP. Therefore, the NRC staff has determined that the proposed Revision 20 to NNECO's NUQAP Topical Report, dated July 23, 1998, continues to comply with the quality assurance criteria of Appendix B to 10 CFR Part 50 and is acceptable. However, this conclusion does not establish the technical validity of the MEPL evaluation performed by NNECO, which forms the basis for the licensee's decision to exclude these consumables from the provisions of Appendix B to 10 CFR Part 50. Section 50.59 and Criterion lli of Appendix B to CFR 10 Part 50 requirements govem the process under which the MEPL evaluation was performed and its bases and conclusions are subject to NRC inspection accordingly.
Principal Contributor: J. Peralta Date: August 27, 1998 J
Millstona Nuclecr Pow:r Station Units 1,2, cnd 3 cc:
Mr. Charles Brinkman, Manager Lillian M. Cuoco Esquire Washington Nuclear Operations Senior Nuclear Counsel ABB Combustion Engineering i
Northeast Utilities Service Company 12300 Twinbrook Pkwy, Suite 330 P. O. Box 270 Rockville, MD 20852 Hartford, CT 06141-0270 Mr. John Streeter Mr. Kevin T. A. McCarthy, Director Recovery Officer - Nuclear Oversight Monitoring and Radiation Division Northeast Utilities Service Company Department of Environmental P. O. Box 128 Protection Waterford, CT 06385 79 Elm Street Hartford, CT 06106-5127 Senior Resident inspector Millstone Nuclear Power Station Mr. Allan Johanson, Assistant Director c/o U.S. Nuclear Regulatory Commission Office of Policy and Management P. O. Box 513 Policy Development and Planning Niantic, CT 06357 Division 450 Capitol Avenue - MS 52ERN Mr. David Amerine P. O. Box 341441 Vice President - Human Services Hartford, CT 06134-1441 Northeast Utilities Service Company P. O. Box 128 Regional Administrator, Region I Waterford, CT 06385 U.S. Nuclear Regulatory Commission 475 Allendale Road Mr. M. H. Brothers King of Prussia, PA 19406 Vice President - Operations Northeast Nuclear Energy Company First Selectmen P. O. Box 128 Town of Waterford Waterford, CT 06385 Hall of Records 200 Boston Post Road Mr. M. R. Scully, Executive Director Waterford, CT 06385 Connecticut Municipal Electric Energy Cooperative Mr. J. P. McElwain 30 Stott Avenue Recovery Officer-Millstone Units 1 and 2 Norwich, CT 06360 Northeast Nuclear Energy Company P. O. Box 128 Mr. William D. Meinert Waterford, CT 06385 Nuclear Engineer Massachusetts Municipal Wholesale Mr. Wayne D. Lanning Electric Company Deputy Director of Inspections P. O. Box 426 Special Projects Office Ludlow, MA 01056 475 Allendale Road King of Prussia, PA 19406-1415 Emest C. Hadley, Esq.
1040 B Main Street Mr. F. C. Rothen P. O. Box 549 Vice President - Work Services West Wareham, MA 02576 Northeast Utilities Service Company P.O. Box 128 Waterford, CT 06385 I
e Millstone Nuclatr Powsr Station Units 1,2, cnd 3 cc:
Citizens Regulatory Commission Mr. B. D. Kenyon (Acting)
ATTN: Ms. Susan Perry Luxton Chief Nuclear Officer-Millstone 180 Great Neck Road Northeast Nuclear Energy Company Waterford, CT 06385 P. O. Box 128 Waterford, CT 06385 The Honorable Terry Concannon Nuclear Energy Advisory Council Deborah Katz, President Room 4035 Citizens Awareness Network Legislative Office Building P.O. Box 83 Capitol Avenue Shelbume Falls, MA 03170 Hartford, CT 06106 Joseph R. Egan, Esq.
Mr. G. D. Hicks Egan & Associates, P.C.
Director-Unit 3 2300 N Street, NW Northeast Nuclear Energy Company Washington, D.C. 20037 P. O. Box 128 Waterford, CT 06385 Mr. J. A. Price Director - Unit 2 John W. Beck, President Northeast Nuclear Energy Company Little Harbor Consultants, Inc.
P. O. Box 128 Millstone - ITPOP Project Off;ce Waterford, CT 06385 P. O. Box 0630 Niantic, CT 06375-0630 Attomey Nicholas J. Scobbo, Jr.
Ferriter, Scobbo, Caruso, Rodophele, PC Mr. Evan W. Woollacott 1 Beacon Street,11th Floor Co-Chair Boston, MA 02108 Nuclear Energy Advisory Council 128 Terry's Plain Road Mr. E. J. Harkness Simsbury, CT 06070 Director-Unit 1 Operations Northeast Nuclear Energy Company Mr. Daniel L. Curry P. O. Box 128 Project Director Waterford, Connecticut 06385 Parsons Power Group Inc.
2675 Morgantown Road Reading, PA 19607 Mr. P. D. Hinnenkamp Director-Unit Operations Northeast Nuclear Energy Company P. O. Box 128 Waterford, CT 06385 I
I l