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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
[Table view] |
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O UNITED STATES a
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NUCLEAR REGULATORY COMMISSION e
WASHINGTc N, D.C. 20066 0001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION REQUEST FOR RELIEF FROM CERTAIN ASME CODE. SECTION XI REQUIREMENTS NORTHEAST NUCLEAR ENERGY COMPANY MILLSTONE NLiCLEAR POWER STATION UNIT NO. 3 DOCKET NO. 50-423 1
1.0 INTRODUCTION
Section 50.55a(g) of Title 10 of the Code of Federal Regulations (10 CFR 50.55a(g)) requires nuclear power facility piping and components to meet the applicable requirements of Section XI of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (hereafter referred as the Code).Section XI of the Code specifies Code-acceptable repair and replacement procedures to be used on components and piping that are inservice.
Altematives to Code requirements may be used by nuclear licensees when authorized by the Director of the Office of Nuclear Reactor Regulation if the proposed attematives to the requirements are such that they are shown to provide ran acceptable level of quality and safety in lieu of the Code requirements [10 CFR 50.55a(a)(3)(i)], or if compliance with the Code requirements would result in hardship or unusual difficulty without a compensating increase in the level of quality and safety [10 CFR 50.55a(a)(3)(ii)].
A licensee may also submit requests for relief from certain Code requirements when a licensee has determined that conformance with cedain Code requirements is impractical for its facility
[10 CFR 50.55a(g)(5)(iii)]. Pursuant to 10 CFR 50.55a(g)(6)(i), the Commission will evaluate determinations ofimpracticality and may grant relief and may impose attemative requirements as it determines are authorized by law.
In a letter dated December 15,1995, Connecticut Yankee Atomic Power Company (CYAPCO) and Northeast Nuclear Energy Company (NNECO) (the licensee), submitted to the NRC certain requests for relief from the ASME Code,Section XI requirements. Specifically, pursuant to 10 CFR 50.55a(g)(5)(iii), the licensee requested (1) relief from using the rules of Article lWA-4000, " Repair Procedures," for repairs on piping, valves, fittings, nominal pipe size 1 inch and smaller, a.d their associated supports; (2) relief from using the rules of Article IWA-4000 and Article IWA-7000, " Replacements," for repair or replacement activities performed on seal welds; and (3) relief from the rules of Articles IWA-4000 and IWA-7000 for repair or I
i replacement activities performed on valve discs and other nonstructural valve intemals that are I
1 Enclosure I
9808260239 980820 PDR ADOCK 05000423 P
PDR 1
~
4 constructed to a Construction Code or a Code Case for all four plants (Haddam Neck, Millstone Units 1,2, and 3). In addition, the !icensee requested, pursuant to 10 CFR 50.55a(a)(3)(i), that Code Case N-389-1, "Altemative Rules for Repairs, Replacements, or Modifications,Section XI, Division 1," be approved for use by all four plants.
By letter dated June 7,1996, the licensee revised its requests for relief and withdrew its previously requested reliefs pertaining to the rules of Articles IWA-4000 and IWA-7000 for repair or replacement activities performed on valve discs and other nonstructural valve intemals that are constructed to a Construction Code or a Code Case. In a letter dated February 18, 1997, CYAPCO withdrew the remaining requests for relief for Haddam Neck based on an earlier decision by the CYAPCO joint owners to permanently cease power operations at the facility. In a letter dated August 14,1998, NNECO withdrew all its remaining requests except for Code Case N-389-1 at Millstone Unit 3. Therefore, this safety evaluation only applies to Millstone Unit 3.
2.0 EVALUATION l
The information provided by the licensee in support of the remaining relief request has been evaluated and the basis for disposition is documented below.
I Millrtone. Unit 3 - Reauest to use Code Case N-389-1. Altemative Rules for Reoairs.
Replacements. or Modifications.Section XI. Division 1 Licensee's Reauest: (As stated)
I The request to use Code Case revision that has not yet been approved by the NRC Staff is being submitted pursuant to 10CFR50.55.a(a)(3)(i).
We request that Code Case Revision N-389-1, "Altemative Rules for Repairs, Replacements, or Modifications,Section XI, Division 1," be approved for use by Haddam Neck plant and Millstone Unit Nos.1,2 and 3. This revision of the Code Case has not yet been incorporated into Regulatory Guide 1.147. This Code Case revision allows a licensee to use later Editions and Addenda of the ASME Code Section XI for Repair or Replacement Activities as with the original l
Case which has been approved by the NRC, but now requires that all related requirements must be met. This additional provision to the Case approved by the ASME, with NRC participation, provides the basis for the approval of our I
request. The attematives which are provided in the Case revision have been determined by the ASME consensus process to provide an acceptable level of quality and safety, Both CYAPCO and NNECO believe that the Staffs approval of these requests i
j will help to optimize our Section XI Repair and Replacement Programs. This will be accomplished by allowing the use of attematives provided in Code Case Revision N-389-1 and by reducing the burdensome documentation associated with repair or replacement activities.
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. Evaluation: The Code of record for the Millstone Unit 3, first 10-year ISI intervalis the ASME Code,Section XI,1983 Edition with the Summer 1983 Addenda. The licensee has requested to use the attematives provided in Code Case N-389-1 for its Repairs and Replacement Program.
The original version of Code Case N-389 was approved by the NRC staff and is listed in Regulatory Guide 1.147, " Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1." Regulatory Guide 1.147, Revision 11, October 1994, states that Code Case N-389 is acceptable subject to the following condition in addition to those conditions specified in the Code Case: The applicant should submit for approval the appropriate edition and addenda of the Code that is to be used for the repair, replacement, or modification before start of the work.
Revision 1 to Code Case N-389 (N-389-1) has been approved by the ASME Code and the staff is currently in the process of incorporating Revision 1 to the Code Case into the forthcoming revision of Regulatory Guide 1.147. Code Case N-389-1 will enable licensees to use the attematives provided in later editions of the Code (that have been approved by the NRC staff) for repair or replacement activities, provided all related requirements of the Code are met.
Since the Code Case requires that an NRC-approved edition of the Code will be used and allits requirements must be met, the attemative proposed by the licensee will provide an acceptable level of quality and safety.
==
Conclusion:==
Request to use Code Case N-389-1 as an alternative to the Code requirements has been proposed by the licensee. The NRC staff reviewed the proposed alternatives for compliance with the provisions of 10 CFR 50.55a(a)(3)(i), which allows licensees to propose alternatives to Code requirements if the proposed altemative would provide an acceptable level of quality and safety. The licensee has proposed to use the attematives provided in Code Case N-389-1 for its Repair and Replacement Program. Code Case N-389-1 has been reviewed by the NRC staff and is currently in process of being incorporated into the forthcoming revision of Regulatory Guide 1.147. The staff finds the attematives provided in Code Case N-389-1 acceptable. The staff, therefore, concludes that the licensee's proposed altemative to use Code Case N-389-1 would provide an acceptable level of quality and safety. Therefore, pursuant to 10 CFR 50.55a(a)(3)(i), the altemative is authorized.
3.0 CONCLUSION
The licensee has requested, pursuant to 10 CFR 50.55a(a)(3)(i), that Code Case N-389-1 be approved for Millstone Unit 3. The staff has concluded that the licensee's proposed alternative is acceptable because it provides an acceptable level of quality and safety. Therefore, the staff concludes that the licensee's proposed alternative is authorized pursuant to 10 CFR 50.55a(a)(3)(i).
i Principal Contributors: G. Georgiev and S. Dembek l
Date:
August 20, 1998 l
l 4
4 Millston] Nucle:r P w r St:ti:n Unit 3 cc:
Lillian M. Cuoco, Esquire Joseph R. Egan, Esquire Senior Nuclear Counsel Egan & Associates, P.C.
Northeast Utilities Service Company 2300 N Street, NW P. O. Box 270 Washington, DC 20037 Hartford, CT 06141-0270 Mr. F. C. Rothen Mr. Kevin T. A. McCarthy, Director Vice President -Work Services Monitoring and Radiation Division Northeast Utilities Service Company Department of Environmental Protection P. O. Box 128 79 Elm Street Waterford, CT 06385 Hartford, CT 06106-5127 Ernest C. Hadley, Esquire l
Regional Administrator, Region i 1040 B Main Street j
U.S. Nuclear Regulatory Commission P.O. Box 549 475 Allendale Road West Wareham, MA 02576 King of Prussia, PA 19406 Mr. John Buckingham First Selectmen Department of Public Utility Control Town of Waterford Electric Unit Hall of Records 10 Liberty Square 200 Boston Post Road New Britain, CT 06051 Waterford, CT 06385 Mr. James S. Robinson, Manager Mr. Wayne D. Lanning Nuclear investments and Administration Deputy Director of Inspections New England Power Company Special Projects Office 25 Research Drive 475 Allendale Road Westborough, MA 01582 King of Prussia, PA 19406-1415 Mr. John Streeter Mr. M. H. Brothers Recovery Officer - Nuclear Oversight Vice President - Millstone Unit 3 Northeast Utilities Service Company l
Northeast Nuclear Energy Company P. O. Box 128
)
P.O. Box 128 Waterford, CT 06385 Waterford, CT 06385 l
Deborah Katz, President l
Mr. M. R. Scully, Executive Director Citizens Awareness Network Connecticut Municipal Electric P.O. Box 83 Energy Cooperative Shelburne Falls, MA 03170
)
30 Stott Avenue Norwich, CT 06360 Mr. Allan Johanson, Assistant Director Office of Policy a'nd Management Mr. David Amerine Policy Development and Planning Vice President - Human Services Division i
Northeast Utilities Service Company 450 Capito! Avenue - MS# 52ERN P. O. Box 128 P. O. Box 341441 Waterford, CT 06385 Hartford, CT 06134-1441 l
Millston) Nuclear Powsr Stition i
Unit 3 l
cc:
The Honorable Terry Concannon Mr. William D. Meinert Nuclear Energy Advisory Council Nuclear Engineer Room 4035 Massachusetts Municipal Wholesale Legislative Office Building Electric Company Capitol Avenue P.O. Box 426 Hartford, CT 06106 Ludlow, MA 01056 l-Mr. Evan W. Woollacott Attorney Nicholas J. Scobbo, Jr.
Co-Chair Ferriter, Scobbo, Caruso, Rodophele, PC Nuclect Energy Advisory Council 1 Beacon Street,11th Fbor 128 Terry's Plain Road Boston, MA 02108 Simsbury, CT 06070 Citizens Regulatory Commission i
MrcJohn W. Beck, President ATTN: Ms. Susan Perry Luxton l
Little Harbor Consultants, Inc.
180 Great Neck Road Millstone -ITPOP Project Office Waterford, CT 06385 P.O. Box 0630 Niantic, CT 06357-0630
]
Mr. B. D. Kenyon (Acting)
Chief Nuclear Officer - Millstone l
Northeast Nuclear Energy Company l
P.O. Box 128 Waterford, CT 06385 Mr. Daniel L. Curry I
Project Director Parsons Power Group inc.
2675 Morgantown Road Reading, PA 19607 Mr. Don Schopfer
- Verification Team Manager Sargent & Lundy 55 E. Monroe Street Chicago,IL 60603 I
Mr. P. D. Hinnenkamp Director-Unit 3 Northeast Nuclear Energy Company P.O. Box 128 1
Waterford, CT 06385 l
Senior Resident inspector Millstone Nuclear Power Station c/o U.S. Nuclear Regulatory Commission P. O. Box 513 Niantic, CT 06357 C____________.___________________.________