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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 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 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 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 ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 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 ML20204C9441999-03-10010 March 1999 Safety Evaluation Denying Licensee Request for License Amend to Revise Frequency of Certain SRs for Electrical Power Sys 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 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 ML20238F2131998-08-28028 August 1998 SER Accepting Defueled Emergency Plan for Emergency Planning for Connecticut Yankee Atomic Power Co 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 ML20237D5001998-08-20020 August 1998 SER Approving Code Case N-389-1, Alternative Rules for Repairs,Replacements,Or Mods,Section Xi,Div 1 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 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 ML20236K3531998-07-0101 July 1998 Safety Evaluation Supporting Amend 218 to License DPR-65 ML20202D1621998-06-30030 June 1998 Safety Evaluation Supporting Amend 193 to License DPR-61 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 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 ML20248C4131998-05-26026 May 1998 SER of Individual Plant Exam of External Events Submittal on Millstone Nuclear Power Station,Unit 3 ML20217M4181998-04-30030 April 1998 Suppl Safety Evaluation Accepting Licensee RCS Pressure & Heat Removal by Containment Heat Removal Sys post-accident Monitoring Instrumentation ML20217K2101998-03-27027 March 1998 Safety Evaluation Supporting Amend 192 to License DPR-61 ML20216G7921998-03-13013 March 1998 Safety Evaluation Authorizing Proposed Alternative to Check Valve Obturator Movement Requirements of OM-10 for SIL Accumulator Outlet for Listed Check Valves ML20203E8521998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(f) for Performing Required Inservice Testing of Certain Class 2 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E9341998-02-17017 February 1998 SER Accepting Request for Relief from Requirements of 10CFR50.55a(g) for Performing Required Exams for Certain Class 1 Components IAW ASME Boiler & Pressure Vessel Code Section XI for Plant,Unit 3 ML20203E2441998-02-0909 February 1998 Safety Evaluation Accepting Re Approval of Realistic,Median Centered Spectra Generated for Resolution of USI-A-46 ML20198R9941998-01-13013 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Millstone Nuclear Power Station,Unit 3 ML20202H7461997-12-10010 December 1997 Safety Evaluation Accepting Licensee Position That Correction of AC-11 Single Failure Vulnerability Unncessary ML20202J0911997-12-0202 December 1997 Safety Evaluation Accepting Proposed Exemption,Which Meets Special Circumstance Given in 10CFR50.12(a)(2)(ii) ML20198S2411997-10-31031 October 1997 SE Accepting Licensee Request for Deviations from Recommendations in Reg Guide 1.97,Rev 2 for Temp & Flow Monitoring Instrumentation for Cooling Water to ESF Sys Components & Containment Isolation Valve Position ML20217K8801997-10-27027 October 1997 Correction to Safety Evaluation Supporting Amend 103 to License DPR-21.Phrase or Rod Block Protection Has Been Deleted from Listed Sentence in Staff Associated SE ML20212G5991997-10-27027 October 1997 Safety Evaluation Supporting Amend 103 to License DPR-21 ML20212F1381997-10-22022 October 1997 Safety Evaluation Supporting Amend 102 to License DPR-21 ML20198M8101997-10-14014 October 1997 SER Accepting Proposed Revs to Util Quality Assurance Program at Facility ML20217M9301997-08-19019 August 1997 Safety Evaluation Accepting Continued Operation W/O High Startup Rate Trip by Nene for Millstone,Unit 2 ML20149J2661997-07-23023 July 1997 Safety Evaluation Accepting Changes & Reanalyses in ECCS Evaluation Models & Application of Models for Plant,Unit 2 ML20141L8821997-05-28028 May 1997 Safety Evaluation Supporting Amend 101 to License DPR-21 ML20141K4201997-05-22022 May 1997 Safety Evaluation Supporting Amend 191 to License DPR-61 ML20138A0111997-04-23023 April 1997 Safety Evaluation Accepting Licensee Proposal,Not to Perform Type C Leakage Rate Testing on 14 Subject CIVs ML20137V5931997-04-15015 April 1997 Safety Evaluation Supporting Amend 100 to License DPR-21 ML20137U3121997-04-10010 April 1997 Safety Evaluation Supporting Amends 99,206 & 135 to Licenses DPR-21,DPR-65 & NPF-49,respectively ML20134A0331997-01-23023 January 1997 Safety Evaluation Accepting Util Proposed Alternatives to ASME Code Requirements 1999-08-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 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 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 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 ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 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 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 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 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 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 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 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 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 ML20209D1881999-07-0101 July 1999 Rev 20,change 9 to Northeast Util QA Program Tr 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 ML20209J0541999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Millstone Unit 2 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 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 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 ML20195H1011999-06-11011 June 1999 Rev 20,change 8 to Northeast Utilities QAP (Nuqap) TR ML20207G6411999-06-0303 June 1999 Safety Evaluation Supporting Amends 105,235 & 171 to Licenses DPR-21,DPR-65 & NPF-49,respectively B17807, Monthly Operating Rept for May 1999 for Mnps,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Mnps,Unit 1.With ML20209J0661999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Unit 2 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 ML20211A6631999-05-31031 May 1999 Revised Monthly Operating Rept for May 1999 for Millstone Nuclear Power Station,Unit 2,providing Revised Average Daily Unit Power Level,Operating Data Rept & Unit Shutdowns & Power Reductions ML20211B7351999-05-31031 May 1999 Cycle 7 Colr 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 ML20206J8351999-05-0707 May 1999 Rev 20,Change 7 to QAP-1.0, Northeast Utls QA Program (Nuqap) Tr 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 B17782, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station,Unit 1.With B17775, Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Nuclear Power Station Unit 3.With ML20205K6141999-04-30030 April 1999 Non-proprietary Version of Rev 2 to Holtec Rept HI-971843, Licensing Rept for Reclassification of Discharge in Millstone Unit 3 Spent Fuel Pool ML20205R3531999-04-30030 April 1999 Addendum 4 to Annual Rept, ML20206E2971999-04-30030 April 1999 Rev 1 to Millstone Nuclear Power Station,Unit 2 COLR - Cycle 13 B17777, Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Millstone Unit 2. with ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 ML20205R8751999-04-0909 April 1999 Provides Commission with Staff Assessment of Issues Related to Restart of Millstone Unit 2 & Staff Recommendations Re Restart Authorization for Millstone Unit 2 ML20205Q5891999-04-0909 April 1999 Rev 20,change 6 to QAP-1.0,Northeast Utils QA Program TR 1999-09-30
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- v. g3 [g g UNITED STATES 3
/ o NUCLEAR REGULATORY COMMISSION n :; WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION FACILITY OPERATING LICENSE NOS. DPR-61 AND DPR-65 .
PROVISIONAL OPERATING LICENSE NO. DPR-21 HADDAM NECK PLANT AND MILLSTONE UNITS 1 AND 2 i
- DOCKET NOS. 50-213, 50-245 and 50-336 1
i
1.0 INTRODUCTION
0'n August 12, 1985. Connecticut Yankee Atomic Power Com any (CYAPCo) and
! Northeast Nuclear Energy Company (NNECo) (the Licensees submitted an j application fer amendment to the technical specifications for the Hadda.n j Neck Plant and Millstone Units 1 and 2. This application requested 1
changes to the specifications governing required plant audits to permit the annual fire protection and loss prevention inspection and audit to be performed by either qualified offsite licensee personnel or a qualified 1
outside independent consultant. The licensee stated that these proposed changes would clarify the uncertainty concerning the implementation of the current audit requirements.
- 2.0 EVALUATION
, Technical Specification 6.5.2.8.1 for the Haddam Neck Plant and 6.5.4.7.e for
' ~
- Millstone Units 1 and 2 requires the annual audit of the licensee's, fire i
protection and loss prevention program shall be perfomed by an outside fim.
By letter from T. J. Martin to W. G. Counsil dated August 1, 1984, the NRC
- transmitted two inspection reports which expressed concern that the relationship between the fire protection auditors and those being audited may not meet
- the present requirements of the technical specifications for Haddam Neck l and Millstone Units 1 and 2.
, The licensee's annual audit is currently being perfomed by Northeast Utilities Service Company (NUSCO), which is part of Northeast Utilities (NU), which in turn,owespartofthelicensee's(ConnecticutYankeeAtomicPowerCompany's)
Haddar Neck Euclear Power Plant. The inspector indicated that NUSCO may not be
, qualified as an outside firm.
Generic Letter 82-21, dated October 6, 1982, from the Director, Division of i Licensing, to all licensees, specified that the annual audit, in accordance with the Standard Technical Specification (STS) 6.5.2.8.1, may be perfomed by qualified utility personnel who are not directly responsible for the site fire
, protection },rogram or an outside independent fire protection consultant, but the i three-year audit in accordance with STS 6.5.2.8.j must be performed by an L
! outside independent fire protection consultant. Haddam Neck Technical i Specifications do not include any requirement for the 3-year audit because j the licensee comitted to annual audits by an outside fim. Therefore, the 1 i
and 3 year audits were combined into one specification.
! .. 8510290219 851021 1 PDR ADOCM 05000213 l P PDR
An accepteble cpproach for the fire protection audits, as set forth in GL 82-21 is to have each audit performed by a qualified audit teer. The teem should include at least a lead auditor from the licensee's_0A .
organization, a systems engineer, and a fire protection engineer. The lead auditor sbculd be qualified per ANSI N45.2.23 as endorsed by Regulatory Guide 1.146. The systems engineer should be knowledgeable in safety systems, operating procedures, and emergency procedures. The fire protection engineer (or engineering consultant) should have the qualifications for membership in the Society of Fire Protection Engineers at the grade of member. The fire protection engineer can be a licensee employee who is not directly responsible for the site fire protection procram for 2 of 3 years, but must be an outside independent fire protection consultant every third year.
The audit team approach will assure that the technical requirements as well as the QA requirements are adequetely audited. These audits would normally encompass an evaluation of existing-documents plus an inspection of fire protection system operability, and inspection of the integrity of fire barriers, and witnessing of procedures to verify that the fire protection program has been fully implemented and is adequate for the objects protected.
Insurance company inspectinns do not satisfy any of the Technical Specification audit reouirements because they do not evaluate plant fire protection programs against NRC requirements. Insurance company inspections do not reassess or re-evaluate the fire protection program, since the insurance company has already agreed to insure the licensee's program as it is being implemented.
Insurance company inspections are generally limited to checking systems and materials for proper condition and maintenance, and evaluating hazardous conditions related to property protection and life safety. However, if the insurance company develops an inspection that has the proper scope and the inspection team includes a person knowledgeable in nuclear safety, we have no objection to an insurance company perfonning these audits in conjunction with a lead auditor from the licensee's OA organization.
By letter dated August 30, 1984, Northeast l'tilities (NU) responded to the NRC by reiterating their position that the Generation Fire Protection Engineering Group within NU fulfilled the requirements of an "outside finn" and as such satisfied the lenguage and intent of the current technical specifications.
By letter dated August 12, 1985, NU submitted proposed revisions to the plant Technicel Specifications to clarify the fire protection auditing requirements.
These revisions reiterated NU practice at this time but did not address the corcerns identified by the inspection reports mentioned above.
1 1
The staff and Fegion I personnel have reviewed the proposed technical specifications and discussed the auditing requirements with the licensees in a September 12, 1985 conference call. Based upon our discussions, we have concluded that NU has not adequately addressed the issue of
" independence" between the groups designing the fire protection systems and those performing the audits. Further the proposed charges do not clearly specify compliance with P!PC positions as stated in Generic Letter 82-21 that a group not associated with the utility should perform,the fire protection audits at least once every 3 years.
In a Senterber 4, 1985 letter from S. Ebneter to J. Opeka, Region I stated that the most recent audits would be accepted to satisfy the reoufrements of the technical specifications. However, as presented in the letter, the sta'f reiterated its concern of separation or independence between the desion and auditing groups, and stated that the utility should provide subrtentiation of the independence of the auditors to meet the requirerents of the current technical specifications and Generic Letter 82-21.
For the reasons stated above, we conclude that the proposed revisions to the technical specifications are not acceptable. We recommend that NU strerely consider use of the generic technical specifications attached to Generic Letter 82-21.
3.0 ACKNOWLEDGEMENTS Principal Contributors: F. Akstulewicz and B. Ferguson, CHEB.
Dated: October 21, 1985.
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