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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 ML20212A7381999-09-10010 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 ML20206C8761999-04-28028 April 1999 Safety Evaluation Supporting Amend 194 to License DPR-61 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 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 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 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 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 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 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 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 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 ML20217K3301999-10-19019 October 1999 Safety Evaluation Supporting Amend 195 to License DPR-61 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 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 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 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 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 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 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 ML20210A0411999-07-15015 July 1999 Rev 20,change 10 to Northeast Util QA Program Tr ML20210C5911999-07-15015 July 1999 Revised Rev 20,change 10 to Northeast Util QA Program TR, Replacing Summary of Changes 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 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 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 ML20196J1821999-06-30030 June 1999 Rev 21,Change 0 to Northeast Utilities QAP (Nuqap) Tr 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 ML20196K1791999-06-30030 June 1999 Addendum 6 to Millstone Unit 2 Annual Rept, 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 ML20196A8451999-06-30030 June 1999 Post Shutdown Decommissioning Activities Rept 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 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 1999-09-08
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UNITED STATES
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5C NUCLEAR REGULATORY COMMISSION wassincTon. o.c. 2osss oooi
\\.s, j SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REG RELATED TO AMENDMENT NOS. 170 69. '69 AND 86 TO FACILITY OPERATING LICENSE NOS. DPR-61. DPR-21. DPR-65 A CONNECTICUT YANKEE ATOMIC POWER COMPANY NORTHEAST NUCLEAR ENERGY COMPANY HADDAM NECK PLANT MILLSTONE NUCLEAR POWER STATION. UNIT NOS
- 1. 2 AND 3 DOCKET NOS. 50-213. 50-245. 50-336. AND 50-423
1.0 INTRODUCTION
+
16, 1993, the Northeast Nuclear Energy Company (NNEC0, By letter dated July the licensee) for Millstone Nuclear Power Station, Unit Nos.1, 2 and 3, and Connecticut Yankee Atomic Power Company (CYAPCO, the licensee) for the Haddam Neck Plant submitted a request for changes to the Administrative Controls-The requested changes would Section 6 of the Technical Specifications (TS).
revise Section 6 of the TS to change the submittal frequency of the Radioactive Effluent Release Report from semiannual to annual to be submitted Also, CYAPC0 and NNEC0 proposed to consolidate the by May 1 of each year. Radioactive Effluent Release Report and the Radioactive E The into a single annual report entitled Radioactive Effluent Report.
requirement to submit these reports has not previously been incorporated in The TS Section 6 of the Millstone Unit 2 TS and would become new TS 6.9.1.6.
would also be changed in the various places where this report is referenced.
r 2.0 EVALUATION The requirements of 10 CFR 50.36a had included a provision which required licensees to submit a report specifying the quantities of each of the principal radionuclides released to unrestricted areas, semiannually, within This requirement was 60 days after January 1 and July 1 of each year.
incorporated in Section 6 of the TS for Haddam Neck and Millstone Units 1 and This requirement had not previously been incorporated in Section'6 of the 3.Hillstone Unit 2 TS but was still required by 10 CFR 50.36a.
On August 31, 1992, 10 CFR 50.36a was revised. The revised 10 CFR 50.36a l
required that a report to the Commission specifying the quantity of each of the principal radionuclides released to unrestricted areas during the previous 12 monihs should be prepared and submitted. The new regulation-also required that the time interval between submissions of the reports must be no longer The licensees' proposal to extend the duration of the subject than 12 months.
9312070330 931123 yDR ADOCK 05000213-PDR
. * =c report from semiannual to annual, thus, complies with the requirements of the revised 10 CFR 50.36a.
The proposal to combine the " Radioactive Effluent Release Report" and the
" Radioactive Effluents Dose Report" into a single submittal entitled
" Radioactive Effluent Report" is acceptabic in that the content of the new The report would be equivalent to that contained in the previous two reports.
changes to the TS, required to reference the combined report in other parts of the TS, are required for consistency and are acceptable.
Based upon the above, the proposed changes to the TS for Haddam Neck and Millstone Units 1, 2 and 3 are acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendments. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendments relate to changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10).
Pursuant to 10 CFR 51.22(b) no environmental impact statement i
or environmental assessment need be prepared in connection with the issuance of the amendments.
5.0 CONCLUSION
The Commission has concluded, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the that:
public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
i Principal Contributor:
D. Jaffe i
Date: November 23, 1993 j
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