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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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1 UNITED STATES
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j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 30e664001
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g Q**4Wl SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION I
RELATED TO AMENDMENT NO. 221 TO FACILITY OPERATING LICENSE NO. DPR-65
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NORTHEAST NUCLEAR ENERGY COMPANY THE CONNECTICUT LIGHT AND POWER COMPANY THE WESTERN MASSACHUSETTS ELECTRIC COMPANY MILLSTONE NUCLEAR POWER STATION. UNIT NO. 2 DOCKET NO. 50-336
1.0 INTRODUCTION
l By letter dated September 19,1995, the Northeast Nuclear Energy Company, et al.
(NNECO/the licensee), submitted a request to change the Millstone Nuclear Power Station, Unit No. 2 (MNPS-2), Technical Specifications (TSs). The requested change would reduce the frequency of the surveillance interval for the safety injection tanks (SITS) from once every 31 days to once every 6 months.
Specifically, the change was requested for TS Section 4.5.1.b. However, TS Section 4.5.1.b was subsequently changed to TS Section 4.5.1.d by Amendment No. 220 to Facility Operating License No. DPR-65, dated September 3,1998, in response to your application dated August 23,1995.
2.0 EVALUATION The MNPS-2 has four SITS that are passive pressure vessels which are partially filled with l
borated water and pressurized with a nitrogen cover gas. During the blowdown phase of a l
design basis loss-of-coolant, the reactor coolant system will depressurize and the nitrogen cover gas will cause the SITS to inject into the reactor vessel via the cold legs. TS 4.5.1.d has a surveillance requirement to verify the boron concentration of each SlT solution at least once per 31 days to demonstrate that the SITS are operable.
The request to reduce the frequency of SIT boron concentration surveillance is a follow-up to NRC Inspection Report 50-336/92-35, dated March 3,1993, which refers to the licensee evaluating the need for a TS change to reduce the frequency of the SIT surveillance which in turn would reduce the number of containment entries during power operation. The reduction in containment entries would reduce personnel radiological exposure in accordance with the licensee's policy to keep personnel exposures as-low-as-reasonably-achievable.
9812230328 981217 PDR ADOCK 05000336 P
PDR l
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. The required minimum boron concentration of the SITS is 1720 parts per million (ppm). As L
stated in the licensee's submittal, the historical concentration data indicates that the boron concentration of the SITS has been greater than the required 1720 ppm during the period of 1981 l
through 1992, with the average and the lowest boron concentration being 1968 ppm and 1756 l
ppm, respectively. The two ways that SIT boron concentration can be reduced is through precipitation or dilution.
Precipitation occurs when the solution of borated water becomes so saturated that the boron settles out of the solution. The solubility limit of boric acid in water is 2.52 wt% at 32 *F, which corresponds to a boron concentration of approximately 4400 ppm. The boron concentration of l-the SITS is well below the solubility limit, which precludes boric acid concentration reduction due l
to boron precipitation.
l Dilution occurs due to the addition of water containing a lower boron concentration than the SITS.
A TS surveillance requirement to perform a boron concentration verification on a solution volume increase of a 1 percent of the tank volume has previously been added to TS 4.5.1.d to guard against this phenomenon. This surveillance requirement ensures that the correct boron.
concentration is maintained and dilution will not occur.
3.0
SUMMARY
The NRC staff has reviewed the licensee's submittal requesting extension of the surveillance interval from every 31 days to every 6 months. The staff has determined that the proposed change to TS 4.5.1.d is acceptable. This determination is based on: (1) there is a TS l
surveillance requirement in the TSs to verify an SIT concentration anytime there is a change in a tank volume 21 percent, (2) the SIT boron concentration is well below the solubility limit of boron, (3) a change to en existing surveillance interval does not impact the Updated Final Safety Analysis Report, Chapter 14, transient analysis, and (4) personnel exposure to radiological exposure will be reduced.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified of the proposed issuance of the amendment.. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes surveillance requirements. The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in l'
individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (60 FR 54722 dated October 25,1995).
Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 l
CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or L
environmental assessment need be prepared in connection with the issuance of the amendment.
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6.0 CONCLUSION
l The Commission has concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the 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 amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor: S. Brewer Date: December 17, 1998 i
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