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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20196G5381999-06-25025 June 1999 Correction to SER Acceping Amends to Added Limiting Condition for Operation,Trip Setpoints & SR for Residual Heat Removal Pump Trip on Refueling Water Storage Tank level-low ML20207A7181999-05-13013 May 1999 Safety Evaluation Supporting Amends 134 & 132 to Licenses DPR-80 & DPR-82,respectively ML20206H2861999-05-0303 May 1999 Safety Evaluation Supporting Amends 133 & 131 to Licenses DPR-80 & DPR-82,respectively ML20206D5661999-04-29029 April 1999 Safety Evaluation Supporting Amends 132 & 130 to Licenses DPR-80 & DPR-82,respectively ML20205B6061999-03-26026 March 1999 Safety Evaluation Supporting Amends 131 & 129 to Licenses DPR-80 & DPR-82,respectively ML20249B6881998-06-11011 June 1998 Safety Evaluation Supporting Amends 128 & 126 to Licenses DPR-80 & DPR-82,respectively ML20249B5961998-06-0505 June 1998 Safety Evaluation Supporting Amends 127 & 125 to Licenses DPR-80 & 82,respectively ML20249B6041998-06-0505 June 1998 Safety Evaluation Supporting Amends 126 & 124 to Licenses DPR-80 & DPR-82,respectively ML20248D4041998-05-28028 May 1998 Safety Evaluation Supporting Amends 125 & 123 to Licenses DPR-80 & DPR-82,respectively ML20248L8761998-03-12012 March 1998 Safety Evaluation Supporting Amends 124 & 122 to Licenses DPR-80 & DPR-82,respectively ML20197B7091998-02-27027 February 1998 Safety Evaluation Supporting Amends 123 & 121 to Licenses DPR-80 & DPR-82,respectively ML20203L4881998-02-17017 February 1998 Safety Evaluation Supporting Amends 122 & 120 to Licenses DPR-80 & DPR-82,respectively ML20203L2981998-02-13013 February 1998 Safety Evaluation Supporting Amends 121 & 119 to Licenses DPR-80 & DPR-82,respectively ML20203M4321998-02-0303 February 1998 Safety Evaluation Supporting Amends 120 & 118 to Licenses DPR-80 & DPR-82,respectively ML20149H4281997-07-17017 July 1997 Corrected SE Re Amends 119 & 117 to Licenses DPR-80 & DPR-82,respectively ML20129G7771996-10-25025 October 1996 Safety Evaluation Supporting Amends 116 & 114 to Licenses DPR-80 & DPR-82,respectively ML20129G9351996-10-25025 October 1996 Safety Evaluation Supporting Amends 117 & 115 to Licenses DPR-80 & DPR-82,respectively ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary ML20117E5541996-08-19019 August 1996 Safety Evaluation Supporting Amends 115 & 113 to Licenses DPR-80 & DPR-82,respectively ML20116J4521996-08-0101 August 1996 Safety Evaluation Supporting Amends 114 & 112 to Licenses DPR-80 & DPR-82,respectively ML20117K4671996-05-28028 May 1996 Safety Evaluation Supporting Amends 113 & 111 to Licenses DPR-80 & DPR-82,respectively ML20100Q4491996-03-0101 March 1996 Safety Evaluation Supporting Amends 110 & 109 to Licenses DPR-80 & DPR-82,respectively ML20092F3411995-08-23023 August 1995 Corrected SE Supporting Amends 107 & 106 to Licenses DPR-82 & DPR-80,respectively ML20082H9121995-04-11011 April 1995 Safety Evaluation Supporting Amends 99 & 98 to Licenses DPR-80 & DPR-82,respectively ML20149H0781994-10-31031 October 1994 Safety Evaluation Supporting Amends 96 & 95 to Licenses DPR-80 & DPR-82,respectively ML20063M1481994-03-0303 March 1994 Safety Evaluation Supporting Amends 90 & 89 to Licenses DPR-80 & DPR-82,respectively ML20063M1111994-03-0202 March 1994 Safety Evaluation Supporting Amends 89 & 88 to Licenses DPR-80 & DPR-82,respectively ML20063M0431994-02-24024 February 1994 Safety Evaluation Supporting Amends 88 & 87 to Licenses DPR-80 & DPR-82,respectively NUREG-0675, SER Concluding That Seismic Margins of Structures & Equipment/Components at Plant Reported in LTSP Final Rept Are Adequate Even After Considering Staff Estimate of Increased Seismic Ground Motions1992-04-17017 April 1992 SER Concluding That Seismic Margins of Structures & Equipment/Components at Plant Reported in LTSP Final Rept Are Adequate Even After Considering Staff Estimate of Increased Seismic Ground Motions ML20092E0021992-01-22022 January 1992 Safety Evaluation Supporting Amends 67 & 66 to Licenses DPR-80 & DPR-82,respectively ML20082V1441991-09-0606 September 1991 Safety Evaluation Supporting Amends 66 & 65 to Licenses DPR-80 & DPR-82,respectively ML20082V2621991-09-0505 September 1991 Safety Evaluation Supporting Amends 65 & 64 to Licenses DPR-80 & DPR-82,respectively ML20081L3021991-06-27027 June 1991 Safety Evaluation Supporting Amends 62 & 61 to Licenses DPR-80 & DPR-82,respectively ML20081F2021991-05-23023 May 1991 Safety Evaluation Supporting Amends 61 & 60 to Licenses DPR-80 & DPR-82,respectively ML20070H1821991-03-0606 March 1991 Safety Evaluation Supporting Amends 59 & 58 to Licenses DPR-80 & DPR-82,respectively ML20055G3241990-07-12012 July 1990 Safety Evaluation Supporting Amends 56 & 55 to Licenses DPR-80 & DPR-82,respectively ML20246K9501989-07-10010 July 1989 Safety Evaluation Supporting Amends 42 & 41 to License DPR-80 & DPR-82,respectively ML20245F8371989-06-22022 June 1989 Safety Evaluation Supporting Amends 41 & 40 to Licenses DPR-80 & DPR-82,respectively ML20244C8551989-06-0707 June 1989 Safety Evaluation Supporting Amends 39 & 38 to Licenses DPR-80 & DPR-82,respectively ML20244C8771989-06-0707 June 1989 Safety Evaluation Supporting Amends 40 & 39 to Licenses DPR-80 & DPR-82,respectively ML20247H9771989-05-23023 May 1989 Safety Evaluation Supporting Amends 38 & 37 to Licenses DPR-80 & DPR-82,respectively ML20247B1201989-05-10010 May 1989 Safety Evaluation Supporting Amends 37 & 36 to Licenses DPR-80 & DPR-82,respectively ML20245L2511989-04-25025 April 1989 Safety Evaluation Supporting Amends 36 & 35 to Licenses DPR-80 & DPR-82,respectively ML20245H6991989-04-14014 April 1989 Safety Evaluation Supporting Amends 34 & 35 to Licenses DPR-82 & DPR-80,respectively ML20247L2931989-03-27027 March 1989 Safety Evaluation Supporting Amends 34 & 33 to Licenses DPR-80 & DPR-82,respectively ML20153E5331988-08-29029 August 1988 Safety Evaluation Supporting Amends 31 & 30 to Licenses DPR-80 & DPR-82,respectively ML20196E4811987-12-28028 December 1987 Safety Evaluation Supporting Amends 26 & 25 to Licenses DPR-80 & DPR-82,respectively ML20238C4611987-12-16016 December 1987 Safety Evaluation Supporting Amends 24 & 23 to Licenses DPR-80 & DPR-82,respectively ML20238C6061987-12-16016 December 1987 Safety Evaluation Supporting Amends 25 & 24 to Licenses DPR-80 & DPR-82,respectively ML20235G7671987-09-18018 September 1987 Safety Evaluation Supporting Amends 21 & 20 to Licenses DPR-80 & DPR-82,respectively 1999-06-25
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20196G5381999-06-25025 June 1999 Correction to SER Acceping Amends to Added Limiting Condition for Operation,Trip Setpoints & SR for Residual Heat Removal Pump Trip on Refueling Water Storage Tank level-low ML20207A7181999-05-13013 May 1999 Safety Evaluation Supporting Amends 134 & 132 to Licenses DPR-80 & DPR-82,respectively ML20206H2861999-05-0303 May 1999 Safety Evaluation Supporting Amends 133 & 131 to Licenses DPR-80 & DPR-82,respectively ML20206D5661999-04-29029 April 1999 Safety Evaluation Supporting Amends 132 & 130 to Licenses DPR-80 & DPR-82,respectively ML20205B6061999-03-26026 March 1999 Safety Evaluation Supporting Amends 131 & 129 to Licenses DPR-80 & DPR-82,respectively DCL-99-045, 1998 Annual Financial Rept for PG&E Corp. with1998-12-31031 December 1998 1998 Annual Financial Rept for PG&E Corp. with ML20249B6881998-06-11011 June 1998 Safety Evaluation Supporting Amends 128 & 126 to Licenses DPR-80 & DPR-82,respectively ML20249B5961998-06-0505 June 1998 Safety Evaluation Supporting Amends 127 & 125 to Licenses DPR-80 & 82,respectively ML20249B6041998-06-0505 June 1998 Safety Evaluation Supporting Amends 126 & 124 to Licenses DPR-80 & DPR-82,respectively ML20248D4041998-05-28028 May 1998 Safety Evaluation Supporting Amends 125 & 123 to Licenses DPR-80 & DPR-82,respectively ML20248L8761998-03-12012 March 1998 Safety Evaluation Supporting Amends 124 & 122 to Licenses DPR-80 & DPR-82,respectively ML20197B7091998-02-27027 February 1998 Safety Evaluation Supporting Amends 123 & 121 to Licenses DPR-80 & DPR-82,respectively ML20203J5141998-02-26026 February 1998 LER 98-S02-00:on 980127,following Security Sys Failure Compensatory Measures Were Not Implemented within 10 Minutes Due to Personnel Error.Caused by Failed Disk Drive. Replaced Disk Drives,Reviewed Security Computer Maint Plans ML20203L4881998-02-17017 February 1998 Safety Evaluation Supporting Amends 122 & 120 to Licenses DPR-80 & DPR-82,respectively ML20203L2981998-02-13013 February 1998 Safety Evaluation Supporting Amends 121 & 119 to Licenses DPR-80 & DPR-82,respectively ML20203M4321998-02-0303 February 1998 Safety Evaluation Supporting Amends 120 & 118 to Licenses DPR-80 & DPR-82,respectively ML20217G5151997-12-31031 December 1997 1997 PG&E Corp Annual Rept ML20205F5881997-07-24024 July 1997 Decommissioning Cost Estimate for Diablo Canyon Power Plant,Units 1 & 2 ML20149H4281997-07-17017 July 1997 Corrected SE Re Amends 119 & 117 to Licenses DPR-80 & DPR-82,respectively ML17264A9381997-07-10010 July 1997 Deficiency Rept Re Potential Safety Hazard Associated w/FM-Alco 251 Engin,High Pressure Fuel tube-catalog: 4401031-2 in Which Dual Failure Mode Exists.Caused by Incorrect Forming Process ML16343A4741997-01-31031 January 1997 WCAP-11595,Rev 2, W Improved Thermal Design Procedure Instrument Uncertainty Methodology Diablo Canyon Units 1 & 2 24 Month Fuel Cycle Evaluation. ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML17083C6231997-01-31031 January 1997 Rev 4 to WCAP-13705, W Setpoint Methodology for Protection Sys Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. ML18102B6911997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Diablo Canyon Power Plant,Units 1 & 2.W/970218 Ltr DCL-97-045, Pacific Gas & Electric Co 1996 Annual Rept1996-12-31031 December 1996 Pacific Gas & Electric Co 1996 Annual Rept ML16342D5541996-12-31031 December 1996 Non-proprietary Nrc/Util Meeting on Model 51 SG Tube Integrity & ARC Methodology. ML20129G9351996-10-25025 October 1996 Safety Evaluation Supporting Amends 117 & 115 to Licenses DPR-80 & DPR-82,respectively ML20129G7771996-10-25025 October 1996 Safety Evaluation Supporting Amends 116 & 114 to Licenses DPR-80 & DPR-82,respectively ML20129J4311996-10-18018 October 1996 Safety Evaluation Approving Corporate Restructuring & Establishment of Holding Company Under Temporary Name PG&E Parent Co.,Inc of Which PG&E Would Become Wholly Owned Subsidiary ML20117E5541996-08-19019 August 1996 Safety Evaluation Supporting Amends 115 & 113 to Licenses DPR-80 & DPR-82,respectively ML20116J4521996-08-0101 August 1996 Safety Evaluation Supporting Amends 114 & 112 to Licenses DPR-80 & DPR-82,respectively ML20116B8491996-07-22022 July 1996 Revised Special Rept SR 95-03:on 950621,EDG 1-2 Failed to Load During Surveillance Testing.Caused by Loose Fuse Holder Contact Clip.Retensioned Loose Fuse Holder Contact Clip & Tightened Loose Wire Connection ML20116B8521996-07-22022 July 1996 Revised Special Rept SR 95-04:on 950718,EDG 1-2 Load Swings Occurred.Caused by Defective Electronic Governor Stability Potentiometer.Replaced Electronic Governor DCL-96-155, Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor1996-07-22022 July 1996 Revised Special Rept SR 95-05:on 950806,EDG 1-2 to Achieve Rated Output Frequency within TS Limits.Caused by Degraded Electronic Governor Performance.Replaced Electronic Governor Motor Operated Potentiometer & Electronic Governor ML20117K4671996-05-28028 May 1996 Safety Evaluation Supporting Amends 113 & 111 to Licenses DPR-80 & DPR-82,respectively ML20236Q2611996-04-15015 April 1996 Rev 0 to DCP M-050284, Design Change Package for Installation of CCW Surge Tank Pressurization Sys for Unit 1 ML20100Q4491996-03-0101 March 1996 Safety Evaluation Supporting Amends 110 & 109 to Licenses DPR-80 & DPR-82,respectively ML20094M6251995-11-21021 November 1995 Final Part 21 Rept of Investigation & Analysis of Suspect Fasteners Event 29257.B&G-Cardinal Discontinued Using Heat Treatment Equipment at Cardinal Facility Until Such Time That Satisfactory Mods Made to Hardware & Procedures ML20092F3411995-08-23023 August 1995 Corrected SE Supporting Amends 107 & 106 to Licenses DPR-82 & DPR-80,respectively ML18064A8631995-08-14014 August 1995 LER 95-004-00:on 950714,determined That Redundant DG Circuits Not Separated Per App R Due to Insufficient App R Program Documentation.Hourly Fire Tour Established in EDG 1-1 Room & Review of LERs for App R Completed ML20082H9121995-04-11011 April 1995 Safety Evaluation Supporting Amends 99 & 98 to Licenses DPR-80 & DPR-82,respectively ML20149H0781994-10-31031 October 1994 Safety Evaluation Supporting Amends 96 & 95 to Licenses DPR-80 & DPR-82,respectively ML18100B2981994-05-24024 May 1994 LER 94-014-00:on 940426,SG 1-2 Automatically Started When Two Indicating Light Sockets Shorted Together Due to Personnel Error.Description of Event & Lessons Learned Will Be Published in Operations Incident Summary.W/940524 Ltr ML20063M1481994-03-0303 March 1994 Safety Evaluation Supporting Amends 90 & 89 to Licenses DPR-80 & DPR-82,respectively ML20063M1111994-03-0202 March 1994 Safety Evaluation Supporting Amends 89 & 88 to Licenses DPR-80 & DPR-82,respectively ML20063M0431994-02-24024 February 1994 Safety Evaluation Supporting Amends 88 & 87 to Licenses DPR-80 & DPR-82,respectively ML16342C3091993-12-31031 December 1993 Monthly Operating Repts for Dec 1993 for Dcnpp Units 1 & 2 ML16342A3691993-08-31031 August 1993 Revised MOR for Aug 1993 for Dcnpp Unit 1 ML16342A3681993-07-31031 July 1993 Revised MOR for July 1993 for Dcnpp Unit 1 1999-07-12
[Table view] |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 110 TO FACILITY OPERATING LICENSE NO. DPR-80 AND AMENDMENT NO. 109 TO FACILITY OPERATING LICENSE NO. DPR-82 PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT. UNITS 1 AND 2 DOCKET NOS. 50-275 AND 50-323
1.0 INTRODUCTION
By application dated December 27, 1995, Pacific Gas and Electric Company (or the licensee) requested changes to the Technical Specifications (Appendix A to Facility Operating License Nos. DPR-80 and DPR-82) for the Diablo Canyon Nuclear Power Plant, Units 1 and 2.
The proposed changes would revise the Technical Specifications to reflect the approval for the licensee to use 10 CFR Part 50, Appendix J, Option B for the Diablo Canyon Nuclear Power Plant, Units 1 and 2 containment leakage rate test program.
2.0 MCKGROUND Compliance with 10 CFR Part 50, Appendix J provides assurance that the primary containment, including those systems and components which penetrate the primary containment, do not exceed the allowable leakage rate values specified in the Technical Specifications and Bases. The allowable leakage rate is determined so that the leakage assumed in the safety analyses is not exceeded.
On February 4,1992, the NRC published a notice in the Federal Reaister (57 FR 4166) discussing a planned initiative to begin eliminating requirements marginal to safety which impose a significant regulatory burden. Appendix J,
" Primary Containment Leakage Testing for Water-Cooled Power Reactors" to 10 CFR Part 50, was considered for this initiative and the staff undertook a study of possible changes to this regulation. The study examined the previous perfomance history of domestic containments and examined the effect on risk of a revision to the requirements of Appendix J.
The results.of this study are reported in NUREG-1493, " Performance-Based Leak-Test Program".
Based on the results of this study, the staff developed a performance based approach to containment leakage rate testing. On September 12, 1995, the NRC approved issuance of this revision to 10 CFR Part 50, Appendix J, which was subsequently published in the Federal Beaister on September 26,-1995, and became effective on October 26, 1995. The revision added Option B j
" Performance-Based Requirements" to Appendix J to allow licensees to voluntarily replace the prescriptive testing requirements of Appendix J with testing requirements based on both overall and individual component leakage rate performance.
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' Regulatory Guide 1.163, " Performance-Based Containment Leak Test Program," was developed.as a method acceptable to the staff for implementing Option B.
This Regulatory Guide states that the Nuclear Energy Institute (NEI) document NEI 94-01, " Industry Guideline for Implementing Performance-Based Option of-10 CFR Part 50, Appendix J" provides methods acceptable to the staff for complying with Option B with four exceptions, which are described therein.
Option B requires that Regulatory Guide 1.163 or another implementation document used by a licensee to develop a performance based leakage rate i
testing program must be included, by general reference, in the plant technical specifications. The licensee has referenced Regulatory Guide 1.163 in the Diablo Canyon combined technical specifications.
Regulatory Guide 1.163 specifies an extension in Type A test frequency to at least one test in 10 years based upon two consecutive successful tests.
Type B tests may be extended up to a maximum of 10 years based upon completion of two coasecutive successful tests and Type C tests may be extended up to 5 years based on two consecutive successful tests.
By letter dated October 20, 1995, NEI proposed technical specifications for implementing Option B.
After some discussion, the staff and NEI agreed on a set of model technical specifications which were transmitted to NEI in =
letter datcd November 2,1995. These technical specifications are to serve as a model for licensees to develop plant specific technical specifications in preparing amendment requests to implement Option B.
For a licensee to determine the performance of each component factors that are indicative of or affect performance such as an administrative leakage limit must be established. The administrative limit is selected to be indicative of the potential onset of component degradation. Although these limits are subject to NRC inspection to enstre that they are selected in a reasonable manner, they are not technical specifications requirements.
Failure to meet an administrative limit requires the licensee to return to the minimum value of the test interval.
Option B requires that the licensee maintain records to show that the criteria j
for Type A, B and C tests have been met.
In addition, the licensee must maintain comparisons of the performance of the overall containment system and the individual components to show that the test intervals are adequate. These records are subject to NRC inspection.
3.0 EVALUATION The licensee's December 27, 1995, letter to the NRC proposes to establish a
" Primary Containment Leakage Rate Program" and proposes to add this program to i
the technical specifications. The program references Regulatory Guide 1.163,
" Performance-Based Containment Leak Test Program" which specifies methods acceptable to the staff for complying with Option B.
This requires a change to existing Technical Specifications. 3.6.1.2, 3.6.1.3, 4.6.1.1, 4.6.1.2, 4.6.1.3, 4.6.1.6.1 and 4.6.3.4 and the addition of the program to section 6.8.4.j of the technical specifications. The changes to the existing TS add a
. references to the, Containment Leak Test Program, delete criteria no longer applicable with option B, and delete specific criteria for surveillance and frequency that are to be controlled by the TS containing the program.
Option B permits a licensee to choose Type A; or Type B and C; or Type A, B and C; testing to be done on a performance basis. The licensee has elected to perform Type A, B and C testing on a performance basis.
The staff finds that the technical specifications changes proposed by the licensee meet the requirements of 10 CFR Part 50, Appendix J, Option B and, are consistent with the model technical specifications included in the staff's NL. ember 2,1995, letter to NEI and are therefore acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the California State official was notified of the preposed issuance of the amendment. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
These amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20-and 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 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 (61 FR 3502). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in'10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
6.0 CONCLUSION
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 iritmical to the common defense and security or to the health and safety of the public.
Principal Contributors: R. Lobel, NRR/DSSA/SCSB J. Pulsipher, NRR/DSSA/SCSB S. Bloom, NRR/DRPW/PD42 Date:
March 1, 1996 O
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