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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20129J4311996-10-18018 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 ML20153E5331988-08-29029 August 1988 Safety Evaluation Supporting Amends 31 & 30 to Licenses DPR-80 & DPR-82,respectively ML20210D1281986-09-11011 September 1986 Safety Evaluation Re Util Response to Generic Ltr 83-28, Items 3.2.1 & 3.2.2.Items Closed ML20132G2611985-07-0808 July 1985 Safety Evaluation Accepting Licensee Response to Generic Ltr 83-28,Item 4.5.1 Re Reactor Trip Sys Functional Testing ML20210E6641984-12-19019 December 1984 SER Supporting Util Submittal Re Physical Security, Safeguards Contingency & Guard Training & Qualification Plans,Per 10CFR73.SALP Input Encl ML20207S8561984-06-29029 June 1984 SER Re Allegation 100 on Solid Debris from Unqualified Paints Inside Containment.Debris Will Not Have Significant Adverse Effect on Operability of Containment Sump & Associated Safety Sys IA-86-679, Sser Re Effect of Breakwater Damage on Saltwater Intake Structure1983-02-15015 February 1983 Sser Re Effect of Breakwater Damage on Saltwater Intake Structure ML20215D9091983-02-15015 February 1983 Sser Re Effect of Breakwater Damage on Saltwater Intake Structure ML20236P4381976-07-0606 July 1976 Evaluation of Applicant 760525 Request for Extension of CPPR-39 to 770101 ML20236B4401974-10-16016 October 1974 Safety Evaluation Supporting Util 730710 Application for OL ML20236B9381969-11-18018 November 1969 Safety Evaluation Supporting Util 680701 Application & Amends to Construct & Operate Second PWR at Diablo Canyon Site ML20151X7191968-01-23023 January 1968 AEC Safety Evaluation in Matter of Licensee Plant 1996-10-18
[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 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 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 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 ML18102B6911997-01-31031 January 1997 Monthly Operating Repts for Jan 1997 for Diablo Canyon Power Plant,Units 1 & 2.W/970218 Ltr ML16342D5351997-01-31031 January 1997 WCAP-14826, Instrumentation Calibr & Drift Evaluation Process for Diablo Canyon Units 1 & 2,24 Month Fuel Cycle Evaluation. 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. 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. 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. 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 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 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 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 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 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 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 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 ML20046A6611993-07-21021 July 1993 Cycle 6 Startup Rept. ML20059G6811993-06-30030 June 1993 Revised MOR for June 1993 for Dcnpp Unit 1 ML16342A3671993-05-31031 May 1993 Revised MOR for May 1993 for Dcnpp Unit 1 ML20045D1731993-05-31031 May 1993 Monthly Operating Repts for May 1993 for Diablo Canyon,Units 1 & 2 ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20141M0471991-12-31031 December 1991 Pge Annual Rept - 1991 ML20086T1001991-12-31031 December 1991 Adequacy of Seismic Margins Assuming Increase in Amplitude of Diablo Canyon Seismic Long-Term Program Horizontal & Vertical Ground Motions Described in Sser 34 ML16341G4871991-11-30030 November 1991 Nonproprietary Technical Justification for Eliminating Large Primary Loop Pipe Rupture as Structural Design Basis for Diablo Canyon Units 1 & 2 Nuclear Power Plants. ML20085D2951991-08-21021 August 1991 Field Exercise Scenario,Aug 1991 ML20070S7311990-12-31031 December 1990 Analysis of Capsule X from Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20065R8731990-11-30030 November 1990 Monthly Operating Repts for Diablo Canyon Units 1 & 2 for Nov 1990 ML20058P5181990-05-11011 May 1990 Accident Sequence Precursor Program Event Analysis 323/87-005 R2, Loss of RHR Cooling Results in Reactor Vessel Bulk Boiling ML20058P5131990-04-0505 April 1990 Accident Sequence Precursor Program Event Analysis 424/PNO-IIT-90-02A, Loop,Diesel Generator Failure & 36 Min Interruption of SDC During Mid-Loop Operation ML20058P5221990-02-0303 February 1990 Accident Sequence Precursor Program Event Analysis Loss of Reactor Protection Sys Bus B Causes Loss of Shutdown Cooling ML20006E5441989-11-30030 November 1989 Review of Flow Peaking & Tube Fatique in Diablo Canyon Units 1 & 2 Steam Generators. ML20006C6681989-11-30030 November 1989 Nonproprietary WCAP-12416, Evaluation of Thermal Stratification for Diablo Canyon Units 1 & 2 Pressurizer Surge Line. ML20246E4891989-06-30030 June 1989 Quarterly Sys Status Rept,2nd Quarter 1989,Sys 65 120V Instrument AC Sys,Sys 66 120V Security UPS Sys & Sys 67 125/250VDC Sys ML20245G9881989-06-16016 June 1989 Has Been Canceled.Resolution of LERs Missing from Lertrk/Scss/Dcs Discussed DCL-89-117, Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 8904181989-04-27027 April 1989 Special Rept:On 890406,main Steam Line Radiation Monitor 1RM-71 Alarmed & Declared Inoperable.Caused by Failure of Detector Tube.Tube Replaced.Monitor Returned to Svc on 890418 ML20247M6281989-03-31031 March 1989 Nonproprietary Advanced Digital Feedwater Control Sys Median Signal Selector for Diablo Canyon Units 1 & 2 ML20246P4461989-03-23023 March 1989 Corrected Diablo Canyon Power Plant Unit 2 Second Refueling Outage Inservice Insp (ISI) Rept ML20236E0581988-12-31031 December 1988 Pacific Gas & Electric Co Annual Rept 1988 ML20247H0761988-11-30030 November 1988 Vol 1 to Bit Elimination Study for Diablo Canyon Units 1 & 2 ML20205S9071988-10-31031 October 1988 Steam Generator U-Bend Tube Fatigue Evaluation ML20153E5331988-08-29029 August 1988 Safety Evaluation Supporting Amends 31 & 30 to Licenses DPR-80 & DPR-82,respectively ML20206E7181988-05-30030 May 1988 Analysis of Capsule U from PG&E Diablo Canyon Unit 2 Reactor Vessel Radiation Surveillance Program ML20195G3301988-04-30030 April 1988 Corrected Monthly Operating Repts for Apr 1988 for Diablo Canyon ML20153B0411988-03-31031 March 1988 Comments on ACRS Subcommittee on Diablo Canyon Meeting on 880223-24 in Burlingham,Ca Re Status of Long Term Seismic Program of Plant 1999-07-12
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SAFETY EVALUATION GENERIC LETTER 83-28, ITEMS 3.2.1 AND 3.2.2 r- PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON' NUCLEAR POWER PLANT, UNIT NO. 1 4
DOCKET NO. 50-275 I. INTRODUCTION On February 25, 1983, during startup of the Salem Unit'1 Nuclear Plant, both circuit breakers in the Reactor Trip System failed to open automatically upon receipt of a valid trip signal.- As a result of that event, the NRC's Office of Inspection and Enforcement issued IE Bulletin 83-01 which described the event and requested specified prompt corrective and preventive actions by licensees. As the cause and ramifications of the event were more clearly developed, the NRC's Office of Nuclear Reactor Regulation issued on July 8, 1983, Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS Events." This letter addressed issues related to reactor trip system reliability and general management capability. The letter was sent to all licensees of operating
- reactors, applicants for operating licenses and holders of construction permits.
One of the areas of reactor trip system reliability considered in Generic 4
Letter 83-28 (GL 83-28), is that the post-maintenance testing of safety-related components other than those in the reactor trip system. This is identified in GL 83-28 as Items 3.2.1 and 3.2.2. This evaluation
- addresses the acceptability of the response to these items provided by the Pacific Gas and Electric Company (the licensee) for the Diablo Canyon Nucicar Power Plant, Unit No. 1 (the facility).
II. EVALUATION Items 3.2.1 and 3.2.2 of GL 83-28 state as follows:
"1. Licensees and applicants shall submit a report documenting the extending of test and maintenance procedures and Technical 1
Specifications to assure that post-maintenance operability testing of all safety-related equipment is required to be conducted and that the testing demonstrates that the equipment is capable of performing its safety functions before being returned to service.
"2. Licensees and applicants shall submit the results of their check of vendor and engineering recommendations to ensure that any appropriate test guidance is included in the test and maintenance procedures or Technical Specifications, where required."
By letters dated November 7, 1983 and March 20, 1986, the licensee l responded to GL 83-28, Items 3.2.1. and 3.2.2.
l 86091900S9 860911 PDR ADOCK 05000275 P PDR i
. . 2 Regarding Item 3.2.1, the licensee's letter of March 20, 1986, states Administrative Procedures NPAP-C6, " Clearances", and AP-C-6S3,
" Post-M a intenance Testing", ensure that appropriate tests are conducted to verify that equipment removed from service for maintenance (either corrective or preventive) is tested prior to its return to service to determine that it is operable and is capable of performing its intended safety functions. The licensee adds that following completion of maintenance work, the appropriate post-maintenance test is run after the equipment is returned to service, but before the equipment is declared " operable".
Regarding Item 3.2.2, (incorporation of vendor recommendations in test and maintenance procedures), the licensee's letter of March 20, 1986, states that the licensee has reviewed the applicable vendor and engineering recommendations to ensure that appropriate test guidance is included in maintenance procedures as required. Regarding post-maintenance test procedures, however, the licensee states a few recommendations require further review to determine if they should be incorporated in future procedure revisions. The licensee estimates this process, including procedure revision, will be completed by June 30, 1986.
III. CONCLUSIONS Based on the licensee's description of facility procedures which require post-maintenance testing of safety-related equipment to demonstrate its operability and capability to perform its intended safety function, we ;
conclude the licensee has satisfactory completed the actions requested by Generic Letter 83-28, Item 3.2.1. Accordingly, this item is closed.
Based on the licensee's statement that applicable vendor and engineering recommendations have been reviewed and are in the process of being incorporated in test and maintenance procedures, as appropriate, we 2
conclude the licensee is acceptably performing the actions request by Generic Letter 83-28, Item 3.2.2.- Accordingly, this item is closed.
Date:
Principal Contributor:
G. Zwetzig i
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