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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20199J6981997-11-11011 November 1997 Rev 2 to 10CFR50.59 Review for Jet Pump Thermal Sleeve Cracking ML20202H1231997-09-30030 September 1997 Small Project Joint Permit Application & Attachments for PECO Energy Co,Peach Bottom Atomic Power Station,Rock Run Creek Low Flow Crossing, to Satisfy PA Dept of Environ Protection & Us Army Corps of Engineers ML20129E8711996-09-26026 September 1996 Rev 0 to 10CFR50.59 Review for Ncr Pb 96-03414,Core Spray T-Box Cracks for Peach Bottom Atomic Power Station,Unit 2 ML20117E6351996-05-31031 May 1996 Seismic Evaluation Rept for Pbaps ML20117E6321996-05-31031 May 1996 USI A-46 Relay Evaluation Rept for PBAPS Units 2 & 3 ML20117E6251996-05-31031 May 1996 Seismic Safe Shutdown Equipment List for PBAPS Units 2 & 3 ML20129A4511996-01-11011 January 1996 Core Spray Sparger Downcomer Modification ML20129A4731995-12-11011 December 1995 Fabrication of Core Spray Line Downcomer Clamp ML20092M8921995-09-30030 September 1995 Shroud Vertical Team Weld Evaluation ML20098B1141995-09-30030 September 1995 Evaluation of Peach Bottom Unit 3 Core Spray Line ML20098B1211995-09-30030 September 1995 Residual Stress Analysis of Peach Bottom Unit 3 Core Spray Pipe to Sleeve Fillet Weld ML20092J8151995-09-15015 September 1995 Core Spray Line Tee-Box Analysis Rept for Peach Bottom Atomic Power Station Unit 3 ML20094H0521995-06-30030 June 1995 Pyrolysis Gas Chromatography Analysis of 21 Thermo-Lag Fire Barrier Samples ML20092K9871995-06-13013 June 1995 Rev 3 to Shroud Stabilizer Hardware ML20083K6611995-04-26026 April 1995 Rev a to Upgraded Eals ML20077M0861995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for RPS for PBAPS, Units 2 & 3 ML20077M0951995-01-31031 January 1995 Nonproprietary TS Improvement Analysis for ECCS Actuation Instrumentation for Pbaps,Units 2 & 3 ML20073J7501994-09-30030 September 1994 Shroud Mechnical Repair Program,Peach Bottom Shroud & Shroud Repair Hardware Stress Analysis ML20079S0911994-09-29029 September 1994 Rev 0 to Application of Screening Criteria ML20073J7411994-09-24024 September 1994 Rev 0 to Stress Rept 25A5607, Shroud Stabilizers ML20072P5791994-08-26026 August 1994 Power System Harmonic Study for Peach Bottom Nuclear Power Plant, Final Rept ML20072L9631993-12-13013 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit-2 Shroud ML20064K4291993-12-0303 December 1993 Evaluation & Screening Criteria for Peach Bottom Unit 3 Shroud Indications ML20059L1391993-11-30030 November 1993 Core Spray Crack Analysis for Peach Bottom Unit 3 ML20059G0901993-10-27027 October 1993 Evaluation & Screening Criteria for Peach Bottom Unit-3 Shroud Indications ML20149G0401993-05-30030 May 1993 Fatigue Evaluation of Peach Bottom II & III Reactor Vessels ML20073E5881991-04-30030 April 1991 Revised Station Blackout Analysis ML20073D0221991-04-30030 April 1991 Full Structural Weld Overlay Design for Peach Bottom Unit 2 RWCU Weld 12-I-1D ML20055J3291990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML18095A3791990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co. ML20055J3271990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20055J3231990-07-20020 July 1990 Decommissioning Rept of Philadelphia Electric Co ML20044H3281990-02-23023 February 1990 Rev a to 30-Month Stability Spec for Rosemount Models 1152, 1153 & 1154 Pressure Transmitters. ML20247N3951989-05-16016 May 1989 Methods for Performing BWR Reload Safety Evaluations ML20236A8351989-01-31031 January 1989 Rev 1 to Peach Bottom Atomic Power Station Units 2 & 3, Verification of Calculated Auxiliary Distribution Sys Voltages by Test ML20236A8501989-01-31031 January 1989 Voltage Regulation Study ML20206K3021988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Peach Bottom Atomic Power Station Unit 3 ML20206K3101988-10-31031 October 1988 Rev 1 to Impact of Reg Guide 1.99,Rev 2 on Limerick Generating Station Unit 1 ML20151M5501988-07-15015 July 1988 Security Problem Root Cause Assessment ML20147A7971988-02-23023 February 1988 Root Cause Investigation of Shutdown Cooling Isolations Peach Bottom Atomic Power Station ML20148H1211988-01-15015 January 1988 Rev 0 to Peach Bottom Atomic Power Station,Units 2 & 3, Response to IE Bulletin 85-003 ML20149D6981988-01-13013 January 1988 Methods for Performing BWR Steady-State Reactor Physics Analyses ML20196K0311987-12-31031 December 1987 1987 Annual Plant Mod Rept,Per 10CFR50.59 ML20236V3311987-11-20020 November 1987 SAR for Peach Bottom Atomic Power Station Spds ML20236J7141987-10-28028 October 1987 Commitment to Exellence Action Plan Status Rept ML20235H5601987-09-0909 September 1987 Methods for Performing BWR Sys Transient Analysis ML20236D1271987-09-0303 September 1987 Rev 0 to Safety Evaluation for Mod 2085,Peach Bottom Unit 3 ML20236K6081987-07-15015 July 1987 Rev 1 to Evaluation of Insulated Blind Barrel Splices on Dual Voltage Motors in Limitorque Actuators 1998-12-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
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' ATTACHMENT C PHILADELPHIA ELECTRIC COMPANY PEACH BOTTOM ATOMIC POWER STATION UNIT 3 DOCKET No. 50-278 ,
. SAFETY EVALUATION FOR THE dFsRAff0R 5f FBKCH 5dffDA Af6sIU F5R2R~EfKfi6R'ORif 3 i.
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SUBJECT:
Safety Evaluation for the Operation of Peach Bottom Atomic Power Station Unit 3 r.
IN{gggUgg{gg Philadelphia Electric Company performed inspections of the Peach Bottom Unit 3 jet pump instruuentation penetrations in response to I.E. Information Notice 84-41 and NRC Generic Letter 84-11. As part of this program, ultrasonic examinations were performed on the five welds associated with each jet pump instrumentation penetration. Circumferential crack-like indications were found on weld No. 2 on each of the two jet pump instrumentation penetrations (see Figure No.1) . In addition to the crack-like indications, the "B" loop No. 2 weld also showed three pin-hole leaks.
Philadelphia Electric Company contracted General Electric company to analyze these indications and to provide their recommendations. All circumferential indications would' require a weld overlay in order to provide the structural reinforcement i O necessary for 18 months of full power operation. The weld overlays were designed and sized as full structural overlays; thus meeting the requirements of NRC Generic Letter 84-11, and providing all ASME Code safety margins.
Overlay weld procedures were prepared to perform these temporary repairs with the concurrence of the on-site representative of the Hartford Steam Boiler Inspection und Insurance Company.- Both. welds received the weld overlays as recommended by General Electric Company. These overlays were
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made to provide additional structural reinforcement and prevent potential leakage.
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m EA9E9E9EEE The "A" loop circumferential indication was in the 12 o' clock position on the safe-end side of the No. 2 weld. The "B" loop circumferential indication with three pin-hole leaks was in the 12 o' clock position on the reducer side of the No. 2 weld. The pipe material at both of these locations is 4" nominal, Schedule 80 TP-304 Stainless Steel. The minimal wall thickness of these ,
i wolds is 0.337".
General Electric Company performed a fracture mechanics analysis on the crack indications identified in both welds. The analyses showed that these indications would not violate the code required safety factor of three for at least 9,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> of full power service'. Although a through-wall leak was present on the "B" loop, the weld was still within the allowable requirements since the ASME Code safety factor of three can be maintained with a through-wall crack of over 40% of the circumference in length.
General Electric Company recommended applying a 0.125" thick by 1.5" long overlay on each weld to assure leak-free operation for a minimum of 18 months of fu11' power operation.
() EY^hEATI96 The ultrasonic exmaination techniques used in the detection of the crack-like indications has been demonstrated to be capable of finding IGSCC cracking at Battelle Columbus Laboratories and the EPRI NDT Center in Charlotte, North Carolina. The ~
technicians participating in.the examination have been certified as being able to detect _ service induced IGSCC by an actual demonstration using cracked specimens in accordance with NUREG IE Dulletin 83-02 and NRC Generic Letter 84-11.
The overlay design applied to these welds is conservative since it was designed to accommodate-a hypothetical.through-wall crack, 360 degrees in circumference. The overlay weld as applied-is a full structural overlay and meets all the requirements of NRC Generic Letter 84-11.
The welding procedures-and welders used to perform the weld 4
overlays were qualified to procedures which meet the requirements.
of the ASME Code Section IX 1980-Edition including the Winter 1981 Addenda. .The welding procedure-required an adequate cooling water flow inside the? pipe which produced desired compressive stresses on-the inside diameter.of=the pipe similar to those O
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O produced by IHSI. Crack propagation into the weld metal is not likely to occur by IGSCC since the high ferrite weld material is not susceptible to IGSCC. The fracture mechanics analysis was done in accordance with Section XI, Appendix X to the ASME Code.
9969bSE198 We have concluded, based on the considerations discussed ,
above, that:
- 1. The Unit 3 ultrasonic examination was conducted by personnel trained in the detection of IGSCC cracking and certified by ultrasonic technique demonstration at Battelle Laboratories in Columbus, Ohio and at the EPRI NDT Center in Charlotte, North Carolina, in accordance with I.E.Bulletin 83-02 and NRC Generic Letter 84-11.
The procedure and instrumentation used in this exmaination has been proven capable of detecting and characterizing intergranular stress corrosion cracking.
. 2. The Fracture Mechanics Analysis performed on the crack indications and the applied overlay temporary repairs possess an inherent safety factor of three and provide O full structural margins in accordance with NRC Generic Letter 84-11.
- 3. The overwhelming laboratory and industry experience to date has shown that 1GSCC will fail in a leak before break manner.
It can be concluded that Unit 3 of the Peach Bottom Atomic Power Station can operate at full-load power for at least 18 months with reasonable assurance that the health and safety of the public will not be endangered by oepration in the proposed manner.
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