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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
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 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 ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively 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 ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles 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 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 ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 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 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) 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 ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20198L3331997-12-18018 December 1997 Safety Evaluation Supporting Approval of Proposed Merger of Atlantic Energy,Inc,& Delmarva Power & Light Co ML20212G8301997-10-24024 October 1997 Safety Evaluation Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively ML20198S2161997-10-24024 October 1997 Safety Evaluation Accepting Proposed Change to Provisions Identified in Rev 14 of PBAPS QAP Description Re Nuclear Review Board Meeting Frequency ML20217J5631997-10-0909 October 1997 Safety Evaluation Supporting Amend 225 to License DPR-56 ML20217J6161997-10-0707 October 1997 Safety Evaluation Re Alternative to Reactor Pressure Vessel Circumferential Weld Insps for Plant,Unit 3 ML20211L6241997-10-0303 October 1997 Safety Evaluation Authorizing Licensee Proposed Use of Code Case N-516-1 to Weld Modified Suction Strainer in Suppression Chamber at Plant ML20217D8161997-09-30030 September 1997 Safety Evaluation Supporting Amend 224 to License DPR-56 ML20211D6201997-09-17017 September 1997 SER Accepting VT-2 Examiner Qualification Request for PECO Energy Company,Peach Bottom Atomic Power Station,Units 2 & 3 ML20216G5601997-09-0404 September 1997 Safety Evaluation Supporting Amends 220 & 223 to Licenses DPR-44 & DPR-56,respectively ML20217M8001997-08-19019 August 1997 Safety Evaluation Supporting Amends 219 & 222 to Licenses DPR-44 & DPR-56,respectively ML20149L2841997-07-23023 July 1997 Safety Evaluation Accepting Licensee Relief Request RR-22 for Plant,Units 2 & 3 ISI Program ML20140B0371997-05-30030 May 1997 Safety Evaluation Accepting QAP Description Change ML20135B4111997-02-19019 February 1997 Safety Evaluation Supporting Amends 218 & 221 to Licenses DPR-44 & DPR-56,respectively ML20149L8681996-11-15015 November 1996 SER Accepting Core Spray Piping Insp & Flaw Evaluation for Plant,Unit 2 ML20149L2441996-01-29029 January 1996 Safety Evaluation Accepting Insp & Evaluation Methodology for Operation of Unit 3 Core Shroud for Duration of Current Operating Cycle,Performed in Response to GL 94-03 ML20058F5641993-11-19019 November 1993 SE Accepting Util 930305 Response to NRC Bulletin 90-01, Suppl 1, Loss of Fill-Oil in Transmitters Mfg by Rosemount ML20057B6441993-09-16016 September 1993 SER Concluding That Safe Shutdown Capability at Plant, Satisfies Requirements of Section Iii.G & Iii.L of App R to 10CFR50 ML20126H9031992-12-23023 December 1992 Safety Evaluation Granting Relief from Inservice Insp Requirements for Facilities ML20127N4941992-11-17017 November 1992 Safety Evaluation Accepting Util 120-day Response to Suppl 1 to GL 87-02 ML20062C7501990-10-26026 October 1990 Safety Evaluation Re Evaluation of Response to NRC Bulletin 90-002, Loss of Thermal Margin Caused by Channel Box Bow ML20246E0331989-08-21021 August 1989 SER Supporting Util Response to Generic Ltr 83-28,Item 2,1 (Parts 1 & 2).Programs Exist for Identifying safety-related Components Required for Reactor Trip Function & Vendor Interface W/Nmss Vendor for Required Components ML20205A8801988-10-31031 October 1988 Safety Evaluation of Util Plan for Restart of Peach Bottom Atomic Power Station ML20148P3351988-04-0101 April 1988 SER Accepting Util Responses to Generic Ltr 83-28,Item 2.2.1 Re Equipment Classification Program for All safety-related Components ML20148E6301988-01-15015 January 1988 SER Accepting Util 840116,0927 & 850805 Responses to Generic Ltr 82-33,Item 6 Re Compliance w/post-accident Monitoring Instrumentation Guidelines of Reg Guide 1.97 Concerning Emergency Response Facilities ML20236D0541987-10-22022 October 1987 Safety Evaluation Supporting Util Repts on Computer Program Analyses Methods Intended for Use in Part of Plant Core Reload Analyses ML20235D2431987-09-22022 September 1987 Safety Evaluation Re Proposed Onsite Storage of Liquid Oxygen & Hydrogen for Implementation of Hydrogen Water Chemistry.Permanent Hydrogen Water Installation Acceptable ML20209H0201987-04-24024 April 1987 Safety Evaluation Supporting Util Re Torus Attached Piping Mods - Mark I Program ML20204C1001986-07-24024 July 1986 Safety Evaluation Supporting Listed Util Responses & Actions Reviewed During Insp on 840913-19 Re Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2 & 4.5.1 ML20141F6071986-04-0808 April 1986 Safety Evaluation Granting Util Requests for Relief from Inservice Insp Requirements of ASME Code,Section XI ML20209C3141986-03-20020 March 1986 Safety Evaluation Supporting Shroud Head Connection Replacement at Facility,Per Util 860107 Submittal 1999-09-24
[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
[Table view] |
Text
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,9, UNITED STATES NUCLEAR REGULATORY COMMISSION s,,' " W[ %l wAsMiNotoN. o. c. 20sss
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- SAFETY EVALUATION PY THE OFFICE OF N'XLEAR REACTOR REGl't ATION RELATED TO RE0 VESTS FOR RELIEF FROM EXAMINATION AND HYOR0 STATIC TEST REQUIREMENTS OF THE 1974 EDITION THROUGH SUMMER 1975 ADDENDA 0F SECTION XI 0F THE ASME CODE PHILADELFHIA ELECTRIC COMPANY PUBLIC SERVICE ELECTRIC AND GAS COMPANY DELMARVA POWER AND LIGHT COMPANY ATL ANTIC CITY EL ECTRIC COMPANY PEACH 00TTOM ATOMIC PCWER STATION, UNITS 2 AND 3 00CKETS NOS. 50-277 AND 50 278 BACKGROUND INFORMATION 10 CFR 50.55a(g)(4) of the Code of Federal Regulations requires components of boilina and pressurized water cooled nuclear facilities to meet the esamination and telt requirements set forth in applicable editions and addenda of Section XI of the A5ME Code throughout their service life s-unless the requirements are impractical to perform and relief from those requirements is granted by the Commission. The intervice inspection pro-gram for a facility is required to be updated to the latest approved edition and addenda of Section XI each ten year interval of facility operation'. '
Information concerning examinations and tests determined to be impractical to perform is required to be included in the program and submitted to the NRC for review and evaluation. Pursuantto10CFR50,55a(g)(5)(iv),where an impractical examination or test requirement is not included in the revised program, the licenlee is required to submit to the NRC the basis for the licensee's determination that the requirements are impractical to perform at its facility not later than twelve (12) months af ter the espiration of the ten year interval, a k 0
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By letter dated May 2, 1983, the NRC transmitted to Philadelphia Electric Company (tne licensee) a Safety Evaluation on impractical }
i examination and testing requirements of the 1974 Edition through l Summer 1975 Accenca of Section XI of the ASME Code for Peach Bottom Units ? end 3. The $1fety Eval'.'rtler granter' rCief fret those Code
,i requirements where the necessary findings could be made and denied the .
other requests. By letters dated December 21 and December 27, 1984, * !
February I and March 13, 1905, the licensee provided additional . [
t information regarding the requests denied and other requests for relief in accordance with 10 CFR 50.55a(g)(5)(ty). The requests and additional information provided in the letters are evaluated below.
This evaluation is an addendum to the evaluation transmitted to Philadelphia Electric Company by the May 2, 1983 letter.
i
[VALUAT!0N Aeouests for relief from the requirements of Section X1, 197* [dition
- through Summer 1975 Addenda, which have been cetermined to ce imsra:ti:a1 to perform have been reviewed by contractor, Science Applications Inter- l national Corporation (SAIC). The contractor's evaluations of the licensee's !
requests for relief and his recommendations are presented in the Technical EvaluationReport(TER) attached. We have reviewed the TER and agree with t
the evaluations and recommendations. However, our basis for granting relief from the visual inspection requirement for the internal surfaces i
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i
_ ~ _ - _ _ _ _ _ _ _ _ _ - _ - - - _ _ _ _ _ _ _ _
3 of pumps and valves and not requiring U1 tnickness measurements at Unit 3 as an alternative is not predicated on the requiremen;s of other licensees, but co the results obtained from the visual inspec-tions parformed on similar components at Unit 2. A summary of our Jetorninations is presented in the folloaina tables.
4 4
. i 9
TABLE 1 CLASS 1 COW ONENTS LICENSEE
. PROPOSED 1W-2600 IW-2500 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EMAN. CAT. COMPONENT EMANINED METH00 EXAMINATION STATUS B5.6 8-L-1 Dumps Casing Volumetric Hydrostatic Granted (Unit 3) Welds Pressure and Leak Tests.
UT Wall Thick-ness Measure-ments 85.7 B-L-2 Sumps Internal Visual Hydrostatic Granted (Unit 3) Surfaces Pressure and '
(UT Wall ,
Leak Tests, Thickness ,
UT Wall Thick- Measurements '
ness Measure- are Optional) ments 86.7 8-M-2 */alves Internal Visual Hydrostatic Granted (Unit 3) Surfaces Pressure and (UT Wall Leak Tests, Thickness UT Wall Thick- Measurements ness Measure- are Optional) ments G
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' TABLE 2
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n.r~9 CLASS 1 COMPONENTS d_~ ~,.r:_
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LICENSEE e'. 3 7 ,e ;. < '-
- PROPOSED r'/ ~
IWB-2600 < IWB-2500 SYSTEN'OR_2 AREA TO BE REQUIRED ALTERNATIVE REtIEF REQUEST' k
ITEM NO.
EXAM. CAT. COMPONENT ' EXAMINED METHOD EXAMINATION r 2 STATUS .'"'-
,y __ .
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IWC-1220 W ' ~
- a"-ECCS Welds IWC-2520' One-Sixth of Granted ./
(Unit 3)* ''
Compo- -
7 Required -
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- tents & -
, During Current ',~
Interval
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'.iping -
cxempt
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1220(c) -
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- Unit 2 Proposed Examinations and Schedule Previously Granted by Letter Dated June 1. 1984, Rivenbark to Bauer.
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0 TABLE 4 PRESSURE TEST IWA-5000 IWB-5000 IWC-5000 & LICENSEE PROPOSED RELIEF SYSTEM OR IWD-5000 TEST ALTERNATIVE REQUEST COMPONENT PRESSURE REQUIREMENT TEST PRESSURE STATUS Class 1, 2 & 3 Four-Hour Hold Time Ten-Minute Hold Time Granted For Uninsulated Piping M
4
9 7-CONCLUSION Based on our review, we conclude that the examination requirements from which relief is sought are impractical; that relief granted from the examination requirements and alternate methods imposed through this document give reasonable assurance of the piping and component pressure boundary structural integrity as required as part of the licensee's inservice inspection program under 10 CFR 50.55a(g); that relief is authorized by law and will not endanger ,
life or property, or the common defense and security, and is otherwise in the public interest considering the burden that could result if the examination requirements were imposed on the facilities.
Dated: June 18, 1985 The following NRC personnel have contributed to this Safety Evaluation:
' George Johnson. * -
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