Letter Sequence Approval |
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MONTHYEARML20086T4871984-03-0101 March 1984 Inservice Insp Plan for ASME Class 1,2 & 3 Components Project stage: Other NLS8400077, Forwards Inservice Insp Plan for ASME Class 1,2 & 3 Components, Per 831216 Commitment1984-03-0101 March 1984 Forwards Inservice Insp Plan for ASME Class 1,2 & 3 Components, Per 831216 Commitment Project stage: Other ML20112F6341985-03-0505 March 1985 Vols 1 & 2 to Rev 3 to Inservice Insp Program for ASME Class 1,2 & 3 Components Project stage: Other NLS8500052, Forwards Vols 1 & 2 to Rev 3 to GE Inservice Insp Program for ASME Class 1,2 & 3 Components. Program Contains One Addl & One Altered Relief Request.Revs to Document Will Not Be Forwarded to NRC W/O Specific Request1985-03-15015 March 1985 Forwards Vols 1 & 2 to Rev 3 to GE Inservice Insp Program for ASME Class 1,2 & 3 Components. Program Contains One Addl & One Altered Relief Request.Revs to Document Will Not Be Forwarded to NRC W/O Specific Request Project stage: Request ML20151Y2801985-09-30030 September 1985 Second Interval Inservice Insp Program,Cooper Nuclear Station, Technical Evaluation Rept Project stage: Other ML20151Y2541986-01-27027 January 1986 Safety Evaluation Re Requests for Relief from Inservice Insp Requirements.Relief Not Granted for Surface & Volumetric Exam of Drywell Piping Spray Welds Since Requirements Not Impractical Project stage: Approval ML20151Y2431986-01-27027 January 1986 Forwards Safety Evaluation & Second Interval Inservice Insp Program Cooper Nuclear Station Re 840301 & 850315 Requests for Relief from Inservice Insp Requirements.Relief Requests Granted Except Requests Re RHR Drywell Spray Project stage: Approval 1985-03-05
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20209H8281999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20206P0481999-05-12012 May 1999 Safety Evaluation Concluding That NPP Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at CNS & Adequately Addressed Actions Requested in GL 96-05 ML20204B3701999-03-11011 March 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Requests for Relief for RI-17,Rev 1 and RI-25,Rev 0.Request for Relief RI-13,Rev 2 Involving Snubber Testing & Is Being Evaluated in Separate Report ML20196J9641998-12-0707 December 1998 Safety Evaluation Accepting Licensee Third 10-yr Interval Inservice Insp Plan Request for Relief RI-27,rev 1 ML20196A2861998-11-23023 November 1998 SER Re Core Spray Piping Weld for Cooper Nuclear Station. Staff Concluded That Operation During Cycle 19 Acceptable with Indication re-examined During RFO 18 ML20196A5241998-11-23023 November 1998 Safety Evaluation Accepting Proposed Alternative to Use UT Techniques Qualified to Objectives of App Viil as Implemented by PDI Program in Performing RPV Shell Weld & Shell to Flange Weld Examinations ML20196A5061998-11-23023 November 1998 Safety Evaluation Re Flaw Indication Found in Main Steam Nozzle to Shell Weld NVE-BD-N3A at Cns.Plant Can Be Safely Operated for at Least One Fuel Cycle with Indication in as-is Condition ML20195H1761998-11-17017 November 1998 SER Authorizing Proposed Alternative in Relief Requests RV-06,RV-07,RV-09,RV-11,RV-12 & RV-15 Pursuant to 10CFR50.55a(a)(3)(ii).RV-08 Granted Pursuant to 10CFR50.55a(f)(6)(i) & RV-13 Acceptable Under OM-10 ML20151Z6141998-09-16016 September 1998 SER Accepting Util Responses to NRC Bulletin 95-002 for Cooper Nuclear Station ML20236R9131998-07-20020 July 1998 SER Accepting Rev 13 to Quality Assurance Program for Operation Policy Document for Plant ML20203K0351998-02-26026 February 1998 SER Approving Third ten-year Interval Inservice Inspection Program Plan,Request for Relief PR-10 for Cooper Nuclear Station.Technical Ltr Rept on Request Relief PR-10 Also Encl ML20212E0811997-10-23023 October 1997 SER Accepting Third 10-yr Interval Insp Program Plan & Associated Requests for Relief for Plant ML20217E6141997-09-23023 September 1997 Safety Evaluation Accepting Util Proposed Changes to Licensing Basis for Plant to Reflect Incorporation of Safer/Gestr Methodology for LOCA Analysis ML20199F7411997-08-14014 August 1997 Safety Evaluation Rept Accepting Design of torus-to-reactor Bldg Vacuum Breakers at Plant ML20210J5731997-08-13013 August 1997 Safety Evaluation Denying Relief Request for Plant Third 10-yr Interval Program for Inservice Testing of Pumps. Request Not in Sufficient Detail to Justify Proposed Alternative ML20148H2381997-06-0606 June 1997 Safety Evaluation Granting Licensee Relief Requests for 10-yr Interval Inservice Insp Program Plan for Plant,Unit 1 ML20138K0241997-05-0707 May 1997 Safety Evaluation Supporting Proposed Rev to RPV Surveillance Capsule Withdrawal Schedule ML20134N6911997-02-19019 February 1997 Safety Evaluation Related to Third ten-year Interval Inservice Testing Program Nebraska Public Power District Cooper Nuclear Station ML20198E1091992-11-25025 November 1992 Safety Evaluation Accepting Licensee 920921 120-day Response to GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Usi A-46 ML20127N3741992-11-19019 November 1992 Supplemental SE Accepting Analysis & Results in Response to SBO rule,10CFR50.63 ML20128C2911992-11-19019 November 1992 Safety Evaluation Accepting Revised ACAD Sys Into Nitrogen Containment Atmosphere Dilution,Eliminating Potential post-accident Oxygen Source ML20059E2781990-08-31031 August 1990 Safety Evaluation Granting Licensee 900525 Relief Requests RP-14 & RP-15 from Requirements to Measure Pump Inlet Pressure & Instrument Ranges,Respectively ML20246B2501989-05-31031 May 1989 Safety Evaluation on Generic Ltr 83-28,Item 4.5.3 Re Reactor Trip Sys Reliability for All Domestic Operating Reactors. Intervals for on-line Functional Testing Consistent W/ Achieving High Reactor Trip Sys Availability at Reactors ML20247A4241989-03-20020 March 1989 Safety Evaluation Accepting Revised Process Control Program Re General Methods of Sampling,Processing,Analysis & Waste Formulation During Solidification of Radwaste ML20205S2031988-11-0303 November 1988 Safety Evaluation Supporting Interim Operability of Piping Sys ML20147B5161988-02-23023 February 1988 Safety Evaluation Supporting Amend 117 to License DPR-46 ML20148C9591988-01-13013 January 1988 Safety Evaluation Concluding That Inservice Testing Program Submitted w/860730 Ltr as Modified in Subj Safety Evaluation Will Provide Reasonable Assurance of Operational Readiness of safety-related Pumps & Valves ML20238C4001987-12-23023 December 1987 Safety Evaluation Supporting Proposed Mod to 10CFR50.62, ATWS Rule ML20237E3261987-12-21021 December 1987 Safety Evalution Supporting Amend 113 to License DPR-46 ML20236B8901987-10-20020 October 1987 Sser Re Alternate Rod Insertion (ARI) Sys.Util Plans for Relocating ARI Position Indication Out of Control Room to Another Location in Control Bldg Acceptable ML20235H0351987-09-23023 September 1987 Safety Evaluation Re Alternate Rod Injection & Recirculating Pump Trip Sys ML20235N4581987-07-10010 July 1987 Safety Evaluation Supporting Util 810707,820623,0730 & 831215 Submittals Re Valve Operability Info for 24-inch Isolation Valves in Purge & Vent Sys.Nrc Conclusion Subj to Valves Being Modified to Have Torque Readjustments ML20214S8741987-05-21021 May 1987 Supplemental Safety Evaluation Re Dcrdr.Listed Activities Must Be Finished in Order to Satisfy Dcrdr Requirements in Suppl 1 to NUREG-0737 ML20212Q9721987-04-16016 April 1987 Safety Evaluation Accepting Util 831104 & 870121 Responses to Generic Ltr 83-28,Items 3.2.1 & 3.2.2, Post-Maint Verification Testing ML20212L1751987-03-0606 March 1987 Safety Evaluation Supporting Util Methodology in Standby Gas Treatment Suction Analysis & Interim Operation for Fuel Cycle 11 Only ML20209A7001987-01-30030 January 1987 Safety Evaluation Accepting Util Response to Vendor Recommended Reliability Verification Testing Per Generic Ltr 83-28,Item 4.5.1 Re Reactor Trip Sys Reliability (Sys Functional Testing) ML20215M5021986-10-27027 October 1986 Safety Evaluation Accepting Util Response to Generic Ltr 82-33 Re Conformance to Rev 2 to Reg Guide 1.97,except for Instrumentation Associated W/Neutron Flux Variable ML20210K2491986-09-25025 September 1986 Safety Evaluation Supporting Analytical Method Used by Licensee to Evaluate Critical Stresses ML20141E9291986-04-10010 April 1986 Safety Evaluation Supporting Amend 98 to License DPR-46 ML20151Y2541986-01-27027 January 1986 Safety Evaluation Re Requests for Relief from Inservice Insp Requirements.Relief Not Granted for Surface & Volumetric Exam of Drywell Piping Spray Welds Since Requirements Not Impractical ML20140C5761986-01-17017 January 1986 Safety Evaluation Supporting 831104 Response to Generic Ltr 83-28,Items 3.1.1 & 3.1.2 Concerning post-maint Testing Verification of Reactor Trip Sys Components ML20134J6301985-08-21021 August 1985 Safety Evaluation Accepting Proposed Mods as Ensuring Safe Shutdown Capability in Event of Fire in Areas of Concern in Accordance W/Requirements of 10CFR50,App R ML20127E7281985-06-10010 June 1985 Safety Evaluation Supporting Response to Generic Ltr 83-28, Item 1.2 Re post-trip Review Data & Info Capability ML20127E1051985-05-0606 May 1985 Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Item 1.1 Concerning post-trip Review Program & Procedure ML20148N2351978-11-0101 November 1978 Safety Eval Rept of Main Stream Isolation Valve Test Results. Util Request for Continuing CNS in Present Fuel Cycle for Addl mid-cycle Msltv Leak Test Is Approved ML20147D3101978-09-29029 September 1978 Safety Evaluation Rept Supporting Amend 52 to Facil Oper Lic DPR-46 Concludes That Installation & Use of New Fuel Racks Can Be Accomplished Safety & Health & Safety of Pub Will Not Be Endangered ML20235F1591968-04-0404 April 1968 Safety Evaluation Re Facility 1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217G7461999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Cooper Nuclear Station ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212C5001999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy ML20210R0381999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Cooper Nuclear Station ML20210J2921999-07-29029 July 1999 Special Rept:On 990406,OG TS & Associated Charcoal Absorbers Were Removed from Svc.Caused by Scheduled Maint on Hpci. Evaluation of Offsite Effluent Release Dose Effects Was Performed to Ensure Plant Remained in Compliance ML20209H8281999-07-15015 July 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Cooper Nuclear Station ML20211A9981999-07-12012 July 1999 Draft,Probabilistic Safety Assessment, Risk Info Matrix, Risk Ranking of Systems by Importance Measure ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209E1061999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Cns.With ML20196B3851999-06-17017 June 1999 Summary Rept of Facility Changes,Test & Experiments,Per 10CFR50.59 for Period 970901-990331.Summary of Commitment Changes Made During Same Time Period Also Encl ML20195K2851999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Cooper Nuclear Station.With ML20206P0481999-05-12012 May 1999 Safety Evaluation Concluding That NPP Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at CNS & Adequately Addressed Actions Requested in GL 96-05 ML20206J0811999-05-0404 May 1999 Rev 14 to CNS QA Program for Operation ML20206P9751999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cooper Nuclear Station ML20205Q0891999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Cooper Nuclear Station.With ML20204G8951999-03-15015 March 1999 CNS Inservice Insp Summary Rept Fall 1998 Refueling Outage (RFO-18) ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20204B3701999-03-11011 March 1999 SER Accepting Third 10-year Interval Inservice Insp Plan Requests for Relief for RI-17,Rev 1 and RI-25,Rev 0.Request for Relief RI-13,Rev 2 Involving Snubber Testing & Is Being Evaluated in Separate Report ML20204C9751999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Cooper Nuclear Station ML20199E6751999-01-14014 January 1999 Monthly Operating Rept for Dec 1998 for Cooper Nuclear Station ML20195B9191998-12-31031 December 1998 1998 NPPD Annual Rept. with ML20196J9641998-12-0707 December 1998 Safety Evaluation Accepting Licensee Third 10-yr Interval Inservice Insp Plan Request for Relief RI-27,rev 1 ML20198D2471998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Cooper Nuclear Station.With ML20196A2861998-11-23023 November 1998 SER Re Core Spray Piping Weld for Cooper Nuclear Station. Staff Concluded That Operation During Cycle 19 Acceptable with Indication re-examined During RFO 18 ML20196A5241998-11-23023 November 1998 Safety Evaluation Accepting Proposed Alternative to Use UT Techniques Qualified to Objectives of App Viil as Implemented by PDI Program in Performing RPV Shell Weld & Shell to Flange Weld Examinations ML20196A5061998-11-23023 November 1998 Safety Evaluation Re Flaw Indication Found in Main Steam Nozzle to Shell Weld NVE-BD-N3A at Cns.Plant Can Be Safely Operated for at Least One Fuel Cycle with Indication in as-is Condition ML20196C4241998-11-20020 November 1998 Rev 1 to Cooper Nuclear Station COLR Cycle 19 ML20195H1761998-11-17017 November 1998 SER Authorizing Proposed Alternative in Relief Requests RV-06,RV-07,RV-09,RV-11,RV-12 & RV-15 Pursuant to 10CFR50.55a(a)(3)(ii).RV-08 Granted Pursuant to 10CFR50.55a(f)(6)(i) & RV-13 Acceptable Under OM-10 ML20195F8601998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Cooper Nuclear Station.With ML20155D9961998-10-31031 October 1998 Rev 0 to GE-NE-B13-01980-24, Fracture Mechanics Evaluation on Observed Indication at N3A Steam Outlet Nozzle to Shell Weld at Cooper Nuclear Station ML20154Q5661998-10-0505 October 1998 Rev 0 to CNS COLR Cycle 19 ML20154L5381998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Cooper Nuclear Station.With ML20151Z6141998-09-16016 September 1998 SER Accepting Util Responses to NRC Bulletin 95-002 for Cooper Nuclear Station ML20154F7931998-08-31031 August 1998 Rev 0 to J11-03354-10, Supplemental Reload Licensing Rept for CNS Reload 18,Cycle 19 ML20153B1101998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Cooper Nuclear Station ML20237E7771998-08-20020 August 1998 Revised COLR Cycle 18 for Cooper Nuclear Station ML20151Q1211998-08-14014 August 1998 Rev 0 to Control of Hazard Barriers ML20237C0591998-07-31031 July 1998 Monthly Operating Rept for Jul 1998 for Cooper Nuclear Station ML20236R9131998-07-20020 July 1998 SER Accepting Rev 13 to Quality Assurance Program for Operation Policy Document for Plant ML20236P2971998-07-0707 July 1998 Rev 2 to NPPD CNS Strategy for Achieving Engineering Excellence ML20236R0931998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Cooper Nuclear Station ML20249A7701998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Cooper Nuclear Station ML20247G6131998-05-13013 May 1998 Part 21 Rept Re Defect Contained in Automatic Switch Co, Solenoid Valves,Purchased Under Purchase Order (Po) 970161. Caused by Presence of Brass Strands.Replaced Defective Valves ML20247G0951998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Cooper Nuclear Station ML20237B6861998-04-24024 April 1998 Vols I & II to CNS 1998 Biennial Emergency Exercise Scenario, Scheduled for 980609 ML20217A1531998-04-16016 April 1998 Closure to Interim Part 21 Rept Submitted to NRC on 970929. New Date Established for Completion of Level I & 2 Setpoint Project Committed to in .Final Approval of Setpoint Calculations Will Be Completed by 980531 ML20216G5331998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Cooper Nuclear Station 1999-09-30
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_ - _ _ _ _ .- __ _._._- .
~/ UNITED STATES
~%o NUCLEAR REGULATORY COMMISSION I wasHWGTON, D. C. 20665 i
\...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO RE0 VESTS FOR-RELIEF FROM INSERVICE INSPECTION REQUIREMENTS NEBRASKA PUBLIC POWER DISTRICT COOPER NUCLEAR STATION DOCKET NO. 50-298
1.0 INTRODUCTION
Technical Specification 4.6G for the Cooper Nuclear Station states that inservice examination of ASME Code Class 1, 2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50.55a(g) except where specific written relief has been granted by the Commission. Certain requirements of later editions and addenda of Section XI are impractical to perform on older plants because of the plants' design, component geometry, and materials of construction. Thus, 10 CFR 50.55a(g)(6)(1) authorizes the Commission to grant relief from those requirements upon making the
-necessary findings.
By letters dated March 1, 1984, and March 15, 1985, Nebraska Public Power District submitted its inservice inspection program, revisions, or additional information related to requests for relief from certain Code requirements determined to be impractical to perform on the Cooper Nuclear Station 1 during the inspection interval. The program is based on the requirements of the 1980 Edition through Winter 1981 Addenda of Sections IX of the ASME Code, and remains in effect until July 1,1994 unless the program is modified or changed prior to the interval end date. ;
2.0 EVALUATION Requests for relief from the requirements of Section XI have been reviewed by
/ the Staff's contractor, Science Applications International Corporation. The i
contractor's evaluations of the licensee's requests for relief and his recommendations are presented in the Technical Evaluation Report (TER) attached. The staff has reviewed the TER and concurs with the evaluations and recommendations. A summary of the determinations made by the staff is presented in the following tables:
m 0602120633 860127 PDR ADOCK 05000290 G ' PDR W
C___ ___._.___.__m________m_ -_m_
i TABLE 1 i CLASS 1 COMPONENTS l .
LICENSEE i
1 PROPOSED SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST
! IWB-2500-1 IWB-2500-1 STATUS COMPONENT EXAMINED METHOD EXAMINATION 1 ITEM NO. EXAM. CAT.
Reactor Shell Welds Volumetric Visual During Granted Bl.11, B-A System Provided 81.12, Vessel and Head Welds (See Hydrostatic Volumetric ,
B1.21, & Test is Performed 81.22 Attachment I i
to Table 1) to Extent
! Practical,
! Volumetric i of Additional .
- Shell Welds 1
, to Achieve ,
- Total Code- A' i Required l
Weld Length, and Visual of Beltline Region Weld
! Areas From j Vessel Interior (No
! Relief Required i for Welds 1M 1,
! VCB-BB-1 and -3, l and VCL-BB-1,-2, and -3) l l
i 4
TABLE l' ,
CLASS 1 COMPONENTS (continued)
LICENSEE l
PROPOSED l
IWB-2500-1 IWB-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST i EXAM. CAT. COMPONENT EXAMINED METHOD EXAMINATION STATUS i ITEM NO.
l B3.100 B-D Reactor Nozzle Inside Volumetric Surface Granted Vessel Radius Section (Nozzles: Head Spray Nozzle N6A, Instrumentation Nozzle N68, and Head Vent Nozzle N7)
B9.11 B-J Contain- Pipe Size > 4 Surface and Visual for Granted i in., Circui- Volumetric Leakage During Provided Y' ment Pene-tration ferential System Surface Assembly Welds (See Hydrostatic and Volu-Attachment Test metric of II to Table 1) First Accessi-ble Pressure Boundary Weld Either Upstream or Downstream of Inaccessible Weld Over 100%
of Its Length, if Practical.
6- .
TABLE 1 l ATTACHMENT I 1
IWB-2500-1 WELD WELD TYPE ITEM NO. COPMENTS l
HMB-BB-1 Botton Head Meridional Bl.22 HIE-BB-2 Botton Head Meridional Bl.22
! HMB-BB-3 Botton Head Meridional Bl.22 -
HMB-BB-4 Botton Head Meridional Bl.22 i 198-BB-5 Bottom Head Meridional Bl.22 HMB-BB-6 Botton Head Meridional Bl.22 M)-BB-1 Bottom Head Circumferential Bl.21 VCB-BA-2 Circumferential Shell Bl.11 Beltline l VCB-BB-1 Circumferential Shell Bl.11 i VCB-BB-3 Circumferential Shell B1.11 VLA-BA-1 Longitudinal Shell Bl.12 Beltline VLA-BA-2 Longitudinal Shell Bl.12 Beltline VLA-BA-3 Longitudinal Shell Bl.12 Beltline .
VLB-BA-1 Longitudinal Shell Bl.12 Beltline VLB-BA-2 Longitudinal Shell Bl.12 Beltline VLB-BA-3 Longitudinal Shell B1.12 Beltline l VLC-BB-1 Longitudinal Shell Bl.12 VLC-BB-2 Longitudinal Shell Bl.12 VLC-BB-3 Longitudinal Shell Bl.12 l
l
l s .
TABLE 1 '"
ATTACIMENT II ,
DESCRIPTION INACCESSIBLE WELD Core Spray Loop A CSA-BJ-25 Core Spray Loop B CSB-BJ-25 Reactor Water Cleanup CWA-BJ-27A Feedwater Loop A FWA-BJ-35 Feedwater Loop B FWD-BJ-34 Main Steam Loop A MSA-BJ-43 Main Steam Loop B MSB-BJ-39 Main Steam Loop C MSC-BJ-43 Main Steam Loop D MSD-BJ-47 HPCI Steam PSA-BJ-22 RHR 20-In Supply RHA-BJ-30A 4 e
l RHR Loop A RHB-BJ-28A RHR Loop B RHC-BJ-24 l RHR 6-Inch Head Spray RHO-BJ-31 j RCIC Steam RSA-BJ-13A l
I w -
TABLE 2 CLASS 2 COMPONENTS LICENSEE PROPOSED IWC-2500-1 IWC-2500-1 SYSTEM OR AREA TO BE REQUIRED ALTERNATIVE RELIEF REQUEST ITEM NO. EXAM. CAT. COMPONENT EXAMINED METH00 EXANINATION STATUS l C1.30 C-A Residual Tubesheet- Volumetric Visual During Granted l
Heat to-Shell System Leakage
! Removal Weld . Test l Heat (Welds i Exchanger RHR-CA-5A I and RHR-CA-l 58) l C5.10 & C5.20 C-F Residual C5.10: C5.10: Visual During Not Granted '
l Heat Pipe Welds < Surface System l Removal 1/2 in. Walt C5.20: Pneumatic &' .
Drywell Thickness Surface Test Spray C5.20: and System Pipe Welds > Volumetric 1/2 in. Wall Thickness C5.11 C-F Floor Pipe Welds < Surface Visual During Granted Penetration 1/2 in. Walt . System Thickness, Hydrostatic Circumferential Test Weld (Weld RHD-CF-9) r w
TABLE 3 CLASS 3 COMPONENTS NO RELIEF REQUESTS l
r TABLE 4 l COMP 0flENT SUPPORTS
! NO RELIEF REQUESTS Y
i I
\
TABLE 5 l
PRESSURE TESTS NO RELIEF REQUESTS i
l _ _ _ _ _ ___ _ _ . - - -. - _
l l
3.0 CONCLUSION
Based on the review summarized above, the staff concludes that the relief granted from the examination and testing requirements and alternate methods imposed through this document give reasonable assurance of the piping and component pressure boundary and support structural integrity, that granting relief where the Code requirements are impractical is authorized by 10 CFR 50.55a(g)(b)(1) and will not endanger life or property, or the common defense and security, and is otherwise in the public interest considering t
the burden that could result if they were imposed on the facility. The relief not granted, for surface and volumetric examination of drywell spray piping welds is denied on the basis that the licensee has not shown the requirements to be impractical. Relief is therefore not authorized by 10CFR50.55a(g)(6)(1).
Attachment:
" Technical Evaluation Report, Second Interval Inservice Inspection Program, Cooper Nuclear Station" Report No.
SAIC - 84/1660, September 1985.
Principal Contributor: G. Johnson /S. Lee Dated: January 27, 1986 ,
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