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| ML20236B890 |
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| Site: |
Cooper  |
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| Issue date: |
10/20/1987 |
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| From: |
NRC |
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| To: |
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| Shared Package |
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| ML20236B869 |
List: |
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| References |
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| NUDOCS 8710260391 |
| Download: ML20236B890 (1) |
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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
[Table view] |
Text
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-/ o4 UNITED STATES
'73 NUCLEAR REGULATORY COMMISSION
[4 WA$mNGTON, D. C. 20555
%; a....j SUPPLEMENTAL SAFETY EVALUATION ON COOPER NUCLEAR STATION
' COMPLIANCE WITH ATWS RULE 10 CFR 50,62-i RELATING TO ALTERNATP ROD INSERTION SYSTEM NEBRASKA PUBLIC POWER DISTRICT DOCKET N0.-50-298 L 1. 0 INTRODUCTION .
On September 23,1987, the_ staff issued its Safety Evaluation (SE) for its !
evaluation of the Alternate Rod Insertion (ARI) system proposed for !
installation in the Cooper Nuclear. Station during the 1988 refueling ;j outage. The SE was based on information provided by the licensee in~its letters dated October. 14, 1985 and April 8, 1987, and in a telecopy provided on August 4,- 1987. In the October 14 letter, the licensee _ stated that the ARI' solenoid valves would be provided with control room position i '
indication. However, in a letter dated October 13, 1987 the licensee requested staff concurrence to provide position indication at another location outside the control room (auxiliary relay room) instead of in '
the control ~ room.
i 2.0 EVALUATION The staff's September 23, 1987 SE acknowledged the licensee's original plans to provide control room solenoid valve position indication. However, i such a feature is not a requirement of 10 CFR 50.62 or staff positions related to implementation of that rule. Control room ARI solenoid valve i position indication would not be necessary in event of an ATWS, since l actual control rod position indication is provided in the control room.
Valve position indication in the Auxiliary Relay Room will facilitate !
surveillance testing of the ARI system. j
3.0 CONCLUSION
I The licensee's plans for relocating ARI position indication out of the control room to another location in the control building are acceptable. ,
Principal Contributor: W. Long October 20, 1987 Dated:
8710260391 871020 PDR ADOCK 05000298 p PDR