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| ENCLOSURE 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF REQUESTS FOR RELIEF FROM EXAMINATION OF REACTOR COOLANT PUMP CASING WELDS AND INTERNAL SURFACES AND VALVE INTERNAL SURFACES DUQUESNE LIGHT BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-344 1 | | ENCLOSURE 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF REQUESTS FOR RELIEF FROM EXAMINATION OF REACTOR COOLANT PUMP CASING WELDS AND INTERNAL SURFACES AND VALVE INTERNAL SURFACES DUQUESNE LIGHT BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-344 1 |
| I. EACKGROUND INFORMATION 10 CFR 50.55a(g)(4) requires that inservice examination of ASME Code Class 1, 2, and 3 components be performed in accordance with Section XI of the ASME Code except where specific written reliefs from those requirements have been granted by the Comission. By letter dated June 17, 1986, Duquesne Light (the licensee) requested relief from the examination requirements of the 1974 Edition through Sumer 1975 Addenda of Section XI for a reactor coolant pump and certain valves at Beaver Valley Power Station, Unit No.1. Following a telephone conference on February 26, 1987, between NRC and Duquesne Light staff members concerning the requests, a revision of the supporting information was submitted by letter dated June 1, 1987. Based on the revised information, the staff has determined that the requirements of the Code are impractical to perform and that the necessary findings can be made to grant , | | I. EACKGROUND INFORMATION 10 CFR 50.55a(g)(4) requires that inservice examination of ASME Code Class 1, 2, and 3 components be performed in accordance with Section XI of the ASME Code except where specific written reliefs from those requirements have been granted by the Comission. By {{letter dated|date=June 17, 1986|text=letter dated June 17, 1986}}, Duquesne Light (the licensee) requested relief from the examination requirements of the 1974 Edition through Sumer 1975 Addenda of Section XI for a reactor coolant pump and certain valves at Beaver Valley Power Station, Unit No.1. Following a telephone conference on February 26, 1987, between NRC and Duquesne Light staff members concerning the requests, a revision of the supporting information was submitted by {{letter dated|date=June 1, 1987|text=letter dated June 1, 1987}}. Based on the revised information, the staff has determined that the requirements of the Code are impractical to perform and that the necessary findings can be made to grant , |
| the reliefs as requested. The bases for our conclusions are presented below. | | the reliefs as requested. The bases for our conclusions are presented below. |
| II. RELIEF REQUESTS} CODE REQUIREMENTS,' SUPPORTING INFORMATION, KRD3TA^FF_EVALUATIOM A. Relief Request Relief is requested from performing the volumetric and visual examination requirements of Section XI for the reactor coolant pumps' casing welds and internal surfaces. | | II. RELIEF REQUESTS} CODE REQUIREMENTS,' SUPPORTING INFORMATION, KRD3TA^FF_EVALUATIOM A. Relief Request Relief is requested from performing the volumetric and visual examination requirements of Section XI for the reactor coolant pumps' casing welds and internal surfaces. |
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20202B8571997-11-18018 November 1997 SE Approving Relief Requests for Second 10-Yr Interval for Pumps & Valves Inservice Testing Program for Beaver Valley Power Station,Unit 2 ML20199F4641997-11-13013 November 1997 SER Related to Reactor Pressure Vessel,Pressurized Thermal Shock Assessment for Beaver Valley Power Station,Unit 2 ML20212G4961997-10-28028 October 1997 SER Accepting Pressurized Thermal Shock Assessment for Beaver Valley Unit 2 Reactor Vessel ML20217J5311997-10-0808 October 1997 Safety Evaluation Re First,Second & Third 10-year Interval Inservice Inspection Program Plan Requests for Relief for Plant,Units 1 & 2 ML20217J5891997-10-0707 October 1997 Safety Evaluation Related to Reactor Pressure Vessel Pressurized Thermal Shock for Beaver Valley Power Station, Unit 1 ML20211D8441997-09-17017 September 1997 SER Approving SG 90-day Rept Submitted by Duquesne Light Co for Beaver Valley Power Station,Unit 1,per GL 95-05 ML20216J5861997-09-0404 September 1997 Safety Evaluation Re Third 10-year IST Program.Approves Valve Relief Requests 1,3 & 4.Valve Relief Request 2 Not Required.Authorizes Pump Relief Requests 1,2,3 & 4 ML20148E1051997-05-28028 May 1997 Safety Evaluation Supporting Amend 204 to License DPR-66 ML20137X1441997-04-0909 April 1997 Safety Evaluation Supporting Proposed Rev to RPV Surveillance Capsule Withdrawal Schedule ML20057B0641993-09-13013 September 1993 Safety Evaluation Granting Relief for IST of Reactor Plant Component Cooling Water Pumps of Plant ML20056F3561993-08-12012 August 1993 Safety Evaluation Granting Licensee 930607 Request for Relief from Certain ASME Code Requirements for Temporary Repairs to Svc Water Sys ML20126H7601992-12-30030 December 1992 Safety Evaluation Approving Valve Relief Requests VRR-27, VRR-43 & VRR-44 & Will Provide Reasonable Assurance of Operational Readiness of Valves to Perform Intended Functions.Relief Request PRR-11 Cannot Be Approved ML20127P2081992-11-20020 November 1992 SER Accepting Util Commitment to Entire GIP-2,including Both SQUG Commitments & Implementation Guidance ML20248D7681989-09-29029 September 1989 Supplemental Safety Evaluation Supporting Util Actions in Response to Open Items in 890510 Safety Evaluation Re Plant Safety Monitoring Sys ML20247N3561989-05-30030 May 1989 SER Supporting Util Actions to Comply W/Item 4.5.3 of Generic Ltr 83-28, Reactor Trip Sys Functional Testing ML20246M1791989-05-10010 May 1989 Safety Evaluation Re Verification & Validation Plan for Plant Safety Monitoring Sys.Hardware Design of Sys Found Acceptable.Verification & Validation Plan Found Incomplete & Unacceptable.Software Design Process Inadequate ML20246D5501989-04-26026 April 1989 Safety Evaluation Accepting Util Submittals on Natural Circulation Cooldown for Unit ML20206G0431988-11-17017 November 1988 Safety Evaluation Concluding That All Issues Raised Under Item Resolved & Item 4.3 Closed ML20153C0911988-08-17017 August 1988 Safety Evaluation Re Licensee 870731 Comments on Sser 5, Section 9.5.1.Fire Protection in Cable Rooms & Containment Constitutes Acceptable Deviations from Branch Technical Position Cmeb 9.5-1 ML20205T0021988-08-10010 August 1988 SER Accepting Util 831104,840330 & 870504 Responses to Item 2.2.1 of Generic Ltr 83-28 Re Equipment Classification Programs for All safety-related Components ML20154R4451988-05-31031 May 1988 Safety Evaluation Re Compliance W/Atws Rule 10CFR50.62.Util Proposed Design Acceptable Subj to Final Resolution of Tech Spec Issue ML20154P4341988-05-24024 May 1988 Safety Evaluation Concluding That Proposed Tech Spec Change Acceptable.No Amend Issued Since Conditions Resulting in Need for Amend to License NPF-73 No Longer Exist ML20154F9841988-05-12012 May 1988 Supplemental Safety Evaluation Concluding That Licensee 851114 Response to Open Issues Noted in 851017 Draft Technical Evaluation Rept of 831104 Submittal Re Salem ATWS Event Action Item 1.2, Post-Trip Review Satisfactory ML20154F9901988-05-12012 May 1988 Supplemental Safety Evaluation Concluding That Licensee 880322 Response to Open Issues Identified in 860722 Draft Technical Evaluation Rept of 840330 Submittal Re Salem ATWS Event Action Item 1.2, Post-Trip Review Satisfactory ML20153B6291988-04-25025 April 1988 Safety Evaluation Granting Util 870616 & 871110 Requests for Inservice Insp Relief for Welds on Nonregenerative Hxs,Per 10CFR50.55a(g)(6)(i) ML20148K5231988-03-18018 March 1988 Safety Evaluation Supporting Util Inservice Testing Program & Requests for Relief ML20234E0531987-12-0808 December 1987 Safety Evaluation Accepting Design Changes to Be Implemented During Unit 1 Cycle 7 Fuel Reload.Tech Spec Change Unnecessary ML20236X4941987-11-0909 November 1987 Safety Evaluation Granting Util 860617 Relief Request from Performing Volumetric & Visual Exam Requirements of ASME Section XI for Reactor Coolant Pumps Casing Welds & Internal Surfaces ML20237B1651987-10-21021 October 1987 Safety Evaluation Supporting Elimination of Primary Component Support Snubbers from Primary Coolant Loops ML20204H7181987-03-18018 March 1987 Interim Safety Evaluation Re Pump & Valve Operability Assurance (SER Confirmatory Issue 13).Pages from Pvort Audit Encl ML20206G2231987-03-12012 March 1987 SER Accepting Licensee Request to Use Damping Values from ASME Code Case N-411 Per Conditions Outlined in Util ML20207P6551987-01-0202 January 1987 SER Accepting Licensee Compliance W/Generic Ltr 83-28,Item 2.1,Part 2 Re Vendor Interface Program for Reactor Trip Sys (RTS) Components & Item 4.5.2 Concerning RTS Online Reliability Testing ML20212B0111986-11-30030 November 1986 Safety Evaluation Granting Util Request for Exemptions from App R Requirements Re Separation of Cables & Equipment & Associated Circuits ML20205G4491986-08-31031 August 1986 Safety Evaluation Accepting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20204G9281986-07-31031 July 1986 Safety Evaluation Supporting Util 860502 Submittal of Westinghouse Reload Safety Evaluation,Beaver Valley Nuclear Plant,Unit 1 Cycle 6 ML20203G2371986-07-28028 July 1986 Interim SER Re Dcrdr Summary Rept & Preimplementation Audit on 860211 & 12.Requirements of Suppl 1 to NUREG-0737 Generally Satisfied.Several Items Remain to Be Completed ML20206H4931986-06-19019 June 1986 Safety Evaluation on Generic Ltr 83-28,Item 4.2.3 & 4.2.4, Preventive Maint Program for Reactor Trip Breakers/Life Testing. Licensee Position Unacceptable ML20205N1151986-04-22022 April 1986 Interim Rept Re Review of Util Response to Generic Ltr 85-12 on Reactor Coolant Pump Trip Criteria.Addl Info Required ML20202C5721986-04-0303 April 1986 Sser Accepting Util 860304 Response to Generic Ltr 83-28, Item 4.3, Seismic Qualification of Shunt Trip Components ML20214E3631986-03-17017 March 1986 Safety Evaluation Supporting Amend 2 to CPPR-105 ML20154N7451986-03-10010 March 1986 Safety Evaluation Supporting Util 850819 Request to Withdraw Original Commitment to Provide Steam Leakage Collection Sys Around Certain Steam Valves 1999-04-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30
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ENCLOSURE 1 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION OF REQUESTS FOR RELIEF FROM EXAMINATION OF REACTOR COOLANT PUMP CASING WELDS AND INTERNAL SURFACES AND VALVE INTERNAL SURFACES DUQUESNE LIGHT BEAVER VALLEY POWER STATION, UNIT NO. 1 DOCKET NO. 50-344 1
I. EACKGROUND INFORMATION 10 CFR 50.55a(g)(4) requires that inservice examination of ASME Code Class 1, 2, and 3 components be performed in accordance with Section XI of the ASME Code except where specific written reliefs from those requirements have been granted by the Comission. By letter dated June 17, 1986, Duquesne Light (the licensee) requested relief from the examination requirements of the 1974 Edition through Sumer 1975 Addenda of Section XI for a reactor coolant pump and certain valves at Beaver Valley Power Station, Unit No.1. Following a telephone conference on February 26, 1987, between NRC and Duquesne Light staff members concerning the requests, a revision of the supporting information was submitted by letter dated June 1, 1987. Based on the revised information, the staff has determined that the requirements of the Code are impractical to perform and that the necessary findings can be made to grant ,
the reliefs as requested. The bases for our conclusions are presented below.
II. RELIEF REQUESTS} CODE REQUIREMENTS,' SUPPORTING INFORMATION, KRD3TA^FF_EVALUATIOM A. Relief Request Relief is requested from performing the volumetric and visual examination requirements of Section XI for the reactor coolant pumps' casing welds and internal surfaces.
Co_mponents Affected Reactor Coolant Pumps (RC-P-1A, IB, IC)
Sec_ tion XI Requirements (74S75)
Table IWB-2500, B-L-1 (Pump Casing Welds) and B-L-2 (Pump Casing) l examinations - The pump casing weld and pump casing of one reactor coolant pump (RCP) will be examined volumetrically and visually, respectively, by the end of the inspection interval.
I 8712090244 871130 PDR ADOCK 05000334 G PDR l
-2 l
l _B_ asis for Reli_ef The examinations of the RCP casing weld and casing internal pressure boundary require the complete disassembly cf the RCP.
Complete disassembly of an RCP would result in large expenditures of manpower and a substantial increase in radiation exposure. Also, possible damage to the pump could occur since these pumps were'not designed for ease of disassembly in the field.
The volumetric examination of the casing weld is extremely technically difficult. The inherent coarse gain structure of ASTM
, A351-65 Grade CF8 material precludes meaningful ultrasonic examination with present technology. The combination of surface radiation levels and material thickness (5" -6" minimum) preclude conventional radiographic techniques, leaving only high-curie Cobalt 60 or MINAC as possible alternatives.
RCP casing examinations performed by other plants have shown no evidence of cracks or surface degradation.
Potential or significant pump degradation would be detected by abnormalities in pump parameters, i.e., pump vibration, bearing temperature, seal flow and by RCS leakage.
Considering the technical difficulty, radiation exposure, cost, and possible damage resulting from pump disassembly, along with past industry results of RCP casing examination and the continuously monitored pump parameters that would detect pump degradation, it is concluded that the required examination will not provide a .
compensating increase in the level of safety to justify such examinations.
Alternate, Examination As an alternative to the B-L-1 examination, the exterior of the pump casing will be visually examined during pressure tests as required by IWB-5000 and a surface examination will be performed on the weld of one Reactor Coolant Pump.
The B-L-2 examination will be performed only when the pump is disassembled for maintenance.
Staff Evaluation and Conclusion Considering the pump design, materials of construction of the pump casing, and the radiation levels associated with performing the required examinations, the staff finds the examinations impractical to perfonn.
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In lieu of the volumetric examination of the pump casing weld and visual inspection of the internal surfaces, the licensee has committed to perform a surface examination of the welds. In addition to the surface examination , a visual inspection of the casing exterior surface will be performed during the hydrostatic test of the reactor coolant system. In the event that the pump has to be disassembled for operational or maintenance purposes, the required visual inspection of the internal surfaces will be performed.
We conclude that the surface and visual examinations which will be performed on the pump casing will provide adequate assurance of its structural integrity and that relief from the volumetric examination of the casing weld and visual inspection of the internal surfaces may be granted.
B. RELIEF REQUEST Relief is requested from performing the visual examination requirements for the internal surfaces of valves exceeding four-inch nominal pipe size.
COMPONENTS AFFECTED Velan, Check SI-10 6" SI-23 6" SI-11 6" SI-24 6" SI-12 6" SI-25 6" SI-15 6" SI-48 12" SI-16 6" SI-49 12" SI-17 6" SI-50 12" SI'-20 6" SI-51 12" SI-21 ;w 6" SI-52 12" -
SI-22 6" SI-53 12" Westinghouse, Gate Target Rock, Relief Valve -
MOV-RC-590 29" RV-RC-551A 6" MOV-RC-592 29" RV-RC-552B 6" M0V-RC-594 29" RV-RC-551C 6" MOV-RC-591 27 1/2" MOV-RC-593 27 1/2" MOV-RC-595 27 1/2" Darlina, Gate Rockwell, Gate M0V-RH-720A 10" MOV-RC-585 8" MOV-RH-720B 10" MOV-RC-586 8" MOV-RC-587 8" Copes / Vulcan, Gate l
MOV-RH-700 14" M0V-RH-701 14" C
Section_XIRequirement(745,751 Table 2500, B-M-2, requires a visual examination of the internal pressure boundary surfaces on selected valves exceeding 4-in.
nominal pipe size each inspection interval.
Basis for Relief The design of the valves is such that disassembly is required to perform the examination. Based on past performance of these valves and the service history of stainless steel valves, the requirement to disassemble one valve of each design type for the purpose of visual examination has a small probability of identifying service-induced flaws or degradation. The required examination would result in unnecessary exposure and cost and is therefore not justified.
Alternate Examination Proposed By Licensee The B-M-2 visual examination, will be deferred until valve disassembly is required for maintenance purposes.
Staff Evaluation and Conclusion The visual examination of the internal surfaces of Class 1 valves exceeding four-inch nominal pipe size necessitates complete disassembly of the valves and, in many cases, drainage of the reactor coolant and associated sy.ctems in which the valves are located. The valves for which reliefefrom the requirement has been requested have cast bodies without welds. Disassembly of these valves and drainage of systems to accomplish the visual _ examination requirement represent an undue hardship without a compensating increase in plant safety.
The licensee has proposed performing the visual examination of the internal surfaces of the valves when disassembly is required for maintenance purposes. The valve bodies are subjected to pressure tests (including hydrostatic) during which visual examinations (VT-2) are required for detection of leakage. The staff finds these tests adequate in providing assurance of the continued structural integrity of the valve bodies and concludes that relief from the visual examination requirements for the internal surfaces may be granted as requested.
Dated: November 9, 1987 Principal Contributor: George Johnson, reviewer I
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