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MONTHYEARML20072G1601983-06-24024 June 1983 Rev 9 to ASME Code Section XI Inservice Insp & Testing Program Project stage: Other ML20072G1491983-06-24024 June 1983 Requests Relief from Requirement Re 10-yr Inservice Insp of Reactor Coolant Pump Casing Welds of ASME Boiler & Pressure Vessel Code,Section XI, Inservice Insp. Request Submitted as Rev 9 to Inservice Insp & Testing Program Project stage: Other ML20134E5931985-08-0909 August 1985 Forwards Rev to Request for Relief 29 & Request for Relief 66 from ASME Boiler & Pressure Vessel Code,Section XI Re Inservice Insp for First 10-yr Interval.Review Requested Prior to 10-yr Outage Scheduled for 850905.Fee Paid Project stage: Request ML20138E1661985-10-11011 October 1985 Safety Evaluation Re 850809 Inservice Insp of Components Relief Requests 29 & 66.Alternative Acceptable & Relief Should Be Granted Project stage: Approval ML20138E1511985-10-11011 October 1985 Forwards Safety Evaluation of 850809 Relief Request from Inservice Insp Requirements Re Hydrostatic Pressure Testing of Pipe Section in Charging Sys & Surface Exam of Valve Pressure Boundary.Relief Granted Project stage: Approval 1985-10-11
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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20203H8331998-02-20020 February 1998 SE Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds for Prairie Island Nuclear Generating Plant,Unit 2 ML20148D5441997-05-16016 May 1997 Safety Evaluation of Prairie Island Nuclear Generating Plant Individual Plant Exam ML20138J9961997-05-0606 May 1997 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of CRD Mechanism Canopy Seal Welds ML20058N8021993-12-0808 December 1993 Safety Evaluation Approving Third 10-yr IST Program Requests for Pumps & Valves,Per 10CFR50.55a(f)(6)(i) & 10CFR50.55a(a)(3)(i) ML20127C0071993-01-0404 January 1993 Supplemental SE Accepting Changes & Additions Described in Rev 1 to Design Rept for Station Blackout/Electrical Safeguards Upgrade Project ML20127C0291993-01-0404 January 1993 Safety Evaluation Accepting pressure-retaining Components of safety-related Auxiliary Fluid Sys Associated W/Edgs ML20127C0241993-01-0404 January 1993 Safety Evaluation Re Audit of Load Sequencer Implementation. Four of Five Items Reviewed Acceptable & Closed.One Open Item Remained Re Electromagnetic Environ Qualification for Lower Frequency Range of 30 Hz to 10 Khz ML20127C0151993-01-0404 January 1993 Safety Evaluation Accepting Instrumentation & Control Sys Aspects of Unit 2 Load Sequencer Sys in Station Blackout/ Electrical Safeguards Upgrade Project ML20128A7301992-11-30030 November 1992 Safety Evaluation Accepting Licensee 920921 120-day Response to Suppl 1 to GL 87-02 Re in-structure Response Spectra ML20128A7171992-11-30030 November 1992 Safety Evaluation Accepting Licensee 920921 120-day Response to Suppl 1 to GL 87-02 as Commitment to Entire GIP-2, Including Both SQUG Commitments & Implementation Guidance. In-structure Response Spectra Addressed in Separate SE ML20151U1181988-08-17017 August 1988 Safety Evaluation Re Compliance W/Atws Rule (10CFR50.62). Design Acceptable Contingent Upon Successful Completion of Human Factors Engineering Studies & Qualification of Isolation Devices ML20235Y4791987-07-13013 July 1987 Supplemental Safety Evaluation Accepting Util 870120 Requests for Relief from ASME Code Requirements Re Inservice Insp & Testing Program for Second 10-yr Interval ML20205Q8071987-03-30030 March 1987 SER Accepting Util 861104 & 840706 Responses to Generic Ltr 83-28,Item 4.5.2 Re ATWS Requirements for on-line Testing of Reactor Trip Sys ML20205M5261987-03-27027 March 1987 Safety Evaluation Denying Util 860819 Proposal to Reproduce Radiographs on Microfilm ML20211Q2971987-02-18018 February 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) for Prairie Island Units 1 & 2 ML20209C2151987-01-21021 January 1987 Safety Evaluation Re Auxiliary Feedwater Sys Reliability (Generic Issue 124) at Prairie Island Units 1 & 2.Util Actively Pursuing Improvements in Sys Reliability & Reducing Sys Challenges ML20214S4131986-11-26026 November 1986 Safety Evaluation Finding Auxiliary Feedwater Sys Adequately Designed,Maintained & Operated.Licensee Actively Pursuing Improvements in Auxiliary Feedwater Sys Reliability & in Reducing Challenges to Sys ML20214C9231986-11-14014 November 1986 Safety Evaluation Supporting Amends 80 & 73 to Licenses DPR-42 & DPR-60,respectively ML20212K8801986-08-15015 August 1986 Corrected Safety Evaluation Accepting Util 860110 Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20203B1551986-07-11011 July 1986 SER Re Util 831104 Response to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification. Program Acceptable. Exemption of Turbine Trip Component from Listing Also Acceptable ML20202A7531986-06-23023 June 1986 Safety Evaluation Supporting Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events ML20199L4491986-06-23023 June 1986 Safety Evaluation Re Util 860110 Projected Values of Matl Properties for Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events.Response Acceptable ML20211A3791986-05-30030 May 1986 Safety Evaluation Re Use of VIPRE-01 Subchannel Thermal Hydraulic Code & WRB-1 Critical Heat Flux Correlation W/Min DNBR Limit of 1.17.Code & Correlation Acceptable ML20211A2111986-05-27027 May 1986 SER Supporting Util Response to Generic Ltr 83-28,Item 1.2, Post-Trip Review (Data & Info Capability) ML20141N0961986-02-25025 February 1986 Safety Evaluation Accepting K(Z) Curve & Current Tech Spec Fq Value of 2.32 ML20138H1951985-10-18018 October 1985 Safety Evaluation Re Util 850422 & 0830 Ltrs Concerning Removal of Rod Cluster Control Guide Tube Thimble Plugs. Plan Acceptable ML20133N2021985-10-18018 October 1985 Safety Evaluation Accepting Util 830415,0915,850118 & 0606 Responses to Generic Ltr 82-33 Re Conformance of post- Accident Monitoring Instrumentation W/Rev 2 to Reg Guide 1.97 ML20138P6301985-10-17017 October 1985 Safety Evaluation Re Util 831104 Response to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Concerning Reactor Trip Breaker Automatic Shunt Trip.Licensee Position on Items Acceptable ML20138E1661985-10-11011 October 1985 Safety Evaluation Re 850809 Inservice Insp of Components Relief Requests 29 & 66.Alternative Acceptable & Relief Should Be Granted ML20133P0521985-08-0505 August 1985 Safety Evaluation Accepting Util post-trip Review Program & Procedures.Nrc Action on Item 1.1 of Generic Ltr 83-28 Completed ML20128M9091985-05-13013 May 1985 Safety Evaluation Supporting Util 831104 Response to Generic Ltr 83-28,Items 3.1.1,3.1.2,3.2.1,3.2.2,4.1 & 4.5.1 ML20062B6451982-07-0909 July 1982 Safety Evaluation Supporting Thermal Hydraulic Margins for Exxon Toprod for Cycle 7 ML20062B6361981-10-20020 October 1981 Safety Evaluation Supporting Thermal Hydraulic Margins for Exxon Toprod for Cycle 7 1999-08-24
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data 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 ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 ML20207J6951999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Prairie Island Nuclear Generating Plant ML20202J7711999-02-0404 February 1999 Simulator Certification Rept for Prairie Island Plant Simulation Facility,1998 Annual Rept ML20202G3761999-01-31031 January 1999 Non-proprietary Rev 7 to NSPNAD-8102-NP, Prairie Island Nuclear Power Plant Reload SE Methods for Application to PI Units ML20207L2811999-01-31031 January 1999 Revised Monthly Operating Repts for Jan 1999 for Pingp,Units 1 & 2 ML20202J1731999-01-22022 January 1999 Safety Evaluation Concluding That NSP Proposed Alternative to Surface Exam Requirements of ASME BPV Code for CRD Mechanism Canopy Seal Welds Will Provide Acceptable Level of Quality & Safety ML20206P7861998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Prairie Island Nuclear Generating Plant.With ML20205H0561998-12-31031 December 1998 Northern States Power Co 1998 Annual Rept. with ML20198J6441998-12-17017 December 1998 Rev 0 to PINGP COLR Unit 2-Cycle 19 ML20206N2731998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20155K6301998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20154H4061998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Prairie Island Nuclear Generating Plant.With ML20202J7991998-09-30030 September 1998 Non-proprietary Version of Rev 3 to CEN-629-NP, Repair of W Series 44 & 51 SG Tubes Using Leaktight Sleeves,Final Rept ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator ML20153B0761998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Prairie Island Nuclear Generating Plant.With ML20237A3961998-08-11011 August 1998 Safety Evaluation on Westinghouse Owners Group Proposed Insp Program for part-length CRDM Housing Issue.Insp Program for Type 309 Welds Inadequate from Statistical Point of View ML20237A8171998-08-0505 August 1998 SER Related to USI A-46 Program GL 87-02 Implementation for Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20236X8531998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Prairie Island Nuclear Generating Plant ML20236R6481998-07-15015 July 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at PINGP Unit 2 - Preliminary Summary Rept ML20236R0771998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Prairie Island Nuclear Generating Plant ML20249A5751998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Prairie Island Nuclear Generating Plant ML20247G7011998-05-31031 May 1998 Metallurgical Investigation & Root Cause Assessment of Part Length CRDM Housing Motor Tube Cracking at Prairie Island Nuclear Generating Plant,Unit 2 ML20248M0561998-05-31031 May 1998 Rev 5 to CEN-620-NP, Series 44 & 51 Design SG Tube Repair Using Tube Rerolling Technique ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) ML20247G2921998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Prairie Island Nuclear Generating Plant ML20217M6901998-04-29029 April 1998 Safety Evaluation Accepting Methodology for Relocation of Reactor Coolant Sys P/T Limit Curves & LTOP Sys Limits Proposed by NSP for Pingp,Units 1 & 2 ML20216C6361998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Prairie Nuclear Generating Plant Units 1 & 2 ML20216H0341998-03-31031 March 1998 Cycle-19 Voltage Based TSP Alternate Repair Criteria 90-Day Rept ML20217D2041998-03-13013 March 1998 Rev 1 to 28723-A, Intake Canal Liquefaction Analysis Rept for Pingp,Welch,Mn ML20236P9801998-03-12012 March 1998 Rev 0 to 97FP02-DOC-01, Compliance Review of 10CFR50,App R, Section Iii.O RCP Lube Oil Collection Sys ML20248L3931998-03-10010 March 1998 ISI Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 971018-971212 Cycle 18,960303-971212 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept 1999-09-30
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O %go UNITED STATES 8 ^ ,% NUCLEAR REGULATORY COMMISSION g ;p WASHINGTON, D. C. 20555
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION NORTHERN STATES POWER COMPANY PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNIT N0. 2 DOCKET NO. 50-306 INSERVICE INSPECTION OF COMPONENTS -
I5I RELIEF REQUEST NOS. 29 AND 66 Introduction By letter dated August 9, 1985, Northern States Power Company (the licensee) requested relief from two requirements of Section XI of the ASME Boiler and Pressure Vessel Code for the Prairie Island Nuclear Generating Plant Unit 2.
The licensee's relief requests pertain to the first 10-year interval which is due to expire at the start of cycle 11 (October 1985) for Unit 2. During the first 10-year interval, the requirements cf the 1974 edition through Sumer of 1975 Addenda of Section XI of the ASME Boiler and Pressure Vessel Code apply.
The licensee, pursuant to 10 CFR 50.55a(g)(5)(iii), submitted by letter dated August 9, 1985, information to support the determination that examinations imposed by the ASME Code are impractical for Prairie Island Unit 2 request.
Evaluation This evaluation addresses two relief requests related to the inservice in-spection of components identified in the licensee's letter dated August 9, 1985. These relief requests are identified as Relief Request No. 29 dealing with hydrostatic testing and Relief Request No. 66 dealing with examination of the internal pressure boundary surface of one valve.
- 1. Relief Request No. 29 A. Component Description The affected component is a Class 2 charging line pipe section down-stream of valves'2 VC-7-10 and 2 VC-7-11. This line includes 35 feet of 2" diameter pipe located outside containment and 4 feet of 3/4" diameter pipe located inside containment. This piping is considered part of the charging system.
B. Code Requirement Pursuant to IWC 5220, Pressure piping systems shall be hydrostatically pressure tested to at least 1.25 times the system design pressure (2485 psig) at a test temperature not less than 100*F.
C. Licensee's Basis for Requesting Relief The piping system described above is not isolable from the Class 1 piping unless a freeze plug is installed in the charging line to the cold leg downstream of the 3/4" bypass line and in the charging line to auxiliary 8510240601 851011 DR ADOCK O 3j6
spray on the regenerative heat exchanger outlet. Although a freeze plug has been used in the past, the licensee is reluctant to utilize this technique because of the hazards associated with installing and maintaining the plug in the pipe system during the test period.
D. Licensee's Proposed Alternative This.section of pipe will be visually inspected in accordance with the rules of IWC 2000 and pressure tested to approximately 2600 psig following each refueling outage as an alternative.
E. Evaluation Because of the design, the charging line downstream of valves 2 VC-7-10 and 2 VC-7-11 cannot be pressurized to the proper test pressure without the utilization of a freeze plug. We agree with the licensee regarding the potential hazards associated with the use of a freeze plug in that, if the freeze plug should break loose during the pressure test, it could damage the downstream piping. It is therefore impractical to meet the code requirements for pressure testing the pipe section described above because of the risk associated with the use of a freeze plug. The 2600 psig test pressure is approx-imately 400 psig below the prescribed test pressure in IWC 5000 and approximately 350 psig above the normal operating pressure.
F. Conclusion Based on the above evaluation, the staff concludes that, for the section of pipe discussed above, the code requirement regarding hydrostatic testing is impractical. It is further concluded that the alternative discussed above will provide adequate assurance of structural integrity of the pipe section described above. Therefore, relief from IWC 5000 of Section XI of the ASME Boiler and Pressure Vessel Code should be granted for the section of pipe described above provided that, following each refueling cycle, the pipe section is hydrostatically tested to approximately 2600 psig and welds are
- g. visually inspected in accordance with IWC 2000 of Section XI of the ASME code.
- 2. Relief Request No. 66 A. Component Description The component concerned with this relief request is a 10-inch motor operated gate valve. The manufacturer is Darling Company and the valve is located in the Unit 2 residual heat removal B return line (valveNo.MV32169).
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I B. Code Requirement IWB 2412 and Table IWB 2500, B-M-2 of Section XI of the ASME Boiler and Pressure Vessel Code, require visual inspection of the internal pressure boundary of valves of the same constructural design, e.g.,
globe or check valves, manufacturing method and manufacturer, that perform similar functions in the system.
C. Licensee's Basis for Requesting Relief The licensee's bases for requesting relief from the Code requirement
, are as follows:
- 1. The disassembly of the valve will require breaking a seal weld and replacing it after the examination of internal pressure boundary is completed. The remaking of the seal weld presents the potential of damaging the valve internals.
- 2. Valve No. MV-32169 is the only gate valve existing in Unit 2 that s was supplied by Darling Company. Therefore, this valve does not represent a population of valves existing in Unit 2 other than MV-32169 itself.
. 3. A hazardous condition will exist during the examination of the valve since there will be a single check valve isolating the
, water in the refueling canal which is flooded during this period.
The check valve is designed to seal at a much higher pressure and temperature than will exist during the examination period
- t of the valve.
4 The later edition of the ASME Code does not require the extent of the examination to include the manufacturer.
- 5. The examination of the same valve in Unit No. I performed in January 1985 showed no evidence of wear, erosion, corrosion or other anomalies. In this case the seal weld between the body and bonnet was not remade because of difficulty and potential >
damage to the valve internals.
D. Licensee's Proposed Alternative As an alternative, the licensee proposes to examine a motor operated valve from a different manufacturer during the Unit 2 refueling and if the residual heat removal system shows evidence of possible valve degradation during hydrostatic testing, to disassemble and examine the subject valve.
E. Evaluation Access to perform an internal surface examination on valve MV-32169 is restricted due to the valve design and the potential hazardous conditions that exist during the examination. The result of the examination of the same valve in Unit 1 gives reasonable assurance
that the internal surface of the valve in Unit 2 has not degraded to the point where its intended safety function would be affected. As a matter of fact, the examination showed no signs of degradation after 10 years of service. In addition it is unlikely that it will be possible to remake the seal weld after the examination based on the experience gained from the examination of the Unit i valve.
F. Conclusion Based on the above evaluation, the staff finds that it is impractical to meet the code requirement by the examination of this valve. As an alternative, the licensee has committed to examine a motor operated valve from a different manufacturer during the Unit 2 refueling outage. In addition, if during hydrostatic testing the residual heat removal system shows evidence of possible valve degradation, then the subject valve would be disassembled and examined.
In conclusion, the staff finds this alternative acceptable and there-fore the relief should be granted.
Date: October 11, 1985 Principal Contributor:
D.C. Di Ianni l
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