Criteria for Determining Justification for Continued Operation When Encountering Major Discrepancies in 'As-Built' Safety-Related EquipmentML20154Q898 |
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Site: |
Prairie Island ![Xcel Energy icon.png](/w/images/6/6c/Xcel_Energy_icon.png) |
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Issue date: |
09/21/1988 |
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From: |
NORTHERN STATES POWER CO. |
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To: |
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Shared Package |
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ML20154Q884 |
List: |
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References |
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NUDOCS 8810040097 |
Download: ML20154Q898 (6) |
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Category:GENERAL EXTERNAL TECHNICAL REPORTS
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept 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 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 ML20196D7341998-11-20020 November 1998 Third Quarter 1998 & Oct 1998 Data Rept for Prairie Island Isfsi ML20198P0571998-09-0303 September 1998 Rev 1 to 95T047, Back-up Compressed Air Supply for Cooling Water Strainer Backwash Valve Actuator 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 ML20247E2671998-05-0505 May 1998 Rev 0 to Pingp,Units 1 & 2,Pressure & Temp Limits Rept (Effective Until 35 Efpy) 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 ML20216D0911998-03-0606 March 1998 Rev 0 to Prairie Island Generating Plant,Units 1 & 2, Pressure & Temp Limits Rept ML20236Q0021998-02-28028 February 1998 Final Rept, Prairie Island Fire IPEEE Technical Assessment ML20216D1171998-02-28028 February 1998 Non-proprietary Final,Rev 2 to Prairie Island,Units 1 & 2, COMS Setpoint Analysis ML20198N8401998-01-0606 January 1998 Non-proprietary Version of Prairie Island Unit 1 Cycle 19 Thimble Deletion Study ML20212B7941997-10-20020 October 1997 Final Rept for Maximum Allowable Primary to Secondary Leak Rate Using ML20141F2771997-06-30030 June 1997 Non-proprietary Rept NSPNAD-97002, Slb Methodology ML20141A9911997-03-0707 March 1997 Rev 1 to Prairie Island Unit 2 45 F Ultrasonic Exam Rept (3rd 10yr) ML20141A9791997-03-0707 March 1997 F Ultrasonic Exam Rept (3rd 10yr) ML20135A9451997-02-28028 February 1997 Spent Fuel Pool Dilution Analysis ML20135A9481997-02-28028 February 1997 NSP Prairie Island Units 1 & 2 Spent Fuel Rack Criticality Analysis Using Soluble Boron Credit ML20136F3921997-02-28028 February 1997 Response to NRC Addl Info Request ML20138G7791996-12-18018 December 1996 Rev 20 to Operational QA Plan ML20132F2951996-12-12012 December 1996 Rev 0 to NSPLMI-96001, Prairie Island Nuclear Generating Plant Ipeee ML20115E8921995-12-31031 December 1995 FERC Form 1:Annual Rept of Major Electric Utils,Licensees & Others for NSP (Minnesota) & (Wisconsin) ML20094P0351995-11-20020 November 1995 NSP PINGP Units 1 & 2 USNRC USI A-46 Resolution Seismic Evaluation Rept ML20094P0451995-11-15015 November 1995 Rev 0 of Vol I of VI of NSP PINGP Units 1 & 2 USNRC USI A-46 Resolution Ssel & Relay Evaluation Rept ML20199A0251995-03-31031 March 1995 Firezone R Single & Multi-Conductor High Temperature 600 Volt,14 AWG-4/0 Awg Specification ML20078N9531995-01-26026 January 1995 Simulator Certification Rept for Prairie Island Plant Simlation Facility 1994 Annual Rept ML20058M8411993-08-18018 August 1993 Plant,Sbo/Esu Project, Design Rept, Rev 2 ML20056H0451993-04-30030 April 1993 Transient Power Distribution Methodology ML20045C1841993-02-28028 February 1993 Criticality Analysis of Prairie Island,Units 1 & 2 Fresh & Spent Fuel Racks. ML20248L4081992-09-0101 September 1992 Annual Rept Review of Meteorological Data 1991 Monticello & Prairie Island Stations ML20092A6671992-01-14014 January 1992 App B Suppl to Generic Licensing Topical Rept EDR-1, Summary of Plant Specific Crane Data Supplied by Ederer Inc for NSP Co Praire Island Nuclear Generating Plant Units 1 & 2 Auxiliary Bldg Crane ML20086T5631991-12-20020 December 1991 Rev 1 to Prairie Island Nuclear Generating Plant Station Blackout/Electrical Safeguards Upgrade Project ML20092A6791991-12-18018 December 1991 Design Criteria for Lifting Sys for TN-40 Dry Storage Cask at Praire Island ML20067B7211991-02-28028 February 1991 Revised Prairie Island Large Break LOCA Calculation Using WCAP-10924,Vol 1,Addenda 4 Model Changes ML20067C9301991-02-0101 February 1991 Simulator Certification Rept for Prairie Island Plant Simulation Facility ML20058J8881990-10-15015 October 1990 Design Rept for Facility Station Blackout/Electrical Safeguards Upgrade Project ML20011D6991989-12-12012 December 1989 Addendum 1 to, Sacm Diesel Generator Qualification Rept. ML20248D6491989-09-29029 September 1989 Rev 0 to Societe Alsacienne De Consts Mecaniques De Mulhouse Diesel Generator Qualification Rept ML20245L2891989-05-25025 May 1989 Used Molded Case Circuit Breakers Installed in Safety- Related Applications, Addendum 1 to Safety Evaluation 252 ML20245G7711989-04-28028 April 1989 Untraceable Molded Case Circuit Breakers Installed in Safety-Related Application, Safety Evaluation 265 ML20248J8881989-03-31031 March 1989 Criticality Analysis of Prairie Island Units 1 & 2 Fuel Racks ML20245L2631988-11-11011 November 1988 Used Molded Case Circuit Breakers Installed in Safety- Related Applications, Safety Evaluation 252 ML20154Q8981988-09-21021 September 1988 Criteria for Determining Justification for Continued Operation When Encountering Major Discrepancies in 'As-Built' Safety-Related Equipment ML20151Q2201988-08-31031 August 1988 Demonstration of Conformance of Prairie Island Units 1 & 2 to App K & 10CFR50.46 for Large Break Locas ML20150F2771988-06-30030 June 1988 Rev 1 to Safety Evaluation of Increased Fq & Fdeltah 1999-09-30
[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
[Table view] |
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- CRITERIA FOR DETERMINING JUSTIFICATION FOR CONTI'tVED OPERATION WHEN ENCOUNTERING MAJOR DISCREPANCIES IN "AS-BUILT" SAFETY RELATED PIPING SEPTEMBER 21, 1988 NORTHERN STATES POWER Co.
PRAIRIE ISLAND NUCLEAR GENERATING PLANT 1717 WAKONADE DRIVE EAS",'
WELCH, MN 55089 8910040097 880926 POR ADOCK 05000282 P F'DC
-. .___-_______-)
TABLE OF CONTENTS PACE ,
1.0 INTRODUCTION
& SCOPE................................. 3 2.0 CRITERIA ............................................ 3
3.0 CONCLUSION
.......................................... S
4.0 REFERENCES
.......................................... 5 t
P Page 2
1.0 INTRODUCTf0N & SCOPE
, These criteria are in' tended to assure the operability require-ments of safety related piping and associated supports if it
, is determined that stresses exceed allowables presented in i the Prairie Island USAR. These criteria permit operation for an interim period only. Modifications will be made which return the system to within USAR allowables by the next re-j fueling outage or sooner if operation permits.
These criteria are intended to expeditiously perform necessary evaluations to determine interim operability and not to delay appropriate actions.
For cases involving components classified as ASME Code Class I where USAR allowables are exceeded, NSP shall be notified upon discovery and NSP shall evaluate reportability require-
! ments per 10CFR50.
I l' 2.0 CRITERIA
- 2.1 Piping Operability Criteria
- The piping analysis shall be in accordance with ASME,Section III NC-3600 service level D limits (Ref. 1).
i The design loading conditions to be applied in the
, analysis shall include the DBE earthquake.
j Following is the pipe stress criteria for justifying continued operation of the plant:
(Sgp + SWT
- 3DBE $ .O Sy} (Ref. 1 equation 9)
)
Where S gp = Longitudinal Pressure Stress
- S = Dead Weight Stress WT i
j SDBE = Stresses Resulting From Design Basis
! Earthquake l S 7 = Material Yield Stress (Reference 1 Appendices)
{
Code Case N-411 allows for increased damping values, 3
independent of pipe diameter, for seismic analysis.
Therefore, increased damping values, in accordance i with reference 2, will be acceptable when performing i these analyses to meet operability. Should the piping stress analysis exceed the value of 2.0 Sy, or pipe supporltc do not meet their operable limits (see Sect.
l 2.2),lthenadditionaliterativeanalysisofthepiping 1 i
\ !
I Page 3 I
. mcy bo required. Tho itorctivo cnolysis may use the knowledge that a support is not capable of withstand-ing the loads, and can be removed from the analysis.
Where feasible, the actual support stiffness may be included in the iterative analysis, along with other
, refinements.
For cases where piping secondary stresses are determined to exceed USAR allowables, a specific case by case approach will be used to determine interim operability.
2.2 Pipe Support & Hanger operability criteria As a first step in evaluating the support, a linear elastic analysis method will be used to determine the stress in the support members. In addition to the leading in Section 2.1, the support loade must include pipe thermal 17 ads and results from free end displace-ment and anchor mction. Supports will be analyzed .
using the allowables listed below to meet cperability requirements.
Structural Steel Tension Fg = 1.20 Sy but 5 0.70 Su Bending F = 1.20 Sy but b
5 0.70 Su Shear Fy = 0.72 Sy but 5 0.42 Su Compression F, < F t
u n t exceed 2/3 Per Combined Stress For axial compression and bending or axial tension and bending, use AISC 1.6., (Ref. 6)
Web Crippling = 1.0 Sy Weld Stress Fy = 0.42 Su (of weld material)
Anchor Bolts Use Factor of Safety of 2 against ultimate tension and shear values.
Snubbers Hydraulic: Load < manufacturers one time load capacity.
Movement < total travel Springs Load within catalog range without bottoming out Struts FS = 2 and < 2/3 Per Page 4
All remaining Use manufacturers publishcd fculted Catalog Items load rating. Where level D allow-ables are not given, and the factor of safety is specified in the catalog, use design allowables but with FS = 2. (Typical catalog FS = 5, therefore use 2.5 x catalog capacity).
Where F t
= Allowable Tensile Stress F = Allowable Bending Stress b
Fy = Allowable Shear Stress F, = Allowable Axial Compressive Stress Fy = Allowable Weld Stress Per = Maximum Strength of Axially Loaded Compression Member Sy = Specified Minimum Field Strength at Temperature (See Note 1)
Su = Specified Minimum Tensile Strength Temperature FS = Factor of Safety NOTE 1: Actual yield strsngth may he used where CMTR's are available for the material.
If a support fails using the linear elastic method, then a more refined analysis may be performed using plastic analysis techniques. The plastic analysis will follow the design rules of ASME Section III, Appendix F. {Ref. 1).
3.0 CONCLUSION
If the above criteria cannot be met, reportability per 10 CFR 50 must be evaluated and system operability requirements per Plant Technical Specifications must be evaluated and appro-priate actions taken.
4.0 .REFEJENCES
- 1. American Society of Mechanical Es.gineers, Boiler and Pressure Vessel Codes,Section III, 1983 Edition, through Winter 1985 Addenda.
- 2. American Society of Mechanical Engineers, Boiler and Pressure Vessel Codes, Case N-411, Dated 9/17/84.
Page 5
- 3. NRC-IE Bulletin 79-02, "Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts," Revision No. 1 (Supplement No. 1), Datad 8/20/79.
- 4. USAS B31.1.0-1967, Power Piping Code.
- 5. Updated Safety Evaluation Report for PINGP.
- 6. "Manual of Steel Construction," American Institute of Stect Construction, Inc., Eighth Edition, 1980.
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