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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
[Table view] |
Text
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j' SAFETY EVALUATION REPORT '
DOCKET NOS. 50-787/306 PRAIRIE ISLAND NUCLEAR GENERATING PLANT, UNITS 1,9 l GENERIC LETTER 83-78, ITEM 4.5.7 REACTOR TRIP SYSTEM RELIARILITY-DN-LINE TESTING ,
[ 3 INTRODUCTION AND
SUMMARY
Generic Letter 83-28 was issued by NRC on July 8,1983, indicating actions to be taken by applicants and licensees based on the generic implications of the Salen ,
i ATWS events. Item 4.5 states a staff position which requires on-line functional 4
testing of the reactor trip system, including independent testing of the diverse j trip features of the reactor trip breakers, for all plants. Item 4.5 ? requires ,
applicants and licensees with piants not currently designed to permit this peri-l odic on-line testing to justify not making modifications to permit such testing.
Ry letters dated November 4,1983, and July 6,1984, the licensee, Northern ' States I
Power Company, responded to the staff position regarding item 4.5.2 of Generic i
- Letter 83-28. Our review of these responses finds them to be acceptable, i
l j EVALUATION 1 The licensee states that Prairie Island is designed to permit on-line testing of the Reactor Trip System and independent testing of the undervoltage and ;
shunt trip attachments of the reactor trip breakers.
1 i
CONCLUSION I
t The staff finds that the Prairie Island Nuclear Generating Plant, Units 1,?,
is designed to permit on-line functional testing of the reactor trip system,
} including independent testing of the diverse trip features o'f the reactor trip breakers. Thus, the applicant meets the staff position of Item 4.5.2 of Generic Letter 83-28
{
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