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| ML20196F408 |
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| Site: |
Prairie Island  |
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| Issue date: |
06/23/1999 |
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| From: |
NORTHERN STATES POWER CO. |
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| To: |
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| Shared Package |
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| ML20196F394 |
List: |
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| References |
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| NSPNAD-8102, NSPNAD-8102-R07, NSPNAD-8102-R7, NUDOCS 9906290199 |
| Download: ML20196F408 (3) |
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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] |
Text
r1 l
c .
l a. Moderator Temperature Coefficient (ag)
Calculations of as are performed using the methods described in Section 2. Cycle specific calculations for this accident are made at unrodded full power.
- b. Doppler Temperature Coefficient (a o)
Calculations of no are performed in accordance with the procedure described in Section 2.
l
- c. Boron Concentration Reactivity Coefficient (a s)
Calculations of as are performed using methods described in Section 2. Cycle specific calculations for this accident are made at unrodded full power.
- d. Shutdown Margin (SDM)
The shutdown margin will be calculated and compared with the limiting assumptions used in the safety analysis using the methods described in Section 2.0.
- e. Nuclear Enthalpy Rise Hot Channel Factor (Fan)
The maximum core Fan is assumed to remain within the current limits as defined in the Technical Specifications for allowable combinations of axial offset and power level. For Prairie Island, the continuous surveillance of the power distribution is accomplished with the excore detectors using the Exxon PDC-iia
3.5.5 Reload Safety Evaluations All the cycle specific parameters discussed above are adjusted to include model reliability factors, RF i, and biases, B. 1 These results are then compared to the bounding
- values assumed in the safety analysis. The cycle specific parameters are acceptable if the following inequalities are met
(
l 9906290199 990623 PDR ADOCK 05 P
Page 71 of 298 Copyright o 1999 by Northem States Power
c ,.
CYCLE SPECIFIC PARAMETERS SAFETY ANALYSIS PARAMETERS i
- a. ax + RFu + Bn 5 cts (least negative bounding value)
- b. n o* (1 - RFo) s ao (least negative bounding value)
- c. a *s (1 + RFa) * (1 + Bs) 2 as (most negative bounding value)
- d. Shutdown Margin 2 Shutdown Margin (bounding)
- e. ( Faa+RFraa+ Bran) * (1+T) s Fan (Technical Specifications) l l
l l
Page 72 of 298 Copyright c 1999 by Northern States Power
F .. . . . .
l .o o l
l l i i l )
l APPENDIX H 1
H.1 Changes Made In Revision 7 To This Report The format of this document has changed slightly between Revisions 6 and 7. Most of this was due to the use of a i different word processor which reformatted the entire document. l For reference, alterations made in Revision 7 are summarized I below.
Rev. 6 Page Rev. 7 Page Description of Change Number (s) Number (s) 1 1* Revision number and date were updated.
2,3 2*,3* Margins were adjusted.
4-12 4-12* Provided additional sections in Table of l Contents, adjusted titles of various figures (but not the actual figures). j 13-14 13-14 Text was added to describe the addition of Appendix G. J 47 49 Changed text to show VIPRE is used rather than COBRA.
{
l l 50 52 The equation for Moderator Temperature j Coefficient was corrected. An error j introduced in Rev. 6 in the inequality for )
excore tilt was also corrected. j 66, 67 69, 70* Corrected the character for delta in the )
text.' Text was added to describe the l
addition of Appendix G.
68 71, 72 Clarification of shutdown margin. ,
84, 97, 88, 101, Provided additional information for the l 133, 145 138, 150 Doppler Coefficient.
131 136 Corrected number of pumps assumed to trip in each figure.
133, 145 138, 150 Added Shutdown Margin-to the Cycle Specific Parameters list and text describing it.
155 160 Correct typo on pressure at which steamline l
break occurs.
157 163 Pressure under (e) is corrected.
188 194 The equati.ns for pere and Aputer were l l corrected.
I 200 206 The equation for Boron Reactivity Coefficient was corrected.
257 264* Corrected the units in two columns.
263 270* Changed f(A) and A to f(AI)and AT. [
n/a 293-298 Added Appendices G and H.
various various* Corrected spelling and grammar, added spaces to separate words, corrected subject / verb l agreement, etc.
- No revision bars are provided for spelling and grammar corrections or text format changes. ,
i Page 298 of 298 a Copyright 81999 by Northem States Power 1
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