Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.ML20039A196 |
Person / Time |
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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: |
12/09/1981 |
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From: |
FRANKLIN INSTITUTE |
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To: |
NRC |
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Shared Package |
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ML20039A197 |
List: |
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References |
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CON-NRC-03-79-118, CON-NRC-3-79-118, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.1.2, TASK-TM IEB-79-01B, IEB-79-1B, RFI-5257-502, RFI-C5257-502, NUDOCS 8112160346 |
Download: ML20039A196 (7) |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20148D5461997-05-16016 May 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for Prairie Island Units 1 & 2 Nuclear Generating Plant L-95-059, Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 21995-12-31031 December 1995 Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 2 L-95-056, Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 11995-11-30030 November 1995 Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 1 ML20058N8091993-11-0404 November 1993 Pump & Valve IST Program Prairie Island Nuclear Generating Plant,Units 1 & 2 Northern States Power Co, TER ML20116A1371992-10-31031 October 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Prairie Island Units 1 and 2 Nuclear Power Plants ML20096G5161992-04-30030 April 1992 Trip Rept:Onsite Analysis of Human Factors of Event at Prairie Island 2 on 920220 (Loss of Shutdown Cooling) ML20063P9311990-07-18018 July 1990 Technical Evaluation Rept Prairie Island Nuclear Generating Plant Units 1 & 2 Station Blackout Evaluation ML20246J9201988-06-30030 June 1988 Technical Evaluation Rept for Evaluation of Odcm,Updated Through Rev 9,Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20215H6701987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components, Prairie Island 1 & 2, Technical Evaluation Rept ML20211N8071986-05-31031 May 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Indian Point 2,Kewaunee,North Anna 1 & 2 & Prairie Island 1 & 2 ML20210L4801986-04-25025 April 1986 Technical Evaluation of Dcrdr for Prairie Island Nuclear Generating Station,Units 1 & 2 ML20206H8621986-02-19019 February 1986 Technical Evaluation of Dcrdr for Northern States Power Co, Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20137X7351985-09-30030 September 1985 IN-PLANT Source Term Measurements at Prairie Island Nuclear Generating Station ML20133N2091985-08-31031 August 1985 Conformance to Reg Guide 1.97,Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20108D0031984-11-30030 November 1984 Conformance to Reg Guide 1.97 Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20111A6471984-09-0707 September 1984 Revised, Inservice Insp Program,Prairie Island Nuclear Generating Plant, Technical Evaluation Rept ML20077J9731983-08-16016 August 1983 Masonry Wall Design,Prairie Island Nuclear Generating Plant,Units 1 & 2, Revised Technical Evaluation Rept ML20076D2121983-05-17017 May 1983 Control of Heavy Loads (C-10),Prairie Island Nuclear Generating Plant,Units 1 & 2, Technical Evaluation Rept ML20077K7731983-02-23023 February 1983 Selected Operating Reactors Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G9301982-12-0606 December 1982 ECCS Repts (F-47),TMI Action Plan Requirements,Northern States Power Co,Praire Island Nuclear Generating Plant Units 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20039A1961981-12-0909 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20040A3851981-11-30030 November 1981 ECCS Review,Prairie Island Nuclear Generating Plant,Units 1 & 2, Informal Rept ML20004D0471981-06-0303 June 1981 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication,Prairie Island Units 1 & 2, Technical Evaluation Rept ML19345E1451980-12-0909 December 1980 Draft Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of ESF Reset Controls for Prairie Island Nuclear Generating Plant,Units 1 & 2. ML19341A9921980-12-0808 December 1980 Metallurgical Analysis,W/Attachment A,Stress Analysis of Failed Steam Generator Support Bolts from Prairie Island, Unit 1. ML19339B8201980-09-19019 September 1980 LWR In-Plant Measurement Program, Informal Monthly Progress Rept for Aug 1980 ML19318B1341980-03-31031 March 1980 Technical Evaluation of Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Prairie Island Nuclear Generating Plants Units 1 & 2. ML19225C5061979-06-21021 June 1979 Fire Protection in Operating Nuclear Power Stations,Prairie Island Station SER Review, Interim Rept 1997-05-16
[Table view] Category:QUICK LOOK
MONTHYEARML20148D5461997-05-16016 May 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for Prairie Island Units 1 & 2 Nuclear Generating Plant L-95-059, Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 21995-12-31031 December 1995 Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 2 L-95-056, Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 11995-11-30030 November 1995 Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 1 ML20058N8091993-11-0404 November 1993 Pump & Valve IST Program Prairie Island Nuclear Generating Plant,Units 1 & 2 Northern States Power Co, TER ML20116A1371992-10-31031 October 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Prairie Island Units 1 and 2 Nuclear Power Plants ML20096G5161992-04-30030 April 1992 Trip Rept:Onsite Analysis of Human Factors of Event at Prairie Island 2 on 920220 (Loss of Shutdown Cooling) ML20063P9311990-07-18018 July 1990 Technical Evaluation Rept Prairie Island Nuclear Generating Plant Units 1 & 2 Station Blackout Evaluation ML20246J9201988-06-30030 June 1988 Technical Evaluation Rept for Evaluation of Odcm,Updated Through Rev 9,Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20215H6701987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components, Prairie Island 1 & 2, Technical Evaluation Rept ML20211N8071986-05-31031 May 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Indian Point 2,Kewaunee,North Anna 1 & 2 & Prairie Island 1 & 2 ML20210L4801986-04-25025 April 1986 Technical Evaluation of Dcrdr for Prairie Island Nuclear Generating Station,Units 1 & 2 ML20206H8621986-02-19019 February 1986 Technical Evaluation of Dcrdr for Northern States Power Co, Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20137X7351985-09-30030 September 1985 IN-PLANT Source Term Measurements at Prairie Island Nuclear Generating Station ML20133N2091985-08-31031 August 1985 Conformance to Reg Guide 1.97,Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20108D0031984-11-30030 November 1984 Conformance to Reg Guide 1.97 Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20111A6471984-09-0707 September 1984 Revised, Inservice Insp Program,Prairie Island Nuclear Generating Plant, Technical Evaluation Rept ML20077J9731983-08-16016 August 1983 Masonry Wall Design,Prairie Island Nuclear Generating Plant,Units 1 & 2, Revised Technical Evaluation Rept ML20076D2121983-05-17017 May 1983 Control of Heavy Loads (C-10),Prairie Island Nuclear Generating Plant,Units 1 & 2, Technical Evaluation Rept ML20077K7731983-02-23023 February 1983 Selected Operating Reactors Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G9301982-12-0606 December 1982 ECCS Repts (F-47),TMI Action Plan Requirements,Northern States Power Co,Praire Island Nuclear Generating Plant Units 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20039A1961981-12-0909 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20040A3851981-11-30030 November 1981 ECCS Review,Prairie Island Nuclear Generating Plant,Units 1 & 2, Informal Rept ML20004D0471981-06-0303 June 1981 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication,Prairie Island Units 1 & 2, Technical Evaluation Rept ML19345E1451980-12-0909 December 1980 Draft Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of ESF Reset Controls for Prairie Island Nuclear Generating Plant,Units 1 & 2. ML19341A9921980-12-0808 December 1980 Metallurgical Analysis,W/Attachment A,Stress Analysis of Failed Steam Generator Support Bolts from Prairie Island, Unit 1. ML19339B8201980-09-19019 September 1980 LWR In-Plant Measurement Program, Informal Monthly Progress Rept for Aug 1980 ML19318B1341980-03-31031 March 1980 Technical Evaluation of Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Prairie Island Nuclear Generating Plants Units 1 & 2. ML19225C5061979-06-21021 June 1979 Fire Protection in Operating Nuclear Power Stations,Prairie Island Station SER Review, Interim Rept 1997-05-16
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20148D5461997-05-16016 May 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for Prairie Island Units 1 & 2 Nuclear Generating Plant L-95-059, Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 21995-12-31031 December 1995 Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 2 L-95-056, Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 11995-11-30030 November 1995 Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 1 ML20058N8091993-11-0404 November 1993 Pump & Valve IST Program Prairie Island Nuclear Generating Plant,Units 1 & 2 Northern States Power Co, TER ML20116A1371992-10-31031 October 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Prairie Island Units 1 and 2 Nuclear Power Plants ML20096G5161992-04-30030 April 1992 Trip Rept:Onsite Analysis of Human Factors of Event at Prairie Island 2 on 920220 (Loss of Shutdown Cooling) ML20063P9311990-07-18018 July 1990 Technical Evaluation Rept Prairie Island Nuclear Generating Plant Units 1 & 2 Station Blackout Evaluation ML20246J9201988-06-30030 June 1988 Technical Evaluation Rept for Evaluation of Odcm,Updated Through Rev 9,Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20215H6701987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components, Prairie Island 1 & 2, Technical Evaluation Rept ML20211N8071986-05-31031 May 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Indian Point 2,Kewaunee,North Anna 1 & 2 & Prairie Island 1 & 2 ML20210L4801986-04-25025 April 1986 Technical Evaluation of Dcrdr for Prairie Island Nuclear Generating Station,Units 1 & 2 ML20206H8621986-02-19019 February 1986 Technical Evaluation of Dcrdr for Northern States Power Co, Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20137X7351985-09-30030 September 1985 IN-PLANT Source Term Measurements at Prairie Island Nuclear Generating Station ML20133N2091985-08-31031 August 1985 Conformance to Reg Guide 1.97,Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20108D0031984-11-30030 November 1984 Conformance to Reg Guide 1.97 Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20111A6471984-09-0707 September 1984 Revised, Inservice Insp Program,Prairie Island Nuclear Generating Plant, Technical Evaluation Rept ML20077J9731983-08-16016 August 1983 Masonry Wall Design,Prairie Island Nuclear Generating Plant,Units 1 & 2, Revised Technical Evaluation Rept ML20076D2121983-05-17017 May 1983 Control of Heavy Loads (C-10),Prairie Island Nuclear Generating Plant,Units 1 & 2, Technical Evaluation Rept ML20077K7731983-02-23023 February 1983 Selected Operating Reactors Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G9301982-12-0606 December 1982 ECCS Repts (F-47),TMI Action Plan Requirements,Northern States Power Co,Praire Island Nuclear Generating Plant Units 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20039A1961981-12-0909 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20040A3851981-11-30030 November 1981 ECCS Review,Prairie Island Nuclear Generating Plant,Units 1 & 2, Informal Rept ML20004D0471981-06-0303 June 1981 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication,Prairie Island Units 1 & 2, Technical Evaluation Rept ML19345E1451980-12-0909 December 1980 Draft Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of ESF Reset Controls for Prairie Island Nuclear Generating Plant,Units 1 & 2. ML19341A9921980-12-0808 December 1980 Metallurgical Analysis,W/Attachment A,Stress Analysis of Failed Steam Generator Support Bolts from Prairie Island, Unit 1. ML19339B8201980-09-19019 September 1980 LWR In-Plant Measurement Program, Informal Monthly Progress Rept for Aug 1980 ML19318B1341980-03-31031 March 1980 Technical Evaluation of Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Prairie Island Nuclear Generating Plants Units 1 & 2. ML19225C5061979-06-21021 June 1979 Fire Protection in Operating Nuclear Power Stations,Prairie Island Station SER Review, Interim Rept 1997-05-16
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20148D5461997-05-16016 May 1997 Technical Evaluation Rept of IPE Submittal & RAI Responses for Prairie Island Units 1 & 2 Nuclear Generating Plant L-95-059, Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 21995-12-31031 December 1995 Technical Evaluation Rept on Third 10-Yr Interval Inservice Insp Exam Plan:Northern State Power Co,Prairie Island Nuclear Generating Plant,Unit 2 L-95-056, Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 11995-11-30030 November 1995 Technical Evaluation Rept on Third 10-Year Interval Inservice Insp Program Plan:Northern States Power Co, Prairie Island Nuclear Generating Plant,Unit 1 ML20058N8091993-11-0404 November 1993 Pump & Valve IST Program Prairie Island Nuclear Generating Plant,Units 1 & 2 Northern States Power Co, TER ML20116A1371992-10-31031 October 1992 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Prairie Island Units 1 and 2 Nuclear Power Plants ML20096G5161992-04-30030 April 1992 Trip Rept:Onsite Analysis of Human Factors of Event at Prairie Island 2 on 920220 (Loss of Shutdown Cooling) ML20063P9311990-07-18018 July 1990 Technical Evaluation Rept Prairie Island Nuclear Generating Plant Units 1 & 2 Station Blackout Evaluation ML20246J9201988-06-30030 June 1988 Technical Evaluation Rept for Evaluation of Odcm,Updated Through Rev 9,Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20215H6701987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components, Prairie Island 1 & 2, Technical Evaluation Rept ML20211N8071986-05-31031 May 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1), Equipment Classification (Reactor Trip Sys Components), Indian Point 2,Kewaunee,North Anna 1 & 2 & Prairie Island 1 & 2 ML20210L4801986-04-25025 April 1986 Technical Evaluation of Dcrdr for Prairie Island Nuclear Generating Station,Units 1 & 2 ML20206H8621986-02-19019 February 1986 Technical Evaluation of Dcrdr for Northern States Power Co, Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20137X7351985-09-30030 September 1985 IN-PLANT Source Term Measurements at Prairie Island Nuclear Generating Station ML20133N2091985-08-31031 August 1985 Conformance to Reg Guide 1.97,Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20108D0031984-11-30030 November 1984 Conformance to Reg Guide 1.97 Prairie Island Nuclear Generating Plant,Units 1 & 2 ML20111A6471984-09-0707 September 1984 Revised, Inservice Insp Program,Prairie Island Nuclear Generating Plant, Technical Evaluation Rept ML20077J9731983-08-16016 August 1983 Masonry Wall Design,Prairie Island Nuclear Generating Plant,Units 1 & 2, Revised Technical Evaluation Rept ML20076D2121983-05-17017 May 1983 Control of Heavy Loads (C-10),Prairie Island Nuclear Generating Plant,Units 1 & 2, Technical Evaluation Rept ML20077K7731983-02-23023 February 1983 Selected Operating Reactors Issues Program Ii,Rcs Vents (NUREG-0737,Item II.B.1), Final Technical Evaluation Rept ML20126E9941982-12-0707 December 1982 Containment Leak Rate Testing Investigations, Monthly Progress Rept for Nov 1982 ML20079G9301982-12-0606 December 1982 ECCS Repts (F-47),TMI Action Plan Requirements,Northern States Power Co,Praire Island Nuclear Generating Plant Units 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20039A1961981-12-0909 December 1981 Equipment Environ Qualification Review of Licensees Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20040A3851981-11-30030 November 1981 ECCS Review,Prairie Island Nuclear Generating Plant,Units 1 & 2, Informal Rept ML20004D0471981-06-0303 June 1981 Auxiliary Feedwater Sys Automatic Initiation & Flow Indication,Prairie Island Units 1 & 2, Technical Evaluation Rept ML19345E1451980-12-0909 December 1980 Draft Technical Evaluation of Electrical,Instrumentation & Control Design Aspects of ESF Reset Controls for Prairie Island Nuclear Generating Plant,Units 1 & 2. ML19341A9921980-12-0808 December 1980 Metallurgical Analysis,W/Attachment A,Stress Analysis of Failed Steam Generator Support Bolts from Prairie Island, Unit 1. ML19339B8201980-09-19019 September 1980 LWR In-Plant Measurement Program, Informal Monthly Progress Rept for Aug 1980 ML19318B1341980-03-31031 March 1980 Technical Evaluation of Proposed Design Mods & Tech Spec Changes on Grid Voltage Degradation for Prairie Island Nuclear Generating Plants Units 1 & 2. ML19225C5061979-06-21021 June 1979 Fire Protection in Operating Nuclear Power Stations,Prairie Island Station SER Review, Interim Rept 1997-05-16
[Table view] |
Text
. _ .- ..
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REQUEST Fox AnnITICNAL INFCRMATICN - ..,..-
t'. ' .
EQUIPMEIC EN7IRCNMENTAL QUALIFICATION (EEQ) '
P1TIIW CF LICENSEES' RESOLUTICN CF CUISTANDING ISSDES . >
FROM NRC EQUIPME!C ENVIRCNMENTAL QUALIFICATICN S&FETY -
EVALUATION REPORTS (SER) AND TMI ACTION. PIAN -
-- INS"ar.7.rn ;.. . . . . EQU Nor,thern States Power, Company ..
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Prairie Island Unit / 7 "1- . : . .-
mecember 9, 1.983. -
- NRC Docket No. 50-se6 2 72.
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NRC TAC Noh 4250p) $f.,6~4 / .
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FRC mailing address is as follows: -
~
Mr. Cyril J. Crane - '
Franklin Research Center The Parkway at Twentieth Street - ;
Philadelphia, PA 19103 ,
Telephone No. 215/448-1353 Telecepy No. 215/448-1296 Telecepy confirmation No. 215/448-1215
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- p - .
e.. - -
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.00. Franklin Research Center h '
A Divisien o(The Franklin Instic.:te w w rm ha.w.ma.r isics maius.scoo SU'Ai Go 3Sc,
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( . 'Fra 1('Res rch Center (FRC) of Philadelphia, Pa. da providing'assie . . . - , . . . - . .
- tance to the U.S. Nuclear Regulatory Conaiss, ion (NRC) for the eqrtipment - ' * -
enfironmental,qualificatien ,(EQ) review of operating ramctors.' FEC will- ~6 p.'
( * - -
performPa'ii'ZEQ"reviewI o k uns iLfcens o's 90-day respanse to ou*M4==== issues from the NBC Equipment Environmental Qualification Safety Eva1==eion Esport .
. (SER), ' . The review will be limited to safety-relatedpquipment potentially exposed to a harsh envf=n===t.' The .'
results wid'be presented in the form of a technical evaluation zaport for .- . ,
~
. u. _.
each Plant., ,, ,. .
This" ' request f'or additional information (RFI) is the ramalt of an evaluation of the information provided by letters dated October 31,'1980 [1].
~
and August 26, 1981 [2].*
A. ..FBC RE7IN OF THE LICENSEI'S 90-DAY RESPONSE TO THE MEC 22Q SE1 _.
Infcrmatien Recuested Eate Received bv FRC**
- 1. FRC requests .ne *.CCA/EE:.3 prcfiles, f or '
inside and outside containment, described on page 4 of Reference 2.
f .
- 2. :n refere.ce to the *.icensee's 90-day respense [2] to tne NRC SIR [3), a legible l .
single copy of each of the following -
qualification documents is requested in crder that the FRC evaluation nay proceed
- a. ,Okenite Company Latter to A. Smith (NSP)
August 31, 1978
( A.2 4. 6) "* -
- b. Kerite ' Company Report KPT-LVC-1 - -
April 13, 1977 (proprietary) .
(A.24.8)
~a ' r.%%=" . 7 j
- Numbers in brackets refer ,to citations found in the list of references.
e, .
"This column wi?1 be ecmpleted by FPC as the requested informattion is -
"- received.
- Nu=bers in parentheses refer to the Licensee's SCN sheet m=shers.
b,, :Franidin Researrh Center AQuamen af The hansan ensams
..as a.e a ***
.. ,= . .
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, /2 '.* -:
. 3 ,; , .'. , . , ,- ~ W. .. / ', k , .Jl, .
, gc.:_%.;Cs157.sa1' ... -
- '***= ...,
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. * ~~
Date Received by FRC** *
. -e
- c. Barton Test Report Fo. R3-285A . '
.' * " . . . ' .- .7' '. '
~
october 1979 . .
~
(A.21.1) ,.'
.. - -.,.,',..B-
... ....a ;.
.~:.....
d.
GE, " Insulating Materials Product Dat'a* '5'~'*.*'#~~~~~*. p[. p-i
-*' ~'
74010A Epoxy Rosin and 74010 Epoxy
.' 'W-i .
Catalyst,' March 24, 1964, and *Effect of
,,~
- ,' ' ~~ -
Radiation on Materials * -
' - (A.24.4) ,
'~ " * -
.~.'
- e. ACME-Cleveland Development Co.
Qualification of NAMCO Controls Limit Switch - Model EA-170, Rev.1 .
I- July 24, 1978 (A.6.5, A.6.9, A.17.2) . . ,
- f. ACME-Cleveland Development Co. Test Plan '
~
r August 31, 1977 . .
(A.16.6, A.12.6, A.12.7, A.2.3, A.2.4, A.4. 4, A. 6.3, A. 6. 4, 6.6, 14.3, A.15.1, ' '
- A.15.2, A.16.8, A.19.5, A.19.6)
- g. " Comparative Beat Resistance. of Hypalon ,
and Nec; ene," by K. Whitleck -
Elastc=ers Research Division of CuPcnt (A.24.9)
- h. ES Calculatien* File Nos. 0910-204EQ-01 0910-205-Okonite-01 0910-205-Ke:ite ,
0910 205-3:W-01
- 1. EOS Repcre Nos. 04-0910-13, June 1981 04-0910-07, June 1981
- j. J. M. Allen (Mcbil Cill' .
Intter to J. Sorenson (NSP)
February 7,,1980 ,
(A.24.2)
. k. D. R. Jones (Chevron USk, Inc.) '
CorresMm!ence with A. Smith (NSP) october 30, 1979
( A.2 4.3)
. +...-
- R. E. Shoults (Westinljhouse)
- 1. -
-r$f- ' Letter to G. A. Reed (Wis-Minn Power) -
January 19, 1977 (A.24.3) g 2-d' Frank!!n Research Center .
j A W alh Fm sumane
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6,
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-RFI-C$257-502;.., Y l95.. .
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Date Received bv FRC** *
'.- - * *. . . ~ -
.D.* ..
.. .~ -
'm. B. C. Lauroesch (CE) .
. . . ~ .
- Corresponden e with J. King (GE) . '
- /, . . .f - "
August 7,1978 'j' ;
( A.24. 4) , -
- .. . .. .' v. . .m....7 .
- f. ';:/
, Z : f .'s T
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?.-
. n. GE Letter to A. Smith (ESP) *
. ' J. - '
November 21, 1978 (Attachment)~ . .
I- . -~~
( A.24. 4) ~.
- o. Robert Kantner (NAMCQ) .
_. ? -
Letter to Paul T. Aoska (NSP) I .
.. c .
November 18, 1980 -
(A.6.5, A.6.9) ,
- p. ' Nuclear Radiation and Switch Applications ---
October 7, 1974
. (A.6.7) :
- q. Honeywell Catalog 50, p. E-2 -
l (A.6.7) _ .
e r. B. Bondow (E-M) ~
I4tter to J. Sorenson (NSP) .
March 25,1980 (A.7.1)
- s. NSC Letter to NSP ,
Component Aging Evaluation September 29, 1980 ,
( A.7.1, A.24.1)
- t. Okenite Company Cest Procedure sent to Mr. Alt.echt (NSP) on April 20, 1978 .
(A.24.6.
see ma . .
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REFERENCES ..
...%. : . ; .-W. p. . , ,
.:,.. :.1.,.p o,., n o,..
2 .
,~.3._., . ._.
.A. . . .~ -
^- ?,"S. cf.. - b4..,. . ',. ., .
- 1. D. E. G11berts, L. O. Mayer- . . . . .. .
. Sm -
1 '
er , n a C . > 3.. * * .T
~4 <- .i?:gm .'".-.n: '.t ",- .3:.:-
Letter to 3. G. Ke .. -
i "C"W , g/f !"
Subject:
Pinal Response to IE Rcilgtin 79-013,' Frairie W.' .
Island Nuclear Generating PlantF;.. *
'6.- '. 7 -.. ? ? -# x.
Northern States Power Company, 31-Oct-40 ,. ' '# . - m
,[f.
R-%jg_'.'. "
{T,:,
5-a :N
. 2. ,. o.' Mayer .
Letter to NRC. Subjects Prairie Island Nuclear
- s. v.- W
- ,.w.. .
. . . l ' ,' ;',*1*4 g. '. ,*'. :
.._. Generating Plant - Response to II Sulletin 79-013 *
.'.'rt'.S ,7
Safety Evaluation Report - Q. - .-
..a. '-?.$
, .'.. . 4
. p. . .. ., ,
- '.J G . f.. ._.j'.- .--
Northern States Power Compsey/ 26-Aug-4~ . g. .
- 'i<a
. 3.
. Office of Nuclear Reactor Regulation
-;;.gg,.
Safety Evaluation Report for Prairie Island Units 1 and 2 -
.[
- Environmental Qualification of safety-Related .
Electrical Equipment 2- . .
. NRC, 12-May-81 - .. . .~
a A
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r l .
,f
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sg . .. a- . , . , , . . , . , ... .
. w
- w. .
s.gra . --
e
. E. . .
. ty-
- b Frank!!n Research Center A DhquSp giThe POWWhh h
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