to Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment.ML20050A056 |
Person / Time |
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Site: |
McGuire |
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Issue date: |
03/10/1982 |
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From: |
FRANKLIN INSTITUTE |
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To: |
NRC |
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Shared Package |
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ML20050A057 |
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.B.3, TASK-2.D.3, TASK-2.E.1.2, TASK-2.E.3.1, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.F.2, TASK-2.G.1, TASK-2.K.2.10, TASK-2.K.3.09, TASK-2.K.3.12, TASK-TM IEB-79-01B, IEB-79-1B, RFI-C5257-521, RFI-C5257-521-R02, RFI-C5257-521-R2, NUDOCS 8203300318 |
Download: ML20050A056 (8) |
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Category:CONTRACTED REPORT - RTA
MONTHYEARML20203J0921998-02-28028 February 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at McGuire Nuclear Station,Units 1 & 2, Final Rept ML20107N0371996-02-29029 February 1996 Submittal-Only Review of McGuire Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20107N0101996-02-29029 February 1996 Submittal-Only Review of Catawba Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20076K9411994-09-30030 September 1994 Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co ML20080E3711994-05-31031 May 1994 Technical Evaluation Rept on Second Ten-Year Interval Insp Program Plan ML20069L8621994-05-31031 May 1994 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Mcguire Nuclear Power Plant ML20071F8851993-08-31031 August 1993 Technical Evaluation Rept McGuire Nuclear Plant Individual Plant Exam Assessment of Human Reliability Analysis,Step 2 Review ML20091H0331991-12-10010 December 1991 Final, Technical Evaluation Rept,Mcguire Nuclear Station, Station Blackout Evaluation ML20086G5981991-10-31031 October 1991 Technical Evaluation:Core Thermal-Hydraulic Methodology Using VIPRE-01,Topical Rept DPC-NE-2004 ML20077E3661991-05-31031 May 1991 Final Review of LOCA Analysis for Duke Power Co,Catawba & McGuire Units W/B&W Fuel Co Reload Fuel BAW-10174,Rev 1 ML20059E2841990-08-29029 August 1990 Emergency Preparedness Exercise for 900814-15, Final Rept Per Insp Repts 50-369/90-15 & 50-370/90-15 ML20063P9121989-10-31031 October 1989 SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20215L7651987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Mcguire 1 & 2, Informal Rept ML20215M1151987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components, Mcguire Units 1 & 2, Informal Rept ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML20205J5841985-11-30030 November 1985 Conformance to Reg Guide 1.97,McGuire Nuclear Station, Units 1 & 2, Preliminary Rept ML20108F4841984-11-19019 November 1984 Evaluation of Detailed Control Room Design Review Summary Rept, Final Technical Evaluation Rept ML20087Q0851983-07-13013 July 1983 Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Technical Evaluation Rept ML20085F2521983-05-19019 May 1983 Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Interim Technical Evaluation Rept ML20070R4231983-01-25025 January 1983 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Vols 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20069E7991982-08-31031 August 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20064N7371982-08-31031 August 1982 Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20050A0561982-03-10010 March 1982 to Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20040G4971981-12-14014 December 1981 Request for Addl Info, Equipment Environ Qualification, Review of Licensees' Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20009E2661981-07-31031 July 1981 Mcguire Nuclear Station Unit 1 Auxiliary Feedwater System Reliability Study Evaluation ML19350B5881980-12-0101 December 1980 Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory Research ML19259B2821978-05-31031 May 1978 Transport of Radionuclides in Urban Environs:Working Draft Assessment. Analyzes the Problem in General & Specifically for New York City 1998-02-28
[Table view] Category:QUICK LOOK
MONTHYEARML20203J0921998-02-28028 February 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at McGuire Nuclear Station,Units 1 & 2, Final Rept ML20107N0371996-02-29029 February 1996 Submittal-Only Review of McGuire Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20107N0101996-02-29029 February 1996 Submittal-Only Review of Catawba Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20076K9411994-09-30030 September 1994 Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co ML20080E3711994-05-31031 May 1994 Technical Evaluation Rept on Second Ten-Year Interval Insp Program Plan ML20069L8621994-05-31031 May 1994 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Mcguire Nuclear Power Plant ML20071F8851993-08-31031 August 1993 Technical Evaluation Rept McGuire Nuclear Plant Individual Plant Exam Assessment of Human Reliability Analysis,Step 2 Review ML20091H0331991-12-10010 December 1991 Final, Technical Evaluation Rept,Mcguire Nuclear Station, Station Blackout Evaluation ML20086G5981991-10-31031 October 1991 Technical Evaluation:Core Thermal-Hydraulic Methodology Using VIPRE-01,Topical Rept DPC-NE-2004 ML20077E3661991-05-31031 May 1991 Final Review of LOCA Analysis for Duke Power Co,Catawba & McGuire Units W/B&W Fuel Co Reload Fuel BAW-10174,Rev 1 ML20059E2841990-08-29029 August 1990 Emergency Preparedness Exercise for 900814-15, Final Rept Per Insp Repts 50-369/90-15 & 50-370/90-15 ML20063P9121989-10-31031 October 1989 SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20215L7651987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Mcguire 1 & 2, Informal Rept ML20215M1151987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components, Mcguire Units 1 & 2, Informal Rept ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML20205J5841985-11-30030 November 1985 Conformance to Reg Guide 1.97,McGuire Nuclear Station, Units 1 & 2, Preliminary Rept ML20108F4841984-11-19019 November 1984 Evaluation of Detailed Control Room Design Review Summary Rept, Final Technical Evaluation Rept ML20087Q0851983-07-13013 July 1983 Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Technical Evaluation Rept ML20085F2521983-05-19019 May 1983 Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Interim Technical Evaluation Rept ML20070R4231983-01-25025 January 1983 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Vols 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20069E7991982-08-31031 August 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20064N7371982-08-31031 August 1982 Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20050A0561982-03-10010 March 1982 to Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20040G4971981-12-14014 December 1981 Request for Addl Info, Equipment Environ Qualification, Review of Licensees' Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20009E2661981-07-31031 July 1981 Mcguire Nuclear Station Unit 1 Auxiliary Feedwater System Reliability Study Evaluation ML19350B5881980-12-0101 December 1980 Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory Research ML19259B2821978-05-31031 May 1978 Transport of Radionuclides in Urban Environs:Working Draft Assessment. Analyzes the Problem in General & Specifically for New York City 1998-02-28
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20203J0921998-02-28028 February 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at McGuire Nuclear Station,Units 1 & 2, Final Rept ML20107N0371996-02-29029 February 1996 Submittal-Only Review of McGuire Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20107N0101996-02-29029 February 1996 Submittal-Only Review of Catawba Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20076K9411994-09-30030 September 1994 Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co ML20080E3711994-05-31031 May 1994 Technical Evaluation Rept on Second Ten-Year Interval Insp Program Plan ML20069L8621994-05-31031 May 1994 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Mcguire Nuclear Power Plant ML20071F8851993-08-31031 August 1993 Technical Evaluation Rept McGuire Nuclear Plant Individual Plant Exam Assessment of Human Reliability Analysis,Step 2 Review ML20091H0331991-12-10010 December 1991 Final, Technical Evaluation Rept,Mcguire Nuclear Station, Station Blackout Evaluation ML20086G5981991-10-31031 October 1991 Technical Evaluation:Core Thermal-Hydraulic Methodology Using VIPRE-01,Topical Rept DPC-NE-2004 ML20077E3661991-05-31031 May 1991 Final Review of LOCA Analysis for Duke Power Co,Catawba & McGuire Units W/B&W Fuel Co Reload Fuel BAW-10174,Rev 1 ML20059E2841990-08-29029 August 1990 Emergency Preparedness Exercise for 900814-15, Final Rept Per Insp Repts 50-369/90-15 & 50-370/90-15 ML20063P9121989-10-31031 October 1989 SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20215L7651987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Mcguire 1 & 2, Informal Rept ML20215M1151987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components, Mcguire Units 1 & 2, Informal Rept ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML20205J5841985-11-30030 November 1985 Conformance to Reg Guide 1.97,McGuire Nuclear Station, Units 1 & 2, Preliminary Rept ML20108F4841984-11-19019 November 1984 Evaluation of Detailed Control Room Design Review Summary Rept, Final Technical Evaluation Rept ML20087Q0851983-07-13013 July 1983 Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Technical Evaluation Rept ML20085F2521983-05-19019 May 1983 Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Interim Technical Evaluation Rept ML20070R4231983-01-25025 January 1983 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Vols 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20069E7991982-08-31031 August 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20064N7371982-08-31031 August 1982 Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20050A0561982-03-10010 March 1982 to Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20040G4971981-12-14014 December 1981 Request for Addl Info, Equipment Environ Qualification, Review of Licensees' Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20009E2661981-07-31031 July 1981 Mcguire Nuclear Station Unit 1 Auxiliary Feedwater System Reliability Study Evaluation ML19350B5881980-12-0101 December 1980 Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory Research ML19259B2821978-05-31031 May 1978 Transport of Radionuclides in Urban Environs:Working Draft Assessment. Analyzes the Problem in General & Specifically for New York City 1998-02-28
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20203J0921998-02-28028 February 1998 Technical Evaluation Rept on 'Submittal-Only' Review of IPEEE at McGuire Nuclear Station,Units 1 & 2, Final Rept ML20107N0371996-02-29029 February 1996 Submittal-Only Review of McGuire Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20107N0101996-02-29029 February 1996 Submittal-Only Review of Catawba Nuclear Station Individual Plant Exam of External Events, Draft Rept ML20076K9411994-09-30030 September 1994 Technical Evaluation Rept:Pumps & Valves Inservice Testing Program,Mcguire Nuclear Station,Units 1 & 2,Duke Power Co ML20080E3711994-05-31031 May 1994 Technical Evaluation Rept on Second Ten-Year Interval Insp Program Plan ML20069L8621994-05-31031 May 1994 Auxiliary Feedwater System RISK-BASED Inspection Guide for the Mcguire Nuclear Power Plant ML20071F8851993-08-31031 August 1993 Technical Evaluation Rept McGuire Nuclear Plant Individual Plant Exam Assessment of Human Reliability Analysis,Step 2 Review ML20141M2141992-03-23023 March 1992 Notification of Contract Execution,Task Order 2, IPE Reviews,Internal Events,Front End Only:Mcguire. Contractor: Science & Engineering Assocs,Inc ML20091H0331991-12-10010 December 1991 Final, Technical Evaluation Rept,Mcguire Nuclear Station, Station Blackout Evaluation ML20086G5981991-10-31031 October 1991 Technical Evaluation:Core Thermal-Hydraulic Methodology Using VIPRE-01,Topical Rept DPC-NE-2004 ML20077E3661991-05-31031 May 1991 Final Review of LOCA Analysis for Duke Power Co,Catawba & McGuire Units W/B&W Fuel Co Reload Fuel BAW-10174,Rev 1 ML20059E2841990-08-29029 August 1990 Emergency Preparedness Exercise for 900814-15, Final Rept Per Insp Repts 50-369/90-15 & 50-370/90-15 ML20063P9121989-10-31031 October 1989 SAIC-88/1943, Technical Evaluation Rept,First Interval Inservice Insp Program,Mcguire Nuclear Station Units 1 & 2 ML20196C1641988-02-0404 February 1988 Independent Assessment & Analysis, Monthly Progress Rept for Period Ending 880131 ML20237J0621987-08-19019 August 1987 Technical Evaluation Rept on Duke Power Co McGuire & Catawba Nuclear Stations Spds ML20215L7651987-05-31031 May 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components,Mcguire 1 & 2, Informal Rept ML20215M1151987-04-30030 April 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2-Vendor Interface Programs for All Other Safety-Related Components, Mcguire Units 1 & 2, Informal Rept ML20211K5101986-11-30030 November 1986 Input for Ser,Mcguire Nuclear Station Units 1 & 2,Millstone Nuclear Power Station Unit 3,Seabrook Station Units 1 & 2, VC Summer Nuclear Station,Vogtle Electric...Reactor Trip Sys Reliability,Item 4.5.2 of Generic Ltr 83-28 ML20197J4641986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Catawba Nuclear Stations 1 & 2,DC Cook Nuclear Power Plants 1 & 2,WB McGuire Nuclear Stations 1 & 2,Sequoyah Nuclear Plants 1 & 2 ML20205J5841985-11-30030 November 1985 Conformance to Reg Guide 1.97,McGuire Nuclear Station, Units 1 & 2, Preliminary Rept ML20108F4841984-11-19019 November 1984 Evaluation of Detailed Control Room Design Review Summary Rept, Final Technical Evaluation Rept ML20087Q0851983-07-13013 July 1983 Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Technical Evaluation Rept ML20085F2521983-05-19019 May 1983 Evaluation of McGuire Units 1 & 2 Undervoltage Trip Attachment Failures, Interim Technical Evaluation Rept ML20070R4231983-01-25025 January 1983 Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification SERs (F-11 & B-60), Vols 1 & 2, Technical Evaluation Rept ML20127A2891982-10-0505 October 1982 Containment Leak Rate Testing Investigations, Progress Summary for Sept 1982 ML20069E7991982-08-31031 August 1982 Control of Heavy Loads, Draft Technical Evaluation Rept ML20064N7371982-08-31031 August 1982 Reliability Analysis of Containment Strength.Sequoyah and McGuire Ice Condenser Containments ML20126F2541982-08-26026 August 1982 Containment Leak Rate Testing, Monthly Progress Rept for Aug 1982 ML20050A0561982-03-10010 March 1982 to Request for Addl Info Re Equipment Environ Qualification Review of Licensee Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20040G4971981-12-14014 December 1981 Request for Addl Info, Equipment Environ Qualification, Review of Licensees' Resolution of Outstanding Issues from NRC Equipment Environ Qualification Safety Evaluation Repts & TMI Action Plan Installed Equipment. ML20009E2661981-07-31031 July 1981 Mcguire Nuclear Station Unit 1 Auxiliary Feedwater System Reliability Study Evaluation ML19350B5881980-12-0101 December 1980 Rough Draft, Analysis of Hydrogen Mitigation for Degraded Core Accidents in Sequoyah Nuclear Power Plant, Prepared for Ofc of Nuclear Regulatory Research ML19259B2821978-05-31031 May 1978 Transport of Radionuclides in Urban Environs:Working Draft Assessment. Analyzes the Problem in General & Specifically for New York City 1998-02-28
[Table view] |
Text
.
REQUEST FOR ADDITIONAL'INFORMATION EQUIPMENT ENVIRO!NENTAL QUALIFICATIdN (EEQ)
REVIN OF LICENSEES' RESOLUTION OF OUTSTANDING ISSUES FROM NRC EQUIPMENT ENVIRONMENTAL QUALIFICATION SAFETY EVALUATION REPORTS (SER) AND 'DtI ACTION PLAN INSTALLED EQUIPMENT
~
Duke Power Company '.
McGuire Unit 1 ll NRC Docket No. 50-369 December 14, 1981 NRC TAC No. 42 538 , Rev. 1, February 23, 1982 Rev. 2, March 10, 1982 ah
. 0. Franklin Research Center t A Division of The Franklin Institute 1 yg33o0,3 h sevrrun FrarMn Parkway. PNia Pa. 19103 (2)S)444.1000
. + 9 s RFI-C52 57-521 Rev. 2, March 10,1982 BACKGROUND of Philadelphia, Pa. is providing assis-Franklin Research Center (FRC) for the equipment tance to the U.S. Nuclear Regulatory Commission (NRC)
FRC will environmental qualification (EEQ) review of operating reactors.
perform an EEQ review of the Licensee's 90-day response to outstanding issues from the NRC Equipment Environmental Qualif1 cation Safety Evaluation Report (SER) and the installed MI Action' Plan equlpment.
~
The review will be limited
- } The to safety-related equipment potentially exposed to a harsh environment.
results will be presented in the form of a technical evaluation report for each plant.
This request for additional information (RAI) is the result of an 17, 1981
evaluation of the information provided by the letter dated August
[1].* FRC previously requested MI Action Plan information by telephone memorandum dated September 8, 1981 [2].
On January 26, 1982, Duke Power submitted a letter concerning the_
t The Licensee qualification schedule for Rockbestos RSS-6-104 cable [51 stated that the cable currently installed for the in-containment high range
'i radiation monitor is unqualified and will be replaced by the new cable if it_
..a is certified by June 1982. (1} **
~'.
g -
A. FRC REVIEW OF THE LICENSEE'S 90-DAY RESPONSE TO THE NRC E DATE RECEIVED BY FRC***
INFOH4ATION REQUMTED l..
In reference to the Licensee's 90-day response [1] to the NRC SER [3], a legible
- single copy of each of'the following l
qualification documents is requested in order that the PRC evaluation may proceed:
- Numbers in brackets refer to citations found in the list of refe
- Throughout the text, in which the underlined material preceding the superscript was added.
- This column will be completed by FRC as the requested information is received.
A .
00bhranklin Research Center A DMe.an of The Frer+sn humame
' RFI-C5257-521 Rev. 2, March 10,1982 DATE RECEIVED BY FRC***
. a. WCAP-9885 Pages IC, 2C, 3C
- b. Duke Letter, Parker to Denton December 19, 1979 Pages 4C, SC
- c. Joy / Reliance Test Report FF-14282 Pages 7C, SC - .
- d. Supplemental Technical Paper TA-4081 Pages 7C, 8C
- e. Joy / Reliance Test Report NUC-9 Supplement, 4/14/80 Pages 7C, 8 i
i'
- f. Valcor Test Report QR-57300-5220-1-1 .
i May 15, 1979 Page llc
- g. Solon Test acport A293-80 Page 15C 1
Solon Test Report A294-80 l!' h.
Page 15C l!
3 1. D. G. O'Brien Test Report ER-252 Page 16C
- j. D. G. O'Brien Test Report ER-227 Page 16C
- k. D. G. O'Brien Test Report ER-2 47 Page 16C ,
- 1. Okonite Test Repor.t N-1 ,
Page 17C
- m. Okonite Test Report FN-1 Page 17C ..
~'
- n. Okonite Test Report 110E Page 17C
- o. Okonite Test Report K-O-1, September 1979 Page 18C nklin Research Center A OMnen of The Fm m
, . 2 e
o-RFI-CS2 57-521 Rev. 2, March 10,1982 DATE RECEIVED BY FRC***
- p. Namco Test Report, March 3,1978 Page 23C
, q. Namco Test Report, February 20, 1978 Page 23C
- r. 3M Test Report 44390-1 Rev 4, Page 24C
- s. Memo to File: MC-1362.03, July 9,1981 Pages 4R, 6R, 7R
- t. Reliance Letter, 8/3/80 Page 32R, 34R
- u. Gould Report OH-302-618 Page 36R v.
Nelson Electric Letter 6/27/80 Page 37R ..
- w. Westinghouse Transformer Div. Report 11/11/77
- x. Westinghouse Life Statement, 11/14/77 Page 38R
- y. Micro Switch Report Letter 615027-1 Page 40R
- z. Barton Test Report 43904-1 Page 41R aa. Duke Analyses on Westinghouse Testing:
MCC 1381.05-00-0101, MCC 1381.05-00-0102 .
i Pages lH, 2H, 3H, 4H, 5H bb. M. L. Ward, Letter"to File MCM 1320.*00 7/17/80 Page 6H cc. Bussman Manufact'uring Report, 3/13/79 -
Pages 10H, llH,12H," 13H dd. Duke Steam Production Qualification Test Facility Report TR-028 Page 25H A 0000 Franklin Research Center A Dmesan of The Frerden busquie
~~~
-- . ~ , . - _ - - . - .
o RFI-C52 57-521 Rev. 2, March 10,1982 DATE RECEIVED BY FRC***
ee. :Sotort Test Report TR3025, April 1980
. Page 29H ff. NAMCO Tes16Caeport for EA-170-302, 3/28/80 Page 30H B. FRCt; REVIEW OF INSTALLED MI ACTION PLAN ITEMS INFORMATION REQUESTED DATE RECEIVED BY FRC***
- 1. ReferAnce. A 4Qes not provide adequate detail
.with.Tespectato identification of MI Action Plan /pquipment installed as of 1/1/81.
- a. Identification of all M I Action Plan equipment installed as of 1/1/81 is requested. -
- b. ; Identification of MI Action Plan
! .; equipment installed with implementation l ; dates after 1/1/81 is requested.
- c. The coryplation of these equipment items with thyr specific sections of NUREG-0737
[4] presented below (as applicable) is ,
requested.
For PWRs, Sections:
1 y IIEl.2, IIE4.2, IIE3.1, IIG1, IIF2, n . IID3, IIK2.10 (B&W), IIB 3, IIE4.1.
s IIK3.12 (WX) , IIK3. 9 (WX) (2 )
3 [The correlation is needed to ensure 3d that all items are included _ in the
- ;t review, e.g., if a transmitter is M identified as -a MI ' Action Plan
- item, d- are the cable and terminal blocks z associated with the device also identified?] -
- d. Forall installed MI Action Plan equipagghddentified, a System Component Evaluation Worksheet (SCEW) (in accordance with 79-OlB format) is requested.
A 000hranklin Research Center
^ * =' N T
~
. RFI-C52 57-521 j
1 .
Rev. 2, March 10,1982 l
l l DATE RECEIVED BY FRC***
- e. FRC requests that Duke insure that the environmental conditions are specified for all 'IMI Action Plan equipment to be '
reviewed, e.g., the postulated accident condition including profiles and also the ~ "'
normal service conditions.
t ... .. . . .
f .' 'The' approximate , installation date for the .. .. _
, 'IMI Action Plan equipment items is * *
' requested so that the appropriate qualification criteria (NUREG-0588 or DDR ~ ~-
' Guidelines) can be used in the EEQ edaluation. (FRC previously requested this information in Referer.ce 3.)
l 2. The qualification documents, e.g., the actual 1
test reports and associated correspondence cited as evidence of qualification listed on -
the SCEW sheets, for all identified '!hI _
Action Plan equipment are requested. ~ [The ~ '
identification of those reports considered to be proprietary is requested so that proper control of documents can be maintained.]
- 3. Where'the Licensee has a standard Owners' Group position with respect to a NUREG-0737 technical area or has requested extensions of i implementation dates, this information is requested'in order to incorporate it into the l review.
C. INSTRUCTIONS FOR TRANSMITTING INEURMATION REQUESTED
- 1. The schedule for completion of the FRC assignment requires that the
! Licensee provide the redpiested information within 3 weeks of the date of f the RAI.
- 2. The Licensee may transmit the requested information as follows:
o complete package,directly to the NRC project manager or -
o copy of cover letter to NRC project manager and complete package to FRC.
4000d Franklin Research Center A DMe.on of The Franen kwamme
RFI-C525[-521 Rev. 2, March 10,1982 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 Telecopy No. 215/448-1296 Telecopy Confirmation No. 215/448-1215 l
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00 Franklin Research Center -
A Ome.an of The FM %
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RFI-C52 57-521 Rev. 2, March 10,1982 REFERENCES
- 1. W. O. Parker, Jr.
Letter to H. R. Denton and E. G. Adensam, NRC.
Subject:
McGuire Nuclear Station, Environmental Qualification of-Equipment, Response to NRC Staff Safety Evaluation Report Duke Power Company, 17-Aug-81 l 2. 141ephone Memorandum C. J. Crane, J. A. Murphy (FRC) with N. B. Lee (NRC) , S. Cbpp (Licensing; Duke Power), D. Murdoch (EEQ Engineer), T. Harrell (EEQ Engineer)
Subject:
Request for Information, McGuire Unit 1
. 8-Sep 3. Office of Nuclear Reactor Regulation Safety Evaluation Report for McGuire Unit l' Environmental Qualification of Safety-Related Electrical Equipment NRC, 17-Apr-81
- 4. NUREG-0737, " Clarification of 1MI Action Plan Requirements" NRC, November 1980 h W. O. Parker, Jr. ~
l Letter to J. P. O'Reilly, NRC.
Subject:
McGuire Nuclear Station Unit 1; Delay in Installation of Environmentally Qualified Cable for In-Containment Radiation Monitor Duke Power Co., 2 6-Jan-82 tl) '
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