|
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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
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y . .: .
OBallellet Pacific Northwest Laboratories ~
1 l Battelle Boulevard -
' P.O. Box 999 Richland, Washington 99352 -
Telephone (509) 375-3782 August 29,-1990 Mr. K. S. West
! Planning, Program, and Management. Support Branch l: Office of Nuclear Reactor Regulation.
I' U.S. Nuclear Regulatory Commission :
Washington, DC 20555
Dear Steve:
FIN B2311 - MCGUIRE EMERGENCY PREPAREDNESS EXERCISE - AUGUST 14-15,- 1990 -
(Inspection Report 450-369,370/90-15) . ,
Enclosed is the final report of the Pacific Northwest Laboratory (PNL) ,
observation during the subject exercise. Only minor-changes have beer, made to-I the-draft;provided to the NRC team leader at the site.
l If you have any questions regarding this-report please contact me on ;-
(509) 375-3782.
Sincerely, c ..
j J cm%
J. D. Jamison, Project Manager #
Operational Health Physics' Occupational & Environmentai Health Protection Section HEALTH PHYSICS DEPARTMENT JDJ:jw -
In triplicate Enclosure cc: RA Erickson, w/ enclosure
'ED Testa, w/ enclosure .
9009100119 90os29 T pDR ADOM 0 % g .
kenty-Ave yws of science ' Ibr DOE and the &rthwest
- ~~
TE35 ;
'h .
MCGUIRE EMERGENCY PREPAREDNESS EXERCISE (Ins'pection Report #50-369,370/90-15)
August 14-15, 1990 A. Name: Glenn-Arthur B. Assignment: Control' Room (CR) for. medical drill on August 14; Simulator CRandTechnicalSupportCenter(TSC)onAugust15.
'C. Site Personnel Contacted: B. McRee, Exercise Director; D. Miller, Lead Controller, Simulator CR; C. Jennings, Lead Controller TSC; R. Tracey, Shift Supervisor (SS) - Medical Drill; A. Perdue, Senior Reactor Operator (SRO), Medical Drill; W. Johnson, Communicator for Medical. Drill'=and -
Exercise; G. Pickler, SS -Simulator; T. McConnell, Emergency Coordinator (EC); R. Leonard, Emergency Preparedness Director D. Positive Findinos
- The SS and SR0 for the medical drill- and all members of the j simulator CR shift performed exceptionally well. Detailed use of l
procedures, coordination between individuals, and_ good. command and l l
control were demonstrated in a quiet, competent manner.. l l
- -The EC and his assistants in the:TSC worked as a highly knowledgeable and smoothly functioning team. Pcoblems were aggressively pursued, potential solutions evaluated, and alternative proposals generated. Proposals were evaluated with approximate time lines to establish priorities. A highly effective,~ professional management atmosphere existed.
1 i
.c .
r E. Negative Findinos '
u
- Coolant sampling procedure does not exist for overriding or
! i bypassing isolated sampling valves. The inabili.ty to obtain a sample prevented core damage assessment.
'
- Excessive use of the announcing system by the EC in the TSC resulted in personnel apparently igt...ing his announcemt .cs. At one point, there were three different groups having intensive conversations / '
discussions immediately adjacent to the EC's desk during.one of' hic announcements.
- The clocks in the TSC were not synchronized. Two- and four-minute differences were noted between three clocks in the TSC, EC area, and dose assessment area.-
- A plot of the radiological plume was not posted in the TSC. -The i
radiation monitoring field teams reported information to be used to ;
generate a plot and a plume discussed, but the visual plot'was not established.
Swipes for determining contamination levels and personnel radiation monitoring of personnel returning to the Operational Support Center (OSC) and TSC hallway were warranted, but not performed. .0SC teams were dispatched to areas in-plant where contamination should have been expected for this scenario.
The capability to trend critical parameters was nct demonstrated.
An attempt to keep track of various pressures, temperatures, and levels of importance on a status board was made, but it confused
, -rather-than clarified the rate of change of different parameters.
2 i
9, - -
F. Chronoloay - Medical Drill Time Observation '
0855- -Arrived in CR. !
0912- SS in CR notified of three personnel. injured in new building containing shredder; SS stated it was a drill. ,
0943 SS heard on in-plant radio system that an ambulance was >
entering the protected area. SS had not been notified that an ambulance been requested. He heard on the radio that a second ambulance had been requested.
0949 SS informed by telephone of the' individual personnel injuries and that all were contaminated.- SS will be notified if i 1
injured personnel requiring hospitslization can not be decontaminated prior to transfer by. ambulance to the hospital.
1007 SS notified that an injured contaminated man had to be transferred by ambulance to a hospital. Emergency Action l Level (EAls), event classification, and eme'rgency notification procedures immediately obtained and put into use. I 1 1 i
1010 Medical Emergency Response Team-notified SS that two contaminated, injured men were being t'ransferred by ambulance to Charlotte Memorial Hospital. 'SS -directed SRO to notify; !
hospital that these two men would be arriving.
1011 Checklist.being followed and-Emergency-Notification form being l
l completed. Unusual Event (UE) declared.
1015 SS going over completed e.aergency notification message with l Communicator, l
3
Time' Observation 1018 Communicator made call-up for notification. Message being transmitted.
1023- Transmission of notification completed.- Good procedure and voice by communicator.
1028 Nuclear Regulatory Commission (NRC) being notified by SS. j 1029 NRC notification completed.
_j 1041 Mcurity telephoned SS with names of all three injured j personnel and notified SS that all three are contaminated and being transferred by ambulance to hospital.
1043 Notification update sent-to include three contaminated, j injured personnel being transferred to the hospital.
1046 NRC notified of three personnel being sent to hospital.
G. Chronology - Exercise Time __. Observation 1045 Arrived in simulator CR.
1105 Players being given initial conditions. Start of exercise 1 delayed due to telephone problems which have been corrected.
1113 Simulator started, i 1119 Pressurizer level decreasing sligh+.ly. Makeup has increased.
Procedures are out and being implemented.
1120 Radiation alarm on C steam generator (SG) steam line.
1122 Pressurizer level being maintained. Reducing power at 5 mega-watts per minute. SS announced tube leak on C SG on public announcingsystem(PA).
4
- )
Time Observation 1123' SS checking technical 'specificatio.is and EALs. Good use of l procedures in CR and good coordination. I 1128 SS discussing tube leak' age in SG with SRO:and plant operators.-
Leakage is 50 gpm or greater. SS declares an Alert. SS is q filling out emergency notification' message. Procedures beiu, .q followed and good communications and cooperation by all shift ,
personnel.
1132 SS informed that resident inspector heard page'and is.enroute ,
to the CR. SS has completed notification message and given to-
'the communicator. <
1135 Call-up completed. One' station did not~ answer. Communicator-proceeding with notifying stations on the line.- Good clear.
voice and procedure use by the communicator.
1139 Notification completed except for county that did not initially respond. Call-up made and notification.being made to that county. !
i 1144 Plant Manager arrivod 'in CR. Being briefed by SS, who is i- using Alert procedure and relief check-off lists. l 1149 SRO checking EALs to determine if radiation alarms existing. 1 would qualify for classification upgrade. Plant Manager told no other EALs are currently being met.
1153 Plant Manager has relieved as Emergency Coordinator, after ai thorough review of plant status, good use of check-off sheets,.
and status reports on procedures being'used.
5
e f Time Observation 1154 EmergencyCoordinator(EC)--hasdirectedthattheTSCbe briefed and that communicator. in TSC notify NRC. i
~
1159 EC still in CR going over Alert notification message that was-transmitted.
1200 EC announced that he is satisfied with his knowledge of plant status and that he was-proceeding to the TSC. He directed ,
that-problem / simulator be stopped until he arrived-at TSC. !
Simulator was stopped.
1207 Departed CR. Enrouw by car to TSC. )
=t 1212 NRC notified of Alert. (Taken-fromcommunicator' slog.)
1218 Arrived in TSC. EC making a status briefing on the PA. i 1225 EC discussing best method to reduce reactor power, trip or i controlled power reductior . :Latter selected as former could induce add hfonal shock and cause SG tube rupture to increase in size.
1226 EC on PA discussing power reducticn and dose readings at site boundary, 0.15 mR/hr.
i' 1229 Accountability requirements and need for site assembly being discussed.
1232 EC on PA. Increased rate of power reduction to get plant- 4 conditions necessary to isolate C SG, Rapidly decreasing- l pressurizer level.
1233 Plant page announcing reactor trip.
1236 CR reports hearing noise that is steam leaking in the a i
doghouse.
6 .;
3 1
,g u -- -, ----
Time ' Observation ,
1237 Safety Injection- (SI)' manually initiated, due to. low and L ' decreasing level in pressurizer.
1241 EC'on PA. 1A ND pump failed to start on SI.
1243 SAE requirements being discussed. - 'I 1245 EC directed CR to conduct Site Assembly. VC/YC Ic3t in CR.
1247 EALs being examined and discussed.
1250 EC on PA. A SG relief valve has lifted. Checking to '
determine which one. Noise monitor alarm on C reactor coolant pump, followed by the pump-stopping. Fuel damage possible.
Primary sample requested.
1253 EC on PA. Field teams have not detected radiation or contamination, but calculated dose rates are .1 mR/hr at site
~
boundary.
1256 C SG code safety relief valve stuck open.
1257 Alarm and site assembly directed on PA.
3 1259 Good discussion at EC desk on SAE requirements using EAls.-
1301 EC declares SAE due to tube leak and steam reli.ef open on C- ,
SC. . Interrupted PA announcement to discuss feeding C SG.
1304 EC now continues 1301 PA announcement.
1308 Four minute difference in clocks.
1309 Simulator is down. Using hard copy data..
1312 EC read and signed SAE emergency notification message.
1313 Discussion on how to establish cooling to CR.
1316 . Simulator is running. EC notified TSC.that bad data may have been received the past 8-10 minutes.
7 I
'l Time: Observation
' 1318 = VC/YC (CR cooling system).is out.of commission due to low oil. l A maintenance person has suffered heat exhaustion, not (
contaminated,.enroute to hospital.
1322 EC is reviewing press release. Alarm'again for Site Assembly. L EC discussing Protective Action Recommendations (PARS).
Directed review of dose rate limits required to go to General Emergency (GE).
s 1331 Field teams reported a 100 mR/hr reading.
1332 Site Assembly completed. All are accounted for.
1340 EC on PA. Three groups in the immediate vicinity are i
continuing their discussions and not listening to the'EC's announcement.
1342 EC on PA. Dose assessment personnel not listening either.
VC/YC (CR cooling system) returned to operation.
1348 Good roundtable discussion between EC and superintendents concerning EAls.
1355 EC on PA. SAE conditions still exist. Approximately 1% fuel damage has occurred. PARS may be necessary,'due to continued I discharge resulting-in accumulated dose to personnel offsite.
L 1415 Level in C SG increasing. Person dispatched to see if relief valve is shut.
1416 EC announces that indication of nuclear. reactor coolant system (RCS) and C SG pressures-equalizing indicate the' steam valve that lifted has reseated. C SG release has been cerminated.
The attempt to trend steam generator levels, pressures, and 8
_ g .-
Time- -Observation '
RCS pressures and temperatures using the TSC status board.was crude land would be confusing.to others who were not involved ;
in the attempt. Status board was not always correct in. '
listing equipment degraded, p-oblems and' times to be Corrected.
1436 EC downgraded to an Alert.
1440 E:necise terminated.
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