Similar Documents at Cook |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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ML17325B6061999-05-21021 May 1999 Proposed Tech Specs Revising Limitations on Positive Reactivity Additions ML17325B5891999-05-0707 May 1999 Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program. ML17325B5901999-05-0707 May 1999 Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys. ML17325B5551999-04-19019 April 1999 Proposed Tech Specs 3/4.8.1.2, Electrical Power Systems & Associated Bases,Providing one-time Extension of 18-month Surveillance Interval for Specific SRs ML17325B4671999-03-0303 March 1999 Rev 5 to Cook Nuclear Plant Restart Plan. ML17335A3581998-12-0303 December 1998 Proposed Tech Specs 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases,Reflecting Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A3681998-12-0303 December 1998 Proposed Tech Specs,Adding New TS Re Distributed Ignition Sys ML17335A3651998-12-0303 December 1998 Proposed Tech Specs 3/4.7.7, Sealed Source Contamination & Associated Bases Addressing Revised Testing Requirements for Fission Detectors ML17335A3621998-12-0303 December 1998 Proposed Tech Specs Removing Obsolete Info to Provide Consistency Between Units 1 & 2 to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17325B4431998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr ML17335A4071998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. ML17335A2781998-10-0808 October 1998 Proposed Tech Specs Sections 3.3.3.8 & 3.3.3.6,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2691998-10-0808 October 1998 Proposed Tech Specs 3.4.1.3 Re Reactor Coolant Loop Requirements in Modes 4 & 5 ML17335A2651998-10-0808 October 1998 Proposed Tech Specs Changing Containment Sys TS Bases 3/4.6.1.4, Internal Pressure & 3/4.6.1.5, Air Temp. ML17335A2341998-09-14014 September 1998 Proposed Tech Specs Page 3/4 5-6,revising Runout Limits for SI Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A2301998-09-12012 September 1998 Rev 3 to Cook Nuclear Plant Restart Plan. ML17335A2721998-09-0404 September 1998 Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project. 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ML17333A8301997-03-26026 March 1997 Proposed Tech Specs Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8331997-03-26026 March 1997 Proposed Tech Specs Involving Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted in Prior Amend ML17333A8261997-03-26026 March 1997 Proposed Tech Specs Removing Administrative Controls Related to Quality Assurance Requirements IAW Guidance of Administrative Ltr 95-06 ML20135C3781997-02-24024 February 1997 Revised Proposed Tech Specs Page Re 3/4, Limiting Condition for Operation & Surveillance Requirements ML17333A7161996-12-20020 December 1996 Proposed Tech Specs Change to Allow for Repair of Hybrid Sleeved SG Tubes in Response to RAI ML17333A7151996-12-20020 December 1996 Proposed Tech Specs 3/4.4.10 Re Reactor Coolant Sys ML17333A5161996-07-22022 July 1996 Proposed Tech Specs,Informing Operations Superintendent Will Have to Hold SRO License,Have Held Senior Operator License or Been Certified to Have Senior Operator Knowledge ML17334B5951996-07-11011 July 1996 Proposed Tech Specs,Supporting Operation of Facility at Increased Core Rated Thermal Power of 3,588 Mwt ML17333A4771996-06-19019 June 1996 Proposed Tech Specs Re Voltage Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking,Per GL 95-05 ML17333A4841996-06-11011 June 1996 ISI & Testing. ML17333A4651996-06-11011 June 1996 Proposed Tech Specs Re Administrative Controls Related to QA 1999-09-23
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17325B5901999-05-0707 May 1999 Rev 1 to PMP 7200.RST.006, Expanded Sys Readiness Review Program for Level 2 Sys. ML17325B5891999-05-0707 May 1999 Rev 5 to PMP 7200.RST.004, Expanded Sys Readiness Review Program. ML17325B4671999-03-0303 March 1999 Rev 5 to Cook Nuclear Plant Restart Plan. ML17335A4071998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. ML17325B4431998-11-0202 November 1998 Rev 4 to Cook Nuclear Plant Restart Plan. with 981216 Ltr ML17335A2301998-09-12012 September 1998 Rev 3 to Cook Nuclear Plant Restart Plan. ML17335A2721998-09-0404 September 1998 Rev 0 to PL-CNSI-98-007, Transportation & Emergency Response Plan for DC Cook Unit 2 SG Project. ML17335A2751998-09-0202 September 1998 Rev 1 to ER-98-012, Evaluation of Dose Rate from U-Tube End of DC Cook SG Lower Assembly. ML17335A2731998-08-21021 August 1998 Rev 0 to ST-307, Structural Evaluation of DC Cook Unit 2 Sgla Package. ML17334A7301998-05-0606 May 1998 Rev 2 of Cook Nuclear Plant Restart Plan. ML17325B5271998-04-0707 April 1998 Rev 1 to Cook Nuclear Plant Restart Plan. ML17334B8041998-04-0303 April 1998 Rev 1 to Valve IST Program for DCP Third 10-Yr Interval. ML17325B5261998-03-0707 March 1998 Rev 0 to Cook Nuclear Plant Restart Plan. ML17333A4841996-06-11011 June 1996 ISI & Testing. ML17333A4701996-02-0808 February 1996 In-Service Pump Test Plan, Units 1 & 2 ML17334B5661995-11-30030 November 1995 Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class,1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 1, Final Plan ML17334B5671995-11-30030 November 1995 Vols I & II of Third 10-Yr Interval Long-Term Inservice Exam Plan for Class 1,2 & 3 Sys & Components for DC Cook Nuclear Plant,Unit 2, Final Plan ML17332A2521994-08-0303 August 1994 Rev 3 to Plant Manager Procedure (PMP) 12 PMP 3150 PCP.100, Radwaste Pcp. ML17332A2491994-08-0303 August 1994 Rev 7 to Plant Manager Procedure (PMP) 12 PMP 6010 OSD.001, Odcm. ML20063K0631994-02-11011 February 1994 Change Sheet 1 to Rev 5 to Plant Manager Procedure (PMP) 12 PMP 6010 RPP.304, Use of HEPA Vacuum Cleaners. W/ Updated Index,Page 14 ML17331B0441993-11-0909 November 1993 Rev 15 to Emergency Response Manual. W/931109 Ltr ML17334B4851993-08-0909 August 1993 Rev 14 to Emergency Response Manual. W/930809 Ltr ML17334B4821993-04-0202 April 1993 Rev 3 of Pump Inservice Test Program. ML17329A5431992-06-11011 June 1992 Change Sheet 7 to Rev 6 to Procedure PMP 2080 EPP.107, Notification of Plant Personnel. ML20077S7281991-03-14014 March 1991 Rev 3 to PMP 6010.OSD.001, Odcm ML17325B3791990-03-0101 March 1990 Change Sheet 1 to Rev 3 to Procedure PMP 2080 EPP.106, Initial Offsite Notification. ML17334B3551990-02-0505 February 1990 Rev 2 to DC Cook Nuclear Plant Units 1 & 2 Inservice Testing Pump Program. ML17334B3561990-02-0505 February 1990 Rev 3 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program. ML17334B3571990-02-0505 February 1990 Rev 3 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program. ML20246M2191989-03-21021 March 1989 Procedure MS-3.2.1.9-1B, Maint & Surveillance Ite Medium Voltage Switchgear Equipment ML17325B0511988-12-0909 December 1988 Interim Acceptance Criteria for Safety-Related Piping Sys. ML17334B1491987-10-0505 October 1987 Rev 2 to DC Cook Nuclear Plant Unit 1 Inservice Testing Valve Program. ML17334B1501987-10-0505 October 1987 Rev 2 to DC Cook Nuclear Plant Unit 2 Inservice Testing Valve Program. ML20212A3191986-10-0202 October 1986 Rev 1 to Procedure 12 PMP 4021 TRP.001, Reactor Trip Review ML17324A9301986-05-29029 May 1986 Rev 0 to Procedure 1MHP2140.082.001, Maint Procedure for Repowering RHR Pump. ML17324A9321986-05-29029 May 1986 Rev 0 to Procedure 1MHP2140.082.003, Maint Procedure for Repowering Pressurizer Backup Heaters. ML17324A9331986-05-29029 May 1986 Rev 0 to Procedure 1MHP2140.082.005, Maint Procedure for Repowering Containment Valves. ML17324A9341986-05-29029 May 1986 Rev 0 to Procedure 1 Thp 6030 IMP.304, Pressurizer PORV Cable Repair. ML17324A9351986-05-29029 May 1986 Rev 0 to Procedure 1 Thp 6030 IMP.305, App R Post-Fire Repowering of In-Containment Valves. ML17334A9711986-05-22022 May 1986 Rev 0 to Procedure 12-OHP 4023.100.001, Unit 1 Emergency Remote Shutdown. ML20213F6011986-05-15015 May 1986 Rev 1 to Procedure PMP 6010.OSD.001, Offsite Dose Calculation Manual ML17324A9001986-05-0101 May 1986 Rev 1 to Procedures Generation Package,Part Iv,Training for Donald C Cook Nuclear Plant Emergency Operating Procedures. ML17324A8991986-05-0101 May 1986 Rev 1 to Procedures Generation Package,Part Ii,Writers Guide for Donald C Cook Nuclear Plant Emergency Operating Procedures. ML17324A8971986-05-0101 May 1986 Rev 1 to Procedures Generation Package,Part I,Specific Technical Guidelines for Donald C Cook Nuclear Plant. ML18005A0161986-05-0101 May 1986 Rev 1 to Procedures Generation Package,Part III, Verification/Validation for Donald C Cook Nuclear Plant Emergency Operating Procedures. ML20195C5361986-03-15015 March 1986 Public Version of Emergency Response Manual for DC Cook Nuclear Plant ML20141D7121986-02-28028 February 1986 Rev 0 to Master Insp Plan ML20137J6061985-12-17017 December 1985 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 2 to Erp 2.07, Outside Agency Liaison, Rev 1 to Erp 2.08, Initial Assessment Group Runner & Rev 2 to Erp 5.01.W/860117 Release Memo ML17334A9441985-11-0505 November 1985 Change Sheet 1 of Rev 9 to Spec DCCFP101QCN, Matl & Application Spec - Initial & Repair Installations, Revising App D Silicon Foam Scope of Work to Identify New Fire Barriers & for Cross Referencing Fire Zones ML17334A9191985-10-15015 October 1985 Implementation Plan of Reg Guide 1.97,Rev 3 for Donald C Cook Nuclear Plant Units 1 & 2, Status Rept 1999-05-07
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- INDIANA & AHICHIGkN ELECTr1/C COMPANY DONALD C. COOK NUCLEAR PLANT Instruction or Procedure Temporary Sheet This temporary sheet applies to Activation and Operation of the Emergency TEMPORARY Y " "*
Instruction or Pr e[ur PMP 2081 EPP.022 Revision No. 3 @1i g- [
The following change ( ) new requirems.7t ( X ) shall be July 27,1983 instituted effective (Date) , ,
- 1. Substitute page 2 of 5 with page 2 of 5 TP-1.
- 2. Substitute page 3 of 5 with page 3 of 5 TP-1.
- 3. Substitute page 4 of 5 with page 4 of 5 TP-1.
- 4. Substitute page 5 of 5 with page 5 of 5 TP-1.
- 5. Revise List of Effective Pages Reason: Clarify conditions identified during an Emergency Plan Drill and keep the procedure intact with the page for page substitution (due to different typing from the word processor.)
I l
This change should be made a permanent revision to the Instruction or Procedure:
11YES ONO O NOT KNOWN, additional review required
! Expiration Dat - Procedure Revision Standard Dist. List No.:
Originator: < d[Id - Distribution:
bhnagement Staff: lC'bWWW Senior Rextor Operator:k_d= - <c--
PNSRC E W etDn ._ D -A1-R3 Plant htuuger/MMutM4D ite 7 - 4 '7 O
, XOO Form No. 4330 REVISED 7/-
- 8309160022 830907 WHrrE - ORIGINA!.
CANARY - ORIGINATOR COPY PDR ADOCK 05000315 - w Rm cory ronM No. ruz 201w REv.2 F PDR rinx
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PMP 2081 EPP4022' ,
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2.3 The Emergency Operations Facility is a support facility
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established for the purpose of performing the above' functions. The EOF shall have appropriate' technical ~
data information and plant records to assist in'the -
- diagnosis of plant conditions to evaluate the potential or actual release of radioactive materials to the
. environment. An Assistant Plant Manager ia this center shall organize and manage I&M support (dose assessment, communication, and radiation protection) resources to support the TSC and control room operators.
3.0 LIMITATIONS AND PFECAUTIONS 3.1 The Emergency Operations Facility shall be activated as necessary for any emergency condition and specifically for' Site Emergencies and General Emergencies. This procedure covers the operation of the EOF until estab'.i-hrent of the AET Energen:y Resporse Organization on-site and/or until deactivation of the EOF.
4.0 INSTRUCTIONS
- 4. l' Upon recognition of the need far, or desirability of
/ activating the EOF, the On-Site Emergency Coordinator
%(, .. shall direct the Communications Director to initiate PMP 2080 EPP.008, Initiating Manning of Emergency Response Facilities and Calling Off-Duty Plant Personnel for the purpose of staffing the E0F.
4.2 Securit', Pe:sonnel are 7xpecte3 ta be the first to arrive at the EOF. Upon arrival, they should perform the following:
4.2.I Unlock Lh.: 60F.
NOTE: During drills, the EOF can be locked open by holding the pushbar TP-1 in and lock it in that position with the door key.
4.2.2 Turn on the radiation monitor. Instructions are posted on the monitor.
4.2.3 Turn on the copier machine.
4.2.4 Establish a log of personnel in the EOF by logging the arrival and departure of al,1.,
personnel. , 4 p
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s Page 2 of 5 Rev. 3 TP-1
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.t Is PMP 2081 EPP.022 4.3 The Radiation Control and Waste Handling Manager shall manage I&M support activities (dose assessment, 3 communications, and radiation protection) from the EOF,
. and interface with the On-Site Emergency Coordinator.
[ Specifically, the RCWEM shall:
4.3.1 Oversee activation of the EOF. See Emergency Plan Procedures, Appendix A, for work space assignments and telephone number.
4.3.2 Establish communications directly as needed, s with the OSEC for the purpose of managing I&M response to the event.
4.3.3 Ensure the EOF assumes responsibility for
.. communication with off-site organizations.
4.3.4 Ensure the EOF assumes dose assesrment and protective action decision-making responsibilities.
NOTE: See PMP 2081 EPP.003, Follow-Up Off-Site Communications, for the conditions and procedure for transfer of communications and dose assecsment to the EOF from the TSC.
4.3.5 Coordinate I&M and Federsi, State, and local response to the event via:
4.3.5.1 Information passed both ways through the communicators.
4.3.5.2 Providing a location for Berrien County, State of Michigan, FEMA, NRC, and AhPSC per.vsunel to coordinate activitie.4 4.3.6 Complete the top portion of PMP 2081 EPP.020, Exhibit C, for use by the Radiological Assessment Director.
4.3.7 Ensure any changes to the " Recommended Emergency Actions for State or County Agencies", listed on Exhibit C, are approved
,by the Recovery and Control Manager prior to-release. to off-site organizations. This function shall be performed by the Radiation Control and Waste Handling Manager prior to the Recovery and Control Manager's arrival.
e Page 3 of 5 Rev. 3 TP-1
. PMP 2081 EPP.022 4.3.8 Ensure Exhibit C is normally developed and
. distributed every 15 minutes.
4.3.9 Remain cognizant of the activities of the Radiation Protection Manager in response to the emergency.
4.3.10 Ensure that security controls are established at the EOF.
4.4 The Communications Director shall perform the following functions:
4.4.1 Establish a chronological history log of events and make this log available to comadnications, dose assessment, radiation protection, and other EOF personnel.
NOTE: The telecopy operator or the runnet shall keep tae 3-ring binders provided for AEPSC personnel and the NRC personnel TP-1 up-to-date. These binders will contain Exhibits B and C as well as the chronological history log.
/ 4.4.2 Ensure that detailed event data, PMP 2081
\, _ EPP.020, Exhibit B, is made available regularly to communications, dose assessment, and radiation protection personnel. No rmally this data will be provided every fifteen minutes by telecopier from the TSC.
4.4.3 Ensure the communicators, dose assessment, and radiation protection personnel are li r e.ay h t up-tn-date regardia;; event <ht 3 ul in .aation required to pert'ca.a their functions.
4.4.4 Establish communication with the Berrien Ccunty Sheriff's Department, Michigan State Police, Nuclear Regulatory Commission (Emergency Notification Sys*em and Healtb Physics Network), American Electric Power Initial Assessment Group, and Public Affairs.
Assume responsibility for this function from the TSC.
Page 4 of 5 Rev. 3 TP-1
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. ,- PMP 2081 EPP.022 4.4.5 Assign an individual, the runner if available, to distribute two sets of flow diagrams and one-line diagrams to the Public Affairs Communication Desk and the Recovery and Control Managers Office.
4.4.6 Communicate requests' from off-site groups to the Technical Director.
4.4.7 Upon completion of any exercise, drill, or-EOF activation, compare the available quantities of expendable items to those listed in Exhibit B, " Required Expendables for the EOF". If less than the minimum quantities listed are available, ensure steps are, or will be, taken to restore quantities to those listed on Exhibit B.
4.5 The Radiological Assessment Director is responsible for:
4.5.1 Performing dose calculations for on-site and off-site areas and reporting these results to the Communications Director and Radiation Control and Waste Handling Manager.
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(, 4.5.2 Recoa. mending protective actions on-site and off-site when appropriate.
4.6 The Radiation Protection Manager is responsible for:
4.6.1 Implementing the emecgency radiatien protection program including personnel monitoring and decontamination.
4.6.2 Directin; activities of Kadia tae Moaituring teams and reporting results to the Radiation Control and W'aste Handling Manager.
4.6.3 Directing the activities of Re-entry and Rescue teams, as appropriate.
4.6.4 Coordinating first-aid activities.
, Page 5 of 5 Rev. 3 TP-1
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PMP EPP It DEX
. , INDIAllA & MICHIGAtl POWER COMPAllY
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's.. . D0tlALD C. COOK i!UCLEAR PLANT .
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PLAtlT !%flAGER PROCEDURE .
Index a .
Identification Ti tle . Cements Number RevisionNoJ[
And Date PMP 2081 EPP.014 Of'f-Site Dose Assessments
~ >Revisioni1 TP-1,1225-83 Exp. NA 10-12-82' TP-2,2-22-83 Exp flA TP-3,5-24-83 Exp fA -
EPP.015 Sampling and Analysis of Revision 0 Watdberr,e P.eleases: . '- ..-4-81
~
EPP.016' Collectiori and ' Analysis of Revision 0-Liquid and Gaseous Samples 4-1-81 EPP.01'7 Int'erpretation of Liquid Revision 0 - -
and Oaseous Samples 4-1-81
.EPP.018 Transporta tion Accidents Revision 1
. Involving Ra'dioactive 6-24-82 .
~ Material -
EPP.019 AEP Emergency Response Revision 0 Organization Activation and 4-1-83 l
. . Managemenc EPP.020 k li . a l.k ri .ni Opr:tio> o r P. c P hn 1 7 ,,
- h, i; :,. , i % c;. m t C r:'m *,;_?;.9
] ( i'E ) ,
i EPP.021 Activation and Operatio'n of itevision 1 i -
the Operations Staging Ai:ea 5-25-82 ~
(0SA) and . Personnel Accountabili ty EPP.022 Activation and Operation..of Revision J. TP-1, 7-27-83 Exp.lNA .
the Emergency Operations '1'28 Facility --
.EPP.023 Activa tion and Operation of CAflCELLED the Emergency Control Center 5-4-82 (ECC) (An Emergency -
. Operations Facility)
[ EPP.024 Activation and Operation of - Revision 1 !
I the Joint Public Information 6-24-82 3 Center (JPIC) (An Emergency .
Operations Facility) m ,. 3
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g initials:
No.
Date:
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DOCUMENT ISSUE RECORD D-3W INDIANA & MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT COLOR CODED DISTRIBUTION DOCUMENT CONTROL - Original MASTER FILE - Purple OPERATIONS - Green ADMINISTRATIVE - Orange LIBRARY - Gold PLANNING - Black MANAGERIAL - Brown OUALITY ASSURANCE - Red IECHNICAL - Pink CONSTRUCTION - YELLOW DOCUMENT DOCUMENT NO. NO.OF DOCUMENT - SUBJECT OR TITLE ORIGINATOR: AND/OR REVISION COPIES ISSUED l
s f
Document lSSue Record Receipt Acknowledgement: -
COMMENTS AND/0R NOTATIONS:
Documents affiliated with this D.I.R. # have been filed in file. Superseded documents have been destroyed or modified as applicaole. ,
n __
m aa Signature Date .
RETURN T0: PLANT DOCUMENT CONTROL *
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