Similar Documents at Cook |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17335A5581999-10-12012 October 1999 Proposed Tech Specs Surveilllance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5611999-10-11011 October 1999 Proposed Tech Specs Pages,Correcting TS Pages Inadvertently Submitted in 990923 Submittal ML17335A5431999-10-0101 October 1999 Proposed Tech Specs Re Containment Recirculation Sump Water Inventory ML17326A1591999-09-23023 September 1999 Proposed Tech Specs Re Movement of SG Sections in Auxiliary Bldg for SG Replacement Project ML17326A1461999-09-17017 September 1999 Proposed Tech Specs Pages for Credit of Rod Cluster Control Assemblies for Cold Leg LBLOCA Subcriticality ML17326A1181999-09-10010 September 1999 Proposed Tech Specs Pages,Revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0941999-08-17017 August 1999 Proposed Tech Specs,Removing voltage-based Repair Criteria, F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarifying Bases Section ML17326A1471999-05-28028 May 1999 Non-proprietary Version of Control Rod Insertion Following Cold Leg LBLOCA at DC Cook,Units 1 & 2. 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. 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. ML17335A1931998-08-28028 August 1998 Proposed Tech Specs Requesting Extension of SG Surveillance TS 4.4.5.3,which TSs Require to Be Performed on 990408,until End of Current Fuel Cycle Currently Scheduled for Mar 2000 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. ML17334B7031998-03-0303 March 1998 Proposed Tech Specs Pages,Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Unit 1 & 2 TS 3/4.6.4 Bases ML20212A7051997-10-21021 October 1997 Proposed Tech Specs 3/4.6.5 Re Ice Weight & Surveillance Requirement ML17333B0751997-10-0808 October 1997 Proposed Tech Specs 3/4.6.5 & 3/4.5.5 Re Ice Weight & SR ML17333B0451997-09-19019 September 1997 Proposed Tech Specs,Deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9891997-08-11011 August 1997 Proposed Tech Specs,Reflecting Changes for Moderator Temp Coefficient Measurement in Response to RAI ML17333A9851997-08-11011 August 1997 Proposed Tech Specs,Allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2121997-08-0101 August 1997 Proposed Tech Specs 4.7.1.2.g Deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig. 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
[Table view] |
Text
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~: ~ ., 4 ~ %. /0 l i i,' h,s 'l','I I4aYv ~ Piwh",1 ~ 0," I, S v., 4,LQ "l4,r Plh ~ 6, ~, 1 +, ill ~ 7 IIIIDIAItM8 /1//lCHIGA/V ElECTRIC COfdPAIIIIY DONALD C. COOK NUCLEAR PLANT PROCEDURE COVER SHEET Phoo~<<e No PMP 2081. EPP.027 Revision No. 0 TITLE UNIT VENT EMERGENCY RELEASE LEVEL DETERMINATION SCOPE OF REVISION SIGNATURES ORIGINAL Rev. I REV. 2 Rev. 0 PREPARED BY QUALITY ASSURANCE REVIEVI INTERFACING DEPAR I'MENT HEAD CONCURRENCE DEPARTMENT HEAD APPROVAL PLANT NUCLEAR SAFETY COMMITI'EE PLANT MANAGER APPROVAL I DATE OF ISSUE a-I-Q 8303250056 83032i PDR ADOCK 05000315
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PNP 2081. EPP.027 LIST OF EFFECTIVE PAGES Pa e Number Revision Number and Date 1 of 9 Revision 0 1-83 2of9 Revision 0 1-83 3of9 Revision 0 1-83 4 of 9 EXHIBIT A Revision 0 1-83 5 of 9 EXHIBIT B Revision 0 1-83 6 of 9 EXHIBIT C Revision 0 1-83 7 of 9 EXHIBIT D Revision 0 1-83 8 of 9 EXHIBIT E Revision 0 1-83 9 of 9 EXHIBIT F Revision 0 1-83 Page 1 of 1 Revision 0, 3-1-83
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INDIANA 8( MICHIGAN ELECTRIC COMPANY DONALD C. COOK NUCLEAR PLANT UNIT VENT B4ERGEHCY RELEASE LEVEL DETERMINATION (I<<
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- i 1.0 PURPOSE 1.1 The purpose of this procedure is to provide guidance in deter-mination of concentrations and release rates of noble gas at the Auxiliary Building Unit Vent.
- 2. 0 REFER ENC ES 2.1 Figure 1, Vent Stack Sampling Lines, AEPSC drawing supplied by P. K. Eapen.
2.2 Computer Program Output; Job tt2001 NSLSSTOP'3 March, 1980, 9:28 p.m.
- 3. 0 INITIAL CONDITIONS 3.1 R-26 has reached or is expected to reach full scale indication.
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3.2 It has been determined by the Shift Supervisor, Plant Radiation Protection Supervisor, their designees, or other responsible r$
plant staff personnel, that additional information on the poten-i] tial releases through the plant vent is needed.
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- 4. 0 PRECAUTIONS'.
4.1 Very high dose rates and high levels of airborne radioactivity 1 may be pr eseht in unexpected locations in the Auxiliary Building.
Precautions to keep internal and external exposure to a minimum shall be taken. These may include, but are not.limited to the following precautions:
4.1.1 At least two individuals shall be sent when there is doubt about the radiological conditions in the Auxiliary Building.
4.1.2 At least one functioning high range dose-rate instrument shall be available at all times. This normally means carrying a suitable spare instrument.
4.1.3 The instruments used for survey may be either GM or Ion Chamber type. If an instrument with a sealed chamber (such as the PIC-6A) is not available, an RM-16 with bullet probe may be used.
Page 1 of 9 Revision 0
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PMP 2081.EPP.027 4.1.4 Normally, if vent release conditions are serious enough to require activation of this procedure, airborne condi-tions in the Auxiliary Building would require the use of pressure demand type supplied air respirators by all personnel invol ved.
- 5. 0 ENVIRONMENTAL CONDITIONS 5.1 In all cases involving a significant increase in airborne acti-vity, licensed Control Room personnel should consult PflP 2080 EPP.001; levels ECC-19 and ECC-13 to determine (EAL's) have been exceeded.
if any emergency action Upon exceeding an EAL, the proper anergency condition shall be declared and the Energency Plan activated by implementing PMP 2080 EPP.001.
6.0 PROCEDURE 6.1 Obtain portable ccmmunication radio frcm the Technical Support Center, Control Room or an Emergency Station. Survey data taken at the sample station should be transmitted to the Control Room every fifteen (15) minutes.
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NOTE: Communication can also be made to the Technical Support Center and Operational Support Center, desired.
if necessary or 6.2 Obtain calibrated, operable, dose-rate reading instruments.
This should include, i f possible, an RM-16 (2 mR/hr to 20 R/hr) with bullet probe. If the range of the RM-16 is expected to be exceeded, a PIC-6A (1 mR/hr to 1000 R/hr) survey instrument from an emergency station should be obtained for use.
6.3 Carefully proceed to the 650'levation sample station.
6.4 Remove the shield plug and insert the detector so that inches from the sample line inside the shield. For exact it is 6 positioning of instruments, see Figure 2 for PIC-6A, or Figure 3 for RM-16 bullet probe.
6.5 If RM-16 with bullet probe is used in shield, slide lead plug up against bullet probe retainer to minimize radiation shine from sample line.
6.6 Open the remote operated sample valves and start the sample pump (controls are located near the sample station).
6.7 Obtain a reading on the survey instrument.
6.8 Using Attachment <1, determine the Activity Factor at Time After Event.
Page 2 of 9 Revision 0
PMP 2081.EPP.027 NOTE 1: Computer program CPM.002 may be used instead of steps 6.8 through 6.12.
NOTE 2: The Activity Factors of Attachment >1 correspond to one (1) R/hr at six inches frcm the sample line (activity uCi/cc factor units ~n>h ). The concentration required to give 1 R/hr will change with time. It is important that Attachment 81 be referenced frequently to insure that the proper activity factor is used.
6.9 Calculate the Unit Yent Release Concentration by multiplying the measured R/hr at the sample station times the activity factor, 6.10 Calculate the Unit Yent Release Rate by multiplying the release concentration times the unit vent flowrate (in CFM) times 4.72E-EXAMPLE:
2.5 R/hr 9 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (1 day)
Activi ty Factor = 5. 2E3 Release Concentration = (2.5)(5.2E3)
= 1.3E4 qCi/cc Release Rate = (1.3E4)(50,000 CFM)(4.72E-4)
= 3. 1E5 Ci/sec 6.11 )e'en ccmpleted, turn sample pump OFF, close valves, remove survey instruments and replace shield plug.
6.12 To detemine Release Concentration and Release Rate of Total Iodine and Iodine 131, obtain Iodine Fraction from Attachment
- 82. Then multiply the Iodine Fraction times values from 6.9 and 6.10 from Attachment 82 and g3.
7.0 . FINAL CONDITIONS 7.1 Record data obtained in appropriate logs.
7.2 Inform the Shift Supervisor and/or Plant Radiation Protection Supervisor of results and any personnel exposure or unusual conditions noted in the Auxiliary Building.
Page 3 of 9 Revision 0
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UNIT VENT EIIFPGFNC" RELEASE DETERHIHATIDll PHP 20&1. EPP.027 104 ACTIVITY FACTOR (HN) vs. TINE (Hours or Days)
EXHISIT 0 I at t ~taa !E I 4 ft I I 't 4 aa' I 4- ffart t
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- 1) Read R/hr 8 sample station; detertt!ine activity factor for Time After Event.
- 2) Calculate Release Concentration by mul- S I tiplying R/hr times activity factor.
- 3) Calculate Release Rate by multiplying release concentration times fiottrate I times 4.72E-4.
EXAHPLE:
I) 2.5 R/hr 9 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (1 day)
~7 Activity Factor ~ 5.25E3 I ~ !'7 4 2) Release Concentration 4 (2.5)(5.25E3) t Itt ~. t In!A 'I af at 7 I t>> it !
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~ e PMP EPP INDEX 4
INDIAiVA 5 i~iICHIGAN . 0'ilER CGMPAi'IY DONALD C. COOK i'lUCLEAR PLANT PLANT MANAGER PROCEDURE Index Identification Ti tl e Revision i'lo. Comments Number And Date PMP 2081 EPP.025 Activation and Operation of Rev$ .sion 1 the Emergency News Source 6-24-82 (ENS) (An Emergency Operations Fac i 1 i ty)
EPP.026 Use of Stable Iodine for Revision 1 Thyroid Blocking During a 9-8-82 Radiation Emergency EPP.027 Uni t Vent Emergency Rel ease Revision Ci Level Determination 3-1-83 Page Ref. Oe... ~3 tfe, e '\ e J wp Y +, eel("e '0 9 Ii n8' e ' e
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PMo EPP INDEX LIST OF EXHIBITS PMP 2081 EPP.025 EXHIBIT A PLAN FOR REPORTING NON-ROUTINE INCIDENTS AT COOK NUCLEAR PLANT PMP 2081 EPP.026 CHECKLIST A USE OF A STABLE IODINE FOR THYROID BLOCKING DURING A RADIATION EMERGENCY PMP 2081 EPP.027 EXHIBIT A UNIT 1 (82 TYPICAL MIRROR IMAGE) VENT STACK SAMPLING LINES EXHIBIT B PORTABLE ION CHAMBER EXHIBIT C (DRAWING OF EQUIPMENT)
I EXHIBIT D UNIT VENT EMERGENCY RELEASE DETERMINATION ACTIVITY FACTOR VS. TIME (HOURS OR DAYS)
EXHIBIT E UNIT VENT TOTAL IODINE RELEASE DETERMINATION PMP 2082 EPP.009 EXHIBIT A EMERGENCY PREPAREDNESS ANNUAL CHECKLIST EXHIBIT B EMERGENCY PREPAREDNESS SEMI-ANNUAL CHECKLIST EXHIBIT C EMERGENCY PREPAREDNESS QUARTERLY CHECKLIST PAGE DATE 9
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