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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20195D0451999-06-0303 June 1999
Proposed Tech Specs,Revised to Agree with Current Facility Defueled TS Format
ML20206N2751999-05-11011 May 1999
Proposed Tech Specs Deleting Figure 5.1-1 Brp Site Map from Defueld TS Subsection 1.16,changing Definition of Site & Other Associated Editorial Changes
ML20154M5431998-10-14014 October 1998
Proposed Defueled Tech Specs & Bases for Big Rock Plant
ML20238E8141998-08-31031 August 1998
Revised Big Rock Point Defueled Emergency Plan
ML20236T6681998-07-21021 July 1998
Proposed Defueled Tech Specs for Big Rock Nuclear Plant
ML20248L5511998-06-0505 June 1998
Draft Proposed Tech Specs Rev,Incorporating Changes Responsive to 980416 RAI
ML20217P3811998-02-28028 February 1998
Revised Defueled Emergency Plan
ML20138G2021997-04-30030 April 1997
Proposed Tech Specs,Illustrating Change to Current Facility License DPR-6
ML20138A9131997-04-22022 April 1997
Proposed Tech Specs,Withdrawing Petition to Implement Option B Performance Based Requirements to App J of 10CFR50
ML20216A9611997-01-0101 January 1997
Rev 13 to Big Rock Point Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program
ML20134H6411996-11-0707 November 1996
Proposed Tech Specs Re New Air Compressor to Svc Air Segment of Svc & Instrument Air Sys
ML20129C4871996-10-15015 October 1996
Proposed Tech Specs Allowing Use of Option B for Type a Test (Containment),Type B Test (Pneumatic Tests to Detect & Measure Local Leakage Rates Across Pressure Retaining, leakage-limiting Boundaries) & Type C Tests
ML20199J7411995-10-0303 October 1995
Rev 6 to Users Guide for Vectora CL-200 Polyethylene High Integrity Containers
ML20058N6421993-10-11011 October 1993
Rev 16 to Vol of Administrative Procedures,Procedure 3.2.1, Maint Order Processing, Pages 21 & 22
ML20056G3931993-08-24024 August 1993
Proposed Tech Specs Reflecting Revision to 10CFR50.36(a)(2) Changing Reporting Requirement for Effluent Releases from Semiannual to Annual
ML20058N6401993-07-15015 July 1993
Rev 20 to Procedure T7-28, Emergency Diesel Generator Auto Test Start
ML20058N6331993-07-15015 July 1993
Rev 142 to Vol 3 of Operating Procedure - Sys SOP-14, Substation
ML20128D7251993-01-29029 January 1993
Proposed Tech Specs Re Administrative Controls
ML20127N4321993-01-11011 January 1993
Third Interval ISI Program
ML20141M5531992-03-10010 March 1992
Rev 8 to Vol 25 to Procedure Big Rock Point Radiological Effluent TS Required Documents,Offsite Dose Calculations & Process Control Program
ML20059A2181990-08-14014 August 1990
Proposed Tech Specs,Reflecting Administrative & Organizational Changes
ML20246J1841989-08-25025 August 1989
Rev 4,Vol 25 to, Big Rock Point Radiological Effluent Tech Spec Required Documents for Offsite Dose Calculation Manual & Process Control Program
ML20245K6991989-06-30030 June 1989
Corrected Proposed Tech Specs Paragraph 3.7 Re Containment Sphere Leakage Testing
ML20247L1141989-05-25025 May 1989
Proposed Tech Specs Aligning Specs to Current 10CFR50 App J Requirements That Permits Removal of 24 H Duration Restriction of Integrated Leak Rate Test
ML20204F8321988-10-10010 October 1988
Proposed Tech Specs Change Re Partial Stroke Testing Following Main Valve Seat Leakage Repairs
ML20154S6481988-09-22022 September 1988
Proposed Tech Specs,Allowing Independent Review & Audit Functions to Be Accomplished by Independent Organizational Unit Rather than Standing Committee
ML20154P2191988-09-21021 September 1988
Proposed Tech Specs Reflecting Editorial & Administrative Corrections to Provide Clarification & Consistency
ML20154D4821988-09-0808 September 1988
Proposed Tech Specs,Removing Organization Charts from Tech Specs & Informing NRC of Onsite Organizational Changes
ML20207C2291988-07-13013 July 1988
Rev 7 to Suitability,Training & Qualification Plan. W/
ML20150C7921988-07-0505 July 1988
Proposed Tech Specs Re Reactor Depressurization Sys Isolation Valves
ML20154L7961988-05-26026 May 1988
Simulation Facility Plan for Big Rock Point to Meet 10CFR55.45(b)
ML20153G0861988-04-13013 April 1988
Rev 2 to Procedure Change Form, Offsite Dose Calculations Manual
ML20153G1041988-04-12012 April 1988
Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program
ML20155A5221988-04-0606 April 1988
Rev 30 to Procedure T30-22, ECCS Valve Tests
ML20148Q4681988-03-31031 March 1988
Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45
ML20148H6331988-03-22022 March 1988
Proposed Tech Specs Re Reactor Depressurization Sys
ML20147E3701988-01-14014 January 1988
Rev 6 to Suitability,Training & Qualification Plans
ML20215M3281987-12-31031 December 1987
Emergency Plan Exercise Scenario
ML20237B9691987-12-14014 December 1987
Proposed Tech Specs,Removing Numerical Designator from I-type Fuel for Each Subsequent Fuel Operating Cycle
ML20236P0671987-11-13013 November 1987
Rev 1 to Big Rock Point IGSCC Insp Program
ML20236N5501987-11-0909 November 1987
Proposed Tech Spec Figure 5.1 & Sections 6.1,6.2,6.3 & 7.3, Making Administrative Changes to Reflect Features & Terminology Used W/New out-of-core Power Range Nuclear Instrumentation.Power Range Monitor Sys Description Encl
ML20236B1201987-07-22022 July 1987
Proposed Tech Specs Changes Consisting of Administrative Corrections
ML20214N9801987-05-29029 May 1987
Rev 0 to Health Physics Procedure HP 10.9, Big Rock Point Radiological Environ Program Sample Collection & Shipment
ML20213A1761987-04-22022 April 1987
Rev 5 to Suitability Training & Qualification Plan
ML20206B4211987-03-12012 March 1987
Public Version of Rev 3 to General Ofc Emergency Planning Procedure GEN-1, Overview, Rev 9 to Copyholders List & Index & Rev 3 to App G, Emergency Telephone Numbers
ML20207T5511987-03-12012 March 1987
Rev 91 to Site Emergency Plan Implementing Procedure EPIP-4B, Operations Personnel. W/Rev 91 to Table of Contents/Effective Pages
ML20210V2981987-02-10010 February 1987
Corrected Page 11 to Tech Spec,Reflecting New Signature Dates
ML20210E5601987-02-0606 February 1987
Proposed Tech Specs,Adding Operability & Surveillance Requirements for Alternate Shutdown Sys & Revising Specs for Active Fire Barriers & Fire Detection Instrumentation for Auxiliary Shutdown Bldg
ML20210C6341987-02-0404 February 1987
Proposed Tech Spec Changes,Adding Table of Uncertainty Factors Associated W/Core thermal-hydraulic Parameters Heat Flux,Maplhgr,Max Bundle Power & Min Critical Power Ratio
ML20207L6871986-12-30030 December 1986
Rev 0 to Emergency Operating Procedure,Training Program
1999-06-03
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20238E8141998-08-31031 August 1998
Revised Big Rock Point Defueled Emergency Plan
ML20217P3811998-02-28028 February 1998
Revised Defueled Emergency Plan
ML20216A9611997-01-0101 January 1997
Rev 13 to Big Rock Point Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program
ML20199J7411995-10-0303 October 1995
Rev 6 to Users Guide for Vectora CL-200 Polyethylene High Integrity Containers
ML20058N6421993-10-11011 October 1993
Rev 16 to Vol of Administrative Procedures,Procedure 3.2.1, Maint Order Processing, Pages 21 & 22
ML20058N6331993-07-15015 July 1993
Rev 142 to Vol 3 of Operating Procedure - Sys SOP-14, Substation
ML20058N6401993-07-15015 July 1993
Rev 20 to Procedure T7-28, Emergency Diesel Generator Auto Test Start
ML20127N4321993-01-11011 January 1993
Third Interval ISI Program
ML20141M5531992-03-10010 March 1992
Rev 8 to Vol 25 to Procedure Big Rock Point Radiological Effluent TS Required Documents,Offsite Dose Calculations & Process Control Program
ML20246J1841989-08-25025 August 1989
Rev 4,Vol 25 to, Big Rock Point Radiological Effluent Tech Spec Required Documents for Offsite Dose Calculation Manual & Process Control Program
ML20207C2291988-07-13013 July 1988
Rev 7 to Suitability,Training & Qualification Plan. W/
ML20154L7961988-05-26026 May 1988
Simulation Facility Plan for Big Rock Point to Meet 10CFR55.45(b)
ML20153G0861988-04-13013 April 1988
Rev 2 to Procedure Change Form, Offsite Dose Calculations Manual
ML20153G1041988-04-12012 April 1988
Radiological Effluent T/S Required Documents,Offsite Dose Calculations & Process Control Program
ML20155A5221988-04-0606 April 1988
Rev 30 to Procedure T30-22, ECCS Valve Tests
ML20148Q4681988-03-31031 March 1988
Rev 2 to Guidance for Development of Simulation Facility to Meet Requirements of 10CFR55.45
ML20147E3701988-01-14014 January 1988
Rev 6 to Suitability,Training & Qualification Plans
ML20215M3281987-12-31031 December 1987
Emergency Plan Exercise Scenario
ML20236P0671987-11-13013 November 1987
Rev 1 to Big Rock Point IGSCC Insp Program
ML20214N9801987-05-29029 May 1987
Rev 0 to Health Physics Procedure HP 10.9, Big Rock Point Radiological Environ Program Sample Collection & Shipment
ML20213A1761987-04-22022 April 1987
Rev 5 to Suitability Training & Qualification Plan
ML20206B4211987-03-12012 March 1987
Public Version of Rev 3 to General Ofc Emergency Planning Procedure GEN-1, Overview, Rev 9 to Copyholders List & Index & Rev 3 to App G, Emergency Telephone Numbers
ML20207T5511987-03-12012 March 1987
Rev 91 to Site Emergency Plan Implementing Procedure EPIP-4B, Operations Personnel. W/Rev 91 to Table of Contents/Effective Pages
ML20207L7441986-12-30030 December 1986
Technical Guidelines. Basis for Guidelines & Description of Plant Encl
ML20207L7171986-12-30030 December 1986
Rev 0 to Plant-Specific Writers Guide for Emergency Operating Procedures
ML20207L7031986-12-30030 December 1986
Rev 0 to Emergency Operating Procedure,Validation Procedure
ML20207L6921986-12-30030 December 1986
Rev 0 to Emergency Operating Procedure,Verification Procedure
ML20207L6871986-12-30030 December 1986
Rev 0 to Emergency Operating Procedure,Training Program
ML20203H6761986-07-21021 July 1986
Public Version of Revised Emergency Plan Implementing Procedures Including,Rev 2 to GEN-1, Overview, Rev 2 to GEN-3, On-Shift Sys Power Controller & Rev 0 to GORT-1, General Ofc Response Team (Gort). W/860730 Release Memo
ML20137X7321986-02-17017 February 1986
Revised Offsite Dose Calculation Manual
ML20154A1081986-02-12012 February 1986
Plan for Big Rock Point Integrated Assessment
ML20138S1081985-10-28028 October 1985
Public Version of Revised General Ofc Response Team/ Emergency Operations Facility Emergency Implementing Procedures,Including Rev 1 to GEN-1, Overview & Rev 1 to EOF-1, Emergency Officer. W/851114 Release Memo
ML20134K2541985-08-26026 August 1985
Plant,Offsite Dose Calculation Manual
ML20134K2661985-08-26026 August 1985
Plant,Process Control Program
ML20136G5481985-08-0202 August 1985
Public Version of Rev 0 to General Ofc Emergency Planning Procedures. W/850814 Release Memo
ML20127G8471985-04-22022 April 1985
Public Version of Revised Emergency Implementing Procedures, Including Rev 12 to General Ofc Response Team/Emergency Operations Facility & Rev 10 to Review & Control of General.... W/850513 Release Memo
ML18047A3241982-05-0303 May 1982
Requalification Program - Reactor Operator & Senior Reactor Operator.
ML18045A4801980-07-31031 July 1980
Cpco Hot License Program-Reactor Operator.
1998-08-31
[Table view] |
Text
~~ _.
' VOLUME 9A BIG ROCK POINT NUCLEAR PLANT Rsvinien 91 SITE EMERGENCY PLAN. Page 1 of 3 IMPLEMENTING PROCEDURE
-- EPIP-4B - OPERATIONS PERSONNEL v
Responsibilities - Establish and maintain Plant operations in a safe condition.
Immediate Actions
- 1. If applicable, initiate "Immediate Operator Actions" of the corresponding Emergency Operating Procedure to mitigate the consequences of the accident.
A. Monitor the area monitor readout panel, including radiation levels and area monitor location. Readings should be taken at approximately 15 minute intervals. Report to the Shift Supervisor any monitors giving high radiation alarms.
B. Monitor the process monitor readout panel, including process monitor location. Report to the Shift Supervisor any monitors giving high radiation alarms.
C. At the " Alert" classification and higher, complete the TSC Data Sheet (Attachment 4B-1) except below the section beginning with Comments /
Corrective Actions, at approximate 15 minute intervals and give to the Operations Superintendent or Shift Supervisor for review and further routing to the HP Group Leader.
NOTE: Page 2 of Attachment 4B-1 need only be filled out if applicable.
/O
\m l 2. If required by Shift Supervisor or Site Emergency Director, with the PA system, announce the location and conditions (including Plant areas to avoid while assembling) of the emergency.
- 3. Upon the declaration of an Alert or as directed by the Site Emergency Director or Shift Supervisor, actuate the emergency siren (continuous two-minute blast). For fire, the siren is a series of short blasts for 30 seconds. For bomb threat, the emergency siren shall not be actuated.
There will be a PA announcement only.
NOTE: Should a fire and an Alert occur simultaneously, the fire siren is to be sounded first with an announcement. This should be immediately followed by the emergency announcement and siren.
Subsequent Actions
- 4. If Radiation Protection personnel are not available, or if necessary, act as " Ambulance Etcort" for injured person (s) per EPIP-6E. When escorting injured individual to hospital in emergency vehicle, take the ambulance emergency kit located in main lobby and the battery-operated air sampler located under the counting bench in Access Control to the hospital.
- 5. Maintain appropriate operations logs during and after the emergency.
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- 6. Assist the SED in controlling the number of personnel in the Control Room area.
8703240122 870312 PDR ADOCK 05000155 F PDR l} r[4/[
PR1082-2531A-BA01-BA05
VOLtME'9A BIG ROCK POINT NUCLEAR PLANT- R;visita 91 SITE EMERGENCY' PLAN IMPLEMENTING PROCEDURE P ga 2 cf 3 EPIP-4B - OPERATIONS PERSONNEL
. ,m. ATTACHMENT 1 TSC DATA SHEET - BIG ROCK POINT PLANT Time tog No Deergency Classification Reactor: Radiological Conditions a) Reactor Pressure (psig) a) Stack Gas Monitor RI-8327 (com) b) Steam Drum Lvl from ( (inches) b) Hi Range Stack Mon RI-8328 (mR/hr) c) Rx Water Above Core Yes O mod c) Rt Range Gassia non RI-832b (R/hr) d) All Rods In Yes O mod (Core Damage) RI-8325 (R/hr) e) General Reactor Condition 4) Area Monitors (mR/hr)
Spent Fuel Storage No. 2 Condensate Demin Entrance No. 8 Machine Shop Area No. 9 a) Containment Pressure (psig)
Turbine Shield Wall No. IT b) Containment Water Level (ft) Radwaste Vault Entrance No. 18 c) M3IV Position Emer Condenser Vent-East No. 20
,d) Ventilation Valves Position Emer Condenser Vent-West No. 21 e) General Containment Condition Other Other Engineered Safeguards: e) Process Monitors: (com) a) Em rgency Condenser level (%) Radwaste Discharge to Canal b) Emergency Condenser Temp: Canal Discharge Service Water Discharge to Canal Icop 1 (*F)
Icop 2 (*F) General Plant Conditions:
\d c) Core Spray System Flow (gpm) d) Backup Core Spray Sys Flow (gpm) e) Containment Spray Sys Flow (spm) f) RDS Status Observations / Maintenance Status:
g) Liquid Poison Status h) Steam Drum Relief Viv Status
- 1) Post Incident Recycle Yes O No O Ooerations Review:
Comments / Corrective Actions:
NJ Distribution: White-Fax Green-Communicator Canary-Tech Pink-HP Goldenrod-Control Room PR1082-2531A-BA01-BA05
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VOLUME 9A BIG ROCK POINT NUCLEAR PLANT ~ Revicion 91 SITE EMERGENCY PLAN Page 3 of 3 IMPLEMENTING PROCEDURE ~
EPIP-4B - OPERATIONS PERSONNEL ,
ATTACHMENT 1 TSC DATA SHEET Iog No Emergency Engineered Safety Chronology of Classification Features Significant Actions (And Other Important Safety Features)
Oper Inope RDS Core Spray &
Recire Sys Containment Spray Emer Condenser Emerger y Safety Relier Vivs Description Rx Protection Sys Liquid Poison Sys Cont Isolation Sys Cont Vacuum Relief Other Inoperable Equipment PR1082-2531A-BA01-BA05
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- h. i TO: DOC CONTROL - USNRC ( b;ghmmmm.v-TRANSMITTAL NUMDER: 009200 -
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PROCEDURE NUMDER:7A TITLE: SITE EMERGENCY PLAN IMPLEMENTING [O " I PROCEDURES TRANSMITTAL: LISTED DELOW ARE NEW/ REVISED PROCEDURES WHICll MUST INSERTED INTO OR DISCARDED FROM YOUR PROCEDURES MANI ,.
DIRECTIONS ACCCMPANY EACH ITEM.
- i. ATTACHED IS PROCEDURt' EPIP-4D, VOL.9A, REV.91, ISSUED PER Q.R. FORM
?407-07. INSERT IN YOUR VOL.9A MANUAL & DISCARD PREVIOUS REVISION.
ALSO ATTACHED ARE (2) LABELS FOR THE INSIDE FRONT COVER OF YOUR 9A MANUAL (DLUE LADEL) & INSIDE COVERSilEE T (YELLOW LADEL). PLEASE AFFIX TO YOUR COPY VOL. 9A.
ISSUED MARCH 12, 1907 BRP
- 2. SIGN, DATE AND RETURN THE ACKNOWLEDGEMENT FORM UITHIN 14 DAYS TO THE BIG ROCK PLANT DOCUMENT CONTROL.
SIGNATLIRE OR INITIALS DATE
.s-mee.=mduew--ee es. wen.ee em=.Mem.-g .e. g e .go. .=w-.me.--..e
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VOLUME 9A BIG ROCK POINT NUCLEAR' PLANT Revioita 91 SITE EMERGENCY PLAN Page 1 of 3 IMPLEMENTING PROCEDURES O
V TABLE OF CONTENTS / EFFECTIVE PAGES PROCEDURE REVISION PAGES EPIP-1 ACTIVATION OF EMERGENCY PLAN 47' 1 - 13 EPIP-3A ACTIVATION OF TECHNICAL SUPPORT CENTER 86 - 1-7 EPIP-3B ACTIVATION OF THE OPERATIONS SUPPORT CENTER 86 1-5 EPIP-3C ACTIVATION OF THE EMERGENCY OPERATIONS FACILITY (BOYNE CITY) 88 1-5 EPIP-4 INDIVIDUAL IMPLEMENTING PROCEDURES 44 1-2 EPIP-4A SITE EMERGENCY DIRECTOR 86 1-5 EPIP-4B OPERATIONS PERSONNEL 91 1-3
'EPIP-4C ON-CALL TECHNICAL ADVISOR 88 1-1 EPIP-4D TECHNICAL SUPPORT GROUP LEADER 86 1-1 EPIP-4E REACTOR ENGINEER 88 1-1 EPIP-4F HEALTH PHYSICS GROUP LEADER 86 1-2 EPIP-4G ON-CALL DOSE ASSESSOR 88 1-1 EPIP-4H CHEMISTRYANDRADIATIONPRbTECTIbNTECHNICIAN 86 1-1 EPIP-4I DEDICATED COMMUNICATOR 64 1-2 EPIP-4J DATA RECORDER 86 1-1 EPIP-4K OSC DIRECTOR 86 1-1 EPIP-4L OSC SUPERVISOR 86 1-1 EPIP-4M SITE ACCOUNTABILITY COORDINATOR 88 1-3 EPIP-4N SECURITY OFFICER 88 1-2 EPIP-40 ASSEMBLY AREA LEADER 88 1-1
'EPIP-4P COUNTY EOC LIAISON 44 1-1 EPIP-4Q JPIC DIRECTOR 88 1-4 9
PR0486-0805A-BA02-BA05
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VOLUME 9A BIG ROCK POINT NUCLEAR PLANT Revisico 91 SITE EMERGENCY PLAN Page 2 of 3 IMPLEMENTING PROCEDURES n
t )
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TABLE OF CONTENTS / EFFECTIVE PAGES PROCEDURE REVISION PAGES EPIP-4R EOF ADMINISTRATOR 86 1-1 EPIP-4S TELEPHONE SWITCHBOARD 90 1-2 EPIP-5A ESTIMATION OF OFF-SITE DOSE 88 1-5 EPIP-5A-1 PLANT SITE METEOROLOGICAL SYSTEM 66 1-4 EPIP-5A-2 BACKUP AND FORECAST METEOROLOGY 46 1-9 EPIP-SA-3 BACKUP MANUAL GAMMA 5 DETERMINATION 71 1-4 EPIP-5A-4 BACKUP MANUAL RELEASE RATE DETERMINATION FOR CONTAINMENT RELEASES 71 1-4 EPIP-5A-5 BACKUP MANUAL RELEASE RATE DETERMINATION FOR STACK RELEASES 71 1-8 g EPIP-5A-6 AUTOMATED DOSE ASSESSMENT PROGRAM 71 1-2
?
EPIP-5A-7 0FFSITE DOSE CALCULATION - MANUAL METHOD 71 1 - 15 EPIP-5A-8 COMPARISON OFFSITE MONITORING DOSE CALCULATIONS Deleted EPIP-5A-9 BACKUP MANUAL RELEASE RATE DETERMINATION FROM BACKUP STACK MONITOR AM-2 71 1-6 EPIP-5B PROTECTIVE ACTION RECOMMENDATIONS FOR OFFSITE POPULATIONS 88 1 - 12 EPIP-5C AIRBORNE IODINE MONITORING UNDER ACCIDENT CONDITIONS - IN PLANT 45 1-7 EPIP-5D PROCEDURE TO DETERMINE EXTENT OF CORE DAMAGE (FOR 0% TO 100% CORE MELTDOWN) 88 1-5 EPIP-5E PROCEDURE TO DETERMINE EXTENT OF CORE DAMAGE (FOR LESS THAN 10% CORE MELTDOWN 50 1-8 EPIP-5F ENVIRONMENTAL MONITORING 69 1 - 12 EPIP-50 0FF-SITE RADIOLOGICAL MONITORING 88 1-3 q EPIP-5H ON-SITE (OUT-0F-PLANT) RADIOLOGICAL SURVEYS 28 1-5 b
PR0486-0805A-BA02-BA05
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VOLU!E 9A BIG ROCK POINf NUCLEAR PLANT R;vicita 91 SITE EMERGENCY PLAN Page 3 of 3
,.s IMPLEMENTING PROCEDURES
.< \
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TABLE OF CONTENTS / EFFECTIVE PAGES PROCEDURE REVISION PAGES EPIP-6A ASSEMBLY / ACCOUNTABILITY / SEARCH AND RESCUE 89 1-5 EPIP-6B PERSONNEL MONITORING EVACUATION AND REASSEMBLY 54 1-7 EPIP-6C REENTRY / RECOVERY 88 16 EPIP-6D EMERGENCY EQUIPMENT AND SUPPLIES:
INVENTORY, MAINTENANCE AND CALIBRATION 58 1-1 EPIP-6E FIRST-AID AND MEDICAL CARE 88 1-6 EPIP-6F EMERGENCY NOTIFICATIONS 89 1 - 12 EPIP-6G TIME-DISTANCE-DOSE PREDICATIONS BASED ON PERCENT CORE MELTDOWN 18 1 - 21 EPIP-6H EMERGENCY DOSIMETRY Deleted C\
'V EPIP-61 TRAINING AND DRILLS 85 1-2 EPIP-6J COMMUNICATIONS TESTS 90 1-8 EPIP-7A GENERAL OFFICE NUCLEAR EMERGENCY IMPLEMENTING PROCEDURES Deleted l
l l
O PR0486-0805A-BA02-BA05 l
