ML20207T551

Rev 91 to Site Emergency Plan Implementing Procedure EPIP-4B, Operations Personnel. W/Rev 91 to Table of Contents/Effective Pages

ML20207T551
Person / Time
Site:	Big Rock Point File:Consumers Energy icon.png
Issue date:	03/12/1987
From:	CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
References
EPIP-4B, NUDOCS 8703240122
Download: ML20207T551 (7)

Text

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' 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.

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\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

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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

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VOLUME 9A BIG ROCK POINT NUCLEAR PLANT Revisico 91 SITE EMERGENCY PLAN Page 2 of 3 IMPLEMENTING PROCEDURES n

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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

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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

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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

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