ML20205B888

Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 4 to EPIP-OSC-16, Emergency Team, Rev 10 to EPIP-EOF-6, Onsite/Offsite Dose Assessment & Rev 3 to EPIP-TSC-8, Emergency Core Damage

ML20205B888
Person / Time
Site:	Fort Calhoun
Issue date:	03/17/1987
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20205B865	List: ML20205B861 ML20205B888
References
PROC-870317-01, NUDOCS 8703300064
Download: ML20205B888 (189)

Text

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VOLUME III

, TABLE OF CONTENTS (Continued)

1. OPERATION SUPPORT CENTER (Continued)

Revision Procedure No. - Title No./Date EPIP-OSC-16 Emergency Team R4 02-26-87 EPIP-OSC-17 Technical Augmentation Staff R1 06-20-85 EPIP-OSC-18 Initial Response Organization Notification R1 10-16-86

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FC/INDEX/01 03-07-87 l

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l VOLUME III

h. TABLE OF CONTENTS (Continued)

2. EMERGENCY OPERATION FACILITY Procedure No. _ Title Revision No /Date EPIP-EOF-1 Activation of Emercency Operation Facility R4 05-23-86 EPIP-EOF-2 Emergency Operation Facility Communication R3 04-30-86 EPIP-EOF-3 Emergency Operation Facility Emergency Instruments and Equipment R7 05-20-85 EPIP-EOF-4 Measurement of Airborne Radioactivity (Incorporated into EPIP-EOF-6)

R3 08-18-82 EPIP-EOF-5 Onsite and Offsite Oose Assessment (Computerized Prog.) (R2 07-18-85)

DELETED 1-23-86 EP!P-EOF-6 Onsite/OffSite Oose Assessment R10 02-26-87 EPIP-EOF-7 Protective Action Guidelines RS 10-16-86 EPIP-EOF-8 Environmental Monitoring R4 10-22-86 EPIP-EOF-9 Personnel Accountability R4 06-20-85 EPIP-EOF-10 Personnel Decontamination R4 03-12-86 l EPIP-EOF-11 Dosimetry and Records R4 04-30-86 EPIP-EOF-12 Site Security I

R2 06-20-85 EPIP-EOF-13 Shif t Supervisor / Site Director l

l Transition R4 06-20-85 EPIP-EOF-14 Site Director to Recovery Manager -

Transition R2 06-20-85 EPIP-EOF-15 Determination of Contamination Release Through Plant Stack (R211-18-83)

OELETED 1-23-86 C iii FC/INDEX/01 03-07-87

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. VOLUME ITI ,

I TABLE OF CONTENTS (continued)

3. TECHNICAL SUPPORT CENTER -

Revision Procedure No. Title No./Date EPIP-TSC-1 Activation of Technical Support Center R6 05-23-86 EPIP-TSC-2 Control Room & Technical Sup' port Center Communication R3 05-05-86 EPIP-TSC-3 Plant and Reactor Operation Support - Alert Classification R2 10-04-84 EPIP-TSC-4 Plant and Reactor Operation Support - Site Area Emergency Classification R3 10-04-84 EPIP-TSC-5 Plant and Reactor Operation Support - General Emergency Classification R2 10-04-84 EPIP-TSC-6 Plant Engineering and Repair R2 09-24-84 EP!P-TSC-7 Emergency Response Assistance Combustion Engineering R1 04-30-86 EPIP-TSC-8 Estimate of Core Damage R3 02-23-87 9

FC/INDEX/01 03-02-87

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VOLUME !!! .

TABLE OF CONTENTS (Continued)

5. PUBLIC INFORMATION Revision Procedure No. Title No./Date EP!P-RR-67 Emergency Recovery Organization's Clerical Assistant R2 12-22-86 EPIP-RR-68 Emergency Recovery Organization's Recovery Manager Secretary R2 12-22-86 EPIP-RR-69 Recovery Organization's Dose Assessment Operator R3 11-12-86 EPIP-RR-70 Emergency Recovery Organization's Recovery Operations Coordinator R1 06-20-85 EPIP-RR-71 Emergency Recovery Organization's Recovery Manager Comunicator R2 12-22-86 EPIP-RR-72 Emergency Recovery Organization's Dose Assessment Specialist R3 02-26-87 EPIP-RR-73 Emergency Recovery Organization's Dose Assessment Data Processor R2 10-16-86 EPIP-RR-74 Emergency Recovery Organization's Chemistry and Environmental Survey Coordinator R2 04-30-86 EPIP-RR-75 Emergency Recovery Organization's Site Representative (Des Moines, Iowa) R1 04-30-86 EPIP-RR-76 Emergency Recovery Organization's EOF Administration Supervisor R2 10-22-86 EPIP-RR-77 Emergency Recovery Organization's Call List Caller R0'12-22-86 FC/INDEX/01 03-07-87

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Y 4 EPIP-0SC-16-1 l

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j Fort Calhoun Station Unit No.1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-OSC-16 l

EMERGENCY TEAM l I. PURPOSE l The purpose of this procedure is to provide instructions for personnel l assigned to Emergency Team positions.

1 II. PREREQUISITE ,

Both the primary and alternate individuals filling ~a particular Emergency Team position. TAG No.1 through TAG No. 24, have been fully trained and are aware of their duties and responsibilities.

!!!. PRECAUTIONS None I

V. PROCEDURE

~

Upon activation of the Initial Response Organization, those individuals assignec to a position on the Emergency Team will carry out their assignment as detailed in Appendix 1 of this Implementing Procedure.

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Fort Calhoun Station Unit No. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EP!P-OSC-16 APPEN0!X-1 EMERCENCY TEAM A. TAG 1 -- RECORDER / PHONE TALKER Reportine location:

Technical Support Center Reports To: -

Site Director Basic Responsibilities:

After receiving call to report to his/her duty station. Recorder / Phone talker will contact the other Recorder / Phone talker and determine who will report to the TSC and who will continue the Initial Response Organization Call List. If the Recorder / Phone talker who is going to continue the call list is contacted at home he/she will remain at home and continue the call list until completed for the Emer t or until notified that no further calling is necessary.gency Action Level, The other Recorder / Phone talker will report to the TSC, pick up the proper tag from the TSC Tag board and infom the Site Director of their presence.

Sets up, operates and maintains the tape recorder.

Briefs the Site Director on accident status and present conditions when he arrives. ,

Maintains emergency log book. Clerical assistance is available through the Security and Administrative Supervisor.

Perfoms telephone comunications.

Receives Operational Data from the Control Room and posts this data on the "FCS Emergency Status Board."

Assumes responsibility for the Conference Operations (COP) Network from the Control Room when the Site Director assumes emergency response actions from the Shift Supervisor.

Man the Conference Operations (COP) Network and provide updated information to State and County officials as directed by the Site Director until transferring CDP Network responsibility to the E.0.F. Comunicator. l

! ISSUED FEB 261987 R4 02-26-87 FC/EPIP/03

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'(, APPEN0!X-1 (Continued)

8. TAG 2, 3 - EMERGENCY RE-ENTRY TEAM Reporting Location:

Operation Support Center Extension in Technical Support Center Building.

Report To: ,

Health Physics / Chemistry Supervisor when re-en'try team required.

Basic Responsibilities:

Re-entry Team personnel will report and receive instructions from the HP/ Chemistry Supervisor thru the Monitor Coordinator.

Procures emergency kit, monitor kits, air samplers, and breathing equipment from storage area.

Obtains and battery checks high range survey instruments.

Obtains a set of protective clothing. Dons shoe covers and coveralls, checks out and puts on a TLD and high range dosimeter. Has other protective clothing ready to don on instruction from Monitor Coordinator.

Checks out a self-contained breathing apparatus for readiness to use. Checks

, the mask for proper fit.

Prepares for entry to the Auxiliary Building, verifies proper dress with the Monitor Coordinator.

1 Enters the Auxiliary Buildirg as directed by the Health Physics / Chemistry Supervisor and instructed by the Monitor Coordinator.

Performsassignedtaskssuchas(a)searchandrescueofinjuredperson(s),

(b) emergency repair to equipment and (c) assistance to Operations in perfonning corrective actions.

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R4 02-26-87 FC/EPIP/03

EPIP-0$Cg16-4 APPEN0!X-1 (Continued)

C. TAG 4 - DOSE ASSESSMENT OPERATOR Reportina Location:

Technical Support Center Building, Room 107 Reports To:

Health Physics / Chemistry Supervisor Coordinates With:

I

, Site Director untti the Health Physics / Chemistry Supervisor arrives at i the TSC.

Basic Responsibilities:

1. Sets up and establishes maps and overlays pertinent to the emergency conditions.

2. Estabilvies direct-line comunications with the Control Room if infonnation is not already available in the TSC to obtain meteorological and radiological data needed to perform Dose Assessment. FC-197

" Meteorological and Radiological Data Worksheet" will be used to record this data.

3. Obtain manual Dose Assessment Data from the Control Room and enter the infonnation into the computer prior to perfonning nonnal computer operations.

4. TheMeteorologicalandRadiologicalDataWorksheet(FC-197) revision number and date will be verified by referring to EP!P EOF 6 Section H in the official set of Operating Manuals maintained in the TSC prior i to their use.

5. Calculates airborne activity, dose rate and integrated dose for locations outside the plant structures and enters this data on FC-195.

6. Ensures the Health Physics / Chemistry Supervisor is receiving calculated data.

Assists the Site Director /HP/ Chemistry Supervisor on evaluation of radiologicaldgtggsrgquired.

FC/EPIP/03 FEB 261987 R4 02 26 87 l

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EPIP-OSC-16-5 t APPEN0!X-1 (Continued)

C. TAG 4-DOSEASSESSMENTOPERATOR(Continued) l Maintains data in a current status.

Refers to EPIP-EOF-6 Section H "Onsite and Offsite Oose Assessment using the computerized program" when perfoming dose ass.tsment duties with

! .. the computer.

l Refers to EPIP-EOF-6 "Onsite and Offsite Dose Assessment" for step-by-step l Procedures using plant parameters and effluent monitors to detennine source

! term.

Contact the National Weather Service in Omaha, telephone number 9-1-402-571-8351. and request 3rojected meteorological weather information if necessary to mate long term dose exposure projections.

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ISSUED FEB 2 61907 FC/EPIP/03 R4 02-26 87 l .

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EPIP-OSC-16-6 1

APPEN0!X-1 (Continued)

D. TAG 5. 6, 7 and 8 - 0FFSITE MONITOR Reporting location:

Operation Support Center Extension in Technical Support Center Building Reports To:

Monitor Coordinator Basic Responsib111 ties:

Obtains monitoring kit, air sampler, water sampling bottles and vehicle.

NOTE: A set of keys for the vehicles are located inside each of the offsite monitor team kits. Kits are numbered to correspond with the OPPD vehicle identification number.

Infoms the Monitor Coordinator / Dose Assessment Specialist prior to any departures.

As directed, proceeds to designated location and takes samples as assigned and analyzes air samples.

Labels each sample and saves separately in olastic bags in accordance with EPIP-EOF-3, " Emergency Instrumentation and Equipment". This procedure l describes in detail how the samples are to be collected and analyzed.

Reports results to the Monitor Coordinator by radio thru the radio operator, Tag 16. When the Recovery Organization has been activated, the offsite ,

monitor team will be under the control of the Dose Assessment Specialist l at the EOF. ,

Comunicates with the Emergency Response Facilities on Channel No.1 the dedicated radio Ifne for emergency field comunication. Other channels can be used if problems develop. ,

Review plant conditions and projected or known release information with Monitor Coordinator or Oose Assessment Specialist periodically while in plume sectors.

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APPEE!X-1 - .

l (Continued) l l

l E. TAG 9 and 10 - GATE MONITOR l

i Reportina Location:

General Services Building Reports To:

Monitor Coordinator i Basic Responsibilities:

Notifies the Monitor Coordinator by telephone when he arrives at his work location to obtain any special instructions.

l Obtains available friskers from the storage area, checks batteries and makes preparations for monitoring personnel and equipment.

Monitors all personnel exiting the plant areat Paying particular attention to hands, feet and head area.

Sends contaminated personnel to the West entrance of the General Services Su11 ding for entry to the personnel decon station.

Monitors all emergency team members returning from the plant closely for .

contaminations properly bags anti contamination clothing, if contaminated.

Monitors all vehicles leaving the plants paying particular attention to vehicle tires and top. Vehicles returning to the site will not be routinely monitored unless specified by Monitor Coordinator.

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. o EP!ft-OSC-16-8 1

APPEN0!X-1 (Continued)

F. TAG 11, 12, 13 and 14 - ONSITE MONITOR Reportine location:

Operation Support Center Extension in Technical Support Center Building Reports To:

Monitor Coordinator Basic Responsibilities:

Obtains a full set of protective clothing including a full face respirator.

TLD and high range dosimeter.

Obtains a survey instrument, clipboard, pencil and survey maps from the emergency locker.

Reports to the monitor assembly room and informs the monitor Coordinator of his arrival.

Informs the Monitor Coordinator of any departures from the TSC.

Maintains survey of on site affected areas. One monitor team will use a vehicle for survey and inspection, if required.

May perfo m in-plant surveys as directed by the Site Director or Monitor Coordinator.

Visually inspect the owner controlled area for personnel occupancy. Owner controlled area consists of the property within the site boundary and the strip of exclusion land directly across the Missouri River which can be viewed from the screen house.

Perfoms habitability check of the Guard Building, Storeroom and a survey of the General Employee Training Building.

Iftheearlywarningsirenshavesour.ded(siteareaandgeneralemergencies) instruct all non-emergency workers to vacate the owner controlled area.

If a site or public evacuation has been declared, report all refusals to vacate by non emergency workers imediately to the Monitor Coordinator who will notify the appropriate county sheriff.

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. o t EPIP-05C-16-9 APPENDIX-1 O -

(Continued)

F. TAG 11, 12, 13 and 14 - ONSITE MONITOR (Continued)

After initial surveys and inspection have been completed, report back to the monitor assembly area to receive more directions from the Monitor Coordinator for continuing surveys.

Return all sample and survey results to the Sample Counter / Dosimetry Issuance ET TAG 21.

Usedoseratesamplelog(FigureEPIP-OSC-13.1)torecordalldoserate survey data which includes time of survey, location; type of survey, i.e.

Beta or Ganna; dose rate in mrom per hour; and name of surveyor. riso at the top of the form, fill in the date and the instruments used and serial numbers.

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9 ISSUED FEB 261987 FC/EPIP/03 R4 02-26-87

EP!h-OSC-16-10 1

kPPEN0!X-1 (Continued)

G. TAG 15 - MONITOR COORDINATOR Reportina location:

Technical Support Center Building, Room 107 Reports To:

Health Physics / Chemistry Supervisor Directs / Coordinates:

Emergency Re-entry Team Offsite Monitor Gate Monitor Onsite Monitor Radio Operator Rescue Squad Monitor Personnel Decontamination Outside Coordinator Basic Responsibilitiest

!s responsible initially to the Site Ofrector for all monitor team activities. When the HP/ Chemistry Supervisor position is manned,, Tag 15 shall report directly to this individual.

Ensures that the TSC Emergency Status Board indicates current conditions and assessments.

Ensures that all surveys and data are documented in the field by the monitor teams and delivered to the TSC.

• Coordinates in plant first aid assistance as needed.

Ensures that all onsite personnel have been checked for contamination.

Ensures that a radiation survey of the Control Room OSC AND TSC has been conducted.

When the Recovery Organization has been formed and the EOF activated, the Oose Assessment Specialist will assume responsibility for the Offsite l Monitor Teams, iS$UED FC/EPIP/03 FEB 261987 R4 02 26 87 4

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• f EPIP-05C-16-11 APPEN0!X-1 ~ -

(Continued)

G. TAG 15 - MONITOR C0ORDINATOR (Continued)

In coordination with the HP/ Chemistry Supervisor, directs onsite and offsite teams when to don protective clothing.

Ensures habitability checks are performed in the Guard Building, Storeroom, General Employees Training Building and the helipad as necessary.

Ensures all radio' transmissions during drills and/or exercises start and end

.with "THIS !$ A DRILL MESSAGE" or "TH S IS AN EXERCISE MESSAGE".

Ensures off-site and on-site monitor teams are briefed on changing plant conditions and known or projected release infomation, periodically when teams are in plume sectors.

Maintains dosimetry log on each of the off-site monitor team members.

Records, on the monitor locations map, monitor team location, survey results and time surveys were taken for each of the field monitoring teams (OPPD teams and state teams).

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9 EPIP-OSCg16-12

. APPEN0!X-1 (Continued)

H. TAG RADIO OPERATOR Reporting Location:

Operation Support Center Extension in Technical Support Center Building.

Reports To:

Monitor Coordinator Basic Responsibilities:

Establishes and maintains radio comunication with Offsite Monitor Teams, and the access road Security Guard from the TSC Building.

NOTE: The Offsite Monitor Teams will use dedicated radio Channel No. 1 for comunication.

Records in writing, all messages received so that the information is distributed and/or transmitted by FAX.

Transmits radio messages as directed to field Emergency Team Members.

Authorizes onsite entry of the Recovery Organization and emergency response personnel from prepared list. Relays entry authorization of other personnel as directed by the Monitor Coordinator.

During drills and/or exercises ensures all radio transmissions start and end with "THIS IS A DRILL MESSAGE" or "THIS IS AN EXERCISE MESSAGE" as appropriate.

ISSUED FC/EP!P/03 R4 02-26 87

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APPENDIX-1 (Continued) 4 I. TAG 17 - MESSAGE DISTRIBUTION / CLERICAL SUPPORT Reporting Location:

Operation Support Center Extension in Technical Support Center Building.

Reports To:

Security and Administrative Supervisor Basic Responsibilities:

Reports to the TSC and checks in with the Security and Administrative Supervisor.

Responsible for the collection and distribution of message traffic within the TSC.

(t Performs other administrative duties as required.

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EPIFt0SC-16-14 I

APPENDIX-1 (Continued)

J. TAG 18 - RESCUE SQUA0 MONITOR Reporting Location:

Operation Support Center Extension in Technical Support Center Building Reports To:

Monitor Coordinator Basic Responsibilities:

Receives instructions from the Monitor Coordinator i.e. name and location of injured personnel and if the injured person is contaminated.

Obtains a radiation survey instrument and performs operational check. Also, obtains a personnel air sampler.

Obtains four (4) high-range, zeroed pencil dosimeters.

Meets the Rescue Squad and issues a dosimeter to each member and ensures they are dressed in protective clothing if the injured person is contaminated.

Briefs them on the location and probable condition of any casualties.

Briefs the Rescue Squad on radiation hazards and other precautions to be taken. -

NOTE: The Rescue Squad personnel do not normally enter the auxiliary building unless personnel injuries dictate this entry is necessary.

The squad will normally be met with the injured personnel at the north emergency exit.

!. Accompanies the Rescue Squad to pick up casualties and provide, rddiological

coverage during the trip to; the hospital.

Furnishes hospital personnel with the following information, if known:

(a)Typesandextentofradiationexposure.

(b) Levels of external contamination. ,

ISSUED FC/EPIP/03 FEB 261987 R4 02-26-87

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C{', (Continued)

J. TAG 18 - RESCUE SOUAD MONITOR (Continued)

(c) Probability of internal contamination.

Collects, reads and records pencil dosimeters from Rescue Squad personnel. ,

Ensures that the Squad members, vehicle and equipment are free of contamination prior to release.

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EPI P'-05C-16-16

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APPENDIX-1 (Continued)

K. TAG 19 - PERSONNEL DECONTAMINATION Reporting Location:

Operation Support Center Extension in Technical Support Center Building Alternate Location:

General Services Building Reports To:

Monitor Coordinator Basic Resocnsibilities:

Reports to the Monitor Coordinator for a briefing.

Will aid in the decontamination of personnel using facilities specified by the Monitor Cocrdinator.

The following equipment will be available for use:

(a) Frisker(RM-14/15/19)

(b) Step-off pad with undress area (c) Containers for contaminated clothing.

NOTE: Each individual who is contaminated or who has contaminated clothing must have this clothing bagged individually with the person's name and the time placed on each bag.

(d) Cleaning materials (soap, brushes, towels, etc.)

(e) Clean clothing (i.e., paper coveralls and shoe-covers).

Uses procedure EPIP-EOF-10. " Personnel Decontamination", to brief personnel on decontamination methods to use (i.e., complete shower, wash hands, etc.).

1 ISSUED '

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- APPEN0!X-1

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K. TAG 19 - PERSONNEL DECONTAMINATION (Continued)

NOTE: Complete showers should be avoided unless absolutely necessary to prevent spread of contamination to other parts of individual's body.

Keeps Monitor Coordinator briefed on personnel decontamination status.

Records names and survey results, initial and final, of personnel admitted to decontamination station.

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APPENDIX-1 (Continued)

L. TAG 20 - CONTROL ROOM DATA COLLECTOR Reporting Location:

FCS Control Room Reports To:

Operations Support Manager Basic Responsibilities:

1. Collect operational, meteorological and radiological data from instrumentation and computer equipment in the Control Room.

2. Information collected is recorded on appropriate Fort Calhoun forms.

(a) Complete all itens, as appropriate for accident, on FC-194. If a particular item does not apply enter "N/A".

(b) Complete all items in Sections I and II, as appropriate for accider.t. on FC-197. For items that do not apply enter "N/A".

3. Deliver completed forms to; the Control Room communicator (phone talker) who will in-turn relay the information to phone talkers in the OSC, TSC and EOF.

4. Data must be collected and provided to the C. R. communicator every 15 minutes.

ISSUED FC/EPIP/03 R4 02-26-87

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APPENDIX-1 '

(Continued)

M. TAG 21 - SAMPLE COUNTER / DOSIMETRY ISSUANCE Reporting Location:

Operation Support Center Extension in Technical Support Center Building.

Reports To:

Monitor Coordinator Basic Responsibilities:

Ensures that all team members needing TLD"s and dosimeters have them.

NOTE: All dosimeters will be zeroed before being issued.

Maintains the TLD/ dosimeter log.

Sets up a counting station and counts all samples brought into the TSC and -

reports results to the Monitor Coordinator. Ensures that all samples are saved and labeled for future counting if needed.

Collects radiation monitoring devices from team members as they return from assigned tasks.

Keeps the Monitor Coordinator informed on counting results/ personnel exposure.

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EPIP-OSC-16-20

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APPENDIX-1 (Continued)

N. TAG 22 - OUTSIDE COORDINATOR Reporting Location:

General Services Building Reports To:

Monitor Coordinator Supervises:

All personnel that have evacuated the plant Basic Responsibilities:

Contacts the Monf ?or Coordinator in the TSC by telephone for instructions.

Coordinates outside activities in the vicinity of the entrance gate and general assembly area during NOE and Alert Emergencies.

Reports to the EOF for re-assignment during " Site Area Emergency" and

" General" Emergencies requiring site evacuation.

Ensures that all personnel that have evacuated the plant are in two groups:

(a) Personnel exiting from the auxiliary building area or (b) Personnel exiting the uncontrolled areas of the plant.

Ensures that all contaminated personnel are sent to the emergency decon station.

Ensures that all vehicles leaving the plant area are monitored (except emergency vehicles).

Reports names of any contaminated / injured personnel to; the Monitor Coordinator.

ISSUED FC/EPIP/03 FEB 2 61987 R4 02-26-87

f EPIP-OSC-16-21 APPENDIX-1

- (Continued)

O. TAG 23 - EOF INFORMATION SPECIALIST Reporting Location:

Emergency Operations Facility Reports To:

Site Director until the Recovery Manager takes full authority Coordinates:

EOF Technical Liaison Media Release Center Site Director Recovery Manager when Recovery Organization is activated Responsibilities:

Monitors status of emergency and relays timely and accurate information to the Media Release Center (MRC). .

Maintains information time log for post emergency reference.

Refer to M.2.6.2 for primary responsibility as related to the Recovery Organization.

Refer to EPIP-RR-40 for reporting assignment and basic duties.

l h ISSUED FC/EPIP/03 FEB 261987 R4 02-26-87 s

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EPIP-0SC-16-22 APPENDIX-1 (Continued)

P. TAG 24 - EOF TECHNICAL LIAISON Reporting Location:

Emergency Operations Facility Reports To:

EOF Information Specialist ,

Responsibilities:

. Monitors status of emergency and assists E0F Information Specialist in j collecting and interpreting nuclear-related data.

Serves as the EOF contact for technical liaison assigned to assist official spokesperson at the Media Release Center (MRC).

Refer to M.2.6.3 for primary responsibility as related to the secondary organization.

Refer to EPIP-RR-41 for reporting assignment and basic duties.

I ISSUED FEB 2 61987 R4 02-26-87 FC/EPIP/03 l - . - - - - . . . . . . _ . . - _ _ . . ,,,_- ----,, -... - -_ ,-..,

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Fort Calhoun Station Unit No.1 .

Emergency Plan Implementing Procedure EPIP.-EOF-6 Onsite/Offsite Dose Assessment I. PURPOSE A. This procedure provides instructions and calculations necessary to determine projected:

1. Whole Body Dose Rates at the Site Boundary

2. Thyroid Dose Rates at the Site Boundary

3. Lung Dose Rates at the Site Boundary

4. Whole Body Dose Rates for Offsite Locations

5. Thyroid Dose Rates for Offsite Locations

6. Lung Dose Rates for Offsite Locations

7. Integrated Whole Body Doses for Selected Locations

]

8. Integrated Thyroid Doses for Selected Locations

9. Integrated Lung Doses for Selected Locations 1 10. Projected Activity at the M.U.D. Intake Due to l Radioactive Liquid Releases i B. This procedure provides instructions and calculations necessary to determine actual offsite dose rates and verify activity release rates utilizing information from the onsite and offsite monitor teams, 1

l C. This procedure provides instructions and calculations necessary to I determine whole body dose from the contamination released through the l

plant stack and deposited on the ground.

D. This procedure provides step by step instructions for onsite/offsite dose assessment using the computer system. .

II. PREREQUISITES A. A radioactive release is suspected or known to be in progress.

B. The person performing dose assessment is trained in the use of and '

familiar with this procedure. l l

l ISSUED

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FC/EPIP/01 FEB 2 61987 R10 02-26-87

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EPIP-EOF-6-2 III. PRECAUTIONS A. This procedure has been prepared primarily for use by shift personnel in the Control Room. However, it may also be used by any dose assessment personnel as an alternate method to computer assessments. When so used, _

the appropriate personnel titles and emergency facility should be substituted for those identified in this procedure.

B. This procedure is divided into eight sections:

1. Section A - Assessment of airborne releases from the ventiliation stack. This section will be used for high readings on effluent monitors:

a. RM-052 (use only if RM-062 is out of service)

b. RM-060 (if RM-060 is offscale high, refer to 01-PAP-7 for using RM-063 accident filter)

c. RM-062

d. RM-063L

e. RM-063M

f. RM-063H

2. Section B - Assessment of airborne. releases from the main steam line. This section will be used for high readings on:

a. RM-064

3. Section C - Assessment of airborne releases from design containment leakage when the containment is isolated. This section will be used for high readings on:

a. ,RM-070

b. RM-071

c. RM-072

d. RM-073 .

e. RM-074

f. RM-075

g. RM-091A/B (use only if RM-070 through RM-075 are offscale/ inoperable)

4. Section 0 - Assessment of airborne releases using key isotopes from air samples. This section will be used if process monitors are offscale/ inoperable.

ISSUED FC/EPIP/01 10 02-26-87 l FEB 2 91987

._____._..m___ _ _ _ _ - , - . _ , , ,

.. - . .. u .= ;~. - .

j , EPIP-E0F-6-3 l

1 III. PRECAUTIONS (Contir)ued) j.G.

i

5. Section E - Assessment of liquid releases indicated by high readings on RM-055/'255A, or an uncontrolled release from the

. monitor tanks to the river.

6. Section F - Determination of actual offsite dose rates and verification of activity release rates by utilizing information from the onsite/offsite. monitor teams.

7. Section G - Determination of contamination release through the i plant stack by'providing a relationship between the effluent radiation monitor readings and the amount of contamination on tha ground and the resulting whole body ganna dose rates.

8. Section H - This section establishes step by step instructions for onsite/offsite dose assessment by use of the computerized program.

Instructions for the operation of the Tektronix-4105 computer teminal and the GE Teminet printers are listed step by step.

lSSUED

{

FC/EPIP/01 FEB 2 61987 R10 02-26-87

EPW-E0F-6-A-1 I

V. PROCEDURE

A. Section A - Assessment of Airborne Releases From the Ventilation Stack.

1. The Shift Supervisor or 'his designee, upon receipt of an alert or alarm indication on one or more effluent process monitors, shall assign the Shift Chemist to perform dose assessment. The Shift HP will be used as the alternate.

2. The person assigned to dose assessment will perform dose assessment determinations for Site Boundary, 2 miles, 5 miles, and 10 miles every 15 minutes until relieved or directed to stop by the Shift Supervisor or his designee. Dose assessment will be completed in accordance with the following:

a. Obtain the " Dose Assessment Forms Booklet" from the Control Room Emergency Gear Locker.

b. Detennine the process monitor to be used for the calculations in accordance with the following:

1. For noble gas (whole body) stack release use:

a. RM-062

b. RM-052 (if RM-062 out of service)

c. RM-063L, M, H (if RM-062/052 are offscale high)

1. For iodine (thyroid dose) stack release use:

a. RM-060

b. RM-063 accident filter (I.A.W. OI-PAP-7)

(If RM-060 is offscale high or out of service)

c. Obtain Attachment A-1 " Airborne Release Data Record - Ventilation Stack". Collect and record the following data for each process monitor assessment:

1. Date and Time

2. Present (or Average) Wind Speed - Wind speed meter is located on the north wall of the Control Room above the fire control and alarm panels (AI-184), or obtain wind speed from the Plant Computer by requesting information from operations personnel. Record wind speed; use the estimated average if the reading is unstable.

Average wind speed should be used if the release has been continuous.

ISSUED FC/EPIP/01 R10 02-26-87 FEB 2 61987

~

4 EPIP-EOF-6-A-2 I

V. PROCEDURE

(Continued) -

s

3. Present Wind Direction - Wind direction meter is located on the north wall of the Control Room above the fire control and alam panels (AI-184), or obtain wind direction from the Plant Computer by requesting information from operations personnel. Record wind direction; use the estimated average if the reading is unstable.

NOTE: This is the direction that the wind is coming from.

4. Present Delta Temperature (AT) - AT meter is located on the north wall of the Control Room above the fire control and alarm panels (AI-184), or obtain AT from the Plant Computer by requesting information from operations personnel.

5 .- Stability Class - Using the table and the AT from Step 4, determine the stability class and circle the correct designation. When a aT is connon to two stability classes, use the class nearest to class G.

6. Stability Conversion Factors - All graphs are based on a l single stability class to reduce the total number of

, graphs needed. Therefore, correction factors are needed

r to adjust dose rates for other stability classes. Simply

- locate the applicable stability class in the left column (from Step 5), and circle all four factors that fall to the right of the class. The factors will be used to adjust the dose rate value in a later step.

7. Affected Sectors - Using the overlay map located on the west wall of the Control Room, place the overlay centerline on the downwind exposure pathway (180* from the wind direction recorded in Step 3). Using the appropriate stability class, locate the applicable lines ,

on the overlay. This will outline the projected plume width. Determine the sectors in the plume pathway and record these sectors.

8. Stack Flow Rate - Stack flow rate meter is located behind the control panel on AI-44. The meter number is FR-758.

Meter reading is in standard cubic feet per minute (SCFM) times one thousand.

9'. Stack Flow Factor - Graphs are based on a stack flow rate of 72,500 SCFM. If actual stack flow rate is different, I the flow rate must be corrected. To correct this, divide the actual stack flow rate by 72,500.

1 ISSUED FC/EPIP/01 Rio 02-26-87 l FEB 2 61987 l .

EPIP-EOF-6k-3 I

V. PROCEDURE

(Continued) .

10. Process Monitor Reading (GCPM) - Record monitor reading (s) in gross counts per minute (GCPM) from affected monitor (s). or dose rate from the RM-063 filter.

It may be necessary to use the chart recorder to determine GCPM if the release has been terminated.

11. Calculated Release Rate - Perform release rate calculation at the bottom of the graph (s). Record the results in curies /second.

12. Actual Release Rate - Multiply the calculated release rate (Step 11) by the stack flow factor (Step 9). Record the results in Curies /Second.

13. Projected Duration of Release - The Shift Supenisor or his designee must determine the projected duration of the release. This infonnation is required to calculate the

projected total dose to a given area. Record this number in hours or a decimal notation for a fraction of an hour.

14 Indicated Dose Rates - Using the selected graphs, locate GCPM at the bottom, plot up to the present wind speed.

If wind speed falls between the indicated slopes, estimate where the lines would intersect. From the point of intersection, plot to the left to find the indicated dose rate. Record the dose rate in REM /Hr for each location,

a. For RM-060 and RM-063 filter, a sample time must be used, which will affect the actual graph results.

The graphs are based on a 15 minute sample time. To compensate, multiply the indicated dose rate from the graph by 15 minutes and divide by the actual sample time. This should be the time since the i accident happened. Record the results in REM /Hr for each location.

15. Actual Dose Rate - Multiply the indicated dose rates (Step 14) by the Stability Conversion factors for each .

location (Step 6) and then multiply the result by the Stack Flow Factor (Step 9). Record the results in REM /Hr.

16. Total Projected Dose to a Selected Location - Multiply the actual dose rates (Step 15) by the projected duration of release (Step 13). Record total projected dose to the selected location in REM for each location.

ISSUED -

FC/EPIP/01 FEB 2 61987 Rio 02-26-87

---,----,-w,-----, -,---.-n-,.,_n, ,--,---,-n,--- - . - , , - - - . - - n -,---- -- - - - - , , , - - - - - - - - - , - - - - -

_ . . . _ _ _ . . . _ _ ~ _

9 EPIP-EOF-6-A-4

I

V. PROCEDURE

(Continued) .

. 17. Report Results to'the Shift Supervisor or his designee -

Much of the information that has been recorded will be used on required report forms which must be completed within 15 minutes of accident classification. Expedite the completion of this form in a clear and accurate manner. Then report this information to the Shift Supervisor or his designee.

18. Protective Action Recommendation - The Shift Supervisor or his designee will compare the total projected dose to a selected location (Step 16) to the Protective Action Guidelines on the bottom of the " Airborne Release Data Record - Ventilation Stack". After detennining the proper recomended actions, he will initial Attachment A-1, and relay the information to the appropriate offsite government agencies.

d. After completion of the " Airborne Release Data Record -

Ventilation Stack" for the affected monitors, standby to repeat the process using new data sheets. Dose assessment must be completed every 15 minutes until relieved or directed to stop by the Shift Supervisor or his designee.

G i

ISSUED FC/EPIP/01 FEB 2 61987 R10 02-26-87

,-a- - - - - . - - . -- . , - . - - - . - _ -- _ _ , , _ , , , . _ , , , , . , - - - - - - - - . . . , - - - - - - - - - - - - - , ,

EPIP-E0F-6-A-5 M$,

CD ATTACHMENT A-1 AIRBORNE RELEASE DATA RECORD (VENTILATION STACK) cn C

. Fate /Ti.e / 7. Affected Sectors (from Sector Map)

2. Wind Speed MPH

3. Wind Direction From: Degrees 8. Stack Flow Rate CFM

4. Delta Temperature (AT) *C 9. Stack Flow Factor (StackFlowRate[ Step 7]*72500)

5. Stability Class (Circle appropriate class) g Class 10. Process Monitor Reading (s) l <-1.9 A Whole Body Thyroid

-1.9 to -1.7 8 i -1.7 to -1.5 C RM-052 CPM RM-060 CPM

-1.5 to -0.5 D RM-062 CPM RM-063 Filter R/Hr

-0.5 to 1.5 E RM-063L CPM 1.5 to 4 F RM-063M CPM

>4.0 G RM-063H CPM

6. Stat,ility Conversion Factors (Circle all 11. Calculated release rate (perform calculation on four in appropriate stability class) bottom of applicable graph)

Class S.B. 2 Mi. 5 Mi. 10 Mi. Whole Body Thyro.J A 7.lE 3 6.4E 3 8.9E 3 1.1E r Ci/Sec Ci/Sec

. B 4.5E r 2.2E r 1.2E 2 1.5E 2

. C 1.1E~1 6.3E 2 3.8E 2 2.6E 2 12. Actual Release Rate (Calculated Release Rate i D 2.9E 3 2.3E 1 1.9E~1 1.6E 3 LStep 11] x Stack Flow Factor [ Step 9]).

1 E 5.3E 1 4.7E l 4.3E 1 4.0E 3 F 1.0 1.0 1.0 1.0 Whole Body Thyroid l

G 1.7 2.1 2.3 2.4 j

Ci/Sec Ci/Sec

13. Projected Duration of Release Hrs.

(From Shif t Supervisor, in hours)

'/01 RIO 02-26-87 FC/ .

h b b- *

-- EPIP-EOF-6-A-6 .

g m ATTACW9ENT A-1 (Continued) ^

AIRBORNE RELEASE DATA RECORD

$ . yn C (VENTILATION STACK) kf D Indicated Dose Rates Stability Conversion Stack Flow Factor Actual Dose Projected Duration Total Projected Protective Action From Graph (s) X Factors X (Step 9) = Rate X of Release = Dose Recommendations REM /Hr (Step 6) REM /Hr (Step 13) REM From Guidelines Hrs Listed Below l Whole Body l l Whole Body l l Whole Body l S.B. X S.B. S.B. ,

2 Mt. X 2 Mi. 2 Mi.

5 Mt. X 5 Mt. 5 Mi.

S.B.

10 Mi. X 10 Mi. 10 Mt .

2 Mi.

l Thyroid l l Thyroid l l Thyroid l .5 Mt.

Indicated Dose Rate X 15 Min. 10 Mi.

Actual Sample Time (Min.)

5.B. X S.B. S.B. [

2 Mi. X 2 Mi. 2 Mi. i 5 Mt. X 5 Mt. 5 Mi. j 10 Mi. X 10 Mi. _

10 Mi.

PROTECTIVE ACTION GUIDELINES: ,

A. W.B. Dose < 1 REM Thyroid Dose < 5 REM i NO PROTECTIVE ACTION REQUIRED B. W.B. Dose > 1 REM Thyroid Dose > 5 REM Shift Supervisor Review:

4 < 5 REM < 25 REM SEEK SHELTER, CONSIDER EVACUATION -

l C. W.B. Dose > 5 REM Thyroid Dose > 25 REM CONDUCT MANDATORY EVACUATION RIO 02-26-87 l

W.B. DOSE RA"E A" S.8' ':M-052 ' i EPIP6 EOF-6-A-7

( FBI WHIS DE SEE )

0.011 N

0.010 'j 0.009 j

. W.S.=3.2 MPH 0.008

\/

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=

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0 100000 200000 ISSUED 31055 40085 500000 600000 700000

'N 2 00 92 2 7~

FEB 2 31987 Rio 02-26-87 1

Cl/SecINOBLE GASl= I GCFM-101 X f 1.34E-71

W.B. DOSE Rfi E 2 N::' ES lRM-052L EPIP-EOF-6-A-8 (FE YARES XDC SEE) 0.0026 BTACK R.0W= 72500 CFi i

0.0024 l

0.0022

/ l W.S.=1H-O.0020

. i 0.0018

- / .

y 0.0016 5 -

/

0

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l FEB 2 61987 R10 02-26-87 ci/Sec(N08LE GASl= ( GCFM-10 ) X ( !.34E-7 ) .

EPJP-EOF-6-A-!!

WH0.EBODYDOSERATESA"5NIESlRM-052 (FRVMR5neses) .

i 0.00044 SM R.0W= 72500 CFN

! 0.00040

~

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0.00036 / ,

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i issuEo 6 CPM ( M-052 )  !

FEB 2 61987 -

RIO 02-26-87

. ci/Sec(NOBLE GASl= ( GCPM-101X( i.34E-7 ) .

_ = . _.

. o O

E0 E BODY DOSE RATES AT 10 LES em-cor-w-10 AN-052)

(Y (FMDEM EBSEE) 0.00009 STAG R3l= 72500 CFH

- o 0.00008

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," .-V.S.= 20'M 0.00001 /

/

/lV O n o n n i u n n i n i n n e i n n o n u n i . . i i . n . . ,,, ,,, ,,, ,,,,, ,, ,, ,,,,,,,,, ,,,,,,,,,

I Nilll Milli EllN elill limil Ital Egg gun ague gg I I'S'lI 8 D GCPN ( M )

FEE 2 61967 RIO 02-26-87 C1/Sec(N0lLE GAS)= ( GCPM-10 )X( i.34E-7 ) .

W.B. DOSE RATES AT S.B. (RM-062) muum se.

o EPIP-EOF-6-/

0.130 STACXFLOW = 72.3 3 m ,

0.120 -

/ 1 0.110 '

~

W.S.=3.3 HPH 0.100 Y i-0.090 0.080 2 ' '

R

/

/ '

5 0.070

/ '

N.S.= 5 m i E0.060 / i

~

h '

j 0.050 s If.S.= 10 PH / l 0.040 , /

f .

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0.020 -

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l

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0 ' " " " " ' " " " " " " " " ' " " ' " " unnin o ne,,,, ,,,,,,,,, ,,,,,,,,,

8 MW N200 300NO #0000 2 0000 600000 mm go0N $200 me:

Issueo GCPN ( E062 )

FEB 2 61987 .

N/Sec 0GLE GAS)= ( GCPM-37 )X( i.6lE-6 )

• I R10 02-26-87 NNOTE: W.B. 00SE= 0 FOR WINO SPEEDS LESS THAN 3.3 WPH. .

i.

-..-,.--.,-...____..._-m-_. , . . . - - - , _ - , _ _ , , , - , - - _ . - _ _ _ _ . . _ - - , . _ _ . _ - - - - - , -

^ = -

. , _ n.. .. _ ___ ~. ._:c;. ~ ~ ~

. o 9 -

W.B. DOSE RATES AT 2 MILES (RM-062) l NMEE EPIP-EOF-6-A-12 0.032 , E M = 72. W H

~

0.030 -

/

0.028

/

l 0.026 0.024

' l

/

0.022 i.S.=iMPH

$0.020 '

N S 0.018

/

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D0 W.S.=2.5 MPH s, O, g .016

.0.014

/ /

/ -

0.012 / .=5 MPH s

/ /

0.010 / /

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0.008 / / W.S.=in NPH y 0.006

~

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0.004 - / - #

0.002

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/ "

" *S*=20 %

0 h' iniinie i niitient 7

eintisiin :::::: : esiinine, e,,,,,,,, ,,,,,,,,, , ,,,,,,,, ,,,,,,,,,

i 1028 80000 mm 20001 allt 2 0001 mm gMI h ISSUED GCPM ( M )

SWOO lee

.. FEB 2 61987 Rio 02-26-87 C1/Sec(NOBLE GAS)= ( GCPN-37 )X( 1.6lE-6 )

W.B. DOSE RATES AT 5 MILES (RM-0Ei2) emwasnases ..

EPIP-EOF- 6-A-13 ,

0.0056 O.0052 >

! 0.0048 r

! 0.0044 '

\

i v.s..e /

0.0040 v 0.003G / ,

i 2

= i E W.S.= 2.5 W H y w 0.0032

$0.0028 # /

u

. / / /

! E 0.0024 /

W.S.=5 HPH 7

- ' / /

0.001G WS"O HPH #

0.0012 ' -

i

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I K8 U E r, 6CPN(M-082)

FEB 2 61987 I C1/Sec 0GLE EAS)= ( GCPH-37 )X( i.6lE-6 )

RIO 02-26-87 l l

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W.B. DOSE RATES AT 10 MILES (RM-062) "

emwasnasee EPIP-EOF-6-A-14

'h O.0011' STA0RDW = 72,500 CFM 0.0010, ,/

i

!' N.

f 0.0009 /

0.0008

' W.S.= 1 - 3.3HPH 8

0.0007 h '

q -

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w

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I S S U E.D n GCPN (llH-062 )

FEB 2 6 B87 ._ .

C1/Sec 008LE 6ASl= ( GCPN-37 )X( i.68E-6 ) Rio 02-26-87

THYROID DOSE RATES AT S.B. (RM-060) -

FmYARmsVDCSgg EPIP-[0F-6.A-15

15Nin.CartridgeTlae 0.320 STACKFLOW=72,500CFX 0.300 )

0.280 5 0.260

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0.240

\

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0.220 \ /

ce 50.200 / /

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/

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l FEB 2 61987 l

C1/hc(*IbOI}E)= ( GCPM-75 )X( 3.7E-9 .' ) Rio 02-26-87 3? 0TE: THYR 010 DOSE = 0 FOR Wit:0 SPEEDS LESS THAtt 3.3 .

W:H l

THYROID DOSE RATES T 2 MILES (RM-060? ._;

FEIREIBIDD SHg EPIP-EOF-6 A-16 O

. 15Nin.CartridgeTime 0.160 SDDRDW = 72,500 (TN 0.150 0.140 '

- /

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3 g .090 0 7 .

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FEB 2 61987 .

Rio 02-26-87 l

C1/Sec(IElIlE)= ( GCPH-75 )X( 5.7E-9 )-

t

. THYROID DOSE RATES AT 5 MILES (RM-060)';- ,

FElTE!!S E3 SEg EPIP-EOF-6.A-17 15 Win.CartridgeTime STADRai = 72,500 CFil 0.036

/

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tttttttti ettttgtt, 0 1030 200000 Emo em 522 20 5 703000 20 2 2000 Es GCPM ( RM-060 )

lSSUED FEB 2 61987 Rio 02-26-87 C1/Sec(ID0DE)= ( GCPM-75 )X( 3.7E-9 )

. e T-iYROID DOSE RATES AT 10 MILES (RM-060)

FE WWE Es g EPI P-E0' -6. A-18

{ '

15 Min.CartridgeTime 0.014 j STAOROW = 72.500 7N 0.013 0.012

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FEB 2 61997 R10 02-26-87

! C1/Sec(IODIE)= ( GCPN-75 )X( 3.7E-9 )

___._______,.________.,,,,,_...,__,,___.._,7 _

W~.B. DOSE RATES AT S.B. (RWOS,3L)

FE115!5EDSEM EPIP-EOF-6 A-19 0.280! - -

ST M N = 72.500 E 0.260

0.240 W.S. '3.3HPH . /

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THYROID. DOSE RATES AT' S.B. (RM-083 FILTER)

(HR WEIN 95 5415)

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• R10 02-26-87 i FEB 2 61987

• Cl/Sec(I(EllE)= 9ET FRTS M ET0X( 3.2it-3 ) -

i .

EPIP, EOF-6-B-1 I

V. PROCEDURE

(Continued)

8. Section B - Assessment of Airborne Releases From the Main Steam Line Using RM-064.

1. The Shift Supervisor or his designee, upon receipt of an alert or alarm indication on RM-064, shall assign the Shif t Chemist to perform dose assessment. The Shift HP will be used as the alternate.

2. The person assigned to dose assessment will perform dose assessment determinations for Site Boundary, 2 Miles, 5 Miles, and 10 Miles every 15 minutes until relieved or directed to stop by the Shift Supervisor or his designee. Oose assessment will be completed in accordance with the following:

a. Obtain the " Dose Assessment Forms Booklet" from the Control Room Emergency Gear Locker.

b. Determine the release pathway from the main steam line.

Operations personnel will determine this by use of OI. PAP-8 and other applicable procedures,

c. This procedure is primarily for initial assessments using RM-064 For more detailed release rate calculations and procedures for use when RM-064 is offscale, refer to 01-PAP-8.

d. Obtain Attachment B-1 " Airborne Release Data Record - Main SteamLine(RM-064)". Collect and record the following data for each assessment:

1 Date and Time 1.

2. Present (or Average) Wind Speed - Wind speed meter is located on the north wall of the Control Room above the fire control and alarm panels (A!-184), or obtain wind speed from the Plant Computer by requesting information from operations personnel. Record wind speed; use the estimated average if the reading is unstable. Average wind speed should be used if the release has been continuous.

3. Present Wind Direction - Wind direction meter is located on the north wall of the Control Room above the fire control and alarm panels (Al-184), or obtain wind direction from the Plant Computer by requesting l

information from operations personnel. Record wind

direction; use the estimated average if the reading is i unstable.

NOTE: This is the direction that the wind is coming from.

i lSSUED FC/EP!P/01 FEB 2 61987 R10 02-26-87

. . ._._.,...___m_.._._

. EPIP-E0F-6-8-2 I

V. PROCEDURE

(Continued)

4. PresentDeltaTemperature(AT)-ATmeterislocatedon the north well of the Control Room above the fire control and alam panels (A!-184) or obtain AT from the Plant Computer by requesting infomation from operations

. personnel. ,

5. Stability Class - Using the table and the AT from Step 4, detemine the stability class and circle the correct designation. When a AT is cosmon to two stability classes, use the class nearest to Class G.

6. Stability Conversion Factors - All graphs are based on a single stability class to reduce the total number of graphs needed. Therefore, correction factors are needed to adjust dose rates for other stability classes. Simply locate the applicable stability class in the left column (from Step 5), and circle all four factors that fall to the right of the class. The factors will be used to adjust the dose rate value in a later step.

7. Affected Sectors - Using the overlay map located on the west well of the Control Room, place the overlay centerlineonthedownwindexposurepathway(180'from the wind direction recorded in Step 3). Using the appropriate stability class, locate the applicable lines on the overlay. This will outline the projected plume

{_ width. Detemine the sectors in the plume pathway and record these sectors.

8. Release Pathway - Circle the detemined release pathway.

This will be: steam safeties, aux. feed pump, or atmospheric dump.

9. Flow Ratio - A correction for actual flow from each release pathway must be detemined, as it affects release rate and total dose rate. The ratio is based on maximum flow through individual (or combinations of) open flowpaths,whichisthendividedby3.268E+06lbm/Hr(the maximum flow rate for all flowpaths). To determine flow ratio, the Shift Supervisor must have detemined the release pathway. For aus. feed pump or HCV 1040 (steam dump) use the listed ratio. For steam safeties, a detemination of main steam pressure must be made. If steam pressure is below 1000 psig, no safeties will be open. As pressure increases, the safeties will open progressively, increasing the ratio as each opens.

Detemine the steam pressures find ratio value on the chart. Circle the value detemined. Ngjf : If more than one pathway is releasing, add appHeable flow rates.

( l88UED FC/EPIP/01 FE8 2 6 W g pg

?

EPIP; EOF-6-8 3 I

V. PROCEDURE

(Continued)

10. RM-064GrossCountsPerMinute(GCPM)-Recordthe indicated GCPM from RM-064 It my be necessary to use the chart recorder to determine GCPM if the release has been teminated.

11. Release Rate Calculation - Subtract 30 from RM-064 GCPM (Step 10), then multiply the result by the flow ratio (Step 9), then multiply the result by the indicated constant. Record the results in curies /second.

12. Projected Duration of Release - The Shift Supervisor or his designee must detemine the projected duration of the release. This information is required to calculate the projected total dose to a given area. Record this number in hours or a decimal notation for a fraction of an hour.

13. Indicated Dose Rate - Using the graphs, locate GCPM at the bottom, plot up to the present wind speed. If wind speed falls between the indicated slopes, estimate where the lines would intersect. From the point of intersection, plot left to the associated dose rate.

Record the results in R/Hr.

14. Actual Dose Rate - Multiply the indicated dose rate (Step

13) by the stability conversion factors for each location (Step 6) and then multiply the result by the flow ratio (Step 9). Record the results in Rem /Hr.

15. Total Projected Dose to a Selected Location - Multiply the actual dose rate (Step 14) by the projected duration ofrelease(Step 12). Record total projected dose to the selected location in REM.

16. Report Results to the Shift Supervisor or his designee -

Much of the information that has been recorded will be used on required report forms which must be completed within 15 minutes of accident classification. Expedite the completion of this fom in a clear and accurate manner. Then report this infomation to the Shift Supervisor or his designee.

17. Protective Action Reconnendation - The Shif t Supervisor or his designee will compare the total projected dose to aselectedlocation(Step 15)totheProtectiveAction Guidelines on the bottom of the "Afrborne Release Data Record-MainSteamLine(RM064)". After detemining the proper reconnended actions he will initial Attachment 8-1, and relay the information to the appropriate offsite government agencies.

1SSUED FC/EP!P/01 FE8 26 1997 R10 02 26 87

, , - - - - , - , , , . - . . - - , _ ,,.-,._n,v _ - . ..,, --,,----,--.,--,.n_

EPIP-EOF-6-8-4 I

V. PROCEDURE

(Continued) .

C. . e. After completion of the " Airborne Release Data Record - Main Steam Line (RM-064)", standby to repeat the process using a new data sheet. Dose assessment must be completed every 15 minutes until relieved or directed to stop by the Shift Supervisor or his designee.

l l

l i

• i 1

lSSUED

((

FC/EPIP/01 FEB 2 6 7987 R10 02-26 87

m ~

g es EPIP-EOF-6-8-5 es sa ATTACMENT 8-1 o- C AIR 90RNE RELEASE DATA RECORD 23 m MAIN STEAM LINE (RM-064)

55. n

1. Date/ Time / 7. Affected Sectors (from Sector Map)

2. Wind Speed MPH

3. Wind Direction From: Degrees 8. Release Pathway Steam Safeties (Circle the applicable pathways) Aux. Feed Pump

4. Delta Temperature (AT) *C Atmospheric Dump

5. Stability Class 9. Flow Ratio .

(Circle appropriate class) g Class (From Table Below): Circle Determined Value:

<-1.9 A Steam Safeties Aux. Feed Atmospheric e l.9 to -1.7 8 Steam Pressure Flow Ratio Pump (FW-10) Guse (HCV-1040)

-1.7 to -1.5 C > 1000 psia .0453 .00275 .0459 l

-1.5 to -0.5 D T 1015 psia .284 l

-0.5 to 1.5 E T 1025 psia .523 1.5 to 4.0 F T 1040 psia .761 l >4.0 G {1050 psia 1.0

6. Stability Conversion Factors (Circle all NOTE: If more than one pathway is releasing, add j four in appropriate stability class) applicable flow ratios.

Class 5.5. 2 Mi. 5 Mi. 10 Mi. 10. SM-064 Reading GCPM l

i A 7.lE 3 6.4E 3 8.9E 3 1.1E r 11. Release Rate Calculation:

l . B 4.5E 2 2.2E 2 1.2E r 1.5E 2 C1/Sec=(m-064 GCPM-30)(Flow Ratio)(6.16)= Ci/Sec C 1.lE 1 6.3E 2 3.8E 2 2.6E r D 2.9E 1 2.3E 1 1.9E 1 1.6E 1 12. Projected Duration of Release: Hrs E 5.3E 1 4.7E 1 4.3E 1 4.0E 1 (From Shift Supervisor, in Hours)

F 1.0 1.0 1.0 1.0 G 1.7 2.1 2.3 2.4 l

b e

RIO 02-26-87 l FC/EI 31 1

m ,

N5 EPIP-E0F-6-8-6 l *" on ATTACMIENT 8-1 (Continued) .

C AIR 90RNE RELEASE DATA RECORD ~

MAIN STEAM LINE (RM-064)

$nn Indicated Stability Fiow Actuai Projected Total Protective Dose Rates Conversion Ratio Dose Duration Projected Action

~

From Graph (s) I Factors I (Step 9) = Rate I of Release = Dose Reccessendations REM /Hr (Step 6) REM /Hr (Step 12) REM From Guidelines Mrs Listed Below l m oie sody l l moie sody l l uhoie sody I s.n. I s.n. s.n.

~

2 Mt. I 2 Mi. 2 Mi.

5 Mt. X 5 Mi. 5 Mi.

S.B.

10 Mt. X 10 Mt. 10 Mi.

2 Mi.

5 Mi.

10 Mi.

! PROTECTIVE ACTION GUIDELINES:

1 A. W.B. Dose < 1 REM NO PROTECTIVE ACTION REQUIRED ,

l

8. W.B. Dose > 1 REM Shift Supervisor Review: i

<5ROI .

SEEK SHELTER CONSIDER EVACUATION C. W.B. Dose > 5 REM CONDUCT MANDATORY. EVACUATION RIO 02-26-87 FC/EPIP/01 l_ _ _

W.B. 00'SE RA"ES A" S.B. M -064 m,.ar.....;

tavannemai

,, su. sin. am. 3.aus tam-3

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l W.B. DOSE RA"ES AT 2 nills)W-064; m e. .....  !

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W.B. DOSE RATES A" 10 NRES )N-06( . en,.co,....1o 10000  :- -. . . . n n  : .- - . .  : n -== =- - . . u n SAT. STN. ROW 3.aIE5 Ul/W

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EPIP-EOF-6-C-l I

V. PROCEDURE

(Continued) ,

C. Section C - Assessment of Airborne Releases From Containment Design Leakage.

1. The Shift Supervisor or his designee, upon receipt of an alert or alarm indication on RM-070, RM-071, RM-072. RM-073 RM-074 RM-075 RM-091A, or RM-0918 shall assign the Shift Chemist to perform dose assessment. The Shift HP will be used as the alternate. ,

2. The person assigned to dose assessment will perform dose assessment determinations for $1te Soundary, 2 Miles, 5 Miles, and 10 Miles every 15 minutes until relieved or directed to stop by the Shift Supervisor or his designee. Dose assessment will be completed in accordance with the following:  ;

a. Obtain the " Dose Assessment Forms Booklet" from the Control Room Emergency Gear Locker,

b. Detemine the need to perform this method of dose assessment based on one or more of the following:

1. High or offscale readings on Containment area monitors.

2. High readings on RM-050/051.

3. Loss of coolant accident (LOCA) in the Containment.

4 Previous criteria combined with no stack flow, indicating that any release will be from Containment leakage.

c. Obtain Attachment C-1 " Containment Release Data Record" from the Oose Assessment Foms Booklet. Collect and record the following data for each assessment

• l

1. Date and Time ,

2. Present(orAverage)WindSpeed-Windspeedmeteris located on the north wall of the Control Room above the fire control and alarm panels (Al-184), or obtain wind speed from the Plant Computer by requesting information from operations personnel. Record wind speedt use the, estimated average if the reading is unstable.. Average wind speed should be used if the release has been continuous.

3. Present Wind Direction - Wind direction meter is located on the north wall of the Control Room above the fire control and alarm panels (Al-184), or obtain wind direction from the Plant Computer by requesting information from operations personnel. Record wind directions use the estimated average if the reading is unstable. ,

NOTE: This is the direction that the wind is coming i ISSUED from.

FC/EP!P/01 FEB 2 61987 R10 02-26 87

EPIP-EOF-6-C-i s

I

V. PROCEDURE

(Continued)

4. Present Delta Temperature (aT) - ai meter is located on the north wall of the Control Room above the fire control ,'

and alarm panels (Al-IS4), or obtain AT from the Plant Computer by requesting inforntion from operations personnel.

5. Stability Class - Uttng the chart and the AT from itep 4 detennine the stability class and circle the core:ct designation. When a 4T is comon to two stability classes, use the class nearest to Class G.

6. Stability Converstor: Factors - All.gefphs are based on a single stability class to reduce tM total number of graphs needett. Theret' ore, correctiors factors arti needed to adjust dose rates for other stability c, lasses. Simply locate the applicable stability class in the left colc.w (from Step Sh and circle all four factors that fall to '

the right ot~ the 'ctus. The factors will be used to adjur.t the dose rate value in a later step.

7. Affec;ed Sectors - Using the overlay N 9 located on the west wall on centerline of the the Control downwindRoom, place exposure the overlay pathway (180

• from the wind direction recorded in Step 3). Uting the appropriate stability class, locate the applicable lines on the overlay. This will outline the pro,".ct.d alume C- width. Detennine the sectors in the pl6te'pathwaf and record these sectors.

8. Area Monitor Nunber/ Dose Rate Petding Determine f.he highest reading area monito". Record the monitor i' umber and the monitor reading in IEtl/Hr.

a. If all containnent aree monitors av inoperabic or offscale, a direct rending (.ith a Teletector or other high range instrument) m st be taken at the approsriate containment penetrations. See Attacwents C-11 and C-12 for the euct location of these penetratteris. Record the reading and circle the appropriato units,

b. A correction factor is required to account for the difference between the location of ttie area monitor and the location of tbf penetratien. Using Attachment C-10, locate the time sinco the accident-at the bottom of tne grap1, plot down to the penetration /ared monitor used, then ole? to the .

lef*, to the appropriate multiplicatica factor.

Record the tesults.

ISSUED FC/EP!P/01 FEB 2 61987 n10 02 tr.. .s7

y, ~ _ _ ._ -- _ _ .

,} - . .

i '

g 1 EPIF-EOF-6-C-3 y IV. PIOCEDURE (Continued)

8. c. The actual monitor reading is determined by bc multiplying the direct reading at the penetration by the multiplication factor (Step .b). - Record the results:in REM /Hr.

9. Calculated Release Rate - Perform release rate-calculation at the bottom of the graph (s). Record the

results in Curies /second.

',/ ,

10. Projected Duration of Release - The shift supervisor or his designee must determine the projected duration of release. .This information is required to calculate the projected total dose to a given area. Record this number in hours or a decimal notation for a fraction of an hour.

. 11. Indicated Dose Rates - Using the selected graph (s), locate

, REM /Hr at the bottom, plot up to the present wind speed.

I i

If wind speed falls between the indicated slopes, estimate

!. where the lines would intersect. From the point of inter-

[ section, plot to the left to find the indicated dose rate.  ;

l- Record the dose rate in REM /Hr for each location.  ;

p ,

12. Actual Dose Rate - multiply the indicated dose rates (Step i 11) by the Stability conversion factors for each location i (Step 6). Record the results in REM /Hr.

j 13. Total Projected Dose to a Selected Location - Multiply i

the actual dose rate (s) (Step 12) by the projected duration j of release (Step 10). Record the total projected dose to.

j the selected locations in REM for each location.

1

14. Report Results to the Shift Supervisor or his designee -

Much of the information that has been recorded will be l

used on required report forms which must be completed I within 15 minutes of accident classification. Expedite i the completion of this form in a clear and accurate

' manner. Then report this information to the Shift h -

Supervisor or his designee. e l

j 15. Protective Action Recommendation - The Shift Supervisor or his designee will compare the total projedted whole f

~ body dose and the total projected thyroid dose to the

! protective action guidelines on the bottom of the

! ; ,' " Containment Release Data Record". After determining the i - proper recossended actions he will initial Attachment C-1

r. and relay the information to the appropriate offsite i .

government agencies, i

l d. After completion of the " Containment Release Data Record",

! standby to repeat the process using new data sheets. Dose l ,' ,

assessment must be completed every 15 minutes until relieved i , or directed to stop by the Shift Supervisor or his designee.

( ,. o

!. ISSUED i ' ' ', FC/EPIP/01 R10 02-26-87 FEB 2 61987

i. .

' 1

- EPIP-EOF-6-C-4 i N

" "m~ ATTACMENT C-1 CONTAINMENT RELEASE DATA RECORD-un , '

a c .-

m -

b Date/ Time / 7. Affected Sectors

2. Wind Speed MPH 8. Affected Monitor Number /

Dose Rate Reading RM- / REM /Hr

3. Wind Direction From: Degrees If area monitor reading is unavailable or off scale, calculate the dose rate by using the following:

4. Delta Temperature (AT) *C A. Take a direct radiation reading at containment

5. Stability Class penetration H-4 or C-2 (see attachments C-11 and (Circle appropriate class) AT Class and C-12 for exact locations). ,

REN/Hr  !

<-1.9 A

-1.9 to -1.7 B B. Using Attachment C-10 locate time since accident, plot down to penetration / monitor used, plot left

~

-1.7 to -1.5 C l

-1.5 to -0.5 D to multiplication factor.

-0.5 to 1.5 E 1.5 to 4 F '

>4.0 G C. Direct reading (Step 8A) x multiplication factor )

(Step 88) = actual monitor reading. Record this  !

6. Stability Conversion Factors (Circle all value in REM /Hr, sin Step 8.  ;.

four in appropriate stability class) ,

9. Calculated Release Rate ' }

Class S.B. 2 Mt. 5 Mt. 10 Mi. (Perform calculation on bottom of graph) -

l t

7.1E

• 6.4E 3 8.9E

• 1.1E r Whole Body Thyroid }

A 1.2E

• 1.5E r l B 4.5E 8 2.2E a t C 1.1E 1 6.3E 2 3.8E r 2.6E 8 C1/Sec Ci/Sec D 2.9E 1 2.3E 1 1.9E 1 1.6E 1 '

4.7E 1 4.3E 1 4.0E 1 10. Projected Duration of Release Hrs (-

E 5.3E 1 F 1.0 1.0 1.0 1.0 (From Shift Supervisor, in Hours) ['

G 1.7 2.1 2.3 2.4 {-

3 f

o L

I e

1. 4 RIO~ 02-26-87 FC/EPIP/01

- I

EPIP-EOF-6-C-5 ATTACHMENT C-1 (Continued)

CONTAINMENT RELEASE DATA RECORD

-n -

$ Total Protective

$ [C Indicated Dose Rates Stability Conversion Actual Dose Projected Duration Projected Action 4 $pC N

, From Graph (s) X Factor (Step 6)

= Rate REM /Hr

.X of Release (Step 10)

= Dose REM Recommendations From Guidelines i REM /Hr Hrs Listed Below l Whole Body l l Whole Body l l Whole Body l S.B. X = S.B.

I 2 Mi. X = 2 Mi. ,

i j 5 Mi . X = 5 Mi. -

S.B.

10 Mi. X = 10 Mt.

i 2 Mi.

Thyroid l Thyroid l l Thyroid l 5 Mi.

l l S.B. X = S.B. 10 Mi.

2 Mi. X = 2 Mi.

5 Mi, i 5 Mi. X =

) .

10 Mi, X = 10 Mt.

I -,

PROTECTIVE ACTION GUIDELINES:

l A. W.B. Dose < 1 REM Thyroid Dose < 5 REM i NO PROTECTIVE*

ACTION REQUIRED i

! B. W.B. Dose > 1 REM Thyroid Dose > 5 REM Shift Supervisor Review:

< 5 REM < 25 REM -

SEEK SHELTER, CONSIDER EVACUATION C. W.B. Dose > 5 REM . Thyroid Dose > 25 REM '

i CONDUCT MANDATORY EVACUATION . .

RIO 02-26-87 FC/EPli .

,_ .. . . . . . . ~ .

EPIP-EOF-6-C-6 <

W.B.

DOSE RATES AT S.8. (CONTAINMENT MONITORS) )

(flR YARMi VDE SPEEIE) -

h CONT. LEAK =1.5CFM 100 _

=

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R10 02-26-87

~

C1/Sec 0GLE GAS)= EA WITE( R/W )X ( i.12E-5 )

,W .B.

DOSE RATES AT 2 MILES (CONTAINMENT M.ON (FE VEM ym m ) EPIP-EOF-6-C-7 CONT. LEM= 1.5 CFN 10 3

7 l

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1SSUED E g g l

FEB 2 61987 AEA MONITOR ( RM )

1 .

Ci/Sec(NOBLE GAS)= AREA NONITORI R& lx ( i.12E-5 ) R10 02-26-87

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1 W.8, DOSE RATES AT 5 MILES (CONTAINMENT MONITORS) l (5 TARIS XDO 9EBE) EPIP-EOF-6-C-8

, , CMT. LEAK =1.5CFM Gi 5

/ \

f 2 /

f / ,

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.1 N.S.= 1 m / T / / '

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t 5 / J' / /

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.001 2 3 4 5 6 789 2 3 4 5 6 783

r ISSUED B 1E7 I {'~ FEB 2 61987 AEA WITE ( Mt )

) .

i C1/Sec 0ERE SAS)= AEA HITE( R/Hr )x( i.12E-5 ) RIO 02-26-87

. _ , , - - - - -.-.- , __ _,--------.-e,-. - , - - - , _ - - - - - . _ - --. . --- . . r-- - - - - - - - , - - - - , - . , , , - - , - - - - , - - - - -

.W .B. DOSE RATES AT 10 MILES (CONTAINMENT MONITORS) '

EPIP-E0f-6-C-9

- IFOIVAIEXIS V M S E E )

CONT. LEAK =i.5CFM i

5 /

/

/ f

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g / / .

5

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x / ,

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5 / / /

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' 8I 2 3 4 8 788 E ISSUED 8 FEB 2 61987 E AEA MONITOR ( R/It- )

R10 02-26-87 C1/Sec(NOBLE GAS)= AREA NONITOR( R/Hr )x( i.12E-5 )

- ^ -

- ' '^-------- --

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! THYROID DOSE RATES AT S.B. (CONTAINNENT NONITORS)

-- EPIP-EOF-6-C-10 (pg yggs gDE SEE)

.h CONT. LEA =1.5CFM 100

)

3  !

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s 5

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g 2 5 g

2 5 g

2 5 g

FEB 2 61987 AIEA MIT51 ('R/W )

RIO 02-26-87 Ci/SecIIDOIEl= AREA MONITORI R/Hr )XI 2.07E-9 ) -

m------ - - , - , , , - -.---v-,~ a,,n,,._wm-n,w,_ - .

EPIP-EOF-6-C-11' THYROID DOSE RATES AT. 2 MILES (CONTAINMENT MONITORS)

~

(RR VEIE VDC SPEBS )

CONT. LEM= 1.5 Cr1 100 i

t I

3 10 ,

/

/

3

/

2 , l <

l ,

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f

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8

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/

i /

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s s' ,,

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.001 2 5 2 5 2 5 2 5 1D ISSUED jg. g g FEB 2 61987 AREA WONITE ( R/Hr )

R10 02-26-87 C1/Sec(IODINE)= AREA WONITOR( R/Hr )X( 2.07E-8 ) .

.._.=- - - - --

z_x. _. _ _;, - :_ _ _ ;- _; -

THYROID DOSE RATES AT 5 MILES (CONTAINMENT MONITORS)

'EPIP-EOF-6-C-12

,p .

(FmVans3DOSEBE)

V CMT. LEAK =1.5CFN 10 ,

1 i

3 i i

/

3 W.S.= 1 M j /

\ ,

7

e .

/ ,

/ / l

/

3 F ,r

/ e r

/ / /

/

W.S.= 5 H l / / -

/ j l /

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/ x ,

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/ l/ / f i

l / / /

3

/

[ r

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l _ n'g ,

, l

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FEB 2 61987 R10 02-26-87

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EPIP-EOF-6-D-1 I

V. PROCEDURE

(Continud)

O. Section 0 - Assessment of Airborne Releases Using Key Isotopes From Air Samples.

1. The Shift Supervisor or'his designee, upon receipt of an alarm indication on one or more process _ monitors or power failure to the process monitors, shall assign the Shift Chemist to perform dose assessment. The Shift HP will be used as the alternate.

2. The person assigned to dose assessment will perform dose assessment deteminations until relieved.or directed to stop by the shift supervisor or his designee. Dose assessment will be completed in accordance with the following: (

a. Obtain the " Dose Assessment Forms Booklet" from the Control Room Emergency Gear Locker,

b. Perform dose assessment as described in Sections A through C of the dose assessment procedure if possible,

c. Should all monitors for a release pathway fail due to loss of power or are offscale, use this method of dose assessment.

d. Obtain Attachment 0-1 " Key Isotope Data Record" from the Dose Assessment Forms Booklet. Collect and record the following data for the affected pathway:

1. Date and Time

2. Selected Location - Circle the selected location for the calculation being perfomed. This will be: Site Boundary, 2 miles, 5 miles, or 10 miles.

3. Present (or Average) Wind Speed - Wind speed meter is located on the north wall of the Control Room above the fire control and alarm panels (AI-184), or obtain wind speed from the Plant Computer by requesting information from operations personnel. Record wind speed; use the estimated average if the reading is somewhat unstable.

Average wind speed should be used if the release has been continuous.

4 Present Wind Direction - Wind direction meter is located on the north wall of the Control Room above the fire control and alarm panels (AI-184), or obtain wind direction from the Plant Computer by requesting information from operations personnel. Record wind direction; use the estimated average if the reading is somewhat unstable. NOTE: This is the direction that the wind is coming 1 rom.

ISSUED FC/EPIP/01 FEB 2 6 I!NT Rio 02-26-87

.. ..az - - - -- --

EPIP-EOF-6-0-2

I.V . PROCEDURE (Continued)

5. Present Delta Temperature (AT) - aT meter is located on the north wall of the Control Room above the fire control and alarm panels (AI-184), or obtain AT from the Plant Computer by requesting information from operations personnel.

6. Stability Class - Using the chart at the end of Attachment 0-1 and the aT from Step 5, determine the stability class and circle the correct designation.

When a AT is common to two stability classes, use the class nearest to Class A.

7. Affected Sectors - Using the overlay map located on the west wall of the Control Reor:, place the overlay centerline on the exposure pathway (180' from the wind direction' recorded in Step 4). Using the appropriate stability class, locate the applicable lines on the overlay. This will outline the projected plume width.

Determine the sectors in the plume pathway and record these sectors. Record adjacent sectors if plume is close to the boundaries.

8. Stack Flow Rate - Stack flow rate meter is located behind the control panel on AI-44. The meter number is FR-758.

Meter reading is in standard cubic feet per minute (SCFM)

{ times one thousand.

9. Present Main Steam Flow Rate - If the release is from primary to secondary, refer to 01-PAP-8 to determine the main steam flow rate. Record the results in cubic feet perminute(CFM).

10. X/Q at Site Boundary - This is required to calculate dose rate if the site boundary is the selected location.

Obtain site boundary X/Q by requesting infonnation from operations personnel or use the following formula:

= 1.0E-04 (g/m3) (Wind Speed)(.447)

11. a. X/Q for Downwind Locations - This is required to calculate dose rate for a downwind location. Using the stability class from Step 6 and the selected location, read chart on the " Key Isotope Data Record" to determine the diffusion factor for the selected location. Circle the diffusion factor to be used.

( lSSUED R10 02-26-87

.FC/EPIP/01 FEB 2 61987

EPIP-E0F-6-D-3 I

V. PROCEDURE

(Continued)

11. b. Now calculate X/Q for the selected location using the following fomula:

Q = (Diffusion Factor)

(8g/M8) (Wind speed)(.447)

12. Whole Body Dose Rate - A determination of specific isotopic concentrations must be made to determine the projected whole body dose rate,

a. Request that Chemistry obtain an air sample using a Gas Marinelli from RM-061 for a stack release or RM-057 for a primary to secondary release, and perform an isotopic analysis on the sample, using the applicable procedures.

b. Obtain Attachment D-2 "Whole Body Dose Rate Calculation Sheet". Obtain the isotopic concentration for each nuclide listed in Column I from the analysis report. Then record the required nuclide concentrations in Column II in C1/m8 NOTE: 1 yCi/cc = 1 C1/m8

c. Calculate the radionuclide release by use of the following formula:

Radionuclide =

(Column II Concentrations) X (Stack Flow Rate /) X (4.72E-04)

Release Rate ( or Main Steam )

(Ci/sec) ( Flow Rate )

Record results in Column III.

d. Calculate the whole body dose rate factor for each isotope by use of the following formula:

Whole Body = (Release Rates From) X (Average Gamma Energy)

Dose Rate ( Column III ) ( in Column IV )

Factor Record results in Column V.

e. Determine the total whole body dose rate. factor by adding all values recorded in Column V. Record the total, ISSUED RIO 02-26-87 FC/EPIP/01

EPIP-EOF-6-D-4 I

V. PROCEDURE

,(Continued)

'O * '

f.- Calculate the whole body dose rate for a selected location by use of the following fomula:

Whole Body = Total Whole Body Dose X (X/Q) X (9.0E+05)

Dose Rate Rate Factor from (mR/Hr) From Step 12c Record results on the " Key Isotope Data Record" in mR/Hr.

i 13. Thyroid Dose Rate - A detemination of specific isotopic concentrations must be made to detemine the projected

, dose rate.

a. Request that Chemistry obtain an air sample using a charcoal cartridge from RM-060 and perfom an isotopic analysis on the sample, using the applicable procedures. The sample should be collected for a time long enough to allow l significant activity deposition.

b. Obtain Attachment D-3 " Thyroid Dose Rate Calculation Sheet". Obtain the isotopic concentration for each nuclide listed in Column I, from the analysis report.

i, Then record the required nuclide concentrations in Column II, in C1/m8 NOTE: 1 uC1/cc = 1 Ci/m8

! {,

c. Calculate the radionuclide release by use of the following formula:

Radionuclide =

(Column II Concentrations) X (Stack Flow Rate) X (4.72E-04)

Release Rate (Ci/sec)

Record the results in Column III.

d. Calculate the thyroid dose rate factor for each isotope by use of the following formula:

i Thyroid Dose =

(Release Rate ) X (Dose Conversion Factor)

Rate Factor (From Column III) ( From Column IV )

Record the results in Column V.

e. Detemine the total thyroid dose rate factor by adding all values recorded in Column V. Record the total.

l ISSUED

(

FC/EPIP/01 FES 2 61987 R10 02-26-87

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EPIP* EOF-6-D-5 IV. . PROCEDURE (Continued)

f. Calculate the thyroid dose rate for a selected location as follows:

1. For time intervals between 0 and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time of the accident use the following formula:

Thyroid = (TotalThyroidDoseRate)X (X/Q)X(1.25E+03)

Dose Rate ( Factor From Step 13e )

(mR/Hr)

2. For time intervals greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time of the accident use the following formula:

Thyroid = (Total Thyroid Dose Rate) X (X/Q) X (8.35E+02)

Dose Rate ( Factor From Step 13e )

(mR/Hr)

Record the results on the " Key Isotope Data Record" in mR/Hr.

14. Lung Dose Rate - A determination of specific isotopic concentrations must be made to determine the projected lung dose rate.

a. Lung dose is not limiting unless thyroid blocking drugs have been administered or there is a long delay between the time of accident and the time of release, during which much of the iodine would have decayed.

b. Request that Chemistry obtain an air sample using a charcoal cartridge from RM-060 and perform isotopic analysis on the sample, using the applicable procedures. The sample should be collected for a time long enough to allow significant activity deposition,

c. Obtain Attachment D-4 " Lung Dose Rate Calculation Shee t" . Obtain the isotopic concentration for each isotope listed in Column I, from the analysis .

report. Then record the required nuclide concentrations in Column II, in Ci/m3 NOTE: 1 ac i/cc = 1 Ci/m3 ISSUED FC/EPIP/01 FE8 2 6 NE7 RIO 02-26-87 9

r-,- . .t._.._..a.__

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f -

EPIP-EOF-6-0-6 l .

I

V. PROCEDURE

(Continued)

d. Calculate the.radionuclide release by use of the following fomula:

Radionuclide =

(Column II Concentration) X (Stack Flow Rate) X (4.72E-04)

Release. Rate (Ci/sec)

Record the results in Column III'.

e. Calculate the lung dose rate factor for each isotope by use of the following fomula:

Lung Dose =

(Release Rate) X (Dose Conversion Factor)

Rate Factor ( Column III ) ( Column IV )

RecordtheresultsinCoiumnV.

f. Determine the total lung dose rate factor by adding all values in Column V. Record the total.

g. Calculate the lung dose rate for a selected location as follows:

1. For time intervals between 0 and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time of the accident use the following formula:

C. Lung Dose = (Total Lung Dose Rate Factor) X (X/Q) X (1.25E+03)

Rate (mR/Hr) ( Step 14f )

2. For time intervals greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time of the accident use the following formula:

Lung Dose = (TotalLungDoseRateFactor)X(X/Q)X(8.35E+02)

Rate (mR/Hr) ( Step 14f )

Record the results on the " Key Isotope Data Record" in mR/Hr.

15. Projected Duration of Release - The Shift Supervisor or his designee must determine the projected durttion of release. This infomation is required to calculate the I projected total dose to a given area. Record this number in hours or a decimal notation for a fraction of an hour.

16. Total Projected Dose to a Selected Location - Multiply the actual dose rate (whole body, thyroid, or lung) by the projected duration of release (Step 15). Record the results on the key isotope data record and circle the appropriate units.

ISSUED FC/EPIP/01 FEB 2 61987 R10 02-26-87

EPIP* EOF-6-D-7 I

V. PROCEDURE

(Cont.inued)

17. Report Results to the Shift Supervisor or his designee -

Much of the information that has been recorded will be used on required report forms which must be completed within 15 minutes of accident classification. Expedite the completion of this form in a clear and accurate manner. Then report this infonnation to the Shift Supervisor or his designee.

18. Protective Action Recommendation - The Shift Supervisor or his designee will compare the total projected dose to a selected location (Step 16) to the Protective Action Guidelines at the end of the " Key Isotope Data Record".

After determining the proper recommended actions he will relay the information to the appropriate offsite government agencies,

e. After completion of the " Key Isotope Data Record", standby to repeat the process using a new data sheet. Dose assessment must be completed until relieved or directed to stop by the Shift Supervisor or his designee.

ISSUED FC/EPIP/01 FEB 2 6 NE7 RIO 02-26-87 m

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. EPIP-EOF-6-0-8 ATTACHMENT 0-1 KEY ISOTOPE DATA RECORD

. Circle Appropriate Answers or Units

1. Date and Time /

2. Selected Location Site Boundary / 2 Mi. / 5 Mi. / 10 Mi.

3. _ Present (or Average) Wind Speed MPH

4. Present Wind Direction DEGREES

5. Present Delta Temperature (AT) , DEGREES "C"

6. Stability Class (from chart at the end of this fom) A/B/C/D/E/F/G

7. Affected Sectors (from overlay map) i

8. Present Stack Flow Rate CFM

9. Present Main Steam Flow Rate (for primary / secondary release only refer to 01-PAP-8) CFM l

10. X/Q at Site Boundary (from operations personnel or calculate using:)

X/Q = 1.04E-4 (Windspeed)(.447) SEC/M8

( Step 3 )

11. X/Q for Downwind:

A. Use the following chart to determine the diffusion factor

-(Circle Diffusion Factor) i STABILITY CLASSES A B C D E F G 2 Mi, 5.53E-8 7.84E-7 5.80E-6 2.15E-5 4.35E-5 1.002-4 2.28E-4 5 Mi. 2.55E-8 3.20E-8 1.20E-6 5.50E-6 1.24E-5 3. 21'E-5 7.38E-5 10 Mi. 1.40E-8 1.80E-8 3.9EE-7 2.05E-6 5.50E-6 1.38E-5 3.33E-5 B. Calculate X/Q using:

Diffusion Factor (Step 11.A.) 2mi = SEC/M3 (Wind Speed)(.447)

( Step 3 ) Smi = SEC/M8 10mi = SEC/M3 ISSUED FC/EPIP/01 FEB 2 61987 R10 02-26-87

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.- EPIP-EOF-6-D-9 l

ATTACl#4ENT D-1 (C'ontinued) -

' (I, .

KEY ISOTOPE DATA RECORD Circle Appropriate Answers.or Units  ;

12. Whole Body Dose Rate A. Request that Chemistry obtain a Marinelli sample from RM-061  !

(RM-057 for primary / secondary release) and perform an isotopic analysis.

B. Using Attachment D-2 "Whole Body Rate Calculation Sheet", record the required nuclide concentrations in Column II in Ci/M8 NOTE: 1 vCi/cc = 1 Ci/m3 , ,

C. Calculate the radionuclide release (Column III) by using the following formula:

Radionuclide =

(Column II Concentrations) X Stack Flow Rate X(4.72E-04)

~

Release Rate or Main Steam (Ci/sec) Flow Rate Step 8 or 9 l

Record the results in Column III.

D. -Calculate the whole body dose rate factor (Column V) for each isotope by use of the following formula:

Whole Body = (Release Rates) X (Average Gasmia Energy)

Dose Rate ( Column III ) ( Column IV )

Factor Record the results in Column V. -

- E. Add all values recorded in Column V l W.B. Dose Rate Factor F. Calculate the whole body dose rate' for a selected location:

1. Whole body dose rate =

(W.B. Dose Rate Factor) X (X/Q) X (9.0E+5)

L ( Step 12.E. ) (Step 10 or 11)

2. Record whole body dose rate for a

selected location MR/HR i -

i h ISSUED l FC/EPIP/01 FEB 2 6 INT Rio 02-26-87

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EPIP-E0F,6-D-10 ATTACHNENT D-1 (Continued)

KEY ISOTOPE DATA RECORD Circle Appropriate Answers or Units

13. Thyroid Dose Rate A. Request that Chemistry obtain a charcoal cartridge sample from RM-060 and perform an isotopic analysis.

B. Using Attachment 0-3 " Thyroid Dose Rate Calculation Sheet",

record the required nuclide concentration in Column II in Ci/M8 NOTE: 1 uCi/cc = 1 Ci/m3 C. Calculate the radionuclide release (Column III) by using the following formula:

Radionuclide =

(Column !! Concentrations) X (Stack Flow Rate) X (4.72E-4)

Release Rate ( Step 8 )

(C1/sec) ,

Record the results in Column III.

D. Calculate the thyroid dose rate factor (Column V) for each isotope by use of the following formula:

Thyroid Dose = Release Rate X Dose Conversion Factor Rate Factor Column III Column IV E. Add all values recorded in Column V Thyroid Dose Rate Factor F. Calculate thyroid dose rate for a selected location:

l

1. For time intervals between 0 and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time of the accident use the following fannula:

Thyroid Dose = (Thyroid Dose Rate Factor) X (X/Q) X (1.25E+3)

Rate (mR/Hr) ( Step 13.E. ) (Step 8)

2. For time intervals greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time

• of the accident use the following formula:

Thyroid Dose = (Thyroid Dose Rate Factor) X (X/Q) X (8.35E+2)

Rate (mR/Hr) ( Step 13.E. ) (Step 8)

3. Record thyroid dose rate for a selected location MR/HR ISSUED FC/EPIP/01 FEB 2 61987 Rio 02-26-87

7 . - _- _ _ _ _ _

. t EPIP-E0F-6-D-11 ATTACHMENT D-1 (Continued)

KEY ISOTOPE DATA RECORD Circle Appropriate Answers or Units ,

j 14. Lung Dose Rate -

2 A. This calculation should be made if thyroid blocking agents have been issued or a long delay occurs between the time of 3 the accident and the time of release.

B. Request that Chemistry obtain a charcoal cartridge sample from RM-060 and perform an isotopic analysis.

C. Using Attachment D-4 " Lung Dose Rate Calculation Sheet",

record the required nuclide concentrations in Column II l in C1/M8 NOTE: 1 pC1/cc = 1 C1/ms ,

i D. Calculate the radionuclide release (Column III) by

, use of the following formula:

Radionuclide Release Rate =

(ColumnIIConcentrations)X(StackFlowRate)X(4.72E-4)

(C1/sec) ( Step 8 )  :

I Record the results in Column III

Ci E. Calculate the lung dose rate factor (Column V) for each isotope by use of the following formula

i

Lung Dose =

(ReleaseRate)X(DoseConversionFactor) 1 Rate Factor ( Column III ) ( Column IV )

]

Record results in Column V F. Add all values in Column V Lung Dose Rate Factor j G. Calculate lung dose rate for a selected location:

1. For time intervals between 0 and 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> l from the time of the accident use the +

following formula:

I Lung Dose Rate = (LungDoseRateFactor) X (X/Q) X (1.25E+3)

(mR/Hr) ( Step 14.F. ) (Step 8) 4

(f ISSUED

FC/EPIP/01 FEB 2 61987 R10 02-26-87

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EPIP-E0F-6-0-12 ATTACHMENT D-1 (Continued)

KEY ISOTOPE DATA RECORD Circle Appropriate Answers or Units

2. For time intervals greater than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> from the time of the accident use the following formula:

Lung Dose Rate = (LungDoseRateFactor) X (X/Q) X (8.35E+2)

(mR/Hr) ( Step 14F ) (Step 8)

3. Record lung dose rate for a select location MR/HR

15. Projected Duration of Release (inhours,fromShiftSupervisor) HOURS

16. Total Projected Dose to 'a Selected Location (projected duration of release (Step 15) X i

actual dose rate (Step 12F, 13F, 14F) MR W.B.

THYROID R LUNG

17. Report Results to Shift Supervisor

18. Protective Action Recommendation (Shift Supervisor Circle One)

If the total projected dose to a selected location (Step 16) is:

A. W.B. Dose < 1 REM Thyroid < 5 REM NO PROTECTIVE ACTION REQUIRED B. W.B. Dose > 1 REM Thyroid > 5 REM

< 5 REM < 25 REM SEEK SHELTER, CONSIDER EVACUATION C. W.B. Dose > 5 REM Thyroid > 25 REM CONDUCT EVACUATION STABILITY CLASSES T ('C) CLASS .

< 1.9 A

-1.9 to -1.7 8

-1.7 to -1.5 C

, -1.5 to -0.5 0

-0.5 to 1.5 E 1.5 to 4.0 F

> 4.0 G ISSUCD FC/EPIP/01 FEB 2 61987 R10 02-26-87

- - . , - , - - - - _ - - - , , , , , + - - - , - , - - - , - - , , , ,-

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. o EPIP-EOF-6-0-13 ATTACMENT D-2

~WHOLE BODY DOSE RATE CALCULATION SHEET COLUMN I COLUMN II COLUMN III COLUMN IV COLUMN V Radio-Radionuclide nuclide Average Gamma Concentration Release Energ Whole Body Radionuclide C1/m3 Ci/sec (Nev/ dis) Dose Rate Factor Kr-88 2.03 E+00 I-131 3.92 E-01 I-133 6.24 E-01 I-135 1.56 E+00 Te-132 2.31 E-01 Xe-133 4.50 E-02 Xe-135 2.62 E-01 C: Cs-134 1.59 E+00 Cs-137 5.36 E-01 Total =

ISSUED FC/EPIP/01 FEB 2 6 N67 RIO 02-26-87

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EPIP-EOF-6-0-14. -

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J c ATTACHMENT 0-3 '

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- THYROID DOSE RATE CALCUf.ATICN SHEET j

COLUMN I COLUMN II COLUMN III COLUMN IV C0QMN */ <

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Radio- Dose f' 'l '

< i Radionuclide nuclide Conversfor Concentration Release Factor ,

-Thyroid Dose )!

Radionuclide Ci/m3 Ci/sec Rem /Ci Factor

. . m.

I-131 1.4 E+06

., i; I-132 6.5 E+03

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4 I-133 - .

1.8 E405 !

I-134 2.5 E+04 -

I-135 '

4.4 E*04 1

Te-132 -

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FC/EPIP/01 FEB 2 61987 4

, s. .kl0 02a26-87 4,

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s; LUNG DOSE RATE CALCULATION SHEET q

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j' (1-t

- 1 ,i COLUMN I COLUMN II COLUMN III COLUMM IV COLUMN V

> 1

Radio- Dose Radionuclide nuclide

, Conversion

. Concentration Release Factor Lung Dose Radionuclide Ci/m3 Ci/sec Rem /Ci Factor

[

I-131 2.4 E+06 I-132 1.0 E+03

I-133 3.1 E+03

I-134 -

I-135 2.5 E+03 a

in Ru-106 3.9 E+06

-Te-132 3.0 E+04 i

l

. G]

I. .

i' Cs-134 5.1 E+04

< - Cs-137 4.0 E+04 l- Ce-144 _

l t

'ji o;

Total =

I

.i I

4 i-

! C'&? '

ISSUED i

l FC/EPIP/01 i FEB 2 61967 RIO 02-26-87 e'

4

---

.-----g- --, . + - - - . , , . - - - - - . , , - , ---,e--, - - - - - ---------n

, im e y

_g ,- , 1, EPIP-EOF,-6-Eli t-l, .

I

V. PROCEDURE

(Cor,tinued) ,

E. Section E - Assess;ne,nt of Liquid Releases.

3 ,

4 1. The Shift Supervisor or his designee, upon receipt of an alert or

, alam indication on RM-055/055A, or noting an uncontrolled. release -

of a monitor tank to the river, shall assign an-individual to

• perfom' dose assessment. This will' normally De the Shift Chemist.

! The SMft HP will be used as his/her alternate. s i

2. The person assigned to~ dose assesunent will perform dose assessment determinations until relieved or directed to stop by the Shift Supervisor.or his designee. Dose assessment will be completed in accordance. with the following:

a. Obtain the " Dose Assessment Forms Booklet" from the Control Room 's Emergency Gear Locker.-

b. Obtain Attachment E-1 " Liquid Release Data Record" from the Oose c ., Assecsrent Forms Booklet. Collect and record the following data:

, 1. lDate and Time C t 2. Tank Release Rate - Obtain from operations personnel in the Control Room. This must be in gallons per minute. , Record tank release rate.

3. Missouri' River Flow Rate and Speed - Contact the Corps of Engineers (phone.221-3020). Record flow rate in cubic feet per second (CFS) and speed in miles per hour (MPH).

4. Detemine if RM-055/055A are functioning. Collect and record the following data:

s a. If RM-055/055A are functioning collect and record the follcwing-data:

1. RM-055/055A Net Counts Per Minute (NCPM) - Read meter, subtract background listed in the Technical Data Book to obtain NCPM. Record the net counts per minute.

2. Obtain graph, Attachment E-2 for RM-055 or Attachment E-3 for RM-055A. Locate present release rate on the left side of the graph.

3. Locate NCPM level at the lower part of the graph.

Plot upward until you intersect with the release value from Step 2.

4. Locate the nearest diagonal line above your point of intersection. Plot up or down that diagonal line until it intersects present river flow rate (shown on right side of graph).

ISSUED FC/EPIP/01 FEB 2 6 887 RIO 02-26-87

-. _ _ _ _ _ _ _ _ _ _ _ - - - - - - - - - - _ _ _ .__ _ _ __]

_ , . . . ,_ .. w ._ _ . _ 2.. _ _ _ ; . - -

EPIP-EOF-6-E-2 I

V. PROCEDURE

(Continued) -

5. At that point of intersection, plot straight upward

. to the indicated total gamma specific activity at the M.U.D. intake. Record this value on the " Liquid Release Data Record" in uCi/ml.

6. Record the activity in the P.A.G. chart at the bottom of the " Liquid Release Data Record",

b. If RM-055/055A'are NOT functioning, collect and record the following data:

1. Obtain tank total specific gamma activity from the latest Liquid Release Permit in the Control Room.

The chemistry group may have to obtain an isotopic analysis to detemine this data. Record this activity.

2. Obtain graph, Attachment E-2 only as it will provide more conservative results. Locate present release rate on the left side of the graph.

3. Locate total tank specific gamma activity on the lower part of the graph, and plot upward until you intersect with the release rate value found above.

O' 4- 'ec t *" " r

• d' 9 " ' '4" 6 > a 4"* er intersection. Plot up or down that diagonal line until it intersects present river flow rate (shown on right side of graph).

5. At that point of intersection plot straight upward to the indicated total gansna specific activity at M.U.D. Record this data on the " Liquid Release Data Record" in uc/ml.

6. Record the activity in the P.A.G. chart at the bottom of the " Liquid Release Data Record".

c. Protective actions (Shift Supervisor or his designee) -

1. Using the total activity calculated above, multiply by the isotope distribution factors shown in Column II of the P.A.G. chart for each radionuclide.

h lSSUED FC/EPIP/01 FEB 2 61967 R10 02-26-87

, - ~ - - -

~

EPIP-EOF-6-E'-3 I

V. PROCEDURE

(Continued)

2. Record results in Column III.

3. Compare the results with the EPA standards liste in Column IV. If any of the calculated values are equal to or greater than these values, notify M.U.D.

(phone 554-7946) and the State of Nebraska (phone 1-473-1721) immediately for appropriate protective actions.

d. After completing the " Liquid Release Data Record" standby to repeat the process using new data sheets.

Terminate procedure when directed to do so by the Shift Supervisor or his designee.

i l

i I

l ISSUED FC/EPIP/01 FEB 2 6 7987 R10 02-26-87 i

l

i i

33 TOTAL EAllE SPECIFIC ACTIMTV AT M.U.D. INTAKE lu.C1/sl )

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1

EPIP-EOF-6-E-4 ATTACHMENT E-1 LIQUID RELEASE DATA RECORD Circle Appropriate Answers or Units

1. Date.and Time . /

2. Tank Release Rate (from control room) GP_M

3. Missouri River Flow Rate and Speed CFS (from Corps. of Engineers, phone 221-3020) MPH

4. A. RM-055 or RM-055A Function h

1. RM-055 or RM-055A NCPM (from control room).

(Gross CPM minus background CPM from' Technical Data Book). NCPM

2. Using Attachment E-2 for RM-055 or Attachment E-3 for RM-055A, locate the tank release rate on left side of graph.

3. Plot straight over until release rate intersects (located onwith lowermonitor part of reading)in graph . NCPM

('

(. 4. Follow nearest higher diagonal line either up or down to intersect present river flow rate (shown on right side of graph).

5. At that intersect, plot straight up to indicated activity at M.U.D. intake. uC1/ml

6. Record activity in P.A.G. chart below, Column I.

B. PA-05$ or RM- t nctioning:

1. Obtain tank ganna specific activity from the latest liquid Release Permit in the control room, uti/ml

2. Using Attachment E-2 only, locate tank release rate on left side of graph.

3. Plot straight over until-release rate intersects with tank specific activity (located at lower part grap y ,.,g

, .gg 5 ,n + . . .%% k. s? ,' ~

ISSUED

)

• WW

{ i FC/EPIP/01 FEB 2 61987 R10 02-26-87

' * '% , . . . .;; .. ; ; , . ,= , ,

EPIP-EOF-6-E-5 ATTAC'HMENT E_1 (Continued)

LIQUID RELEASE DATA RECORD Circle Appropriate Answers or Units

4. Follow nearest higher diagonal line either up or down to intersect present river flow rate (shown on right side of graph).

5. At that intersect, plot straight up to indicated activity at M.U.D. intake, uCi/ml

6. Record activi.ty in P.A.G. chart below, Column I.

5. Protective Action Determination Column I Column II Column III Column IV Radionuclide Total Isotope Projected E.P.A.

Activity Distrib. Activity Standards

> Factor at MUD (uC1/ml)

Col. I X t

Col. II I-131 0.15 3.0E-09 CS-IN 0.45 2.0E-05 CS-137 0.10 2.0E-07 CO-60 0.30 1.0E-07 H-3 0.70 2.0E-05 A. Multiply Coluan I value times each Column II value, record in Column III.

I B. If Column III value is equal to or r than Column IV, call M.O.D.

nd recomend protective W and to actions Statebe taken. of Nebraska The protective action would be to terminate intake of Missouri River water at the Florence Station. .

as-e 1

FEB 2 61987 FC/EPIP/01 Rio 02-26-87

_ , . . . - < - - ,--w,,__.,_,___,,,,..,_-~._ , _ ____ ..-._.%,.._ - _ _ - , . _ . - _ . _ _ , , . , _ , _ - _ _ . _ _ , . . _ _ _ . - . _ . - ,

m _ _ . . . . _ . _ . . _ . .

l

. EPIP-EOF-6-F-1 e I

V. PROCEDURE

(Continued)

(,

F. Section F - Determination of actual offsite dose rates and verification of activity release rates by utilizing infonnation from the Onsite

( and/or Offsite Monitor Teams.

1. The HP/ Chemistry Supervisor or the Emergency Coordinator shall

- designate someone to complete the following steps to find the actual offsite dose rates.

2. Obtain the whole body dose rate from the monitor team for direct radiation dose rate measurements and enter in Attachment F-1.

3. Calculate actual thyroid dose rate for selected locations as follows:

Actual Thyroid Dose Rate = 1.55E+09 X X, uCi/cc (mrem /Hr)

4. Record actual dose rates on Attachment F-1.

5. Report the data recorded on Attachment F-1 to the HP/ Chemistry .

Supervisor or Emergency Coordinator for his review and then update the Status Board.

6. If the actual dose rates are higher than the predicted dose rates, the HP/ Chemistry Supervisor or the Emergency Coordinator shall

(-. review the current recomended protective actions and revise them as necessary.

7. Protective Action Guidelines ,,

A. W.B. Dose < 1 REM Thyroid < 5 REM NO PROTECTIVE ACTION REQUIRED B. W.B. Dose > 1 REM Thyroid > 5 REM

< 5 REM < 25 REM SEEK SHELTER, CONSIDER EVACUATION C. W.B. Dose > 5 REM Thyroid > 25 REM -

CONDUCT EVACUATION

• X = Specific activity supplied by monitor team (in uCi/cc).

( ISSUED FC/EPIP/01 R10 02-26-87

EPIP1E0F-6-F-2 ATTACHMENT F-1 ONSITE/0FFSITE DOSE RATES: PREDICTED-ACTUAL DOSE RATES (MR/HR)

PREDICTED ACTUAL DATE TIME LOCATION DISTANCE W.B. THYROID W.B. THYROID h

4 REMARKS:

1SSUED 1

l l FC/EPIP/01 FEB 2 6197 RIO 02-26-87 8

- - . - - , - .----,c ,c.,-- - - - - - , . - _ , - , , , - , , ..._.,__s,,,_,,.n,.,, . - , . - , - e - - , , - + - . . , , -,- ,. - .-

-,----.n -

y .

. EPIP-EOF-6-G-1 I

V. PROCEDURE

(Continued) 10 G. Section G - Whole Body Dose Detemination from Contamination Released Through the Plant Ventilation Stack. .

1. The Shift Supervisor or his designee, upon receiving an alert or alam indication on RM-061, shall assign the Shift Chemist to perform dose assessment. The Shift HP will be used as the alternate. .

2. The person assigned to dose assessment will perform dose assessment deteminations until relieved or directed to stop by the Shift Supervisor or his designee. Dose assessment will be completed in-accordance with the following:

a. Obtain the " Dose Assessment Foms Booklet" from the control

~

room emergency gear locker.

b. Obtain Attachment G-1, " Contamination and Whole Body Dose Rate Data Record", from the Dose Assessment Forms Booklet. Collect and record the following data:

1. Date and Time -.

2. Selected Location - Using Attachment G-2, find the -

affected sector and detemine the selected downwind location for the calculation being perfomed. -

3. Present Wind Direction - Wind direction meter is located on the north wall of the Control Room above the fire control and alam panels (AI-184), or obtain wind .

direction from the Plant Computer by requesting infomation from operations personnel. Record wind ..

direction; use the estimated average if the reading is unstable.

NOTE: This is the direction that the wind is coming from.

4. Stack Flow Rate - Stack flow rate meter is located behind the control panel on AI-44. The meter number is FR-758.

Meter reading is in standard cubic feet per minute (SCFM) times one thousand. Convert this value to M87sec using the following conversion:

(Stack Flow Rate) X (4.72E-04) = Stack Flow Rate in M3/.sec

5. Relative Deposition Factor (D/Q) - Detemine the relati.ve deposition factor for the selected downwind location (Step 2) by using Attachment G-2, " Relative Deposition Factors", the wind direction (Step 3), and the selected location.

If the selected downwind location is between

(; NOTE:

two of the listed distances, use the next ISSUED FC/EPIP/01 R10 02-2 W 7 FES 2 61987

EPIP , EOF-6-G-2 I

V. PROCEDURE

(Continued)

6. Projected Duration of Release - The Shift Supervisor or his designee must detemine the projected duration of release. This information is required to calculate the projected total dose to a given area. Record this number in seconds.

7. Request that Chemistry obtain a particulate air sample from RM-061, RM-060, or RM-063 (if RM-061 and RM-060 are unavailable) and perform an isotopic analysis on the sample, using the applicable procedures.

A. Record the required radionuclide concentrations (in uc/cc) in Column II.

'B. Calculate the radionuclide release rates by use of the following fomula:

Radionuclide = (ColumnIIValues)X(StackFlowRateStep4)

Release Rate (Ci/sec)

Record the results in Column III in Ci/sec.

C. ' Calculate the contamination deposition by use of the following formula:

Contamination = (Column III Values) X (D/Q Step 5) X (Release Duration Step 6)

Deposition (Ci/M8)

Record the results in Column IV in Ci/Ma, D. Calculate the whole body dose rate for each nuclide by use of the following formula:

W.B. Dose Rate =

(Column IV Values) X (Dose Conversion Factor)

For Each Nuclide ( Column V Values )

(R/Hr)

Record the results in Column VI in mR/Hr.

8. Total the values recorded in Column VI and record the total at the bottom of Attachment G-1.

9. Total Projected Dose to a Selected Location - Multiply the total whole body dose rate (Step 12) by the projected

, duration of release (Step 6). Record the results on the

" Contamination and Whole Body Dose Rate Data Record" and circle the appropriate units.

10. Compare the total projected dose to a selected location i to the " Protective Action Guidelines" at the top of i Attachment G-2. -

i' ISSUED FC/EPIP/01 FEB 261987 R10 02-26-87 j

. EPIP-EOF-6-G-3 i

I

V. PROCEDURE

(Continued) 0 -

c. Report the results to the Shift Supervisor. H.P./ Chemistry Supervisor, or the Emergency Coordinator if the EOF is activated.

d. Standby to repeat this procedure as required.

C

( FC/EPIP/01 lSSUED FEL 2: PJD ' RIO 02-26-87

l EPIP EOF-6-G-4 I ATTACHMENT G-1 CONTAMINATION AND WHOLE BODY DOSE RATE DATA RECORD Circle Appropriate Answers or Units

1. Date. and Time /

2. Selected Location /

Sector Distance

3. Present Wind Direction DEGREES

4. Stack Flow Rate (Stack Flow Rate SCFM) X (4.72E-04) = M3/Sec

5. Relative Deposition Factor (0/Q) M2 (Use Attachment G-2, Wind Direction, and Selected Location)

6. Projected Duration of Release (from Shift Supervisor) SEC

7. Request that Chemistry obtain particulate air sample from RM-061, RM-060, or RM-063.

(Step A) (Step B) (Step C) (Step 0)

I II III IV V VI Radion- Isotopic Release Contamination Dose Whole nuclide Analysis Rate Deposition Conversion Body Dose (uc/cc) (Ci/sec) (Ci/M2) Factor Rate (R/Hr)

(Column II)X (Column III)X(0/Q)X RM-061/RM-060 (Stack (Release Duration) (Column IV)X RM-063* Flow Rate) (Column V)

Mn-54 5.8 Co-60 1.7E+01 Sr-89 5.6E-04 I-131 2.8 I-133 3.7 I-135 1.2E+01 Cs-134 1.2E+01 Cs-137 4.2 Ba-140 2.1 La-140 1.5E+01

8. Total W.B. Dose Rate (Total of Column VI) R/HR

9. Total Projected Dose to a Selected Location (Step 8 Result)(Projected duration of release-Step 6)+ 3600 l REM l

10. Compare the total projected dose to a selected location to the Protective Action Guidelines at the top of Attachment G-2. Report to Shift Supervisor.

• Use only if RM-060 and RM-061 are not available.

1SSUED FC/EPIP/01 RIO 02-26-87 f'tB 26 567

t t

s -,

, v.

"' W ATTACHMENT #C-2 O m .

c' C RELATIVE DEPOSITION FACTORS oo m and bC N PROTECTIVE ACTION REC 00MENDATIONS

. PROTECTIVE ACTION REC 009tENDATIONS

< 1Ress Whole Body Dose No Protective Action Required '

> 1Reus But < SReum Whole Body Dose Seek Shelter, Consider Evacuation 1

> 5 teen Whole Body Dose r l

Conduct Evacuation l l

i i

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EP I,P-EO F-6-H- i.

I

V. PROCEDURE

(Continued)

H. Section H - Onsite and Offsite Dose Assessment Using the Computerized Program.

1. Purpose This procedure establishes step by step instructions for the operation of the Tektronix-CX-4107A computer terminal and the GE-Term 1 Net printers. The Tektronix is used to execute the Emergency Assessment of Gaseous and Liquid Effluents (EAGLE) computer program while the TermiNets are used to make hardcopies of l EAGLE's results. The computer program is the preferred method for performing dose assessment, with other methods intended as alternate and backup methods.

2. Prerequisites

a. Emergency classification has been initiated per EPIP-05C-1.

b. The Emergency Plan has been activated per EP!P-OSC-2.

c. Post Accident Procedure O!-PAP-7 is available.

d. The Technical Data Book is available.

e. The Tektronix terminal, GE TermiNet printer, and all associated  !

equipment are available in the TSC and EOF dose assessment areas and hooked up as diagcammed in Figure H-1.

, f. The appropriate form must be filled out for each plume with

meteorological data and appropriate radiological data.

f

3. Precautions

a. Always use the lowest level winds and differential temperature data as input to the program,

b. Use the 10 meter temperature value as ambient temperature.

Effluents exit temperatures should remain at their default values.

c. Update and perform the dose assessments every fifteen (15) minutes.

f IS$UED FEB 261987 FC/EPIP/01 R10 02-26-87  ;

~

EPlP-EOF-6-H-2

.IV. PROCEDURE (Continued)

!O 4. Limitations and Actions

a. If the VM/ CMS is down or comunication with the computer via the Tektronix terminal cannot be established, the "Onsite and Offsite Dose Assessment" can be performed by using other sections of EPIP-EOF-6.

b. Dose calculations cannot be performed on both terminals (one in the TSC and one in the EOF) concurrently. The program must be ended by one party (TSC or EOF) on a given plume before the-next party (TSC or EOF) can start calculation on the next plume.

Tabular and Graphics displays for previous plumes can, however, be executed by a second party while the first party is performing calculations on the current 15 minute plume.

'.c The dose calculations have to be ended on the current 15 minute plume before switching to the tabular and/or graphics displays menu for additional data on the current plume.

5. Procedure A. Running EAGLE on VM/ CMS (Preferred Method)

1. Entering the Computer System The accessibility between the VM/ CMS and the Tektronix terminal is provided via 3274 61-C controllers. The log-on l and program calculations consist of the following steps:

a. Turn Tektronix terminal on, you will be on MVS.

b. Enter the following comand and hit < ENTER > to

, access VM/ CMS: "VMg"

c. Press the < ENTER > key to clear the screen then log-on to VM/ CMS as follows:

At TSC: "L TSC TSC" At EOF: "L EOF EOF" NOTE: Screens providing system user's information will show up. Page through these screens by pressing the < CLEAR > key until the screen asking "Is this an emergency?" appears.

l

,( ISSUED i FC/EPIP/01 R10 02-26-87 l

r.

EPIP'-EOF-6-H-3 I

V. PROCEDURE

(Continued)

d. Enter in "YES" and press the < ENTER > key when ,

asked if this is an Emergency.

e. Enter in " EAGLE" after the prompt (R;) and press < ENTER >.

l

f. The program will prompt you to the following menu l indices on the screen:

MENU EMERGENCY ASSESSMENT OF GASEOUS AND LIQUID EFFLUENTS EAGLE l

1. ATMOSPHERIC OIFFUSION AND DOSE CALCULATIONS

2. TA8ULAR DISPLAYS OF MODEL RESULTS

3. EXIT

g. Enter in "1" and press the < ENTER > key to start the program. The menus within the program will guide you to various options that are available for diffusion and dor calculations.

NOTE 1: If you incorrectly make an entry but have not pressed the

< ENTER > key, you can use the < <-------> key to go back and make the correct entry.

NOTE 2: If you incorrectly make an entry and have pressed the < ENTER >

key, then continue to make entries. The next page displayed will be a sunnary of the entries you made on the previous page.

By entering "N0" and hitting < ENTER > EAGLE will re-ask for~ l those entries.

NOTE 3: If you should accept a summary pa e that does contain a wron entry, then continue to make entr es, enter "N" and hit <ENT!R> l when EAGLE asks if you wish to distribute a page of output and then end calculation as stated in Step 1. You can now go back to Step g and re-run that plume.

ISSUED FC/EPIP/01 6W R10 02-26-87 i

. . .-- _ . ~ . . -.

EPIP-EOF-6-H-4 I

V. PROCEDURE

(Continued) .

h. When a page of output is completed, EAGLE will ask if you wish to distribute tW; page. By entering a "Y" and pressing < ENTER > (orbyjusthitting< ENTER >)

that page of output will be printed out at each of the TermiNet locations.

1. After completing your entries for Recommended Offsite Protective Actions, the following message will appear:

C0fetENTS -

If you do not wish to send any additional coseents, hit

< ENTER >. If, however, you do wish to send out some additional comments, skip a space (you may not use the first column) and type in those comments. When you are ready to type on the next line, hit < ENTER >, skip a space, and continue. After you complete your last line of comments, hit < ENTER > twice to continue with

EAGLE.

j. End the program for " Atmospheric Diffusion and Dose Calculations" by entering "END" and hitting < ENTER > at the end of a given plume. This will prompt you to the menu indices shown in Step f. Enter a "2" and hit

< ENTER > to see the tabular displays.

NOTE: Tabular displays can be exited by following instructions on the screen for Tabular Display Menu.

2. Leaving the Computer $_ystem (VM/ CMS)

It is important to log-off the system when you are finished.

When you get to the menu indices shown in step f enter a "3" and hit < ENTER >. When the prompt (R;) appears, enter

" LOG 0FF" and hit < ENTER >.

IMPORTANT NOTE: Should problems occur wt ch are not covered in this procedure, go to the trouble shooting section at the end of this procedure for further assistance.'

{ lSSUED FC/EPIP/01 6W R10 02-26-87

EPIP-EOF-6-H-5 I

V. PROCEDURE

(Continued) .

B. Terminet Printers The Terminet printers are used to produce a hardcopy of EAGLE's results. There are Terminet printers located at the TSC, E0F, and three state locations (one in Nebr. and two in Iowa). When EAGLE is prompted to distribute a page of output, all printers will simultaneously print that page within a matter of seconds.

1. Initial Setup of G.E. TermiNet Printer

a. On the left keypad the only key that should be pressed in is the <ALL CAPS > button,

b. Set the right-hand upper switch to FULL.

c. Set the right-hand lower switch to 120.

d. Make sure that the wiring setup is in accordance with Figure 1.

e. The modem buttons should be in the following positions:

AL-out, ST-out, ROL-out, HS-in, TK/DT-in

2. Operation of G.E. TermiNet Printer

a. Turn on TermiNet printer; power switch located on back of machine.

NOTE: If INTERRUPT light goes on it usually indicates that you're out of paper or print head is pulled away from the paper,

b. Dial the appropriate phone number for the following Terminet locations:

TSC-4049 EOF-4050

c. Upon hearing data tone: -

1. Press modem TK/DT button to "out" position.

2. Hang up phone,

d. When you get connected to the system, an OPPD banner will be displayed. If the banner does not appear, press

<RETLRN>.

THIS PAGE CONTAINS PRIVACY AND/OR PROPRIETARY INFORMATION R10 02-26-87 FC/EPIP/01 ISSUED FEB 2 61987

, EPIP-EOF-6-H-6

~

I

V. PROCEDURE

(Co'ntinued)

Cl' e. Press < ESC > key. Press <CTL> button', hold it down, and press the <E> key. The following message should appear.

< <LINE NUMBER SUPPRESSED > >

NOTE: If a < <LINE NUMBER PRINTED > > appears instead or if at some time when using the TermiNet lines of arrows (<- <- <- <- <-) should start appearing, then try Step e again,

f. Press < ESC > key. Press the <CTL> button, hold it down,

, and press the <0> key. The following message should appear:

<< TIME OUT FACTOR IS 3 MIN, ENTER MULTIPLIER X 3 MIN >>

<< X=9 - NO TIME OUT, X=D - DISCONNECT IPMEDIATELY >>

g. Enter a "0" (zero) and press < RETURN >.

You should now get the following message:

" ENTER ONE OF THE FOLLOWING COPNANDS" followed by some consnand examples.

h. Enter the following log-on and then press < RETURN >:

At TSC - "L EAGLES TSCPRT" At EOF - "L EAGLE 6 EOFPRT" l

i Some messages will now appear which are intended for l OPPD computer users. After a few lines of messages, a "MORE..." message will' appear on the right side.

, Anytime a "MORE..." appears, do the following:

1

1. Press the < ESC > key and then the <X> key.

NOTE: Should you hit < RETURN > instead of performing 1. (above), you will get a " HOLDING" message. Anytime you get a " HOLDING" message, hit l

< RETURN > which will give you back a "MORE..." message, and then perform 1. (above).

lSSUED

{

FC/EPIP/01 FF.B 2 61lB7 RIO 02-26-07

EPIP, EOF-6.H.7

~

IV'. PROCEDURE (Continued)

1. After the messages to the computer users are completed, the following message should appear which indicates you're logged.on and in " monitor" mode:

<<< WAITING FOR DATA EAGLE.n>

. PRESS THE ' RETURN' KEY, TWICE. TO LOG 0FF.

-TYPE ' REPRINT' AND PRESS THE ' RETURN' KEY TO REPRINT THE LAST TABLE d RECEIVED, IF ANY.

NOTE: If you do not get this message but get a RECONNECTED message instead, erter a "B" and hit < RETURN >. You will receive a RUNNING RUNNING VM READ or over on the right-hand side of the paper. Press < RETURN >

and either a page of output will print out or another VM READ message will appear. If you get the VM READ message, enter REPRINT, hit < RETURN >, and the last page of output you received will be printed as well as the WAITING FOR DATA" message.

J. When a page of output from EAGLE is sent out, the following message will appear:

RUNNING POSITION THE RIBBON OF THE PAPER CRT AT THE TOP OF A NEW PAGE. PRESS THE RETURN KEY TO PRINT OUT A PAGE.

Position paper and hit < RETURN >. The page of output will be printed followed by the " WAITING FOR DATA" message (Step i). The printer will wait in a " sleep" mode until another page of output is sent out indicated l

by the " POSITION THE RIBBON" message.

NOTE: If you should press < RETURN > after the " WAITING FOR DATA" message appears but there is no output ready to be printed, a "VM REA0" or "CP READ" will appear. Enter " REPRINT", hit < RETURN >,

and the " WAITING FOR DATA" message will appear.

! Wait until " POSITION THE RIBBON" message appears.

ISSUED FC/EPIP/01 R10 02-26-87 FEB 2 61987 ,

, EPIP-EOF-6-H-8 IV. , PROCEDURE (Continued) ~

Ci k. To logoff system, press < RETURN) a few times until the OPPD banner again appears.

1. Press modem TK/DT button to "in" position.

m. Turn TemiNet printer off.

Additional Notes

1. Should problems occur, hit the < RETURN > key 2 or 3 times to log-off and then one more time to get the OPPD banner. Go back and start again at Step 2.e. If you cannot log-off by hitting < RETURN > 2 or 3 times, turn off the power and start over at step 1.

NOTE: If you turn off the power and start again you will get a

" RECONNECTED" message.

2. To advance paper a single space at a time, depress <LF> key. To advance fast forward, set right hand upper switch to " Inhibit Send" (or

" Local")anddepress<RPT) and <LF> keys simultaneously. Return right-hand upper switch to " FULL" for normal operation.

3. If the upper right-hand switch is set at " Inhibit Send" (or " Local") or if the TemiNet is not in " monitor" mode, the pages of output from

' EAGLE will not be printed. However,whentheupprright-handswitch is set to FULL or the TemiNet put into " monitor mode, all those pages of output will then be printed out.

4 If any problems come up which are not covered in this section proceed to next section.

C. Troubleshooting Dose Assessment Computer Hardware / Software

1. Checkout of G.E. TemiNet Printers

a. Setup

1) Go back to Section 1 and make sure setup is correct,

b. Network Problems .

1) If any problems are encountered when dialing-up to gettheprinteronline(i.e.,busysignal,ringbut no answer, or an answer but no carrier signal 1, tone])

proceed to Part 2 of this procedure and report the problem.

ISSUED FC/EPIP/01 FEB 2 6157 R10 02-26-87

EPIP-EOF-6-H-9 I

V. PROCEDURE

(Continued)

c. Printer Problems

1) If you do get a carrier signal but still experience problems:

a. Turn off printer,

b. Lift cover and move print head to center of page,

c. Turn on printer. If the printhead does not move and position itself to the left hand side of the printer, proceed to Part 2 of this procedure and report the problem.

NOTE: When you turn the printer on, the power and motor lights should be the only ones on.

If the interrupt alarm light is on:

1. Lift cover and check that:

a) Run/ Load lever is forward, b) Paper is properly feeding through printer.

2. If interrupt light is still on,

proceed to Part 2 of this procedure and report problem.

If light is not on:

a) Pressinthe(LOCAL] button located on the left of the printer.

b) Type on keyboard.

c) If printer fails to print what you are typing, proceed to Part 2 of this procedure and report the problem.

1 ISSUED

)

FC/EP!P/01 FEB 2 61987 R10 02-26 87

'^

EPIP-EOF-6-H-10 1

IV.'. PROCEDURE (Continued)

G *

d. Modem Problems If after, perfonning all the previous steps you still have problems, perfom the following:

1) Call Rixon at (301) 622-1333 and ask the modem coordinator to call back into the data phone' .

(the phone connected to the Rixon modem) for related checkout.

NOTE: Rixon checkout service is available 8:00 a.m.-5:00 p.m. Monday-Friday.

2) If there is a modem problem or there is no modem problem but the printer still isn't working properly, proceed to Part 2 of this procedure and report the problem.

2. Reporting of Problems

a. When any problems with the dose assessment computer hardware / software occur, do the following:

1) Call the Infonnation Center at 4224 or 4324 and inform the person answering that you are having

C- a' name "',-' "" '^'

location and the'"*"

nature***** of the problem '.""'

, NOTE: Be sure to use the word " EAGLE" which will help the person answering in identifying the problem area.

1 e

(' lSSUED FC/EPIP/01 RS 2 8 W g pg

e ,

EPIP-EOF-6 W-11

, .,3 ,.

• re-sw

- v, d'%-

id2 Feda, nee, 4 r.'

• j

• [,'e '

. METEOROLOGICAL AND RADIOLOGICAL DATA WORKSHEET12-11-a5

' TIME  : DATE: ,19 (HR: MIN) PLUME NO.

I METEOROLOGICAL DATA II RADIOLOGICAL DATA

1. Steek flos case afm g, pg-962 geom

2. Condene.c off goe flos . t e erm. 2. RM-968 gepm IfM2-eE7 ONLyI

3. RM-861 gepm

3. Set. Steam Fles lbm/he 4 RM-963 gepm

4. Wind speed et 19 meters MPH (Circles L. M. or HI

5. Wind direcsson from

5. RM-063 mr/he ,,ir/h, gkg FILTER S. Ambiens tempereswee as is meter, ( *C/*F I

7. Temperature difference ( A T) (*C e 100m) 6. RM-057 gepm e 1.1948 of a X No. er voeuwe messa hogging M.

2.15 ofa X No. of voeuum pwape t an Nees>el operetaenei .

7. RM-064 Com

8. Contatnment Monitor Reactng R/he III STA8ILITY CLASSES A T (*C) CLASS AT(-1.9 A I

-1. H af t-1. 7 8

-1. 7< AT -1.5 C

-1. 5( AT -0. 5 0

-0.5( AT 1.5 E 1.5( AT 4.0 F 4.0( AT G IV RADIOLOGICAL RELEASE DATA /

RM-862 - NCBLE GAS ( STACK) /

/

erm = ( neomi '

0a X 4.72E-0V STACK 'LCW RATE (see iti,st, Feat ,en /

/

RELEASE RATE t01 s Ca/see k cpm e -

pC /cc RM-968 - I00Def ( STACK)

Semple Volume (ce) e CRM-060 flom aete ( cfm) =) m CTime coetridge in

• service ( mins 3 = C 28.317 ( co/f tJI 2 a ao e The everage flom este for RM-968 is approssmately 2.3 of m.

ofm u I "CD*I Qs X 4.72E-84 STACK Flow RATE ( Sensitivity Feesor e x eo)

Semp1.Vol.

RELEASE RATE (0) = Ct/see

. ,,m/,C.

ISSUED FEB 2 61987 MAU U4-40-d/

EPIP-EOF-6-H-12 FC-197 2 of 2 Form Rev. 4 RM.861 - PARTICULATE 12-11-45 Sample Volume (cc) = CRM-961 flow rete ( efm) *3 C(Semple colleotaeg tame (mtn) 3 x C28.317 (cc/fs3 3 t

= oc e The everage flew rete for RM-861 is appronsmetely 7 ofm.

Os ofm a C - nep 3 = 4.72E-84 STACK FLOW RATE ca 1 C 4.5GE + 85 ey =

C ( il pct (SAMPLE VOLUME) 3 RELEASE RATE (Q) = C /sec RM-063 - ( L . M. OR H) - Noble Cas( STACK) cfm a i ^*A*3 0= X 4.72E-94 X 2.31 STACK FLOW RATE ( Sen.stivity peegere)

RELEASE RATE (Q) e C /seo com e

pCs/cc RM-963 ACCIDENT FILTER DOSE RATE

1. Sempling Vol.t eci st RM-063 or H flow este 500 cc/ min) X ( Samp1. Tame Man.) = ca

2. Net Falter Actavsty = 0.7027 wCa/mr/br X Net Fsiter Oose Rete (me/hel = pCs Os efe = CNet Ftitor Activtty t wCs) 3 X 4.72E-04 STACK FLCW RATE CSempitng volume (cell )

CI '

S

~

$ i 1

RELEASE RATE (0) Cs/sec .

RM-257 - Noble Gee ( Cder Off geel 0m erm . ( neon) X 4.,<,6E-06 CONCENSER CFF GAS FLCW RATE ( Senstsavg ty Footere)

RELEASE RATE (C) Cs/see com uCn/co RM.064 - Noble Ces (Mein Steam) e Steam Flo Rete a lbm/he (From OI-PAP.8) 0m blm/he u I s**1 4

X 2.11e-94 STEAM FLOW RATE ( Senettivity Feeterol RELEASE RATE (0) a C /e.o com p

..................C.L./.c.o.......................................................................................................

( 1) 08TAIN THE MONITOR SENSITIVITY FACTOR FROM THE iS SUED TECHNICAL. DATA 800K

- ( 2) SENSITIVITY FACTOR FOR RM-963M = 2.9E+83 cpm /uC /cc Il .

SENSITIVITY FACTOR FOR RM-963H = 1.33+91 cpm /uC /cc - ..

Miu Uz-ze-57 M R$ g

- -, . . - . , - - - - - - ,-, . , - - - . _ - - - - - - - - - - - . - --- -. - - . _ _ - - - c. - - - - --- --

DOSE ASSESSMENT COMPUTEfl SETUP J MM M

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I Fort Calhoun Station Unit No.1 .

EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-TSC-8 l  ! -

TECHNICAL SUPPORT CENTER +

\ . ,

4

'~

r Estimate of Core Damage I. PURPOSE 1 r, -

f ,

r A. This procedure contains four sections to provide independent and redundant estimates of the type and degree of core damage which may.have occurred during an accident situation. Use the sections that will yield the quickest and/or most accurate assessment of il deniage first, as determined from the guidance below and the attached j( flow chart.

FAST TRANSIENT: Obtain' samples using the Post Accident Sampling

! System (PASS) and estimate core damage by using containment hydrogen

{ measurement (EPIP-TSC-8-C) and isotopic data analysis (EPIP-TSC-8-B)

. . followed by containment radiation dose rate analysis (EPIP-TSC-8-A).

fore damage can be estimated using Core Exit Thermocouple (CET)

J temperatures, but results are not expected to be very accurate for-j *ast' acting transients.

} SLOW TRANSIENT: Use core exit thermocouple temperatures (CfIP-TSC-8-D)andcontainmentradiationdoserateanalysis (EFIP-TSC-8-A) for an early estimate of core damage. *When

f.

! conditions pemit, the Post Accident Sampling System (PASS)

!L should be used to obtain samples for containment hydrogen

! measurement (EPIP-TSC-8-C) and isotopic data analysis j (EPIP-TSC-8-8) to enhance earlier damage indications.

f .

( , ,

8. This procedure is divided into the following four sections:

lD 1. Section A - Containment Dose Rate Analysis uses

- radiation readings from RM-091A and RM-0918 to estimate

? the type and degree of core damage. '

1 I 2. Section 5 - Isotopic Data Analysis uses post accident j ,

sample isotopic data to determine the type and degree of

, core damage.

3. Section C - Containment Hydrogen Measurement detemines f the sources of hydrogen generated in containment and relates n them to the type and degree of core damage.

4 I 4. Section 0 - CoreExitThermocouple(CET)Temperaturesare trended to relate temperature changes in the CET's to the type and degree of core damage.

I -

4'-

( ,

ISSUED j 4 FC/EPIP/02 r FEB 8 4 att R3 02-23-87

. s i i .

l u_ 1_'_.. _ _ _ _ _ _ __ - _ _ _ _ _ _ _ . _ . _

M l , .. .

EPIP-TSC-8-2

's L

x- ,

bi TYPE I' OP' TRANSIENT FAST .

SLOW -

TRANSIENT l TRANSIENT l

t RAOIATION ISOTOPIC CORE EXIT RAOIATION DOSE RATES ANALYSIS THERMCCOUPLES DOSE RATES l EPIP-TSC-8-1 EPIP-TSC-8-2 EPIP-TSC-8-4 EPIP-TSC-8-1 l

l

}

}

r i HYOROSEN ISOTOPIC -

MEASUREMENT ANALYSIS EPIP-TSC-8-5 EPIP-TSC-8-2 l

l CORE EXIT HYOROGEN THERMOCOUPLES MEASUREMENT EPIP-TSC-8-4 EPIP-TSC-8-5 L

EPIP-TSC-8 CORE DAMAGE ASSESSMENT PROCEDURE FLOW CHART ISSUED FC/EPIP/02 gg 3 gy R3 02-23-D i

. . . . _ . . . _. - . _ ~ ~ .

.~.-. .

EPIP-TSC-8-A-1 SECTION A -

Estimate of Core Damage Using Containment Radiation Dose Rates I. PREREQUISITES A. A plant accident with the potential for core damage has occurred.

B. Wide Range Radiation Dose Monitors RM-091A and RM-0918 are operable and able to measure area dose rates in containment resulting from fission products dispursed in the building atmosphere and plated out on the building surfaces.

II. PRECAUTIONS AND LIMITATIONS A. The total quantity of fission products c.aasured at monitor locations in containment may be changing rapidly due to transient plant conditions. Therefore, multiple measurements should be obtained within a minimum time period and under stabilized plant conditions when possible. Samples obtained during rapidly changing plant conditions should not be weighed heavily into the assessment of core damage.

RM-091A and RM-0918 have an upper radiation reading limit of IE7 R/HR 9

B. This procedure only provides an upper limit estimate of the progres-sive core damage and cannot accurately distinguish between the condi-tions of fuel cladding failure and fuel overheat when the resulting dose rates are the same. This procedure does not attempt to identify C: the extent of any potential fuel melting.

C. This procedure is intended for use when the fission product inventory in the core has had sufficient time to reach equilibrium. Based upon the fission products of concern, equilibrium conditions are achieved s after 30 days of operations at constant power. Reactor power is

i considered to be constant if it has not changed by more than 10%.

This procedure can be applied following non-constant periods of operation and when the reactor has produced power for less than 30 days. The assessment of core damage for less than 30 days of opera-tion will underpredict the actual conditions.

l

. ISSUED '

l FC/EPIP/02 FE8 8 8 387 R3 02-23-87 l

' I

.---.- ., ,,, . -..-n

. - -.-. .. , -. , .-- - , ,~. --- - . _ ,,,, - -- - .n.-- - _,,-n.,.. - - - . , , . - ,. - - , - . . - - . .,

EP!P-TSC-8-A-2 II

I. PROCEDURE

A. Record the following plant indications.

CONTAINMENT BUILDING Radiation Dose Rate Rads /hr.

Time of Measurement Date Time Prior 30 days power history: Power, Percent Duration, Days B. Time of reactor shutdown Date Time C. Plant Power Correction The measured radiation dose rate inside the containment building is to be corrected for the plant power history. To correct the measured dose rate to the corresponding value had the plant been operating at 100 percent power, follow the guidelines below.

For operation at constant power for more than 30 days, apply a simple ratio of power. Reactor power is considered to be constant if it has not changed by more than 210%.

To correct the radiation dose rate for the case in which reactor power level has not remained constant during the 30 days prior to the reactor shutdown, engineering judgement is used to determine the most representative power level. The guidelines below should be used in making this determination.

The average power during the 30 day period is not necessarily the most representative value to be used for the correction to equilibrium conditions.

The power levels at which the reactor last operated should weigh more heavily in the determination than the earlier power levels.

1 i

I ISSUED FC/EPIP/02 FEB 2 3 587 R3 02-23-87

~ ^-

J .._.. n _ . _ .__m._,.. _. _ A 2._ _

EPIP-TSC-8-A-3 II

I. PROCEDURE

(Continue'd) -

C. Plant Power Correction (Continued)

Continued operation for an extended period should weigh more heavily than brief transient periods.

For operation less than 30 days this procedure can still be employed, however, the estimate of core damage is expected to be an under-prediction of actual conditions.

D. Apply the following equation to detemine the radiation dose rate ,

corresponding to equilibrium full power source inventory conditions.

~

Equilib'ium r , Measured X 100

• Dose Rate Dose Rate 7. Reactor Power Level t

• dose rate correction factor E. To detennine the decay correction for the radiation dose rate, record the time between measurement of the dose rate and reactor shutdown, recorded in Step B.

Time duration for this measurement = hours F. Estimatie the extent of core damage using the equilibrium dose rate (step III.0), the duration of reactor shutdown, and the analytically

(- determined dose rates provided in Enclosure 2. Use engineering 1 judgement to determine which category of core damage shown on Enclosure 2 is more representative of the plotted value. Consider the following criteria when making this determination:

Some dose rate measurements could have been recorded during periods of transient conditions within the plant. Measurements made during stable plant conditions should weigh more heavily in the assessment of core damage.

Dose rates significantly above the lower bound in the category of major fuel overheat may indicate concurrent fuel pellet melting.

This procedure can not be employed to estimate the degree of fuel

, pellet melting.

l I

Fuel cladding failure should be anticipated for dose rates within any category of fuel overheating. This procedure can not dis-tinguish the relative contributions of the two categories to the total dose rate, but does give an estimate of the highest cate-gory of damage.

Dose rates corresponding to the two categories of major cladding failure and initial fuel overheat are observed to overlap on Enclosure 2. The evaluation of other plant parameters may be required to distinguish between them. However, concurrent conditions may be anticipated.

'{' ISSUED FC/EPIP/02 MB 3 3 1987 ,,, R3 02-23-87

.- ,m.~_.._-_.7 ....,,.._,,w,., -.__,.,,..e-_. _.-._m , _,...,.m. . _ . . _ . - . _ . , _ . , , _ _ _ . . . . . _ _ _ _ . _ . - _ . , _ _ _ _ _ _ _

4 n -

n '

k Enclosure 1 j 3 R Radiological Characteristics of NRC Categories of Fuel Damage 8

• Release of Characteristic ,

NRC Category of Mechanism of Source of Characteristic , Isotope Expressed as a j

gy Fuel Damage Release Release Isotope Percent of Source Inventory

.- c No Fuel Damage Halogen Spiking Gas Gap I 131, Cs 137 Less than 1 g '" ~

Tramp Uranium Rb 88 Initial Cladding Gas Gap Less than 10 Failure I

Intermediate Clad Burst and Gas Gap Xe 131m. Xe 133 10 to 50 i Cladding Failure > Gas Gap Diffusion I 131. I 133 Release t

Major Cladding Gas Gap Greater than 50 l

i Failure Initial Fuel Pellet fuel Pellet Cs 134 Rb 88, Less than 10 Overheating Te 129. Te 132

) Grain Boundary 10 to 50 Intermediate Diffusion fuel Pellet Fuel Pellet ,

- Overheating Major Fuel Pellet Diffusional Release Fuel Pellet Greater than 50 Overheating From 002 Grains Fuel Pellet Melt -

Fuel Pellet. Less than 10 5 Intermediate Fuel' Escape from Molten Fuel Pellet Ba 140, La 140 10 to 50 N '

Pellet Melt > Fuel La 142, Pr 144 4 o

~

b Major Fuel Pellet Fuel Pellet Greater than 50 T

& Melt ,

N

• 0 e

~._....

-- ~

. . _ . . . . . . . _ . ~ . . . . _ . . . _

? *

. EPIP-TSC-8-A-5

~ ~ '

ENCLOWRE 2 C.t-' 'v 'ea' a ^'v='= 'aa 'a" a=='='"'

DOSE RATE INSIDE A CYLINORICAL CONTAINMENT l

1 100 l

1 10I #g

• +e,,

'*'4, f( I **< #++g

1. 4 >

1x1d - 4e

• '!/ '4sc 4sg 1x103 1C

[0 100 TIME POST ACCIDENT, HOURS c CYLINDRICAL CONTAINMENT

~

ISSUED F'/EPIP/02 C

FE8 2 3 37 , R3 02-23-87

EPIP-TSC-8-B-1 SECTION B Estimate of Core Damage Using Isotopic Data I. PREREQUISITES A. A plant accident with-the potential for core damage has occurred.

B. Isotopic activities are available per 01-SL-2 or 01-PAP-2.

C. Computer program UTYPASS is available for execution.

D. The Post Accident Sampling System (PASS) is operable and has the

. capability to obtain and analyze the identity and concentration of fission product isotopes in fluid samples which have the potential to be highly radioactive.

II. PRECAUTIONS AND LIMITATIONS The assessments of core damage obtained by using this procedure are only estimates and represent lower limit estimates of clad damage.

The total quantity of fission products measured at monitor locations in containment may be changing-rapidly due to transient plant conditions.

Therefore, multiple measurements should be obtained within a minimum time period and under stabilized plant conditions when possible. Samples obtained during rapidly changing plant conditions should not be weighed heavily into the assessment of core damage.

II

I. PROCEDURE

Es,timation of Core Damage Using Isotopic Analysis j A. Perform an isotopic specific activity analysis by obtaining samples l

based on the following criteria:

TYPE TRANSIENT SAMPLE LOCATIONS a) Rapid Depressurization Reactor Coolant, Containment -

of Primary System. . . . . . . . . . . . . . . . . . Atmosphere , Conta inment Sump i .

l b) Slow Depressurization of Primary System EARLY......................... Reactor Coolant LATER......................... Reactor Coolant, Containment l

t Atmosphere, Containment Sump i

ISSUED FC/EPIP/02 R3 02-23-87 FEB 2 31987 l

.._.L..---...

EPIP-TSC-8-B-2 II

I. PROCEDURE

(Continued)

NOTE: If the core damage es'timate is performed after purging containment, the noble gas concentrations should be adjusted to reflect the initial concentrations prior to the purge operation.

B. Using OI-SL-2 or 01-PAP-2, obtain and analyze the selected samples for fission product specific activity and record in Table 1. All of the isotopes listed in the table may not be observed in the sample.

C. Record the time of reactor trip. Date / Time .

D. If the Saf~tye Injection Tanks (SIT's) and/or Safety Injection Refueling Water Tank (SIRWT) have been used during the transient,

. complete Table 2.

E. Determine the elapsed time between reactor trip and sample measurement:

hours F. Cenplete Table 3 on Power History.

G. This step uses the computer program UTYPASS on the IBM PC to provide an estimate of core damage using isotopic analysis. If access to the IBM PC is not available, proceed to Step I to access the program on the terminet.

1. Insert the UTYPASS floppy disk, found in the Core Physics Supervisor emergency packet, into the "A" floppy drive.

2. Enter the following statements, in order:

CD\EPIP CR (Carriage Return)

COPY A: **. CR PE CR CR EDIT USERI.PRG CR

3. Input the information from Tables 1, 2 and 3 by using the arrow, PgDn and PgUp keys on the right side of the keyboard to, modify the input data file as outlined in Appendix A.

4. Enter the following statements, in order:

FILE USERI.PRG NOTABS CR QUIT CR PRGPASS CR l( ISSUED FEB 231987 .

FC/EPIP/02 R3 02-23-87 l l

EPIP-TSC*8-B-3 II

I. PROCEDURE

(Continued) .

. G. 5. When "Stop - Program Terminated." appears on the screen, enter the following statements:

PE CR EDIT USERO.PRG CR

6. Use the arrow, PgDn and PgUp keys to view the output, or use the F7 function key on the left side of the keyboard to print the output file

7. When finished, return the floppy disk to the Core Physics Supervisor emergency packet and type the following:

QUIT CR QUIT CR CD\ CR H. CORE DAMAGE ASSESSMENT The conclusion on core damage is made using the three parameters developed above. These are:

1. Identification of the fission product isotopes which most characterize a given sample, step B, Table 1.

2. Identification of the source of the release from program output or step L, if manual calculation was used.

3. Quantity of the fission product available for release to the environment expressed as a percent of source inventory from program output or step 0 if manual calculation was used.

Compare the three parameters above to the definitions of the 10 NRC categories of fuel damage found in Enclosure 1. Core damage is not anticipated to take place uniformly. Therefore when evaluating the three parameters listed above, the procedure is anticipated to yield a combination of one or more of the 10 categories defined in Ehclosure 1.

These categories will exist simultaneously.

CONCLUSIONS:

ISSUED r FEB 231987 FC/EPIP/02 R3 02 23 87 i

__ _ - _ _ ._____ _ _ _ _ _ _ _ . _ _ _ _ _ .__ _.___~ _ - . _ _ _ _ _ _ _ , , _ . _ _ _ _ _ _

. EPIP-TSC-8-8-4 II

I. PROCEDURE

(Continued) .

G: I. This step uses the computer program UTYPASS on the terminet to provide an estimate of core damage using isotopic analysis. If access to UTYPASS or the terminet is not available, continue with procedure Step J for manual calculation toward an isotopic core damage estimate.

~

1. To use the Combustion Engineering computer system upon which UTYPASS resides, SET TERMINET TO HALF DUPLEX l Dial 1-800-243-3202 or 1-203-683-0411  ;

or 1-203-683-2734 Once the computer has been accessed, use the.following sequence to 2.

log on and access UTYPASS.

USER NAME, PASSWORD:  ;

OMAHA, 9 CR  !

XEDIT,UTYPASS,P CR Perform input changes as outlined in Appendix A Q,,RL CR i

3. To submit the computer job, type:

SUBMIT, UTYPASS,T CR

4. When the job is complete, use the following comand to identify the job name.

ENQUIRE,UJN CR

5. To print the results, input the following sequence:

TRMDEF,PW=136. CR

~

QGET,LfN CR COPY,LfN CR

6. Summarize the core damage results as directed in procedure Step H.

l t

l C 1 SUED FC/EPIP/02 R3 02-23-87 FEB 2 31987

p.

EPIP-TSC-8-B-5

, II.

I. PROCEDURE

(Continued) f-J. Complete the Enclosure 3 worksheet to correct the measured sample l specific activity to standard temperature and pressure as follows.

NOTE: This portion of the procedure is only to be used when access to UTYPASS is not available.

1. Reactor coolant liquid samples.are corrected for system temperature and pressure using the factor for water density provided in Enclosure 2. The correction factor obtained from the enclosure is divided into the measured value to obtain the density corrected value.

2. Containment building sump samples do not require correction for temperature and pressure within the accuracy of this procedure.

3. Containment building atmosphere gas samples are corrected using the following equation.

14.7 Specific Activity (STP) = Specific Activity x ( ) (T1 + 460)

Pg + 14.7 492 T,Pi i

= Measured Sample temperature and pressure recorded in step 8.

K. Correct the sample specific activity at STP for decay back to the time of reactor shutdown, as recorded in step C, using the following equation. Enclosure 4 is provided as a worksheet.

Ao= A

-Ar Where:

e Ao = the specific activity of the sample corrected back to the time of reactor shutdown, pci/cc.

A = the measured specific activity, pci/cc.

A = the radioactive decay constant, 1/sec.

t = the time period from reactor shutdown to sample analysis, sec.

1SSUED R3 02-23-87 FC/EPIP/02 FEB 2 31987 1

1

, ._ _ p -- - m.. -_ . _1 EPIP-TSC-8-B-6

{ III.

L.

. PROCEDURE (Continued)

Identification of the Fission Product Release Source.

1. Calculate the following ratios for each noble gas and iodine isotope only using the specific activities obtained in step L.

Enclosure 5 is provided as a worksheet.

Noble Gas Ratio = Noble Gas Isotope Specific Activity Xel33 Specific Activity Iodine Ratio = Iodine Isotope Specific Activity I-1315pecific Activity

i. 2. Determine the source of release by. comparing the results obtained to the predicted ratios provided in Enclosure 5. An accurate comparison is not anticipated. Within the accuracy of this procedure it is appropriate to select as the source that ratio which is closest to the value obtained in step L.1.

M. Calculate the total quantity of fission products available for release to the environment. Enclosure 6 is provided as a worksheet.

1. The quantity of fission products found in the reactor coolant is calculated as follows.

a. If the water level in the reactor vessel recorded in step B

(~- indicates that the vessel is full, the quantity of fission products found in the reactor coolant is calculated by the following equation.

Total Activity (C1) = Ao (uci/cc) x RCS Volume Where:

Ao = the specific activity of the reactor coolant sample corrected to time of reactor shutdown obtained in step K,

.uci/cc.

RCS Volume = the full reactor coolant system water volume corrected to standard temperature and pressure using Enclosure 2.

b. If the water levels in the reactor vessel and pressurizer recorded in step B. Table 1 indicates that a steam void is present in the reactor vessel, the quantity of fission products found in the reactor coolant is calculated using the equation from step M.1.a.

c. If the water level in the reactor vessel recorded in step B is below the low end capability of the indicator, it is not possible to detennine the quantity of fission products from this sample because the volume of water in the reactor coolant system is unknown. Under this condition, assessment

[L of core damage is obtained by using the containment sump sample.

ISSUED R3 02-23-87 FC/EPIP/02 FEB 231987 .

EPZP-TSC-4-B-7 II

I. PROCEDURE

(Continued) -

M. 2. The quantity of fission products found in the containment building sump is determined as follows,

a. The water volume in the containment building sump is detennined from the sump level recorded in step B Table 1 and the curve provided in Enclosure 7.

b. The quantity of fission products in the sump is calculated by the following equation.

Total Activity, Ci = Aa (u i/cc) c x Sump Volume Where:

Ao = the specific activity of the containment sump sample corrected to the time of reactor shutdown obtained in step K, u ci/cc.

! 3. The quantity of fission products found in the containment building atmosphere is determined as follows. ,

a. The volume of gas in the containment building at the time of the accident, is corrected to standard temperature and pressure using the following equation.

t 492 Gas Volume (STP) = Gas Volume x (14.7 +P)x 14.7 (Tt + 460) )

Where:

r T,Pi 1 = Containment Atmosphere temperature and pressure recorded in step B, Table 1.

i

! 4. The total quantity of fission products available for release to the environment is equal to the sum of the values obtained from each sample location.

l l

FC/EPIP/02 ISSUED R3 02-23-87 FEB 2 31987 .

_ _. ._ . . . . _ . _ ~ .

EPIP-TSC-8-B-8 ,,

(i

~

II

I. PROCEDURE

(Continued)

N. PLANT POWER CORRECTION The quantitative release of the fission products is expressed as the percent of the source inventory at the time.of the accident. The equilibrium source inventories are to be corrected for plant power history. Use infomation from step F, Table 3.

1. To correct the source inventory for the case in which plant power level has remained constant for a period greater than four radioactive half lives the following procedure is employed.

Enclosure 8 is provided as a worksheet,

a. The fission products are divided into two groups based upon the radioactive half lives. Group 1 isotopes are to be employed in the case where core power had not changed greater than 10 percent within the last 30 days prior to the reactor. shutdown. Group 2 isotopes are to be employed in the case where core power had not changed greater than 10 percent within the last 4 days prior to the reactor shutdown.

b. The following equation may be applied to the fission product Group which meets the criteria stated in N.I.a only.

4

Group 1 Power Correction Factor =

l Steady State Power Level for Prior 30 days 100 Group 2 Power Correction Factor =

Steady State Power Level for Prior 4 Days 100

2. To correct the source inventory for the case in which plant power level has not remained constant prior to reactor shutdown, the following equation is employed. The entire 30 days power history should be employed. Enclosure 9 is provided as a worksheet.

Power Correction Factor = I,P, (1-e 4Tj) e~ j 100 Where: ,

P3 = steady reactor power in period j t = duration of period j t) = time from end of period j to reactor shutdown

, O FC/EPIP/02 ISSUED R3 02-23-87 FEB 2 31987 .

I

EPIP-TSC-8-3 II

I. PROCEDURE

(Continued)

0. Comparison of Measured Data with Source Inventory The total quantity of fission products available for release to the environment obtained in step M.4 is compared to the source inventory corrected for plant power history obtained in step N.2. This comparison is made by dividing the two values for each isotope and calculating the percent of the corrected source inventory that is now in the sampled fluid and therefore available for release to the environment. Enclosure 10 is provided as worksheet.

P. CORE DAMAGE ASSESSMENT Summarize the core damage results as directed in procedure step H.

i 1

l I

FC/EPIP/02 ISSUED R3 02-23-87

FEB 2 31987 .

e p

, EPIP-TSC-8-B-l'a  !

~

Td8LE1 3 .

.s Temperature Pressure F psia Containment Gas Loop RCS (Tave)

Reactor Vessel Level  %

Pressurizer Level  %

Containment Sump Level  %

Specific Activity (microcuries/cc)

RC CA CS Isotope Xe-131M Xe-133 Kr-88

{

Kr-85 Kr-87 t

I-132 i

l I-133 I-135 I-131 l Cs-134 j Te-132 j l Ba-140 l Ru-103 .

i Time of Sample Measurement ISSUED C- FC/EPIP/02 Fra a: 1st

.~-w-----..----w,.-,,----y., --,w-_ . _ . - . , _

EPIP-TSC-.8-8-11 e

TABLE 2 Safety Injection Tank Level, %

Before After SI-6A SI-6B SI-6C SI-60 SIRWT Level (Inches)

Before After SIRWT i

1 iSSUkD R3 02-23-87 FC/EPIP/02 FEB231987

^ ~~ ^

,~. . .: . . .. . . :.~ . ^

- ^

~.'

EPIP-TSC-8-B- 12 TABLE 3 .

30 DAY P0nER HISTORY

, P Tj Tj 3

0 e

Up to 8 Intervals May be Revised Pj = Steady reactor power operated in period j % full power NOTE: In each period, the variation of steady power should be limited to 1105.

Tj = Duration of operating period j (days)

To j = Time between the end of operating period j and time of reactor shutdown (days) 1 e

e FC/EPIP/02

{

~ ISSUED m

R3 02-23-87 FEB 23 h

EPIP-TSC-8 8- 13

- APPENDIX A User input guide for core dariage estimate computer program PRGPASS.

CARD 1 20 - 25 30' 35 l 40 5 to -

15

' (

HOURS TlIIMIE1= .Hl0lUIRIS l ll [ tgi t lgll 11 I t iI1 1 f11 1 Hours is in FS.1 fonnat starting in Card Column 12 l

Hours is the time fro:n reactor trip until the primary sample is read.

i l

CARDS 2 through 5 - SI Tank Levels 10 15 20 25 30 35l 40 5

101.1010 0fEl+1010 101.1010 .0lEl+1010 1Ii1 1It t l SlIl-161X .IIl1 Cards 2 through 5 are for SI, 6A, 68, GC, 60 tank levels before use and af ter use. The levels are in percent. Format is E9.3,1X, E9.3 starting in Card Column 12.

ISSUED FC/EPIP/02 ,

R3 02-23 87 MS 3 3 BW s

r - -- -- ----

1.2.2 n . ~ ; ~

l . .

EPIP-TSC-8-B- 14 CARD 6 - SIWRT Level .

30 35 40 20 25 10 15 5

INITIAL FINAL i

IIII II' '

IllI Ii1 I II!I 'II I '

.SlllRlWIT liiI Level is input in Card inches.

6 is for SIWRT level before and after use, if any.Fomat is E9 .

CARD 7 - Contairment Temperature and Pressure 30 35 'a0 15 20 25 5 10 TEMP. PRESS.

lIl1 1if I IIfI ffI I I C 10l NI TI A . IlNI MI T1 lll1 fit i l

i Card 7 is for input of containment temperature (*F) and containment pressure These values should correspond to the time the contairment (PSIA). Format starting in Card Column 12 is E9.3,1X, atmospheric sample was taken.

l t

E9.3.

l CARD 8 - Gas Sample Temperature and Pressure 40 5 10 15 20 25 30 35 TEMP PRESS.

i

,G lA IS I It. l.10[ 0lPI lll1 gg,g ggl[ lif I IIII Itt i Card 8 is for input of the gas sample temperature (*F) and pressure (PSIA).

The fomat starting in Card Column 12 is E9.3,1X, E9.3.

FC/EPIP/02 1SSUED R3 02-23-87 FES 3 3 W

EPIP-TSC-8-B 15 CARD 9 - Core Average Reactor Coolant System Temperature 30 35 40 15 20 25 5 10 TEMP.

liI I IfI f EIM1 Pt t IIII ffif fIII Iit i RlCis t IT Card 9 is .for input of the core average RCS temperatures (*F) corresponding to the time when the primary sample was taken. Fomat starting in Card Column 12 is E9.3. I CARDS 10 through 21 - Isotopic Information 20 25' 30 35 40 5 10 15 CA CS RC IIII II f 1 1111 111 f Ilsl0lT10 .PIEI I I IIII f11 I Cards 10 through 21 are for input of isotopic infornation.

The activities input are in microcuries/cc.

The reactor coolant values start in Card Column 12, i The contain:56nt atmospheric values start in Card Column 22.

The containment sump values start in Card Column 32.

If a sample is not read for a particular isotope or a region is not sampled, input zero's.

The femat for each card is A10, IX, E9.3,1X, E9.3,1X, E9.3.

The isotope cards must be in the following order. .

CARD # ISOTOPE 10 XE-133M 11 XE-133 12 KR-88 13 KR-85 14 KR 87 15 I-132 16 I-133 17 I-131 CS-134 l ISSUED -

18 19 TE-132 20 BA-140 FEB 2 3 W 21 RU-103 R3 02-23-87 FC/EPIP/02 .

-. ~ , - - - - - - - . , , , - _ , - . - - . - - , . . , . . , , , - , , . , - - - . - - - - , - . , _ . . _ . , , , , , , , _ _ _ - -

a- .- - -

2.  :.:-... -- -- - - -

EPIP-TSC-8 16 CARD 22 - Choice to use Noble Gases or Cs-134/I-131 for overtienting Calcula-1 tions.

25 30 15 an 10 15 20 5'

N1 IIII Ii11 1I1 I ClH10f f 1C El l 1 I i 1 'I I fi1 I 11 I i N1 = 0 Use I-131 and Cs-134*

= 1* Use Nobel Gases

• Use the data.for Iodine or Cesium only when the data for noble gases is not available.

CARD 23 - Number of Values in History File (Cards 24 through 31)

'O 5 10 15 20 25 30 1c an N

l1l1 IIII IIt t P]WlRIST ll 11 l11I fi1 I II I I N = Number of power changes for 30 Days prior to trip, N = 1 to 8.

Integer forriat in Card Column 12.

l

, FC/EPIP/02 ISSUED

{r RC S S E R3 02-23-87 1

EPIP-TSC-8 17 *

' CARDS 24 through 31 - Power History 10 15 20 25 30 35 40' 5

POWER DAYAT DAYTTL lll1 lIII IIlI fit i itlI II I I II11 1ti t The power history is for the 30 days prior to shutdown. Up to 8 power changes may be modeled.

1 POWER =. Power level in percent of full power. flote 10%

levels are sufficient modeling changes.

DAYAT = Ouration of operating period (Days).

DAYTIL = Time between the end of the operating period and the time of reactor shutdown (Days).

FOPJtAT = 15X, F5.1, SX, FS.1, SX, FS.I.

i l

ISSUED R3 02-23-87 FC/EPIP/02 3g l

t

i O n -

C) a e

i .

A lj  ; Enclosure 1 .

j 3  !

1 4 Radioloelcal Characteristics of INtc Categories of Fuel Damage i i 8

• l Release of Characteristic

{ NRC Category of Mechanism of Source of Characteristic Isotope Expressed as a  !

- Fuel Dammee Release Release Isotope Percent of Source Inventory i 3 #

! w. ,

l * 's #

C No Fuel Damage Halogen Spiking Trasp Uranium Gas Gap I 131. Cs 137 Ab 88 Less than 1 .! '

l ,' m

~

D Initial Cladding Gas Gap Less than 10  !

Failure -

Intermediate Clad Surst and Gas Gap Xe 131a, Xe 133 10 to 50 '

i Cladding Failure > Gas Gap Diffusion I 131. I 133 ,

! Release j Major Cladding Gas Gap Greater than 50 i l Failure j Initial Fuel Pellet Fuel Pellet Cs 134, Rb 88, 'Less than 10 '

I Overheating Te 129. Te 132 ,

I

) Grain Soundary I Intermediate ' Diffusion Fuel Pellet 10 to 50 -

! Fuel Pellet :I

! . Overheating .

Major Fuel Pellet Diffusional Release Fuel Pellet Greater than 50 Overheating From 002 Grains Fuel Pellet Malt -

Fuel Pellet Less than 10 h

i 5 Intermediate Fuel

• Escape from Molten Fuel Pellet 8a 140, La 140 10 to 50 $1

! o Pellet Malt > Fuel La 142, Pr 144 ,P m .

A Major Fuel Pe11et Fuel Pellet Greater than 50 i'

[ Malt E ,

~ .  :

f .

t

EPIP-TSC-8-849 ENCLOSURE 2 RATIO (F H 0 (ENSITY TO H O GSEITY AT 2 2 STP vs TB rERATtfE 700 1

M -

400 -

G 300 -

200 =

, 100 -

1 I I I O 0.50 O 0.25 0.75 1.0

1. d #STP FC/EPIP/02 ISSUED g

- .. R3 02-23-87

, - - - - ,,--n.,--.,----,,--..-----.,,.-,--.,--,,-r,.,

. . . - ....:x - = . . . . - . : .. ---s..

EPIP-TSC-8-B ~ 20

== = $

O

- - ,sms - - - c=en.

Sample Number:

Location:

Time of Analysis:

Temperature. *F:

Pressure. PSIG:

f Measured Specific Activity Correction Specific Activity Isotope ( Table 1 ),UCi/cc Factor 9 STP, sci /cc Kr 87 Xe 131m Xe 133 I 131 1 132 1 133 I 135 Cs 134 -

BM Ta 129 i Te 132 .

l Sr 89 Sa 140 La 140 La 142 Pr 144 ISSUED FC/EPIP/02 - R3 02-23-87 RB23 W M b um , d $ 9-

_ . - -.,-,m . - - - - - - ,

.c .

s

~

T;lP-TSC-8-621 -

g-ENCLO9JRE 4 IEC0fE) F 2 CAY C015ECTION

^'

2 -

i 't Time of 'Aeactor Shutdown, Step IV.C.

~

Sample Number: ,

Location:

' Time of Analysis:

g

.y . - ~ - /- ,

I Des.ay Specific Activity '

Decay "crmeted Constant, 9 STP (Enclosure 3), Spedfic Activity' )

"Cilce

i Isotooe 1/sec ' /cc Kr 87 1.5,(-4) --

Xe 131m 6.7(-7) ,,

Xe 133 1.5,(-6) ,

I 131 9.9(-7) 1 132 S.4 (-5) -

(

l I 133 9.3'(-6) s I 135 2.9(-5) ' -

Cs 134 1.1(-8)

Rb 88 .

5.5. (d) .

f Te 129 1.7(-4) .

'4 Te 132 2.5 (-6)

Sr 89 1.6(-7) .

l Ba 140 6.3(-7) i- La 140 4.8 (-6) .

La 142 -

1.2(-4) .

I Pr 144 6.7(4)

~

R3 02-23-97 FC/EPIP/02 FE8 2 3 sp

^

i ,

E' i*

, - . - . . - - . - - , - .~ ,,-.....-.---.___.--._,.--.,..-.,---,--,...----,--.,,.,,,.,---.__....-.----.-,J',--,-

, __ m l, , Q

~

Q._ , * :~' ' . Q "'.;

o x 4

=

. t

. / n a'

. M - ~

ENCLOSUE 5

]-

- ~

s .

4 B

~ .

L 3 IEttH) 0F FISSIM PIEDUCT F N'SolEE IIEMi!FICATIM - . .:_

i ~ _ .

, s

/

! 3* mm sample number: ,

i .

i

= c Location:

"3 l

i l O -

Decay Corrected l Activity Ratio Identified Calculated Fuel Pellet.

i Specific Activity  !

l la Gas Sep Source IsotopeNatio* Inventary_ .

7 i

Isotope (Enclosure 4).'*I/cc -

0.2 0.001 ,

Kr 87 .

l

0.003 0.001-0.003 Xe 131m l 1.0 1.0 i' Xe 133  ;

1.0 1.0 ll I 131 [

i 1.4 0.01-0.05 1

I 132 4

2.0 0.5-1.0 0.1-0.5 i I

1.8 t l I 135 9 l m (

l '

A f e

Noble Gas RatioDecay

= Decay Corrected Noble Gas Specific Activity y o

• Corrected Xe 133 Specific Activity co c'o 7'

~

I' lodine htte = Decay Decay Corrected Corrected 1-131 IodineSpecificIsotope ActivitySpecific Activity "

m i s i e-

, i 1

' ' j'J EPIP-TSC-8-B-23 -

sa

n. ,l EM10SURE 6 ECGE (F IELEASE EJANTITY s

'$ Ratactor Coolant Containment Sump Containment Total Sample Number, Sample Mus6er. Atumsphere Sample Quantity Isotope C1 -

Ci Number , C1 Ci y

Kr 87 Xe 131m Xe 133

. I 131 I 132' t

I 133 ,

s, s e I 135 Cs 134 Rb 88 Ta 129 Te 132 >

. St C9 Ba 140 .

?"

La 140

-3 La 142 4 "

Pr 144 ISSUED '

pp R3 02-23-87 ggg g g ,, . - - - - - - - - ,.e m-

.e a a L -

e.ge% fk ,p g, a kg4 44g,Iynam I w Ma -,M WU *a% 4 9

9 4 4

4

, EPIP-TSC-8-B 24 LEVEL vs VOLUME f

9 8 .

S M

N m

~

7 .

m W

• i 3

g

/

M N

N g.

p 5 ,

u. -  ;

i j ~

1 W m

4 I

l t, .

l 3 . .

- e W

W D

2 .

O no i .

m W

m R R R R t t t t t t t I O t t t t I t t t t t i R R t I f I t t t t I e t

• f iit t t 0 10000 20000 30000 40000 50000 VOLUME, M

' C. ISSUED l

FC/EPIP/02 O 02-23-87 t i _ - . , , _ . - - - - - . = , . _ . . . _ . - . . _ , _ _ . . - , . - _ . , _ _ _ . _ . - - - - . - . - - - _ _ _ - - . _ - . -..,___---_-om, . .

EPIP-TSC-8.-B- 25 -

ENCLOSUE 7A

.CONTAINMENTSUMPCURVE LEVEL VS, VOLUME sm.S. na

. 19 14.71 in /

m - n.s 7 e

- an .

r

/

m G

N -

2.M '

W t -

i a -

. s.s E

m 4

i sa - e.m m

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3 4.01

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, n ,... . .....n .. n.n. .ninn. ene""'"'""'""'""""'""""""'"'"""'""""'""""

8 2 4 g g 10 12 14 18 18 3 22 24 50s 1005 ISSUED SUMP LEVEL - INCHES R3 02-23-87 II FC/EPIP/02 .

l t

.. ... . = : ~ _ - - .

, EPIP,-TSC-8-B- 26 0 .

== 8 ' .

M (F STEADY STATE POLER C(HECTI(M Sample Number:

Location:

Steady Statei 30 Days Power Level:

Steady State 4 Day Power Level:

Fuel Power Equilibrium Corrected History Correction x Source- = Source Isotope Grouping Factor Inventory Inventory Gas Gap Inventory Kr 87 2 3.6(0)

Xe 131m 1 -

2.7(4)

Xe 133 1 1.3(7)

C'l. I 131 1 4.4(6)

I 132 2 4.9(3)

I 133 2 4.4(6)

I 135 2 7.0(5)

Fuel Pellet Inventory Kr 87 2 1.8(7)'

Xe 131m 1 2.9(5)

Xe 133 1 1.5(8)

I 131 1 4.8(7)

I 132 2 7.0(7)

I 133 2 1.5(8) ,

I 135 2 8.6(7)

Cs 134 1 6.1(6)

Rb 88 2 2.9(7)

Te 129 2 1.6(7)

Te 132 1 7.0(7)

Sr 89 1 3.9(7)

Ba 140 1 8.0(7)

La 140 1 8.4(7)

La 142 2 1.0(8)

Pr 144 2 6.5(7)

O' ISSUED FC/EPIP/02 R3 02-23-87 FE8 8 3 Ed ,

-~ _____

1 EPIP-TSC-8 27 ENCLOSLE 9 ECGW (F TRANSIENT PONER CGUECTI(M l

l l

i Sample Number:

l Location:

l Prior 30 Day Power History: Power % Ouration, Days Power Correction x Equilibrium Source . Corrected Source Isotope Factor Inventory Inventory

, Gas Gap Inventory l Kr 87 3.6(0)

Xe 131m 2.7(4)

! Xe 133 1.3(7)

I 131 4.4(6) c I 132 4.9(3) l I 133 4.4(6)

I 135 7.0(5)

Fuel Pellet Inventory Kr 87 1.8(7)

Xe 131m 2.9(5)

Xe 133 1.5(8)

I 131 4.8(7) l I 132 7.0(7) l I 133 1.5(8)

I 135 '8.6(7) .

Cs 134 6.1(6)

Rb 88 2.9(7)

Te 129 1.6(7)

Te 132 7.0(7)

Sr 89 3.9(7)

Ba 140 8.0(7)

La 140 8.4(7)

La 142 1.0(8)

Pr 144 6.5(7) i S S U E D *.8 '

R3 02-23-87 R/ EPIP/02 FU 3 3 M ,

^^ ^

a. . .

. . . . _ - . -. . _ :. _ _ . _ . a _ . .. .

. , EPI P-TSC-8-B- 28 i((

1 BCLOSINE 10 IECGB (F PEIEENT IELEAE Total Quantity Power Corrected Available For Release e Source Inventory x 100 =-

!sotope (Enclosure 6) C1 C1 ( Enclosure 8 or 9 ) Percent Gas Gao Inventory Kr 87 ,

Xe 131 Xe 133 I 131 1 132 1 133 1 135 Fuel Pellet Inventory Kr 87

-('

, Xe 131m Xe 133

(!

I 131 I 132 '

1 133 I 135 Cs 134 Rb 88 Te 129

. Te 132 Sr 89 Ba 140 La 140 La 142 Pr 144 l

h e e 6

FC/EPIP/02 .

O e

l( ,

ISSUED FEB 2 3 W R3 02-23-87 f

i

EPIP-TSC-8-C-1 SECTION C t

Estimate of Core Damage Using Hydrogen In Containment I. PREREQUISITES A plant accident with the potential for core damage has occurred.

A.

B. The Post Accident Sampling System (PASS) is operable and has the capability to obtain and analyze the identity and concentration of fission product isotopes in fluid samples which have the potential to

. be highly radioactive.

II. PRECAUTIONS AND LIMITATIONS The assessments of core damage obtained by using this procedure are only estimates and represent lower limit estimates of clad damage.

This procedure only estimates the percentage of rods which have progressed to at least clad rupture or clad embritt'ement, and does not attempt to predict the physical configuration of those rods which

! have progressed beyond local clad fragmentation.

This procedure assumes there are no voids measurable by the Reactor Vessel Level Monitoring System. However, if the hydrogen samples are 4 taken under conditions in which a measurable void does exist, the attached addendum contains guidelines to estimate the added contribution of hydrogen, by that source, to the total hydrogen I

measured.

This procedure provides an estimate of only the percentage of rods which have progressed to at least clad rupture or clad embrittlement, and does not attempt to predict the physical configuration of those rods which have progressed beyond local clad fragmentation.

l l

l 1

l I

l S S U4EdD

~ ~

FC/EPIP/02 FEB 2 3 IN7 l

. .. z . .:. = :=. . : . - : L r'- w :,==..:nar - --- -- -- -

EPIP-TSC-8-C-2 II

I. PROCEDURE

' 0' Estimation of Core Damage Using Hydrogen ' Measurement

a. Record the estimates for core uncovery and recovery times using instrument records from the Reactor Vessel Level Monitoring System, Core Exit Thermocouple Temperature and Core Exit Thermocouple j Saturation Margin.

Estimated Estimated Instrument Core Uncovery Time Core Recovery Time Reactor Vessel Level Lower Limit Elevation Lower Limit Elevation Monitoring System Uncovers. Recovers.

Time Time i

l Core Exit Themo- Start of Continuous Rapid Tempe'rature i couple Temperature Rise or Exceed of 600F. Drop to Saturation.

Time Time

Temperature Temperature Core Exit Themo- Start of Superheat. Return to Saturation couple Saturation Time or Subcooling.

Margin -

Time

b. Interpret the data from step a to determine the best estimate for the time period of core uncovery and obtain the range of RCS pressure (pressurizer pressure) indicated for this time period. The superheat Cr derived from the thermocouple temperature and corresponding system pressure is considered as the best indicator for core uncovery during 4 - core boiloff and should be used but should be compared with other indicators to help identify possible anomolies. Record these values below.

Core Uncovery Core Recovery i Time ,

Pressure

c. Observe available instrument records to detemine if there was some reactor vessel inlet flow during the rising temperature portion of the core uncovery period up to approximately the time of peak core exit thermocouple temperature.

Charging Flow Rate GPM Letdown Flow Rate GPM HPSI Flow Rate GPM LPSI Flow Rate GPM

! Other Flow Rate GPM NOTE: Net inlet flow indicates that this procedure may have additional bias which underpredicts clad damage.

l{"

i ISSUED R3 02-23-87 FC/EPIP/0? FEB 2 3 W

-*-c-- -

---e.- -m-, .w--_ w v.ww-ww.er,,.r,m ,ww-,,,e,--e.----o,---ver-er-w---ww- we w www-*e--,-==se, - w e m--=--rver-.w-

. _l EPIP-TSC-8-C-3 l

III. P'ROCEDURE (Continued)- 1

d. Obtain a liquid sample from the RCS hot leg and a gas sample from the 1 containment atmosphere and record the conditions in the containment at  !

the time these samples are obtained, below. Analyze the samples for hydrogen concentration using the PASS procedure and record these results below. Estimate the total cubic feet of hydrogen at standard temperature and pressure as outlined.

Reactor' Coolant System Containment Sampling Time Atmosphere Pressure psig Pressure psig Atmosphere Temperature F Temperature F Has Hydrogen Recombiner Yes/No Operated Reactor Vessel Coolant Level  % Does Pressure or Temper- Yes/No ature History Indicate a Pressurizer Level  % Hydrogen Burn Cont. Sample X Cont. Vol. X (32 + 460) Normal Temp. = Ft3 Hydrogen (Vol. %/100) (Ft3) + 460 at STP X 1.05 x 10 X 492 =

Hot leg Sample X RCS Vol. X Density Ratio 1000 = Ft3 Hydrogen (cc/kg @ STP) (Ft3) (Enclosure 2) at STP X 6395 X 1000 =

Total =

Record total hydrogen measured in step g, also.

ISSUED FC/EPIP/02 FE8 3 8 Wy R3 02-23-87

^ - ^ ~ ' ' - ~

EPIP-TSC-8-C-4 II

I. PROCEDURE

(Continued) .

O I e. Record the containment temperature at selected time intervals and calculate the hydrogen generated by oxidation of containment materials utilizing the typical plant production rate from Enclosure 3.

1 2 3 4 5

! Avg. Containment Time at Start Interval H,(Prod. ft8/hr)Rate Produced =

of Intervals Duration (hr) Interval (*F Temp. During) (Enclosure 3) H2X4 Accident Starts i

1 C

~

Sampling Time 1

Long Term Hydrogen Production in Containment, Total =

ft3 9STP ,

Typical Short tem rapid hydrogen production by containment aluminum 1000 SCF l

Total Hydrogen Production In Containment SCF Record total in step g also.

I i

ISSUED i FC/EPIP/02 rge :3 gg7 R3 02-23-87

---

r-,--.,----_e-... re---,-.-------nn-n.,_n.-. n,w,,---,,,._n, ,------,--n,,,.e-m,,--__--,--r--. r,,,=-~-n ,,--n , ,,

EPIP-TSC-8-C-5 II

I. PROCEDURE

. (Continued)

f. Record the data requested below and utilize the curve of Enclosure 4 to obtain the cubic feet of hydrogen at STP generated by radiolysis.

l Determine the approximate power to be used as follows:

For the case in which the operating power is constant or has not changed by more than 210 percent for a period greater than 30 days, that power is used.

For the case in which the power has not remained constant during the 30 days prior to the reactor shutdown, engineering judgement is required to determine the most representative power level. The last power levels at which the reactor operated should weigh more heavily in the judgement than the earlier levels. Continued operation for an extended period q should weigh more heavily in the judgement than brief transient levels.

For the case in which the reactor has produced power for less than 30 days, the procedure may still be employed. However, the estimate of hydrogen from radiolysis will be too high and therefore the calculated hydrogen by core oxidation will be too low. Hence an underprediction of core damage may result. -

Prior 30 day power history Power, percent Duration, Days

\

Power to use in evaluating long term hydrogen production by radiolysis = (1500, ht) X .

Reactor Trip Time hrs Sampling Time (see step d) hrs Decay Time (Sampling Time - Trip Time) hrs Enter abscissa on Enclosure 4 with above decay time and read two values for hydrogen produced by radiolysis, one from each curve, in cubic feet of hydrogen at STP per Mwt operating power. Multiply by above power and record as follows: -

Hydrogen Produced Operating Total Hydrogen Limit Curve (SCF/ h t, Enclosure 4) Power Produced (SCF)

Upper Lower Using results from Radiological Damage Assessment Procedure, estimate which results should be used; upper limit for major fuel overheat, lower limit for initial fuel overheat or appropriate estimate between the two curves for intermediate fuel overheat. Circle corresponding g value of hydrogen above and also record in step g.

I5 SUED R3 02-23-87 FC/EPIP/02 FE8 2 3 IIIF

_._ _ . _ ._, . N . .. _ . - - ..

j s 1 EPIP-TSC-8-C-6 l

II

I. PROCEDURE

(Continued)

g. Enter the amounts of hydrogen from steps d, e, and f below.  ;

Hydrogen Measur'ed, Step d. SCF Hydrogen Produced in Containment, Step e. SCF Hydrogen Produced by Radiolysis, Step f. SCF Subtract Step e and.f from d to get l Hydrogen Produced by Core Clad Oxidation SCF '

Divide by (2570 SCF/1% Clad Oxidized) =  %

)

.= 5 Core Oxidated

h. Enter the abscissa of the curve on Enclosure 5 with the "% Core Oxidized" from step g. Use the curve labeled with the pressure closes to but greater than the RCS pressure during the core uncovery period as obtained and recorded in Step b. Read on the ordinate of Enclosure 5, the percent of fuel rods with ruptured clad and record below. Note that the sensitivity of measurement of hydrogen is comparable to the ,

range of oxidation on Enclosure 5. Hence, small amounts of clad rupture are not reliably predicted by this procedure.

l

% of Fuel Rods with Ruptured Clad =  %

! (; i. Enter the abscissa of the curve on Enclosure 6 with th "% Core lU 0xidized" from step g. Read on the ordinate the lower and upper values of the range indicated by the curve for the percent of fuel rods which have embrittled clad and record below.

Percent of Fuel Rods with Local 0xidation Embrittlement Range - Upper  %

l - Lower  %

l For a given percent oxidation of the core clad, the lower limit j.

estimate of embrittled clad in step i is, for most accident scenarios, the least amount of potential fuel structural failure. Step g may be interpreted as follows:

When the pressure during uncovery from step b is less than about 100 psia, a rapid core uncovery by blowdown is concluded. Heatup

.with minimum clad oxidation occurs. The extent of potential clad structural failures by melting may be greater than the upper-limit of embrittlement from step i as detennined by oxidation.

Hence, use the upper limit from step 1.

When there is inlet flow while the core is uncovering, the rate of uncovery is slower than assumed in the derivation of the curves on Enclosure 5 and 6. For a measured total amount of oxidation, the local percentage oxidation is probably greater along a shorter length of the upper portion of the fuel. Hence,

,?

gog ghe upper limit from step 1.

FC/EPIP/02 FE8 2 3 NW R3 02-23-87

- - , - -,,,.---r-..-,-,.m.,-~w, ,-.,.,e - , - - -.,-,m._...m,, _+--v-- . _ _ _ _ - , . . . - . , . . . . - - . . - -

EPIP-TSC-8I C-7 II

I. PROCEDURE

(Continued)

k. CORE DAMAGE ASSESSMENT The conclusion on core damage is made using the two results from above. These are:

1. Percentage of. fuel rods with ruptured clad, step h.

2. Percentage of fuel rods with embrittled or structurally damage clad, step i.

Knowledgeable judgement is used to compare the above two results to the definitions of the 10 NRC categories of fuel damage found in Enclosure 1. Core damage does not take place uniformly. Therefore when evaluating damage using these results, Enclosure 1 may yield a combination of categories of damage which exist simultaneously.

)

I$ SUED FC/EPIP/02 R3 02-23-87 g ,,

- m,--- - - . _ , - ,m-- - , _ , , - - , , , - , _ _ _ - , , - , , , - . - . , - - _ , , _ , , _ _ , . . . , . _ , y-_- _ ..,..r_-,y,---,-.--m - . , -

-m-.-__w_.. , , . ,

0 Q..

l m *

~ . .

m Enclosure 1 . -

j q -

j g Clad Damage Characteristics of NRC Categories of Fuel Damage t'

Mechanism Characteristic Measurement Percent of E m INtc Category Temperature Range Damage Rods Range (*F) of Damage Measurement m of Fuel Damage C -- -- Less Than 1 No Fuel Damage $750 None g ,m 0 _

Maximum Core <1550*F* Less Than 10 Initial Cladding Rupture Due to Gas Gap Exit Failure Overpressurization Thermocouple <!700*F* 10 to 50

! Intermediate >1200-1800 Temperature j Cladding Failure 72300*F i MajorCladding 721 Greater Than 50 ,

Failure - Oxidation r Loss of Structural Amount of Equivalent Core Less Than 10 }

Initial Fuel Pellet Integrity Due to Hydrogen Gas Oxidation

Overheating Produced <31 [

I Fuel Clad <!81 p

)1800-3350 0xidation (Equivalent to t Intermediate 1 0xidation 4 Fuel Pellet- ofCore) f Overheating. _

7651 Greater Than 50 l Major Fuel Pellet

. Overheating 9

9 i

y' i

5 .

M.

o .

' ~  ?

m I U

! Ea i w

! Values Given for Pressure <!200 psia and Burnap >0.

• Depends on Reactor Pressure and fuel Burnup.

EPIP-TSC-8-C-9 ENCLOSURE 2 RATIO OF H2O TO H2O DENSITY AT STP vs TEMPERATURE

= -

400 -

800 -

400 ..

J 300 -

l m -

100 -

l t i e f O 0.50 0.75 O 0.25 1.0

1. ACTMSTP 66suto FEB 3 3 IIST R3 02-23-87 l

4 EPIP-TSC-8-C- 60 J 1

ENCLOSURE 3-

(( J TYPICAL HYDROGEN PRODUCTION RATE

'"~ FROM ALUNINUM Ale ZINC vs. TBFERATIEE I .

1000 .

9. =

M =

1 gm .

i i

g -

j son -

B no -

i >

1 i

E -

i M =

I .

! 1on =

l C:. a=

300 too 300 280 iSiSDU E o R3 02-23-87 TEMPERATURE,*p

---

.~.-y.,_ _ _ - , , _ . _

I . .

l l EP!P-TSC-8-C-1g l -

spectFIC RADIOLYTIC HYOROGEN PRODUCTION, SCF HP

• i 2 m a i

i i

i i

~

i i

i i i i

[

5 -

5 a

M - a n

E I!

t S E F g .

m d f 5 m e g S

d E 1

h m M lg M

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a w

m

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Q 5 2 5

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N I E D l -

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I S S U.E D 2 R3 02-23-87 FC/EPIP/02 e

e- , - - - - -- .-, , - - - -,e,,e,y--._,,--y - , , _ --,,,,-.-,m .. m,yg-- _---ww-_ _-- _ ,-- .- _--

, . _. , ,_ _ _ _7__-.

+ ,

• s l EPIP-TSC-8-C- 12

~

ENCLOSt#IE 5 .

l 0 -CENT na Roos um -o l

CLAD vs CORE CLAD OXIDATION 1200'P 100 ., /

RUPTURE TEMPERATURE 80 .

S a

$ 1800*P w /

g 80 1800* P z

8 40 , ,

g WHEN THE PRESSURE USE CURVE LASELED IN STEP & 13 WITH TEMPERATURE .l 20 -

< 100 PS8A 1200*P

< 1200 PS8A 1800*P (10EO PS8A 1800* P

• O d ' ' '  ! I I

O 0.5 1.0 1.5 2.0

% OX10ATION OF CORE CLAD VOLUME

.. FC/EPIP/02 1SSUED FE8 s a Nul R3 02-23-87 )

o.

1  :  !  ! l.) , !4  !; '.  ; [ll jll !l F

_ C

/

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1 1 F

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0 0

0 0 F S . 5 2

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IH%

NE W1 T

H LNT E

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O OAD X WNE R I TCTO D U AOO A NLYTS TE A T

I IVHLW E O LEE I N LACT C N0 4 e C TOH L O OO R O

_ F RRAEO S

. EON X U C PDOI R O I S XD E R S 3IA E B0DT RY0AI ,6 C A TO L 0 0 e PBPI N IOSO A OII NE D LLA N V

O L

YO QFO FT B

R I

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0 i HH0 M P E E D P N I

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- 1 2 0 1 3 0 1

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7 .

EPIP-TSC-8-C-14

. Fort Calhoun Station Unit No. 1 ADDENDUM TO EPIP-TSC-8-C

.Ca .

Estimation of hydrogen Volume in Reactor Vessel Head Void 1

I. PURPOSE The purpose of this addendum is to provide a guideline for estimating the .

amount of hydrogen gas contained in a void at the top of the reactor vessel. This volume of hydrogen is added to the measured hydrogen in procedure Step d. of EPIP-TSC-8-C to yield the total hydrogen generated by-all sources. .

II. PRECAUTIONS AND LIMITATIONS '

This addendum should only be used to supplement the procedure when the

- primary system could not be filled prior to taking the liquid sample. This addendum can then be used to estimate the hydrogen in the vessel void which is not evident from the hot leg liquid sample.

This addendum only applies when the coolant level is above the hot leg and the remainder of the primary system is filled. Verification that the steam ,

generator tubes are filled can be provided by the existence of natural convection flow in the primary system. ,

The reactor vessel level monitoring system is required to provide the reactor coolant level. The volume of the void is obtained by relating the

{- volume in the vessel above the reactor coolant level to the value of level for the Fort Calhoun reactor vessel design.

This addendum only provides the analytical means to estimate the hydrogen contained in the void. The presence of other gases including helium, nitrogen and fission product gases will add uncertainty to the result.

II

I. PROCEDURE

a. Determine the conditions of the void as follows:

V = Void volume (ft8), derived from measurement of coolant level l TL = Temperature of liquid at coolant surface (*F)

PSAT = Water saturation pressure at temperature Tg

• PTOT = Reactor coolant system pressure (psia) i b. A first approximation is made using the following assumptions:

i l The partial pressure of vapor in the void is equal to the saturation pressure at the liquid temperature. T. This implies no heating of the

void gas by the reactor vessel walls or head. They are normally at .

, reactor outlet temperature and could remain above the temperature of  :

! the void causing the vapor to be superheated.

I

{> ISSUED FC/EPIP/02 FE8 s 3 m R3 02-23-87

.~.---,-.--,n_.n., ,,.e--,, __-.

EPIP-TSC-8-C-f5 ADDENDUM (Continued)

All the non-condensible gas in the void is assumed to be hydrogen and there is no helium or fission product gas from ruptured fuel rods and no nitrogen from the Safety Injection Tanks. A second approximation which eliminates this assumption is given in Step d.

c. Calculate the amount of hydrogen as follows:

P H PTOT - PSAT P,

H 492 FT3 H 9STP=(V)(14.7)(Tg + 460)

Add this amount to the total hydrogen in Step d. of EPIP-TSC-8-C.

d. A second approximation can be made using the Post Accident Sampling System and measuring the total gas and hydrogen dissolved in the hot leg liquid sample. This approximation assumes the following:

The gases have the same values of Henry's law constant which relates the partial pressure of a gas to the amount of gas dissolved in a liquid sample at equilibrium.

The dissolved gas is not in equilibrium with the gas in the void, the dissolved concentrations are still in the same relative proportion as if equilibrium did exist.

e. The partial pressure of hydrogen is calculated from:

(cc/kg)

PH , = (PTOT - PSAT)

(cc/kg)

Calculate the amount of hydrogen in the vessel head void by using the equation above in Step c.

l 3

ISSUED R3 02-23-87 FC/EP!P/02 FEB 231987

. , . - - - - - - - - - - . .-- , , , , , - - . , , . . - - - - ~ - - . , - - _ , , - - . - . - - - . ,,,,,,,---c.. - - - - , , - - , ,

EPIP-TSC-8-D-1 SECTION D -

(' ,

Estimate of Core Damage Using Core Exit Thermocouple Temperatures I. PREREQUISITES A. A plant accident with the potential for core damage has occurred.

B. An operational core cooling instrumentation system which includes core exit themocouple temperatures, pressurizer pressure and core level indications. It should be able to select and permanently record the highest thermocouple temperature for convenient, later inspection.

II. PRECAUTIONS AND LIMITATIONS The assessments of core damage obtained by using this procedure are only estimates and represent lower limit estimates of clad damage.

This procedure provides an estimate of damage up to the time the core temperature reaches about 2300'F. At that point the rods are expected to have ruptured clad but little other structural degradation. More severe core damage cannot be quantified by this procedure.

Although this procedure yields a more inunediate assessment of core damage, accuracy is limited to relatively less severe accidents such as slow core uncovery by boiloff of the reactor coolant. For other more rapid uncovery scenarios this procedure could yield a very low estimate for the number of rustured rods. In general, for core (e uncovery at pressures below a mut 1200 psia there is high confidence that at least the predicted estimate of rods are actually ruptured.

II

I. PROCEDURE

Estimation of Core Damage Using CET Measurements

a. From the recordings of maximum core exit themocouple temperature and reactory coolant system pressure as a function of time, obtain and record the following data.

Maximum Core Exit Thermocouple Temperature F Time of Maximum Temperature ,

Pressurizer Pressure at Above Time psia

( FC/EPIP/01 ng l85UED iggy U ""

EPIP-TSC-8-0-2 II

I. PROCEDURE

(Continued)

b. Select the curve on Enclosure 2 which is labeled with a pressure approximately equal to or greater than the pressure recorded above.

Enter the abscissa at the maximum temperature from above and read on the ordinate the percent of the fuel rods which have ruptured clad and record below.

Percent of ruptured rods, f,

c. The result in step b is probably a lower limit estimate of damage.

Some judgement on the bias is available as follows.

A smooth core exit thermocouple recording and an uncovery duration of 20 minutes or longer will yield a good prediction of clad ruptures.

A large break is indicated when the pressure in step a drops below 100 psia in less than two minutes after accident initiation. This causes undetected core heatup followed by flashing during refill. Depending on the rate of refill, the 4

thennocouple temperature may rise rapidly then quench when the core is recovered. Under these conditions, this procedure could yield a very low estimate for the percent of rods ruptured.

4 If the pressure in step a is above about 1650 psia, it could exceed the rod internal gas pressure, depending on rod burnup, 4

and cause clad collapse onto the fuel pellet instead of outward 4

clad ballooning. The clad rupture criteria are less well defined for those conditions, but at temperatures above 1800*F where the a highest pressure curve applies in step b, clad failure sufficient to release fission gas is likely and this procedure may be used to obtain estimates of damage.

i

d. CORE DAMAGE ASSESSMENT Use the percent of rods ruptured from step c and the clad damage characteristics of Enclosure 1 to determine the NRC category of cladding failure. This procedure yields damage estimates in categories 2, 3 or 4.

NRC category of cladding failure from Enclosure 1 I

i i

I

{ Issure FC/EPIP/0? Pts 3 3 aft * .

R3 02-23-87 e

O ,

b b ,

~

l .

i 2 '

? y .. .

' Enclosure 1 .

7 E Clad Damnee Characteristics of IntC Cateeories of Fuel Damage Mechanism Characteristic Measurement Percent of IIIC Category Temperature E

'$ of Fuel Dessee Range (*F) of Damage Measurement Range Dammes Gods e.

• • Less Then 1  :

W I C Ilone

• • f Ils Fuel temage l

S 'o, . Less Then le

! Rupture Due to Maximum Core <1550*F*

Initial Cladding Exit ,

Gas Gap Failure Overpressurization Thermocouple <1700*F* 10 to 50 Intermediate >1200-1000 Temperature Cladding Failure h300*F Major Cladding D1 Greater Than 50 Failum - Guidation r

Loss of Structural Anount of Equivalent Core Less Than 10 Initial Fuel Pellet Integrity Due to Hydrogen Gas oxidation U 4

Overheating <35 Fuel Clad Produced (Equivalentto <!85 I Intermediate )1000-3350 0xidation 5 Outdation Fuel Pellet' ofCere) {

Overheating _

% 55 Greater Than 50 i Major Fuel Pellet Overheating u

$ {

q r 4 i

'B - r.

?y b bo ,

a i

Values Given for Pressure <!200 psia and Burnup 10 t

• Depends on lleactor Pressure and Fuel Burnup.

EPIP-TSC-8-0-4 , _!

ENCLOSLNE 2 -

PERCENT OF FUEL RODS WITH RUPTURED CLAD vs MAXINUM CORE EXIT THERMOCOUPLE 1EMPERATURE 1

l WHEN THE PRESSURE USE CURVE LABELED IN STEP a IS WITH TEMPERATURE -

< 100 PSIA 1200*F

< 1200 PSIA 1500*F

< 1680 PSIA 1000*F 100 Q

1200*F Q

$ CLAD RUPTURE g TEMPERATURE B

ga0 -

e B

1500*F E

g 1800*F lE y20 - -

0 1200 1400 1600 1000 2000 2200 MAXIMUM CORE EXIT THERMOCOUPLE TEMPERATURE ISSUED FLE s 3 nu FC/EPIP/02 -

R3 02-23-87

-:------------ -- . - . _ _ ; _s .2_ .__ _ .

EPIP-RR-72-1 Fort'Calhoun Station Unit No.1

• C,

• EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-RR-72 i

l Emergency Recovery Organization's Dose Assessment Specialist I. PURPOSE The purpose of this procedure is to detail assignment and responsibilities of personnel in the Emergency Recovery Organization filling the position of Dose Assessment Specialist.

II. PREREQUISITE Both primary and alternate individuals filling the position of Dose Assessment Specialist have been fully trained and are aware of their duties and responsibilities.

III. PRECAUTIONS None

( I

V. PROCEDURE

Upon activation of the Emergency Recovery Organization, those individuals assigned to the position of Dose Assessment Specialist shall carry out this assignment in Appendix 1 of this Implementing Procedure.

• \

ISSUED

{ FEB 261987 FC/EPIP/03 R3 02-26-87 i..... ..

EPIP,RR-72-2

Fort Calhoun Station Unit'No. 1 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP-RR-72 APPENDIX 1 TOSE ASSESSMENT SPECIALIST

~

A. Personnel Assianment ,

Primary (Job Title)

By Recovery Manager' Designation l

Alternate-(lob Title) .j By Recovery Managst Designatior. - -

7 B. Reportina Location Emergency Operations Facility i

C. Reports To: >

N-  ;

Dose Assessment Coordinator -

D. Supervises / Coordinates, ,

Offsite Monitor Teams t

. s E. Primary Responsibility 3, ,

Provide control and direction of offsite moniter CeJas, reco'?d cf,' site '

monitor team readings and locations and provWe continuous uptated '

information to the Ocse Assessment Coordinator. ' s S '

• F. Basic Duties: '

s

1. Upon notification ~of Emergency Recovery Organizatic.i activation,*de primary and/or alternate Oose Assessment Specialist designate (s wim -

report to their assigned location and inform the. Dose Assessment

• i ;

Coordinator of his/her presence. .

s

2. Be prepared to provide cound-the-clock .supprt. - 'i i

s \ -

3. Assume control of offsite. monitor teims from the monitor coordfrhtor '

when directed by the Oose A,ssessment Coordinator! ,

4. Maintain constant radio connu11 cation; .vith all offsite teams and monitor radio communications between onsite monitor teams, TSC and '

the FCS access Read Secvity Guard. l Iscuro , 3, FC/EPIP/03 R370244 -81 I

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n. _ _ _.  : . __ u_; -

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EPIP-RR-72-3 i ,

F. Basic Duties: (Continued) i 5. Coordinate with states to direct offsite monitor teams to specific j ,

monitor locations within the affected sectors.

6. Ensures off-site monitors are briefed on the plant condition and projected or known release information periodically when teams

! are in plume sectors.

7. 0ttain monitor team locations and survey results from state field

monitoring teams..

8. Record offsite monitor teams sample readings on FC-165 and pass g- s this infomation to the clerical assistant for distribution.

' ~

- 9 ' Record projected and measured dose rates on correlation sheet (attachment F-1, EPIP-E0F-6). Notify the Dose Assessment c Coordinator or the Emergency Coordinator of any discrepancies

'immediately, s

10. Maintain dosimetry log on each of the off site monitor team

. members.

J t; '

11. Record, on the large monitor locations map, monitor team location,

' survey results and time surveys were taken for each of the field t

monitoring teams (OPPD teams and state teams).

> [' 12. Contact the National Weather Service in Omaha 9-571-8351 and request

Q projected meteorological weather information necessary to make long l , term dose projections. Provides this infomation to the Dose y / C,, Assessment Operator and Dose Assessment Coordinator. ,

i

13. Assist the Dose Assessment Coordinator as needed.

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