ML20070T276

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures EPIP-OSC-8 Re Medical Assistance & EPIP-TSC-1 Re Activation of Technical Support Ctr

ML20070T276
Person / Time
Site:	Fort Calhoun
Issue date:	01/07/1983
From:	OMAHA PUBLIC POWER DISTRICT
To:
Shared Package
ML20070T264	List: ML20070T268 ML20070T276
References
PROC-830107-01, NUDOCS 8302080279
Download: ML20070T276 (23)

Text

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. VOLUME III OMAHA PUBLIC POWER DISTRICT - FORT CALHOUN STATION EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS

1. OPERATION SUPPORT CENTER Revision Last Review Procedure No. Title Date Date EPIP-OSC-1 Emergency Classification ~ R1 7-14-81 EPIP-05C-2 Emergency Plan Activation R5 7-09-82 7-09-82 EPIP-0SC-3 Notification of Unusual Event Actions R1 4-?3-82 4-23-82 EPIP-0SC-4 Alert Event Actions -R1 4-23-82 4-23-82 EPIP-0SC-5 Site Area Emergency Actions R1 1-14-82 1-14-82 EPIP-0SC-6 General Emergency Actions R1 1-14-82 1-14-82 EPIP-0SC-7 Personnel Rescue R1 8-24-82 8-24-82 EPIP-0SC-8 Medical Assistance R1 11-10-82 11-10-82 EPIP-0SC-9 Emergency Repairs, Corrective Actions and Damage Control R0 4-23-82 4-23-82 EPIP-0SC-10 Initial Assessment of Plant Parameters and Effluent Monitors j to Detemine Source Term R1 8-26-82 8-26-82 EPIP-0SC-11 Initial Dose Assessment Based on Plant Instrumentation R1 8-31-82 8-31-82 EPIP-0SC-12 Accidental Actuation of Early Warning Siren System R0 11-4-82

2. EMERGENCY OPERATION FACILITY Revision Last Review Procedure No. Title Date Date EPIP-EOF-1 Activation of Emergency Operation Facility R0 2-2-0-81 l

l '

8302080279 830202 9 PDRADOCK05000g 1-07-83

TABLE OF CONTENTS )

(Continued)

Revision Last Review Procedure No. Title Date Date EPIP-EOF-2 Emergency Operation Facility Communication R1 9-22-82 9-22-82 EPIP-E0F-3 Emergency Instrumants and Equipment R2 3-2-82 3-2-82 EPIP-EOF-4 Measurement of Airborne Radioactivity (Incorporated intoEPIP-E0F-6) R3 8-18-82 8-18-82 EPIP-EOF-5 Onsite Dose Assessment R3 8-18-82 8-18-82 (Incorporated into EPIP-E0F-6)

EPIP-E0F-6 Onsite/0ffSite Dose Assessment R3 8-18-82 8-18-82 EPIP-E0F-7 Protective Action Guidelines R1 4-23-82 4-23-82 EPIP-E0F-8 Environmental Monitoring R1 5-13-82 5-13-82 Personnel Accountability EPIP-EOF-9 R2 8-31-82 8-31-82 EPIP-E0F-10 Personnel Decontamination R2 11-01-82 11-01-82 EPIP-E0F-11 Dosimetry and Records R1 9-14-82 9-14-82 EPIP-EOF-12 Site Security R0 2-20-81 EPIP-E0F-13 Shift Supervisor /EDO to ED0 Transition RO 7-14-81 EPIP-E0F-14 EDO to Recovery Manager Transition R1 11-10-82 11-10-82

EPIP-E0F-15 Determination of Contamination Release Through Plant Stack R1 11-10-82 11-10-82 l EPIP-E0F-16 Continuing Dose Assessments Based On Plant Instrumentation R0 4-23-82 4-23-82

( EPIP-E0F-17 Initiation of Public Warning R0 1-14-82 1-14-82 l

Offsite Radiological Surveys EPIP-EOF-18 R2 5-04-82 5-04-82 11 1-07-83

b VOLUME III TABLE OF CONTENTS (Continued)

3. TECHNICAL SUPPORT CENTER Revision Last Review Procedure No. Title Date Date EPIP-TSC-1 Activation of Technical Support Center R2 11-10-82 11-10-82 EPIP-TSC-2 Technical Support Center Communication R1 9-22-82 9-22-82 EPIP-TSC-3 Plant and Reactor Operation Support - Alert Classification R1 11-04-82 11-04-82 EPIP-TSC-4 Plant and Reactor Operation Support - Site Area Emergency Classification R2 11-09-82 11-09-82 EPIP-TSC-5 Plant and Reactor Operation Support - General Emergency Classification R1 11-4-82 11-4-82 EPIP-TSC-S Plant Engineering and Repair R1 11-10-82 11-10-82 4

J iii 1-07-83

.. . ~ . - . - . . . .. - ...

VOLUME III TABLE OF CONTENTS (Continued)

]

4. RE-ENTRY AND REC 0VERY ORGANIZATION Revision Last Review Procedure No. Title Date Date EPIP-RR-1 Activation of Recovery Organization R2 4-30-82 4-30-82 EPIP-RR-2 Re-entry and Recovery Communication R0 2-20--81 EPIP-RR-3 Re-entry to Evacuated Area R0 2-20-81 EPIP-RR-4 Re-entry and Recovery On-Site NRC Coordination R0 2-20-81 EPIP-RR-5 Technical Specification Modifications R0 2-20-81 12-14-82 EPIP-RR-6 Population Exposure Projection R3 9-7-82 9-7-82 EPIP-RR-7 Recovery Decontamination R0 2-20-81 12-14-82 EPIP-RR-8 Waste Management R0 2-20-81 EPIP-RR-9 Re-entry and Recovery Equipment .

Procurement R0 2-20-81 EPIP-RR-10 Recovery Organization's Recovery Manager R1 4-23-82 4-23-82 EPIP-RR-11 Recovery Organization's Technical Support Manager R0 7-14-81 EPIP-RR-12 Recovery Organization's Licensing Administrator R0 7-14-81 EPIP-RR-13 Recovery Organization's Core Physics Coordinator . R0 7-14-81 1

EPIP-RR-14 Recovery Organization's Systems Analysis / Procedure

Support Coordinator R0 7-14-81 EPIP-RR-15 Recovery Organization's j Shift Support Coordinator R0 7-14-81 iv 1-07-83

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VOLUME III ,

TABLE OF CONTENTS i

[' (Continued) )

4. RE-ENTRY AND RECOVERY ORGANIZATION (Continued)

Revision . Last Review Procedure No. - Title Date Date EPIP-RR-16 Recovery Organization's Instrument and Control Support Coordinator RO 7-14-81 EPIP-RR-17 Recovery Organization's Security and Technical' Support Administrative Supervisor R1 8-31-82 8-31-82 EPIP-RR-18 Recovery Organization's Plant Operations Manager R0 7-14-81

, EPIP-RR-19 Recovery Organization's .

Shift Operations Supervisor RO 7-14-81 EPIP-RR-20 Recovery Organization's Instrument and Control Supervisor RO 7-14-81 EPIP-RR-21 Recovery Organization's Maintenance / Quality Control Supervi sor RO 7-14-81 ~.

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EPIP-RR-22 Recovery Organization's Health Physics / Chemistry Supervisor RO 7-14-81 EPIP-RR-23 Recovery Organization's Procedure / Training Supervisor RO 7-14-81 EPIP-RR-24 Recovery Organization's Emergency Coordinator RO 7-14-81 EPIP-RR-25 Recovery Organization's Dose Assessment Coordinator RO 7-14-81 EPIP-RR-26 Recovery Organization's Environmental Survey and Analysis Coordinator RO 7-14-81 EPIP-RR-27 Recovery Organization's Radiochemical Analysis Coordinator RO 7-14-81 b

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v 1-07-83

VOLUME I;;

TABLE OF CONTENTS (Continued)

.')

4. RE-ENTRY AND RECOVERY ORGANIZATION (Continued)

Revision Last Review Procedure No. Title Date Date EPIP-RR-28 Recovery Organization's Dosimetry Coordinator RO 7-14-81 EPIP-RR-29 Recovery Organization's Administrative Logistics Manager R0 7-14-81 EPIP-RR-30 Recovery Organization's Administrative Support Coordinator R0 7-14-81 EPIP-RR-31 Recovery Organization's Finance Coordinator R0 7-14-81 EPIP-RR-32 Recovery Organization's Accommodations Support Coordinator R0 7-14-81 EPIP-RR-33 Recovery Organization's Commissary Support Coordinator R0 7-14-81 EPIP-RR-34 Recovery Organization's Communications Support Coordinator R0 7-14-81 EPIP-RR-35 Recovery Organization's Human Resources Coordinator R0 7-14-81 EPIP-RR-36 Recovery Organization's Material Management Coordinator RO 7-14-81 EPIP-RR-37 Recovery Organization's Transportation Coordinator R0 7-14-81 EPIP-RR-38 Recovery Organization's Accounting Coordinator R0 7-14-81 EPIP-RR-39 Recovery Organization's Media Release Center Director R0 7-14-81 EPIP-RR-40 Recovery Organization's E0F Information Specialist R0 7-14-81 vi 1-07-83

VOLUME III I~ TABLE OF CONTENTS (Continued)

4. RE-ENTRY AND REC 0VERY ORGANIZATION (Continued)

. Revision last Review Procedure No. Title Date Date EPIP-RR-41 Recovery Organization's E0F Technical Liaison RO 7-14-81 EPIP-RR-42 Recovery Organization's ENC Information Specialist ' R0 7-14-81 EPIP-RR-43 Recovery Organization's ENC Technical Liaison RO 7-14-81 EPIP-RR-44 Recovery Organization's Public Information and Rumor Control Supervisor R0 7-14-81 l EPIP-RR-45 Recovery Organization's Clerical Supervisor R0 7-14-81

EPIP-RR-46 Recovery Organization's Internal Services Coordinator R0 7-14-81 EPIP-RR-47 Recovery Organization's Design and Construction Manager R0 7-14-81 EPIP-RR-48 Recovery Organization's Utility Engineering Director R0 7-14-81 EPIP-RR-49 Recovery Organization's Architect Engineering Director R0 7-14-81 EPIP-RR-50 Recovery Organization's Director of Nuclear Steam Supply System RO 7-14-81 EPIP-RR-51 Recovery Organization's Director of Construction R0 7-14-81 EPIP-RR-52 Recovery Organization's Construction Quality Ass

3ance Director R0 7-14-81 EPIP-RR-53 Recovery Organization's Manager of Waste Management R0 7-14-81 b..

vii 1-07-83

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s.. . _ . . _ . . . , . . - ~ ~ ~ - . _ _ , . _ . _ _ _ . _ .. _ _ . _

VOLUME III TABLE OF CONTENTS

)

(Continued) i

4. RE-ENTRY AND RECOVERY ORGANIZATION (Continued)

Revision Last Review

, Procedure No. Title Date Date EPIP-RR-54 Recovery Organization's Radwaste/ Technical Support Coordinator R0 7-14-81 EPIP-RR-55 Recovery Organization's Scheduling / Planning Manager R0 7-14-81 EPIP-RR-56 Recovery Organization's

Advisory Support Coordinator RO 7-14-81 EPIP-RR-57 Recovery Organization's Nuclear Fuel Supplier Representative RO 7-14-81 EPIP-RR-58 Recovery Organization's-Architect Engineering Representative (GibbsandHill) R0 7-14-81 EPIP-RR-59 Recovery Organization's

. Architect Engineering Representative RO 7-14-81 EPIP-RR-60 Recovery Organization's Radiological Assessment Representative R0 7-14-81 EPIP-RR-61 Recovery Organization's Site Representative RO 7-14-81 EPIP-RR-62 Recovery Organization's NRC and FEMA Representative R0 7-14-81

-e viii 1-07-83

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VOLUME III

,7 TABLE OF C'NTENTS (Continued)

G. PUBLIC INFORMATION

! Revision Last Review Procedure No. Title Date Date EPIP-PI-1 PUBLIC INFORMATION (Crisis Communication Plan) R2 9-14-82 9-14-82 a

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ix 1-07-83

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EPIP-OSC-8-1

(^. Fort Calhoun Station - Unit No. 1 Emergency Plan Implementing Procedure EPIP-0SC-8 MEDICAL ASSISTANCE Method for obtaining quick medical assistance, primarily transportation and treatment, for major person injuries at the Fort Calhoun Station.

I. PURPOSE

! This procedure provides the instruction to identify personal in-

. juries, procure emergency first aid and receive specialized medi-cal treatment.

! II. PREREQUISITE A. The injured person has been moved, if possible, from a radia-tion area or shielding installed to reduce radiation exposure.

B. The injured person has been decontaminated and protective clothing removed, if possible.

IV. PRECAUTION A. In case of severe injury, first aid and medical assistance takes precedence over contamination control.

B. The injured person should not be left unattended. A fellow employee should remain with the victim for first aid and encouragement until full treatment is provided.

• V PROCEDURE

1. Injuries sustained outside the radiation control areas shall

' receive medical assistance in accordance with Standing Order G-14, Personal Injuries.

2. Locate the injured person and ensure this information is available at the Control Room and Emergency Operation Facility.

3. Minor injuries should be treated at the Station First Aid

facilities. Follow up service and major injuries should be handled in accordance with the remainder of this procedure.

, R1 11-10-82 NOV 101982

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-7 EPIP-OSC-8-2 V. PROCEDURE (Continued)

-]

4. If a major radiological injury was received or it has not been determined that the person is contamination free, contact the Blair Rescue Squad (Telephone 911) for advanced first aid and emergency transportation. Emphasize that the injury occurred at the Fort Calhoun Power Station, 0.P.?.D.

5. Notify the University of Nebraska Medical Center, Radiation Treatment Facility (Telephone 559-5299) that a radiation acident i:as occurred at Fort Calhoun Station and the hos-pital will receive the injured person in approximately 45 minutes. Describe known radiological and medical informa-tion available.

6. Activate Emergency Team Members 2 and 3, if necessary, to perfonn re-entry and rescue activities. Operators and C/RP Technicians should be utilized if the Emergency Team has not reported. -

7. Activate Emergency Team Member 18 to perform Rescue Squad Monitor activites. An Operator or C/RP Technician should be utilized if the Emergency Team has not reported.

8. Ensure the location of the injured person is coordinated.

Monitor 18 and the Security Force should share this informa-tion.

9. Provide the UMMC with additional information after the Rescue Squad vehicle has deparud the site.

10. Provide notification and report to Production Operations Management threugh the Training and Safety Coordinator that an injury requiring hospital assistance has occurred.

l lSSUED R1 11-10-82 NOV 101982

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. t. O EPIP-E0F-14 FORT CALHOUN STATION UNIT N0. 1 Emergency Plan Implementing Procedure EPIP-E0F-14

(

EDO to Recovery Manager Transition I. PURPOSE This procedure provides the instruction to be followed by the ED0 and Recovery Manager regarding the EDO to Recovery Manager transition..

II. PREREQUISITE A. The emergency has been placed into one of the three higher emergency classifications requiring activation of the Recovery Organization.

NOTE: Alert classification does not necessitate full Recovery Organization activation. '

b Recovery Organization activation has been accomplished in accordance-with Implementing Procedure EPIP-RR-1.

III. __

PRECAUTIONS A. All significant events and actions shall be logged in the operations log book.

B. The Emergency Operations Facility has been detennined to be habit-able.

C. The transition may occur by telephone from two different emergency facilities. Ensure all communications are clear and understood.

(

IV. PROCEDURE A. The Recovery Manager shall review the following infonnation during the ED0 to Recovery Manager transition.

1. Current Plant Status:

Review primary system pressure and temperature status.

Review primary system chemistry parameters to determine the extent of core damage if any.

I Review operational status of all available heat sinks L that could be employed for the removal of decay heat.

! Review operational status of nuclear instrumentation i systems.

FC-41 g "@ - g;) R1 11-10-82 NOV 101982

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EPIP-E0F-14-2 IV. PROCEDURE (Continued)

Review any abnonnal situations involving plant systems and alignments. _'

Review the emergency operations log book i

2. Radiological Assessments Status:

Review current radiological release data, including meteorological data, activity release estimates and dose assessments.

l Review current on-site and off-site radiation, con-tamination and airborne surveys.

! Review the graphics of present emergency conditions i and projections on the status board.

l 3. Emergency Actions:

Review status of any in-plant evacuation measure that-may have been taken including an accountability of plant personnel and visitors.

l Review status of any contaminated and/or injured personnel that may have been transported to UfMC or Blair Memorial Hospital for treatment.

4. Notification and Recommendations: ,

i Detennine emergency notification status of outside emergency response organizations.

Review recommended protective actions that may have l been transmitted to local and state governments.

l

5. Status of Emergency Response Organizations:

Review activation statu's of the Emergency -Team and Technical Augn mtation Staff.

Detennine activation status of Operation Support Center.

Detennine activiation status of Technical Support Center.

Detennine that the activation status of the remainder of the Recovery Organization is progressing smoothly and that the Emergency Team and Technical Augmentation Staff are functioning within this organization.

FC-41 ISSLqu W

R1 11-10-82 NOV 101982

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EPIP-E0F-14-3 IV .' PROCEDURE (Continued) -

O B. 1. _ Following the review of this pertinent information the f' Recovery Manager will relieve the ED0 of emergency duties, responsibilities and authority.

2. The ED0 replaced by the Recovery Manager will assist the Recovery Manager as an ex-officio member of the Recovery Manager staff until re-assigned by the Recovery Manager.

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$2 R1 11-10-82 NOV 101982

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l

~ l EPIP-E0F-15-1 Fort Calhoun Station Unit No. 1 Energency Plan Implementing Procedure I EPIP-EOF-15 ,

1 Detemination of Contamination Release Through Plant Stack I. PURPOSE

)

To provide a relationship between the effluent radiation monitor readings and the amount of contamination on the ground and the resulting whole body gamma dose rates.

II. PREREQUISITES A. The Emergency Operations Facility has been activated per EPIP-EOF-1.

III. PRECAUTIONS NONE IV. PROCEDURE

1. Project the amount of contamination deposited on the ground at selected downwindlocation(s).

a. Obtain the wind direction at 10 meters from the control room and enter in Table E0F-15.1.

b. Detennine '.ne affected wind sector with, letter designation A to R, using .he wind direction data from Step l'.a above. (affected wind ser .or is the sector opposite to the wind direction sector).

Enter tr.e affected wind sector in Table E0F-15.1.

l c. Obtain the stack flow rate from the congrol room and enter in l Table E0F-15.1; convert this value to m3/sec and enter in Table E0F-15.1.

d. Determine the relative deposition factor (D/Q) for a selected downwind distance from Table EOF-15.2 and enter in Table E0F-15.1.

NOTE: If the selected downwind distance is between two of the listed distances, use the next SMALLER distance.

e. Determine the duration of a release from the stack and enter in -

Table E0F-15.1.

l f. Draw air samples on particulate filters from the stack via RM-060 and RM-061 air pumps.

r

g. Remove particulate filters and return to the laboratory for per-

\g formance of isotopic analysis of radionuclides listed in Table E0F-15.1 and enter the data in Column II of Table E0F-15.1.

NOV 10 p g R1 11-10-82 w

EPIP-E0F-15-2 .s

h. Calculate the radionuclides release rates by multiplying values s in Column II by the stack flow rate and enter the data in Column '

III of Table E0F-15.1.

1. Calculate the contamination deposition by multiplying the values in Column III by D/Q and the release duration; enter the data in Column IV of Table E0F-15.1.

2. Project Whole Body Gamma Dose Rates from radionuclide deposited on the ground.

a. Multip,1y the contamination deposition in Column IV by the dose conversion factor for each 'radionuclide from Column V and enter the data in Table E0F-15.1.

b. Sum the whole body dose rates values and Column VI and enter in Table E0F-15.1.

3. Refer to Table E0F-15.3 for protective action guidelines for accumulated l Whole Body doses received from the contamination deposited on ground.

4. Notify the Emergency Coordinator of the above evaluated results.

l 5. Reassess the situation and/or repeat Steps 1 through 3 as necessary.

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R1 11-10-82 NOV 101982

EPIP-E0F-15-3 ),

EN i

-C4 Q TABLE E0F-15.1 h Amount of Contamination on the Ground and Whole Body Gama Dose Rates O

1. Wind Direction at 10 meters from Control Room: Degrees at hrs.

2. Affected Wind Sector: (LetterdesignationAtoR)

3. Stack Flow Rate frori Control Room: cfm x 4.72 E-04 =

m3/Sec

4. Relative Deposition Factor (D/Q) from Table E0F-15.2: m-2 at miles .

5. Release Duration (Projected or actual): Sec I I II III IV V VI l Dose Whole Isotopic Analysis Release Rate Contamination Conversion Body Dose Radionuclide pCi/cc ) (C1/Sec) Deposition (C1/m2) Factor (mrem /hr)

Using Using (Column II x Stack (Column III x D/Q (mren-m2/ (Column IV x RM-060 RM-061 Flow Rate) xReleaseDuration) Hr-C1) Column V) i i i Mn-54 5.8E+03 l l l

^

i C0-60 l l l i

1.7E+04 l i

g

,l Sr-89 I l 5.6E-01 l a I i l I-131 l 2.8E+03 l l 1 l

s I-133 3.7E+03 l l l l

I-135 1.2E+04 l l I I Gs-134 I 1.2E+04 l 2  ! 1 l 1 Cs-137 I  : 4.2E+03

'h' i i l

I

,. Ba-140 l l 2.1E+03 i l

Rco La-140 i i i i

I 1.5E+04 i

.N l  !  !

Total Whole Dose Rate =

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EPIP-E0F-15-5 f~ Table E0F-15.3 Whole Body Dose Protective Action Guidelines Projected Dose to Population (Rem) Recommended Actions Comments

<1 No planned protective action. State Previously recommended may issue advisory to seek shelter actions may be re-await further instructions. Monitor considered or ter-environmental radiation levels. minated.

1 to <5 Seek shelter as a minimum. Consider If constraints evacuation. Evacuate unless con- exist, consider-straints make it impractical. ation should be Monitor environmental radiation given to evacua-levels. Control access. tion of pregnant women a children.

<5 Conduct mandatory evacuation. Seeking shelter Monitor environmental radiation would be an alter-levels and adjust area for manda- native if evacua-tory evacuation based on these tion were not levels. Control access. possible.

ISSED R1 11-10-82 NOV 101982

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l EPIP-TSC-1-1 l

( Fort Calhoun Station Unit No.1 Emergency Plan Implementing Procedure EPIP-TSC-1 ACTIVATION OF TECHNICAL SUPPORT CENTER Method for activation of the Technical Support Center (TSC) for emergency operations assistance during Alert, Site Area and General Emergency classes.

I. PURPOSE This procedure provides the instruction for the TSC Manager and his staff to initiate support to the reactor operating personnel in admini- -

strative, communication, and technical evaluation functions.

II. PREREQUISITES (

A. The emergency has been classified as Alert, Site or General (Pro-cedure EPIP-0SC-1) by the Shift Supervisor or Emergency Duty Officer.

B. Personnel assigned operational, mechanical, electrical and radio-logical emergency support have been adequately trained.

III. PRECAUTIONS A. Although activating the TSC is optional for ' Notification of Unusual Event' emergency classes, it is advisable that TSC members report to the plant when notified to share their expertise.

l B. The TSC is sized for 20 technical persons. The TSC Manager must limit off-site support to ensure optimum working space.

IV. PROCEDURE

1. Check and initiate operations of radiological equipment to ensure monitoring capability and continued habitability of TSC.

2. Establish communications with control room and emergency response facilities (EPIP-TSC-2).

3. Provide plant and reactor operation support in accordance with implementing procedures EPIP-TSC-3, 4, 5 and 6.

4. Relieve reactor operator of auxiliary duties and communications not directly related to reactor system manipulations.

5. Maintain emergency offsite support group coordination until activation of E0F has been confimed.

6. Review technical data displays and plant records available. (A Safety Parameter Display System will eventually standardize informa-tion for safety assessment.)

R2 11-10-82 NOV I O 1982 -

EPIP-TSC-1-2 IV. PROCEDURE (Continued) .s-

7. Provide detailed analysis and diagnosis of abnormal plant conditions to control room operations.

8. Evaluate any significant release of radioactivity from the plant.

9. Maintain open communication with the control room and EOF.

10. Establish a long term schedule for staffing the TSC and control room with additional manpower if the emergency class .fs increasing or a duration of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is anticipated.

ISSUED R2 11-10-82 NOV 10 EE2

l

EPIP-TSC-4-1 FORT CALHOUN STATION UNIT N0.1 Emergency Plan Implementing Procedure )

EPIP-TSC-4

^ TECHNICAL SUPPORT CE!!TER PLANT AND REACTOR OPERATION SUPPORT - SITE AREA EMERGENCY CLASSIFICATION I. PURPOSE This instruction provides general guidelines to Technical Support Center personnel as to the type of support / assistance that may be requested during an incident classified as a Site Area Emergency.

II. PREREQUISITES A. Emergency classification has been defined per EPIP-OSC-1.

B. Technical Support Cer/:er has been activated per EPIP-TSC-1.

III. PRECAUTIONS None I

V. PROCEDURE

1. Rendar support / assistance as requested by OSC.

Example: Monitor primary coolant temperature / pressure

instrumentation and maintain minimum of 50* subcooling for particular system pressure.

2. Establish contact with Region IV NRC, A-E, C-E. l

'SSUED 9 !!E2, R2 11-9-82 NOV

- ~~ ~

~ -

s

. EPIP-TSC-6-1

/

Fort Calhoun Station Unit No.1  :

Emergency Plan Implementing Procedure l EPIP-TSC-6 '

TECHNICAL SUPPORT CENTER PLANT ENGINEERING AND REPAIR I. PURPOSE This instruction provides general guidelines to the Technical Support Center personnel to perfona engineering work, and repair. supervision after any incident requiring activation of the TSC that caused equipment damage.

II. PREREQUISITES A. Emergency classification has been defined per EPIP-0SC-1 B. Technical Support Center has been activated per EPIP-TSC-1 C. The recovery organization has been activated per EPIP-RR-1 D. Incident emergency status has been terminated and repair operations are beginning.

III. PRECAUTIONS None IV. PROCEDURE

1. Evaluate extent of damage resulting from incident.

2. Propose repair schedules, based upon evaluation of Step 1, to expedite recovery and return, to power operation.

3. Implement repair schedules.

(

' ISSUED R1 11-10-82 NOV 101982

.