Text

Public Version of Revised Emergency Plan Implementing Procedures,Including Procedure F3-2 Re Classification of emergencies,F3-5 Re Emergency Notification & F3-9 Re Emergency Evacuation
	ML20073Q903
Person / Time
Site:	Prairie Island
Issue date:	03/22/1983
From:	Schullke D; NORTHERN STATES POWER CO.
To:	;
Shared Package
ML20073Q896	List: ML20073Q899; ML20073Q903;
References
	PROC-830322-01, NUDOCS 8305030226
	Download: ML20073Q903 (129)
	v • d • e

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PAGE 1 OF 2 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR PROCEDURES I l GENERATING PLANT ,

l l NORTHERN STATES POWER COMPANY Number: TABLE OF CONTENTS Rev: 18 l l History Copy l l -s , , Retention Time: Lifetime l

l. g l TITLE:

l Supt. Rad Protection l EMERGENCY PLAN l l l IMPLEMENTING PROCEDURES l l l TABLE OF CONTENTS l 1 l l l I I l l l

[ l l l NUMBER TITLE REV # l l

l l 1 Onsite Emergency Organization 2 l I

l l 2 Classifications of Emergencies 3 l l

l l 3 Responsibilities During a Notification of l l Unusual Event 2 l l

l l 4 Responsibilities During an Alert, Site Area, l l or General Emergency 7 l l

. l 5 Emergency Notifications 7 l 1

l l 6 Activation and Operation of Technical l l Support Center 2 l 1

l l 7 Activation and Operation of Operational l l Support Center 3 l l

l l 8 Recommendations for Offsite Protective l l Actions 1 l l

l l 9 Emergency Evacuation 2 l 1

l l 10 Personnel Accountability 3 l l

l l 11 Search and Rescue 1 l 1

l l 12 Emergency Exposure Control 2 l l l l 13 Offsite Dose Calculations 3 l l l l 14.1 Onsite Radiological Monitoring 2 l l 1 l 14.2 Operations Emergency Surveys 0 l 15 Responsibilities of the Radiation Survey l l Teams During a Radioactive Airborne Release 5 l 8305030226 030422 PDR ADOCK 05000282 I F PDR l 0 l IBM l

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Table of Contents .

Page 2 )

,, Rev. 18 NUMBER TITLE REV #

16 Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release 3 17 Core Damage Assessment 1 18 Thyroid Iodine Blocking Ageat (Potassium Iodide) 1

, 19 Personnel and Equipment Monitoring and Decontamination 0 20 Manual Determination of Radioactive Release Concentrations 2 21 Establishment of a Secondary Access Control Point 2 22 Prairie Island Radiation Protection Greup Response to a Monticello Emergency 2 -

j 23 Emergency Sampling 4 24 Record Keeping During an Emergency . 1 25 Re-Entry 2 26 DELETED 27 DELETED i

28 Review and Revision of Emergency Plans 0 l 29 Emergency Security Procedures 1 l

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af PAGE 1 OF 48 l l EMERGENCY PLAN IMPLEMENTING l l PRAIRIE ISLAND NUCLEAR PROCEDURES l l GENERATING PLANT l l NORTHERN STATES POWER COMPANY Number: F3-2 Rev: 3 l l History Copy l l , Retention Time: Lifetime l l -

l TITLE:

l Supt. J'ac Protection l CLASSIFICATIONS OF

' l Approved By: ( c, EMERGENCIES l l Plant'Hanager ,1 l l l l l l OC Date: 8 -M - 7/3 l l I i l l

l l 1.0 PURPOSE l

l l

l The purpose of this procedure is to specify the Emergency Action l l Levels that indicate that an emergency condition exists and to l l properly classify the emergency into one of the four graded levels of l l emergency classifications.

l l

l l 2.0 APPLICABILITY l 1

l l This instruction SHALL apply to all Shift Supervisors, Control Room l l Operators, Shift Technical Advisors and Emergency Directors. l l

l l 3.0 PRECAUTIONS l

l 1

l 3.1 The operator should believe his indications and take action l l based on those indications, however, he shall attempt to l l verify his indications by checking secondary or coincident l l indicators. l l

l l 3.2 Continuously monitor the control room instrumentation, radia- l l tion monitors, or any other developments which wculd be l l indicative of further system degradation. Be prepared to l l escalate to a more severe emergency classification. l I

l l l l

l 4.0 DISCUSSION l i I l

l 4.1 Definitions l l 1 l 4.1.1 Notification of Unusual Event - events that are in l l progress or have occurred which indicate a potential l l degradation of the level of safety of the plant. l l l l 1 l No releases of radioactive material requiring offsite l l response or monitoring are expected unless further l l degradation of safety systems occurs. l l l

, l 1 l l 1 l l l IBM .I l

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F3-2 Rcv. 3' ,

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4.1.2 Alert - events are in progress or have 3'

occurred which involve actual or potential substantial degradation of the level of safety of the plant. It is the lowest level of emergency classification when some necessity for emergency planning and offsite response is necessary.

Any releases expected are limited to small fractions of the EPA Protective Action Guideline exposure levels.

4.1.3 Site Emer2ency - events are in progress or have occurred which involve actual or likely major failure of plant functions needed for protection of the public.

Any releases are not expected to exceed the EPA Protective Action Guideline exposure levels except near the site boundary.

4.1.4 General Emergency - events sre in

, progress or have occurred which involve actual or imminent substantial core degradation or melting with a potential )

for loss of containment integrity.

Releases during a General Emergency can be reasonably expected to exceed the EPA Protective Action Guideline exposure levels offsite for more than the immedi-ate site area.

4.1.5 Emergency Action Levels (EAL) - specific instrument readings, surface or airborne contamination levels or radiation dose rates that designate a specific emergency class requiring emergency measures for that class.

4.2 Summary Attached to this procedure is a Summary of Emerg'ency Action Levels. This table identifies '

the four emergency classifications, the initiating I

conditions (s), emergency actions levels for each classification, and, where applicable, specific instruments and indications to be used 1

to detect and classify an emergency.

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F3-2 Rev. 3 Page 3 The emergency action levels for each classification and the instrument readings and indications listed do not reflect a complete list of instrumentation that will show abnormal indications but does list those key parameters useful in classifying the event.

The Summary of Emergency Action levels lists the initiating conditions as required by Appendix 1 of NUREG-0654 and accidents analyzed in the Prairie Island FSAR.

5.0 PROCEDURE 5.1 Any significant event that may be classified as an emergency condition shall be reported to the Shift Supervisor immediately.

I I l NOTE: The events may be instrumentation l l readings or visual observations made l l by plant personnel. 1 I I 5.2 Attempt to verify the initial indication by comparing the indication to redundant instrument channels or to other related parameters, visual observations, and field reports as applicable.

5.3 Assess the situation and determine the emergency classification, using the guidelines of Attachment 1.

I I l NOTE: Personnel should become familiar with l l Attachment I during training sessions. l I 1 5.4 Take immediate actions, using applicable plant operating procedures, Sections C and E of the Operations Manual, l to return the plant to normal (or cold shutdown, if

determined to be necessary).

l 5.5 Declare the appropriate emergency classification and perform actions as specified in the appropriate responsibility procedure applicable to emergency classification:

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5.5.1 For a Notification of Unusual Event, proceed to F3-3 l 5.5.2 For an Alert, Site or General Emergency,

! proceed to F3-4.

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F3-2 Rav. 3

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5.6 Continue to assess and respond to the emergency '

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condition.

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l NOTE: Watch for changing parameters or l l visual indication of further system l l degradation and be prepared to es- l l calate to a naore severe emergency (

l classification as indicated by the l l Emergency Action Levels in Attach- l l ment 1. l l

1 5.7 As plant conditions stabilize, downgrade or terminate the emergency classification, as appropriate, as per the guidelines of Attach-ment 1.

l l

l NOTE: Depending upon the severity of the l l accident, it may not be possible to l l downgrade the emergency classification l l following the guidelines of Attach- l s l ment 1. Therefore, once the plant ( )

l is in a stable mode and long-term l l cooling has commenced, the emergency l l condition may be reclassified and/or l l terminated and long-term recovery l l initiated. The Emergency Director l l should consult the Emergency Manager l l prior to reclassification and/or l l termination and initiation of the l l long-term recovery. l l

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4 4 F3-2 Rev. 3 Page 5 Attachment 1

SUMMARY

OF EMERGENCY ACTION LEVELS I

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F3-2 Rev. 3 Page 6 ATTACHMENT 1 INITIATING CONDITION INDEX )

No. Condition Description Page 1 Safety System Functions 7 2 Abnormal Primary Leak Rate 10 3 Abnormal Coolant Temperature / Pressure 13 4 Abnormal Primary / Secondary Leak 14 5 Core Fuel Damage 16 6 Loss of 2 of 3 Fission Product Barriers 17 7 Secondary Coolant Anaomaly 24 8 Radiological Effluents 27 9 Major Electrical Failures 30 10 Control Room Evacuations 33 11 Fires 34 ,

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12 Plant Shutdown Functions 35 13 Fuel Handling Accidents 38 14 Coolant Pump 40 15 Serious or Fatal Injury 41 16 Security Threats 42 17 Hazards to Plant Operations 43 18 Natural Events 46 19 Other 48 IBM

F3-2 Rev. 3 Page 7

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Attachment 1 CONDITION #1 SAFETY SYSTEM FUNCTIONS Initiating Condition Indication Used Classification ECCS initiated and dis- 1. First out on reactor trip panel: Alert charge to vessel. a. Containment High Pressure NOTE: FSAR Sections SI-Reactor Trip; or 14.2.4 b. A Steam Generator Lo-Lo 14.2.5 Pressure SI; or 14.2.6 c. B Steam Generator Lo-Lo 14.3 Pressure SI; or

d. Pressurizer Lo Pressure SI and_

2. Confirmation'from indicators:

a. 2/3 High Containment Pressure (4psig) PI-945, PI-947, PI-949; or

b. 2/3 Lo Steam Line Press. Loop A (500 psig) PI-468, PI-469, PI-482A; or

c. 2/3 Lo Steam Line Press. Loop B (500 psig) PI-478, PI-479, PI-483A; or

d. Lo Prz. Press (1815 psig)

PI-429, PI-430, PI-431

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3. Confirmation of SI Flow indicated by FI-925 and FI-924.

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4. Manual SI-Reactor Trip initiated if r Auto SI did not occur at confirmed f indicator setpoints (#2 above) or when pressurizer level is off scale low on at least 2/3 channels, LI-426, LI-427, LI-428.

l Loss of Containment Loss of Containment Integrity, defined Notification of i integrity requiring by Technical Specification 3.8, Unusual Event shutdown by technical which requires a unit shutdown, specification as determined by the Shift Supervisor.

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F3-2 .

Rev. 3 Page 8 Attachment 1

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CONDITION #1 (Cont'd)

SAFETv SYSTEM FUNCTIONS Initiating Condition Indication Used Classification Loss of engineered safety Engineered Safety Feature found Notification of feature requiring shutdown inoperable, as defined by Unusual Event by Technical Specification Technical Specification 3.3, which requires a unit shutdown, as determined by the Shift Supervisor.

oss of fire protection Loss of fire protection systems, Notification of system function requiring defined by Technical Specification Unusual Event shutdown by Technical 3.14, which requires a unit shutdown, Specification as determined by the Shift Supervisor.

Failure of a cafety or Pressurizer safety or relief valve Notification of relief valve in a safety opens and then fails to reset, as Unusual Event related system to close indicated by:

following reduction of w applicable pressure. 1. (a) Annunciator " Pressurizer )

Safety / Relief Valve Flow"; and (b) Annunciators; (1) " Pressurizer Pown.r Relief line High Temp; or (2) " Pressurizer Safety Valve l line A or B High Temp" t

l o_r, (c) Safety / Relief line high Tenper-ature indicated by s

l (1) Pressurizer safety valve outlet temperature, TI-436 >

225 F; or (2) Pressurizer safety valve outlet temperature, TI-437 >

225*F; or l (3) Pressurizer relief valve outlet temperature, TI-438 >

225*F.

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Attachment 1 CONDITION #1 (Cont'd)

SAFETY SYSTEM FUNCTIONS Initiating Condition Indication Used Classification Steam Generator safety or relief valve Notification of opens and then fails to reset, as Unusual Event indicated by:

1. Visual and/or audible ind'ication at vent stacks of open steam ,

generator safety or relief valve; and

2. As determined by Shift Supervisor IBM i

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& e F3-2 Rev. 3 Page 10 Attachment 1 ~

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CONDITION #2 ABNORMAL PRIMARY LEAK RATE Initiatina Condition Indication Used Classification Primary system leak rate 1. Primary system leak rate, other Notification of from unidentified or uncon- than controlled leakage cources, Unusual Event trolled sources exceeding exceeds Technical Specification Technical Specifications 3.1.c; and

2. Requires a unit shutdown, as determined by the Shift Supervisor.

Primary coolant leak rate 1. (a) Decreasing pressurizer level, Alert greater than 50 gpa as indicated by LI-426, LI-427, LI-428; or (b) High radiation levels in cont..n-ment, as indicated by:

R2 High Alarm - 50mR/hr; or s R7 High Alarm - 50mR/hr; or ;)

R-11 (Containment Positiog)

High Alarm - 5 x 10 eps, or R-12 (Containment Positiog)

High Alarm - 6 x 10 cpo; and

2. Annunciator " Charging Pump in Auto High/ Low Speed"; and

3. Charging line flow (FI-128B)

' greater than 50 gpm more than Letdown Flow (FI-134).

l l NOTE: Rapid Temperature decreasel l in RCS results in same l l indications however no l l primary coolant leak rate. l l l IBM 4 e - n - - - + , - - - - -

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. r F3-2 Rev. 3 Page 11 Attachment 1 CONDITION #2 (Cont'd)

ABNORMAL PRIMARY LEAK RATE Initiating Condition Indication Used Classification Loss of coolant accident 1. No Pressurizer Level indicated Site Area Emergency with leak rate in excess of by'LI-426, LI-427, LI-428 available pump capacity (Charging, High Head In- and jection, and Low Head In-jection). 2. All available pumps running as indicated by the red light at the switch.

Small LOCA and initially 1. LOCA has occurred; and General Emergency successful ECCS. Subsequent failure of containment heat 2. Inadequate containment cooling removal systems over several exists, as indicated by:

hours could lead to core melt and likely failure of (a) Containment temperature has containment, become excessive, ) 300*F, and is still rising; or (b) Containment pressure > 23 psig with minimum containment pressure suppres-sion equipment not available:

(1) No fan cooler units operating and less than two spray pumps; EE (2) No spray pumps operating and less than four fan cooler units; EE (3) Less than two fan cooler units running with one spray pump.

Small and large LOCI"s 1. Loss of coolant indicated by: General Emergency with failure of ECCS to perform leading to (a) (1) Pressurizer low pressure severe core degradation trip (1900 psig); or i or melt in from minutes RCS pressure decreasing l to hours. Ultimate failure uccontrollably; of containment likely for melt sequences. and

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t a F3-2 Rev. 3 Page 12

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Attachment 1 j CONDITION #2 (Cont'd)

ABNORMAL PRIMARY LEAK RATE Initiating Condition Indication Used Classification (2) High containment pressure; or High containment humidity; or High containment sump levels; or High containment radiation levels and (3) Steam Generator's A and B pressures equal EE (b) (1) Decreasing RCS pressure; and (2) Loss of subcooling margin

((10 F) and -

2. Fuel Damage indicated by:

a. R48 High Alarm - 200 R/hr; or R49 High Alarm - 200 R/hr EE

b. High RCS activity, ) 300 pCi/cc iodine equivalent, as determined by sample anaylsis and

3. Loss of ECCS indicated by (a) High head SI failure; or (b) Low head SI failure.

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F3-2 Rev. 3 j Page 13 Attachment 1 i CONDITION #3 ABNORMAL COOLANT TEMPERATURE / PRESSURE Initiating Condition Indication Used Classification Abnormal coolant tempera- At Steady State Power Operations; Notification of ture and/or pressure or Unusual Event abnormal fuel temperatures 1. T avg > 564 F; or-outside of Technical

, Specification limits. 2. RCS. pressure > 2385 psig; g

3. RCS pressure ( 2205 psig, and core exit temperature > 620*F, as indicated by a valid thermocouple; E

4. Core Subcooling Margin ( 10 F.

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F3-2 Rev. 3 Page 14 Attachment 1

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CONDITION #4 ABNORMAL PRIMARY / SECONDARY LEAK Initiating Condition Indication Used Classification Primary / Secondary leak When shutdown commences, as deter- Notification of' rate exeeding Technical mined by the Shift Supervisor Unusual Event Specification of 1.0 gpm and Duty Engineer requiring a unit shutdown Failure of steam generator 1. First out on reactor trip panel: Alert tubels) resulting in " Pressurizer Low Press SI" ECCS initiation and

2. Confirmation from Prz. Press indi-cators, PI-429, PI-420, PI-431, (2/3 Low pressure, 1815 psig).

and

' 3. Annunciators:

a. "A SG High Water Level" )

or

b. "B SG High Water Level" and

4. Confirmation from SG level indi-cators:

a. LI-461, LI-462, LI-463 (2/3 greater than 67%)

or

b. LI-471, LI-472, LI-473 (2/3 greater than 67%)

5. Safety injection flow indicated by FI-925 and FI-924 and pump discharge pressure corresponding to flow Failure of steam generator 1. First out on reactor trip panel: Site Area Emergency tube (s) resulting in ECCS " Pressurizer low pressure SI" initiation and loss of offsite power and IBM

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F3-2 Rev. 3 Page 15 Attachment 1 CONDITION #4 (Cont'd)

ABNORMAL PRIMARY / SECONDARY LEAK Initiating Condition Indication Used Classification

2. Confirmation from Prz. Press indicators: PI-429, PI-430, PI-431 (2/3 low pressure, 1815 psig) and

3. Annunciators:

a. "A SG Water Level High" or

b. "B SG Water Level High" and

4. Confirmation from SG level indi-cators:

a. LI-461, LI-462, LI-463 (2/3 greater than 67%)

or

b. LI-471, LI-472, LI-473 (2/3 greater than 67%)

and

5. Safety injection flow indicated by FI-626 and FI-928 ang

6. All of the following indicators:

a. 4.16 KV bus voltage (0 Volts)

Buses 11-14 and 21-24 and

b. D1 and D2 generators running and closed in on safeguard buses:

(1) D1 & D2 Tach, (* 900 rpm)

(2) D1 & D2 Volts, (4260-4380 Volts)

(3) Safeguard breakers closed Bus 15, Breaker 15-2 Bus 26, Breaker 26-2 Bus 16, Breaker 25-6 Bus 25, Breaker 16-/

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F3-2 Rev. 3 Page 16 Attachment 1

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CORE FUEL DAMAGE Initiating Condition Indication Used Classification Fuel Damage Indication 1. Hi Alarm on letdown line radiation monitor, R-9, indicating greater Notification of than 1 R/hr and confirmed by Unusual Event portable instrumentation ST

2. High coolant activity s...,ple:

a. exceeding Technical Specifi-

cation for total specific activity in primary coolant or

b. exceeding Technical Specifi-cation limit on primary coolant iodine activity which requires a unit shutdown.

Severe loss of fuel 1. Very high coolant activity sample; Alert cladding n3 300 pCi/cc iodine equivalent, as /

determined by chemical analysis !

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2. Letdown line radiation monitor R-9 in alarm mode and indicating greater than 10 R/hr, as con- '

firmed by portable instrumentation Degraded core with 1. Degraded core, indicated by:

possible loss of Site Area Emergency coolable geometry (a) High primary coolant activity,

) 300 pCi/ce; or (b) High core exit temperature, ,

indicated by exit thermocouples,

) 700'F; or (c) Inadequate subcooling margin,

( 10 F; or (d) IndicatioE of core uncovered (Shift Supervisor's opinion) and

2. Loss of coolable geometry, indicated by:

(a) Core AT increasing; or :

(b) No core AT; or (c) Shift Supervisor's opinion IBM l

F3-2 Rev. 3 Page 17 m Attachment 1 CONDITION #6 LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Initiating Condition Loss of 2 of 3 fission Three permutations exist for loss of product barriers with a 2 of 3 fission product barriers with potential loss of 3rd a potential loss of 3rd barrier; barrier (e.g., loss of 1. Failure of cladding and primary primary coolant boundary coolant boundary with potential clad failure, and high loss of containment.

potential for loss of 2. Failure of cladding and containment containment). with potential loss of primary toolant boundary.

3. Failure of containment and primary coolant boundary with potential loss of cladding.

These 3 permutations are represented in the following 5 cases, each with its own set of EAL's:

, Indication Used Classification CASE 1: Loss of clad, 1. LOSS OF CLAD & LOCA, INDICATED General Emergency loss of primary coolant EY:

boundary (LOCA), and high A.(1)(a) Very high coolant activity potential for loss of sample; 300 pCi/cc iodine containment equivalent, as determined by chemical analysis EE (b) Letdown line radiation monitor R-9 in alarm mode and indicating greater than 10 R/hr, as con-firmed by portable instrumentation and (2)(a) Pressurizer low pressure trip (1900 psig); or RCS pressure decreasing uncontrollably; and (b) High containment pressure; or High containment humidity; or High containment sump levels; or High containment radiation levels IBM

F3-2 Rev. 3 Page 18 Attachment 1 CONDITION #6 (Cont'd)

LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification and (c) Steam Generator's A and B pressures equal EE B. Valid high radiation levels in containment, as indicated by:

(a) R-48 High Alarm - 200 R/hr; or (b) R-49 High Alarm - 200 R/hr; and

2. POTENTIAL FOR LOSS OF CONTAINMENT, INDICATED BY:

A. Containment pressure approaching design pressure (46 psig) and increasing. ')

EE B. Loss of containment cooling capability indicated by minimum containment pressure suppression equipment not available:

(1) No fan cooler units operating and less than two spray pumps EE (2) No spray pumps operating and less than four fan cooler units EE (3) Less than two fan cooler units running with one spray pump EE C. Control Room status lights indicate both Train A and Train B Containment Isolation valves not closed for any containment penetration and Shift Supervisor's opinion.

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F3-2 Rev. 3 Page 19

,. Attachment 1 CONDITION #6 (Cont'd)

LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification CASE 2: Loss of clad, 1. LOSS OF CLAD, AND LOSS OF PRIMARY General Emergency loss of primary coolant COOLANT BOUNDARY (SG TUBE RUPTURE),

boundary (SG tube rupture), INDICATED BY:

and high potential for loss of containacut. A.(1) Loss of clad (a) Very high coolant activity sample; 300 pCi/cc iodine equivalent, as determined by chemical analysis EE (b) Letdown line radiation monitor R-9 in alarm mode and indicating greater than 10 R/tr, as con-firmed by portable instrumentation and (2) SG Tube Rupture (a) First out on reactor trip panel:

"Pretsurizer Low Press SI" and (b) Confirmation from Prz. Press indi-cators, PI-429, PI-420, PI-431, (2/3 Low pressure, 1815 psig) and t

l (c) Annunciators:

l "A SG High Water Level" j or i "B SG High Water Level" and (d) Confirmation from SG level.indi-cators:

LI-461, LI-462, LI-463 (2/3 greater than 67%)

! and (e) Safety injection flow indicated by FI-925 and FI-924 and pamp l

discharge pressure corresponding to flow-IBM l

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F3-2 Rev. 3 Page 20 Attachment 1

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CONDITION #6 (Cont'd)

LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS -

Indication Used Classification or B. Steam Line Monitor in valid high .

alarm mode: .

R-51, > 100 mR/hr; or {

R-52, > 100 mR/hr ;

and *

2. POTENTIAL FOR LOSS OF CONTAINMENT, INDICATED BY: -

A. Steam Generator safety or relief valve opens and then fails to reset, as

indicated by: .

(1) Visual and/or audible indication at vent stacks of open steam generator safety or relief valve; and s (2) As determined by Shift Supervisor EE B. Imminent failure of MSIV, as determined by Shift Supervisor CASE 3: Loss of clad, 1. LOSS OF CLAD, INDICATED BY: General emergency containment failure, and a high potential for loss A. Very high coolant activity sample; of the RCS boundary. 300 pCi/cc iodine equivalent, as determined by chemical analysis EE B. Letdown line radiation monitor R-9 in alarm mode and indicating greater than 10 R/hr, as con-firmed by portable instrumentation and

2. LOSS OF CONTAINMENT, INDICATED BY:

A. Control Room status lights indicate ,

both Train A and Train B Containment Isolation valves not closed for any containment penetration and Shift Supervisor's opinion.

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F3-2 Rev. 3

, Page 21 Attachment 1 CONDITION #6 (Cont'd)

LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification 2E B. Steam line break downstream of MISV, and open-close indicator shows MSIV not closed.

EE <

C. Steam line break between containment and the MSIV.

and

3. POTENTIAL FOR LOSS OF THE RCS BOUNDARY, INDICATED BY:

A. Loss of ECCS indicated by a loss of High head SI capability.

CASE 4: Loss of RCS 1. LOSS OF RCS BOUNDARY (LOCA), General Emergency boundary (LOCA), loss of INDICATED BY:

containment, and high potential for loss of A. Pretsurizer low pressure trip cladding. (1900 psig); or RCS pressure decreasing uncontrollably; l and

. B. High containment pressure; or High containment humidity; or High containment sump levels; or High containment radiation levels and C. Steac Generator's A and B pressures equal and

2. LOSS OF CONTAINMENT, INDICATED BY:'

A. Control Poom status lights indicate both Train A and Train B Containment Isolation valves not closed for any containment penetration.

and B. Shift Supervisor's Opinion l

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6 s F3-2 Rev. 3 Page 22 Attachment 1

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CONDITION #6 (Cont'd)

LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification and

3. POTENTIAL FOR LOSS OF CLADDING, INDICATED BY:

A. Reactor vessel level low and decreasing (Shift Supervisor's

opinion)

EE B. Core exit thermocouples > 700'F and increasing

.9I C. Loss of ECCS indicated by a loss of High head SI capability.

CASE Si Loss of RCS 1. LOSS OF RCS BOUNDARY (SG TUBE General Emergency 3 boundary (SG Tube Rupture), RUPTURE) INDICATED BY: !

loss of containment, and high potential for loss of A. First out on reactor trip panel:

cladding. " Pressurizer Low Press SI" and B. Confirmation from Prz. Press indicators, PI-429, PI-420, PI-431, (2/3 Low pressure, 1815 psig).

and C. Annunciators. I

, "A SG High Water Level" or "B SG High Water Level" and D. Confinnation from SG 1evel indicators:

(1) LI-461, LI-462, LI-463 (2/3 greater than 67%)

or (2) LI-471, LI-472, LI-473 1

(2/3 greater than 67%)

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F3-2 Rev. 3 Page 23 Attachment 1 CONDITION #6 (Cunt'd)

LOSS OF 2 0F 3 FISSION PRODUCT BARRIERS Indication Used Classification a,gg E. Safety injection flow indicated by FI-925 and FI-924 and pump discharge pressure corresponding to flow.

a,gg F. High Radiation on Condenser Air Ejector and/or Steam Generator Blowdown radiation monitors, and

2. LOSS OF CONTAINMENT, INDICATED BY:

A. Steam line break downstream of MSIV, and open-close indicator shows MSIV not closed.

EE B. Steam line break between containment and the MSIV.

and 3'. POTENTIAL FOR IOSS OF CLADDING, INDICATED BY: 1 i

A. Reactor vessel level low and decreasing (Shift Supervisor's opinion).

EE B. Core exit thermoccuples > 700*F and increasing.

EE C. Loss of ECCS indicated by a loss of High head SI capability.

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9 F3-2 Rev. 3 Page 24 Attachment 1

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CONDITION #7 SECONDARY COOLANT ANOMALY Initiating Condition Indication Used Classification Rcpid depressur'zation i of 1. (a) Steam General A/B Pressure Notification of Secondary Side Differential, > 100 psig; and Unusual Event (b) High Containment Pressure, 4 psig; EE 6

2.(a) Hi Steam Flow, .745 x 10 lb/hr; and (b) Lo-Lo T,y ,540*F EE

3. Steam line pressure Safety Injection Signal; EE N

4. Failed Open Steam Dump, Relief, j or Safety Valve; HI

5. Shift Supervisors Opinion l

Rapid depressurization 1. First out on reactor trip panel: Alert of secondary side (any a. "A Steam Generator Lo-Lo Steam Line Break with pressure SI" 0-50 gpm primary to or secondary leak rate) b. "B Steam Generator Lo-Lo Note: FSAR 14.2.5 Pressure SI" -

and

2. Confirmation from Steam Generator pressure indicators:

a. PI-468, PI-469, PI-482 (2/3 less than 500 psig), ,

or

b. PI-478, PI-479, PI-483 (2/3 less than 500 psig)

IBM

. r F3-2 Rev. 3 Page 25 Attachment 1 CONDITION #7 (Cont'd)

SECOMDARY COOLANT ANOMALY Initiating Condition Indication Used Classification and, if primary to secondary leak rate is occurring:

3. Hi radiation on:

a. R-15 Air Ejector Rad Monitor inalarmmogereadinggreater than 5 x 10 cpm; and

4. Leak rate as calculated Steam line break with 1. First out on reactor trip panel: Site Area Emergency greater than 50 gpm pri- a. "A Steam Generator Lo-Lo mary to secondary Pressure SI" leakage and indication b. "B Steam Generator Lo-Lo of fuel damage Pressure SI" and

2. Confirmation from Steam Generator pressure indicators:

a. PI-468, PI-469, PI-482 (2/3 less than 500 psig),

or

b. PT-478, PI-479, PI-483, (2/3 l

i less than 500 psig) l and 1

3. Primary to secondary leakage t

indicated by:

a. R-15 Air Ejector Rad Monitor, in alarm m de reading l

> 5 x 104cpm; and

b. leak rate calculation > 50 gpm;

, and l

4. Indication of fuel damage:

a. Primary sample > 300 pCi/cc Iodine 131 equivalent; or

b. Steam Line Monitor in valid high alarm mode:

R-51, > 100 mR/hr; or R-52, > 100 mR/hr.

IBM l

l

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F3-2 Rev. 3

. . Page 26 Attachment 1

]

CONDITION #7 (Cont'd)

SECONDARY COOLANT ANOMALY Initiating Condition . Indication Used Classification or

c. High Containment Radiation levels indicated by:

R48 High Alarm - 200 R/hr; or R49 High Alarm - 200 R/hr; Transient initiated by 1. a. Loss of main condenser which General Emergency loss of feedwater and includes all Condensate and condensate systems Main Feed Pumps; and (principal heat removal b. Loss of all Aux Feedwater; and system) followed by c. No High Head Safety Injection failure of emergency feedwater system for or extended period. Core melting possible in 2. a. Successful High Head Safety several hours. Ultimate injection with failure of containment (1) Less of main condenser which ,

3 likely if core melts. includes all Condensate and .)

Main Feed Pumps; and_

(2) Loss of all Aux Feedwater and

b. Either of the following not established within 30 minutes:

(1) Aux Feedwater; or (2) Normal RHR Cooling IBM

F3-2 Rev. 3

, Page 27 Attachment 1 CONDITION #8 RADIOLOGICAL EFFLUENTS 4

Initiating Condition Indication Used Classification l'

Airborne Radiological Any of the following gaseous effluent Notification of effluent Technical monitors in valid alarm mode reading Unusual Event Specification limits greater than:

exceeded

1. IR-22 (5 x 103 cp,)

Note: FSAR Section 14.2.2 2. 2R-22 (5 x 10 cpm)

Due to relehse rate of radioactive gases (except halogen and particulates with T 1/2 > 8 days) averaged over 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months exceed I (kfg) = 1.1 x 105 ,3/sec d

per Technical Specification 3.9.B.I.b Liquid Radiological Any of the following valid liquid Notification of

, effluent Technical effluent monitor readings which Unusual Event Specification limits exceed:

exceeded (1) R-18 High alarm setpoint and Note: FSAR Section isolation valve fails to

{ 14.2.2 close.

(2) R-19 High alarm setpoint (while blowdown is directed to river) and isolation

valve fails to close.

Due to release rate of radioactive liquids exceeding values listed in 10CFR20, Appendix B, Table II, Column 2, per Technical Specifica-tion 3.9.A.1.b.

Airborne Radiological Any of the following valid gaseous Alert effluents greater than effluent monitor readings:

ten times Technical Specification instantan- 1. IR-22 Hi-Hi Alarm (> 5 x 1044cpm) cous limits (an instan- 2. 2R-22 Hi-Hi Alarm (> 5 x 10 cpa) taneous rate which, if 3. IR-50 Greater Than 1.2 mR/hr continued for over two 4. 2R-50 Greater Than 1.2 mR/hr hours, would result in about I mR at the site Due to release rate'of gases exceeding ,

boundary under average Technical Specification 3.9.B.I.b by meterological conditions) a factor of 10.

4 IBM

F3-2 Rev. 3

, Page 28 CONDITION #8 (Cont'd) '

RADIOLOGICAL EFFLUENTS Initiating Condition Indication Used Classification Airborne Effluent 1. Any of 'the following valid gaseous Site Area Emergency monitors detect' levels effluent monitor readings:

corresponding to greater than: (a) 1R-50 Hi Alarm (70 mR/hr)

1. 50 mR/hr whole body (b) 2R-50 Hi Alarm (70 mR/hr) for onc-half hour or

2. 250 mR/hr for one-half or hour for the thyroid, or

3. 500 mR/hr whole body 2. Offsite dose projection calculations for two minutes, or result in the following dose projec-

4. 2500 mR/hr to the tions at the site boundary, ' greater thyroid for two minutes than:

at the site boundary for adverse meterology (a) 50 mR/hr whole body for 1/2 hour; or (b) 550 mR/hr thyroid for 1/2 hour; or (c) 500 mR/hr whole body for 2 minutes; or 3

(d) 5500 mR/hr thyroid for 2 minutes )

or,

3. Radiation Survey Teams measure dose rates greater than 50 mR/hr for 1/2 hour or greater than 500 mR/hr for 2 minutes (beta + gamma) at the site boundary; E

4. Radiation Survey Teams measure thyroid dose rates (equivalent I-131 Concentrations), at the site boundary, which are greater than:

(a) 250 mR/hr for 1/2 hour, or (b) 2500 mR/hr for 2 minutes.

IBM

F3-2 Rev. 3 Page 29 Attachment 1 CONDITION #8 (Cont'd)

RADIOLOGICAL EFFLUENTS Initiating Condition Indication Used Classification Effluent monitors detect 1. Any of the following valid gaseous General Emergency levels corresponding to: effluent monitor readings in alarm mode, reading greater than:

1. IR/hr whole body, or

2. SR/hr thyroid (a) 1R-50 (1000 mR/hr) at the site boundary (b) 2R-50 (1000 mR/hr) under actual meteorologi-cal conditions or,

2. Offsite dose projection calcula-tions result in the following dose projections at the site boundary, greater than:

(a) 1R/hr whole body; or (b) 5R/hr thyroid; or or,

3. Radiation Survey Teams measure dose rates greater than IR/hr whole body or

4. Radiation Survey Teams measure thyroid dose rates (equivalent I-131 Concentrations), at the site boundary, which are greater than 5R/hr.

i Radiation levels or 1. Unexpected radiation levels Alert airborne contamination above 1000 mR/hr which indicate a severe degradation in the control or of radioactive materials (e.g. , increase of factor 2.Widespreadcontamjnationabove of 1000 in direct radia- 10,000 dpm/100 cm beta gamma or 2

tion readings within 500 dpm/100 cm alpha activity facility).

t l

i IBM l

- er w-?e -m- ar- er - - - - - + - - - - -- --- a -'we' W y --

/

F3-2 Rev. 3

, Page 30 Attachment 1

]

CONDITION #9 MAJOR ELECTRICAL FAILURES Initiating Condition Indication Used Classification Loss of Offsite' Power All of the following indicators: Notification of Note: FSAR Section 1. 4.16 KV Bus Voltage (0 Volts) Unusual Event 14.1.9 a. Bus 11(21), 4119304 (4172804)

b. Bus 12(22), 4119305 (4172805)

c. Bus 13(23), 4119306 (4172806)

d. Bus 14(24), 4119307 (4172807) and

2. D1 & D2 Generators up to Speed and Voltage and Supplying Safe-guard buses:

a. D1 (D2) Tach (900 rpm)

b. D1 (D2) Gen. Volts (4260-4380 Volts)

c. Safeguard bus breakers closed:

Bus 15, Breaker 15-2 ,

Bus 26, Breaker 26-2 >

Bus 16, Breaker 25-6 Bus 25, Breaker 16-7 Loss of onsite AC Power Loss of both diesel generators Notification of Capability Unusual Event

Loss of offsite power All of the following indicators: Alert

! and loss of all onsite 1. 4.16 KV Bus Voltage (0 Volts) l AC power (See Site Area a. Bus 11(21), 4119304 (4172804)

Emergency for extended b. Bus 12(22), 4119305 (4172805) i

~

loss). c. Bus 13(23), 4119306 (4172806)

Note: FSAR Section d. Bus 14(24), 4119307 (4172807) 14.1.11 and i 2. Loss of both diesel generators Loss of offsite power All of the following indicators: Site Area Emergency and loss of onsite AC 1. 4.16 KV Bus Voltage (0 Volts) power for more than a. Bus 11(21), 4119304 (4172804) 15 minutes b. Bus 12(22), 4119305 (4172805)

IBM

F3-2 Rev. 3 Page 31 Attachment 1 CONDITION #9 (Cont'd)

MAJOR ELECTRICAL FAILURES Initiating Condition Indication Used Classification

c. Bus 13(23), 4119306 (4172806)

d. Bus 14(24), 4119307 (4172807) and

2. Loss of both diesel generators and

3. Blackout has occured for more than 15 minutes.

Failure of offsite and 1. Loss of AC power, (offsite & General Emergency onsite power along with onsite) indicated by:

total loss of emergency feedwater makeup capability a. 4.16 KV Bus Voltage (0 Volts) for several hours. This (1) Bus 11(21), 4119304 (4172804) would lead to eventual (2) Bus 12(22), 4119305 (4172805) core melt and likely (3) Bus 13(23), 4119306 (4172806) failure of containment. (4) Bus 14(24), 4119307 (4172807) and

b. Loss of both diesel generators and

2. Turbine driven Aux Feedwater pumps inoperable for several hours.

Loss of all onsite DC All of the following annunciators Alert power (See Site Area received:

Emergency for extended loss).

1. " Safeguard Train A DC Control Power Supply Failure" and

2. " Safeguard Train B DC Control Power Supply Failure" IBM

F3-2

, Rev. 3 Page 32 Attachment 1

]

CONDITION #9 (Cont'd)

MAJOR ELECTRICAL FAILURES Initiating Condition Indication Used Classification l NOTE: 4 annunciators numbered:l l 47018-0501 l l 47018-0502 l l 47518-0501 l l 47518-0502 l Loss of all vital onsite All of the following annunciators Site Area Emergency DC power for more than - received:

15 minutes. 1. " Safeguard Train A DC Control Power Supply Failure" and

2. " Safeguard Train B DC Control Power Supply Failure" l NOTE: 4 annunciators numbered:l )

l 47018-0501 l l 47018-0502 l

' l 47518-0501 l l 47518-0502 l and i

3. Loss of DC Power has lasted more than 15 minutes.

t i

1

( IBM

F3-2 Rev. 3 Page 33 Attachment 1 CONDITION #10

-CONTROL ROOM EVACUATIONS Initiating Condition Indication Used Classification Evacuatian of the control As required by the Shift Supervisor Alert room anticipated or re-quired with control of shutdown systems estab-lished from Hot Shutdown Panels and local stations Evacuation of the control As required by the Shift Supervisor Site Area room and control of shutdown Emergency systems not established from hot shutdown panel and local stations within 15 minutes I

l IBM

?.

F3-2 Rev. 3

. Page 34 Attachment 1 m ?

.)

CONDITION #11

FIRES ,

Initiating Condition Indication Used Classification Fire within the plant As reported by Fire Brigade Chief Notification of lasting more than 10 Unusual Event minutes after initial use of fire extinguishing equipment Fire potentially affecting 1. Observation that fire could Alert safety systems affect safety systems; and

2. Shift Supervisor's opinion Fire comprising the func- 1. Observation of major fire that Site Area tions of safety systems. defeats safety systems Emergency /

or functions; and

2. Shift Supervisor's opinion IBM i

F3-2 Rev. 3 Page 35 Attachment 1 CONDITION #12 PLANT SHUTDOWN FUNCTIONS Initiating Condition Indication Used Classification Nonfunctional indications 1. Annunciators: Notification of or alarms in the Control a. "NSSS Annunciator System Unusual Event Room requiring a plant Power Failure" shutdown or

b. "B0P Annunciator System Power Failure" and

2. Failed indication as determined by the Shift Supervisor All alarm (annunciators) Annunciators received: Alert lost 1. "NSSS Annunciator System Power Failure" and

2. " BOP Annunciator System Power Failure" Most or all alarms (annunc- Annunciators received: Site Area iators) lost while unit is 1. "NSSS Annunciator System Power Emergency not in cold shutdown or Failure" during plant transient or

2. "B0P Annunciator System Power Failure"'

I during a transient, as determined by the Shift Supervisor i

Complete loss of any As determined by Shift Supervisor Alert function needed for plant cold shutdown Complete loss of any As determined by Shift Supervisor Site Area function needed for plant Emergency

, hot shutdown IBM

, e-t

F3-2

Rev. 3 Page 36 Attachment 1

]

CONDITION #12 (Cont'd)

PLANT SHUTDOWN FUNCTIONS Initiating Condition Indication Used Classification Turbine Failure requiring 1. High Vibration (7 mils) Notification of a reactor / turbine trip Unusual Event and

2. High-High Vibration (14 mils) as indicated by Control Room recorder and alarms Turbine Failure causing 1. High Vibration (7 mils) Alert casing penetration and

2. High-High Vibration (14 mils) as indicated by Control Room 3 recorder and alarms '

and

3. As determined by Visual Inspection Failure of the reactor 1. Any Reactor Trip Setpoint and Alert protection system to redundancy requiring a reactor initiate and complete trip has been exceeded a trip which brings the reactor suberitical and i

2. Intermediate range detector output not decaying i

Transient requiring 1. Failure to bring reactor subcriti- Site Area Emergency

operation of shutdown cal with control rods; and systems with failure to scram (continued power 2. No indication of core damage; and generation but no core damage immediately evi- 3. Shif t Supervisor's opinion that dent). a transient is in progress IBM

F3-2 Rev. 3 Page 37 Attachment 1 CONDITION #12 (Cont'd)

PI. ANT SHUTDOWN FUNCTIONS Initiating Condition Indication Used Classification Transient requiring opera- 1. Reactor remains critical after General Emergency tion of shutdown systems trip; with failure to scram which results in core and damage or additional failure of core cooling 2. Indication of overpressurization and makeup systems (which of RCS because of inability to could lead to core melt) remove heat, as indicated by:

(a) RCS pressure greater than safety v:lve setpoint (2485 Psig); or (b) Rapidly increasing containment pressure and temperature I

i i

l J

IBM

F3-2 Rev. 3 Page 38 Attachment 1 CONDITION #13 '

'}

FUEL HANDLING ACCIDENTS Initiating Condition Indication Used Classification Fuel damage acc~ident 1. Any of the following containment Alert with release of radio- rad monitors in valid alarm mode activity to contain- and reading greater than:

ment (a) R2 - 350 mR/hr; or Note: FSAR Section (b) R7 - 350 mR/hr 14.2.1 or

2. The containment vent monitor in valid alarm mode, reading greater than:

(a) R11 - 1056 cpm; or (b) R12 - 10 cpm and 3

3. Shif t Supervisor's opinion >

Fuel damage accident with 1. Any of the following valid Alert release of radioactivity radiation monitor readings:

to the fuel handling building (a) R-22 HiHi Alarm, > 5 x 104cpm; or Note: FSAR Section (b) R!50, > 1.2 mR/hr 14.2.1 and

2. Spent Fuel Pool Area Monitor .

R-5 in valid alarm mode reading > 350 mR/hr and

3. Shift Supervisor's opinion IBM

l F3-2 Rev. 3 Page 39 Attachment 1 CONDITION #13 (Cont'd)

FUEL HANDLING ACCIDENTS Initiatina Condition Indication Used Classification Major damage to spent 1. For fuel damage in containment: Site Area fuel in containment or (a) Any of the following valid Emergency fuel handling building radiation monitor readings:

(e.g., large object (1) R48 Hi Alarm - 200 R/hr; or damages fuel or water (2) R49 Hi Alarm - 200 R/hr .

loss below fuel level) and (b) Shift Supervisor's opinion SE

2. For fuel damage in the Spent ruel Pool:

(a) Valid Radiation Mocitor readings en:

(1) R50 Hi Alarm, > 70 mR/hr; or-(2) RS, in alarm mode reading

> 1R/hr and (b) Shif t Supervisor's opinion e

IBM w r r -

- . - _ . - . - . _ -. . _ - - = - -

. . s F3-2 Rev. 3

.Page 40 i.

)

Attachment 1 CONDITION #14 COOLANT PUMP

-Initiating Condition Indication Used Classification

~

Coolant pump seizure 1.'RCP Trip (over current 86 Alert leading to fuel failure lock-out);

Note: FSAR Section

] 14.1.8 and l

2. Primary sample analysis indicating fuel failure (> 300 pCi/cc iodine 131 equivalent) 4 IBM

F3-2 Rev. 3

Page 41 Attachment 1 CONDITION #15 SERIOUS OR FATAL INJURY Initiatina Condition Indication Used Classification Transportation of a As determined by the Shift Supervisor Notification of seriously or fatally Unusual Event injured (may or may not NOTE: Serious injury is considered involve contamination) to be one that will require individual from site to admission for treatment or hospital for treatment observation for an extended period of time (greater than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ) r 1..

IBM

F3-2 Rev. 3 -

Page 42 Attachment 1 . ,)

CONDITION #16 SECURITY THREATS -

9 Initiating Condition Indication Used Classification Security threat; or Per security plan Notification of attempted sabotage Unusual Event Ongoing security Per security plan Alert compromise Imminent loss of Per security plan Site Area Emergency physical control of plant Loss of physical control Per security plan General Emergency of plant

)

4 IBM

F3-2 Rpv. 3-Page 43 Attachment 1 CONDITION #17 HAZARDS TO PLANT OPERATIONS Initiating Condition Indication Used Classification Aircraft crash onsite 1. Visual observation by plant Notification of or unusual aircraft personnel and/or plant security Unusual Event activity over facility personnel; and

2. Reported to the Shift Supervisor Aircraft crash in the Visual observation by plant Alert protected area personnel and/or plant security personnel Aircraft crash within Visual observation by plant Site Area Emergency protected area and affect- personnel and/or plant security ing vital structures by personnel impact or fires with plant not in cold shutdown Near or onsite 1. Visual observation by plant Notification of explosion personnel and/or plant security Unusual Event personnel; and 3

2. Reported to the Shift Supervisor Known explosion damage Visual observation by plant Alert to facility affecting personnel plant operation l

Severe damage to engi- Visual observation by plant Site Area Emergency i neered safety system personnel j equipment from explo-i sions with plant not in cold shutdown Near or onsite toxic or Gaseous hazards being experienced Notifie . tion of l

flammable gas release or projected, onsite (out of plant), Unusual Event as detected by portable instrumentation, which exists in concentrations greater than:

l IBM

e f F3-2 Rev. 3 '~

i

Page 44 t

CONDITION #17 (Cont'd) i HAZARDS TO PLANT OPERATIONS Initiating Condition Indication Used Classification

] (1) 80 ppm hydrazine; or (2) 25 ppm chlorine; or (3) 500 ppm ammonia; or (4) explosive limits as detected by explosive meter, 1 and, reported to the Shift Supervisor Entry into the plant Gaseous hazads being experienced Alert environs of toxic or or projected, within the plant, flammable gases as detected by portable instru-mentation, which exists in concen-trations greater than:

(1) 80 ppm hydrazine; or (2) 25 ppm chlorine; or (3) 500 ppm ammonia; or (4) explosive limits as detected ~.,

by explosive meter, )

and, reported to the Shift Supervisor d

Entry of toxic or Gaseous hazards being experienced or Site Area Emergency flammable gases into projected within vital areas of the vital areas with plant plant, as detected by portable instru-not in cold shutdown mentation, which exists in concentrations greater than:

(1) 80 ppm hydrazine; or (2) 25 ppm chlorine; or (3) 500 ppm ammonia; or (4) explosive limits as detected by explosive meter, and, reported to the Shift Supervisor j

Missible impacts from Visual observation by plant personnel Alert whatever source on and/or plant security personnel facility IBM

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

m J

F3-2 Rev. 3 Page 45 Attachment 1 ,

CONDITION #17 (Cont'd)

HAZARDS TO PLANT OPERATIONS Initiatina Condition Indication Used Classification Severe damage to engin- Visual observation by plant personnel Site Area Emergency eered safety system from missiles with plant not in cold shutdown b

1 i

IBM

C' F3-2 -

Rev. 3 Page 46 Attachment 1 CONDITION ()18

'}

NATURAL EVENTS Initiating Condition Indication Used Classification Any earthquake' Annunciator " Seismic Event" received Notification of on the seismograph Unusual Event Earthquake greater than Annunciator " Operational Earthquake" Alert Operational Basis Earth- received on the seismograph quake Earthquake greater than Annunciator " Design Basis Earthquake" Site Area Emergency Design Basis Earthquake received on the seismograph with plant not in cold shutdown Any tornado visible from Visual cbservation by plant personnel site Notification of and/or plant security and reported Unusual Event to the Shift Supervisor. s

)

Any tornado striking the Visual observation by plant personnel Alert facility and/or plant security and reported to the Shift Supervisor.

50 year flood 686' elevation Notification of Unusual Event Flood levels approaching 692' elevation - requires both units Alert design levels to be shut down Flood levels exceeding 698' elevation - highest level Site Area Emergency design levels with plant transformers will function not in cold shutdown Low water levels being 672.5' elevation - (At 672.5' Notification of experienced or projected elevation, both 11 and 21 cooling Unusual Event beyond usual levels water pumps trip)

IBM

i F3-2 e Rev. 3 l Page 47 Attachment 1 CONDITION #18 (Cont'd)

NATURAL EVENTS 3

Initiating Condition Indication Used Classification Low water levels being Approximately 669.5' elevation Alert experienced or projected to be near design levels Low water levels being 1. Approximately 666.5' elevation Site Area Emergency experienced or projected corresponding to loss of set of to be greater than design ~

miter gates or loss of one spill-levels or failure of vital way gate equipment with plant not in cold shutdown. or

, 2. Major vital equipment failure at low water level Sustained winds being Sustained wind speed indicated by Alert experienced or projected met tower in excess of 90 mph near design levels Sustained winds being in Sustained wind speed indicated by Site Area Emergency excess of design levels met tower, in excess of 100 mph being experienced or pro-jected with plant not in cold shutdown Any major internal or As determined by the Shift General Emergency external events (e.g., Supervisor and/or Emergency fires, earthquake, sub- Director stantially beyond design levels) which could or has caused massive damage to plant systems re-sulting or potential for resulting in large releases to the offsite environment in excess of the EPA Protective Action Guides

(

IBM l

F3-2 Rev. 3 Page 48 Attachment 1

) i CONDITION #19 OTHER Initiating Conditions Indication Used Classification Conditions that warrant Duty Engineer and Shift Supervisar Notification of increased awareness on the concurrence Unusual Event part of a plant operating 3

staff or state and/or local offsite authorities 1

Conditions that require Duty Engineer and Shift Supervisor Notification of plant shutdown under concurrence Unusual Event Technical Specification requirements or involve other than normal con-trolled shutdown Conditions that warrant Duty Engineer and Shift Supervisor Alert activation of Technical concurrence Support Center and near-site Emergency Operating 3/

Facility Other plant conditions Shif t Supervisor opinion Site Area Emergency that warrant activation of emergency operating centers and monitoring teams or a precautionary notification to the public near the site Other plant conditions Shift Supervisor's opinion General Emergency exist, from whatever source, that make release of large amounts of radio-activity in a short time period possible, e.g., any core melt situation.

IBM l

PAGE 1 OF 31 l l EMERGENCY PLAN IMPLEMENTING l

, l PRAIRIE ISLAND NUCLEAR PROCEDURES l l GENERATING PLANT l l NORTHERN STATES POWER COMPANY Number: F3-4 Rev: 7 l l History Copy l l ,s , , Retention Time: Lifetime l l l TITLE:

l Supt. Jad Propect on l RESPONSIBILITIES DURING l l Approved By: (cJ {/ /D ),

l AN ALEitT, SITE AREA OR l l -

,1 l GENERAL EMERGENCY l l

l PlanManager' [> l l l l l OC Date: 3 -M- 73 l l l l l l 1.0 PURPOSE l l l l The purpose of this instruction is to delineate the responsibilities of l l various emergency organization personnel and onsite organizations l l required to respond to an Alert, a Site Area Emergency or a General l l Emergency. l l l l l l 2.0

SUMMARY

l l l l A graded scale of response is provided for the different classes of l l emergencies, each requiring a specific response by emergency l l organization personnel for the protection of the public health and l l safety. l l l l 2.1 Alert l l 1 l A. Definition l

l 1 l The Alert Conditions are events which are in progress or have l l occurred which involve actual or potential substantial l l degradation of the level of safety of the plant. l l l 1 l l Some releases of radioactive material to offsite areas are l l probable. Hence there is some necessity for emergency l l planning and response by offsite agencies. Any radioactive l l release will be limited to a small fraction of the EPA l l Protective Action Guideline exposure levels. l 1 l l B. Purpose of Alert Class l l l

[ l The purpose of the Alert Emergency classification is to (1) l l assure that emergency personnel are readily available to l l respond it the situation becomes more serious or to perform l l confirmatory radiation monitoring, if required; (2) provide l l offsite authorities current status information. l l l l C. Plant Actions and Responsibilities: l 1 I .

l l l l l l l IBM l l

\ _

1 F3-4 Rev. 7 Page 2 ,

m

)

1. Promptly inform State and/or local authorities of Alert status and reason for Alert as soon as discovered.

2. Augment resources by activating onsite Technical Support Center, onsite Operational Support Center and Near-Site Emergency Operations Facility (EOF).

3. Assess and respond to the Alert condition.

4. Dispatch onsite or offsite survey teams and associated communications (if aceded).

5. Provide periodic plant status updates to offsite authorities.

6. Provide periodic meteorological assessments to offsite authorities and, if any releases are occurring, dose estimates for actual releases.

7. Close out by verbal summary to offsite authorities.

or s

8. Escalate to a more severe class.

D. State and/or Local Offsite Authority Actions:

1. Provide fire or security assistance, if required.

2. Augment resouces by activating Emergency Operating Centers and EBS to standby status.

3. Alert to standby status key emergency personnel including monitoring teams and associated communications.

4. Provide confirmatory offsite radiation monitoring and ingestion pathway dose projections if actual releases substantially exceed technical specification limits.

5. Maintain alert status until verbal closeout.

or

6. Escalate to a more severe class.

2.2 Site Area Emergency l A. Definition l

IBM l

. - = .

F3-4 Rev. 7 Page 3 F

J The Site Area Emergency describes events which are in progress or have occurred which involve actual or likely major failures of plant functions needed for protection of the public.

Significant offsite releases are likely to occur or are occurring but where a core melt situation is not expected although severe fuel damage may have occurred.

Any radioactive releases are not expected to exceed the EPA Protective Action Guideline exposure levels except near the site boundary.

B. Purpose of Site Area Emergency Class The purpose of the Site Area Emergency classification is to (1) assure that response centers are manned; (2) assure that monitoring teams are dispatched; (3) assure that personnel required for evacuation of Near Site areas are at duty stations if the situation becomes more serious; (4) provide current information for and consultation with offsite authorities, and (5) provide updates for the public through offsite authorities.

. C. Plant Actions and Responsibilities:

1. Promptly infone State and/or local offsite authorities of Site Area Emergency status and reason for emergency as soon as discovered.

2. Augment resources by activating onsite Technical Support Center, onsite Operational Support Center and the Near-Site Emergency Operations Facility (EOF).

3. Assess and respond to the Site Area Emergency.

4. Dispatch onsite and offsite survey teams and associated communications (if needed).

5. Provide a dedicated individual for plant status updates to offsite authorities.

6. Make senior technical and management staff onsite ,

available for consultation with NRC and State on a periodic basis.

7. Provide meteorological and dose estimates to offsite authorities for actual releases via a dedicated individual.

IBM

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F3-4 -

Rev. 7 Page 4

] .

8. Provide release and dose projections based on available plant condition information and foreseeable contingencies.

9. Close out or recommend reduction in emergency class by contacting offsite authorities.

or

10. Escalate to General Emergency class.

D. State and/or Local Offsite Authority Action:

1. Provide any assistance requested.

2. If sheltering near the site is desirable, activate the Public !

Notification System within at least 2 miles of the plant.

3. Provide public within at least 10 miles, periodic updates on emergency status.

4. Augment resources by activating Emergency Operating Centers and EBS to standby status. ,_s

5. Dispatch key emergency personnel including monitoring teams and associated communications.

6. Alert to standby status other emergency personnel (e.g.,

those needed for evacuation) and dispatch personnel to Near-Site duty stations.

7. Provide offsite monitoring results to licensee and others and jointly assess them.

8. Continuously assess information from licensee and offsite monitoring with regard to changes to protective actions already initiated for public and mobilizing evacuation resources.

9. Recommend placing milk animals within 2 miles on stored feed and assess need to extend distance.

10. Provide press briefings, perhaps with licensee.

11. Maintain Site Area Emergency status until closeout or reduction of emergency class.

or

12. Escalate to General Emergency class.

IBM

- 4.. - - - . ~ .

, ~ .r- .--_ _ -, - - . .

m F3-4

Rev. 7 Page 5 2.3 General Emergency A. Definition The General Emergency describes events in progress or which have occurred which involve actual or imminent substantial core degradation or melting with the potential for loss of containment integrity. Radioactive releases can be reasonably expected to exceed the EPA Protective Action Guideline exposure levels offsite for more than the immediate site area, hence, Protective Actions may have to be taken for protection of the general public.

B. Purpose of General Emergency Class The purpose of the General Emergency classification is to (1) initiate predeteonined protective actions for the public; (2) provide continuous assessment of information from licensee and offsite measurements; (3) initiate additional measures as indicated by actual or potential releases; (4) provide current information for the public and consultation with offsite authorities, and (5) provide updates for the public 1 through offsite authorities.

C. Plant Actions and Responsibilities l 1. Premptly inform stace and local offsite authorities of General Emergency status and reason for emergency as soon as discovered.

2. Augment resources by activating onsite Technical Support Center, onsite Operational Support Center and Near-Site Emergency Operations Facility (EOF).

3. Assess and respond to General Emergency.

4. Dispatch onsite ano offsite survey teams and associated communications.

5. Provide a dedicated individual for plant status updates to offsite authorities.

6. Make senior technical and management staff onsite available for consultation with NRC and State on a periodic basis.

i IBM i

~

F3-4 Rev. 7 Page 6

7. Provide meteorological and dose estimates to offsite authorities for actual releases via a dedicated ,

individual.

8. Provide release and dose projections based on available plant condition information and foreseeable contingencies.

9. Close out or recommend reduction of emergency class by briefing of offsite authorities at EOC by phone.

D. State and/or Local Offsite Authority Actions

1. Provide any assistance requested.

2. Activate immediate public notification of emergency status and provide public periodic updates.

3. Recommend sheltering for 2 mile radius and 5 miles downwind and assess need to extend distances. Consider advisability of evacuation (projected time available vs estimated evacuation times).

m

4. Augment resources by activating Near-Site EOC and any other primary response centers.

5. Dispatch key emergency personnel including monitoring teams and associated communications.

6. Dispatch other emergency personnel to duty stations within 5 mile radius and alert all others to standby status.

7. Provide offsite monitoring results to licensee and others and jointly assess these.

8. Continuously assess information from licensee and

, offsite monitoring with regard to changes to protective l actions already initiated for public and mobilizing i evacuation resources.

9. Recommend placing milk animals within 10 miles on stored feed and assess need to extend distance.

10. Provide press briefings, perhaps with licensee.

11. Maintain General Emergency status until closecut.or reduction of emergency class.

IBM

(

F3-4 Rev. 7 e

Page 7 3.0 PRECAUTIONS (1) All personnel shall stay clear of any areas as announced over the public address system.

(2) All personnel shall refrain from using the public address system or telephone system during an emergency.

(3) When the evacuation alarm is sounded, listen for instructions over the public address system before evacuating.

(4) Anyone working in a contaminated area when the evacuation alarm sounds should remove as much protective clothing as time permits, especially gloves, booties or rubbers. If wearing a double suit, removal of outside clothing would only be necessary. Proceed to the designated assembly area. If unable to remove all protective clothing, inform personnel in charge at the assembly area of your condition.

! l l NOTE: When the evacuation alarm sounds during a DRILL, i l remove ALL protective clothing prior to evacuating. l

( l I (5) When exiting the Protected Area via the Guard House, proceed through the portal monitor quickly. Step through without stopping. All I.D. cards (badges) shall be collected and checked out by the Guard Force, so an early printout of all personnel within the Protected Area can be obtained.

(6) Everyone shall remain at assembly area for monitoring and accountability checks until released by the Emergency Director or directed for reassignment for duty within the plant. Follow ins t r uc tir,rm from the Assembly Point Coordinator. When dcps. ting the site property, obey all instructions from traffic contrci personnel.

l l

l 4.0 APPLICABILITY This instruction shall apply to all plant per.connel.

l 5.0 ORGANIZATIONAL CONTROL l S.1 Overall Responsibility - Emergency Director 5.2 In-Charge, Control Room - Shift Supervisor l

l l

IBM l

l

F3-4 Rsv. 7 Page 8

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Technical Support Center - TSC Coordinator Operational Support Center - OSC Coordinator Assembly Point - Assembly Point Coordinator 5.3 Assistance, Control Room - Control Room Operators

- Shift Technical Advisor

- Supt Operations '

TSC - Operations Committee

- Shift Emergency Communicator

- Radiological Emergency Coordinator

- Engineering support as needed (i.e.,

systems experts)

OSC - Extra Operators

- Rad Survey Teams

- Maintenance Supervisors

- I & C Supv & Coordinators

- Chief Station Electrician and Alternates

- Additional Support as needed 4

6.0 RESPONSIBILITIES 9y 6.1 Shift Supervisor of the affected unit.

(1) Proceed to the Control Room (if not already there)

! I I l NOTE: The Shift Supervisor of the affected i l unit shall remain in the Control Room l l at all times during accident conditions l l until properly relieved. l 1

I (2) Implement the appropriate Emergency Operating Procedures and a

respond to the emergency condition with the objective of returning the plant to a normal safe condition (or ccid shutdown, if determined to be necessary).

(3) Monitor plant conditions to determine when the threat to plant safety has passed. Be prepared to escalate to a more severe emergency class, if required.

(4) Coordinate, with the Emergency Director, all plant operations which may impact on radioactivity releases.

6.2 Shift Supervisor of the unaffected unit:

IBM h

F3-4

.e Rev. 7 Page 9 (1) Assume the position as Emergency Director.

(2) Start the ddties and responsibilities as assigned to the Emergency Director as specified in Section 6.3. Use Attach-ment A, Emergency Director's Checklist (PINGP #571).

(3) When the designated Emergency Director arrives onsite, update him on the current plant status and formally transfer the

, Emergency Director responsibilities over to that individual.

(4) Assist the Shift Supervisor of the affected unit, as required in section 6.1.

6.3 Emergency Director (1) Assume the role as Emergency Director. Use Attachment A, Emergency Director's Checklist (PINGP #571).

l (2) Determine the plant status. Report to the Control Room and become familiarized with the situation and sequence of events preceeding and propagating the Emergency Condition.

t, (3) Announce, or ensure that the following message is announced over the public address system:

ATTENTION ALL PLANT PERSONNEL:

A (N) (pick correct class):

ALERT, or SITE AREA EMERGENCY, or GENERAL EMERGENCY HAS BEEN DECLARED.

ALL MEMBERS OF THE ONSITE EMERGENCY ORGANIZATION REPORT TO YOUR EMERGENCY DUTY STATIONS. ALL OTHER PERSONNEL STANDBY FOR FURTHER INSTRUCTIONS.

Repeat announcement.

IBM

F3-4 Rev. 7 Page 10 l i

, l NOTE: A plant evacuation will normally be l l initiated during an Alert, a Site Area l l Emergency, or a General Emergency, l

l however, the Emergency Director must l l consider special conditions, (e.g., l l high winds or tornado) where an evacu- l l ation is not feasible or when the on- l l site assembly point is not habitable. l I 3 l See procedure F3-9, " Emergency Evacua- l l tion", for specific evacuation l l criteria. l l l (4) Contact the STA and SEC (if not already done so), and have them report to the Control Room immediately.

(5) Assist the SEC in completing the Notification Report Form, Figure 1, F3-5 (PINCP #577).

(6) Designate the SEC to complete the notification of state, local, and NSP personnel, in accordance with F3-5, " Emergency ,

Notifications". l l

l l NOTE: State and local authorities shall be notified 1 l within 15 minutes of the declaration of the l

, l emergency class. l l

l (7) Direct the SEC to activate the onsite emergency organization, in accordance with F3-5, " Emergency Notifications", and to notify any other appropriate plant personnel, as deemed neces sa ry.

i (8) Notify any other offsite support agencies required to provide assistance to respond to the emergency condition, e.g., local l support services, such as fire fighting, ambulance. hospital, l , etc. See " Emergency Preparedness Telephone Directory local i support services phone numbers.

(

l l

l NOTE: These contacts should be coordinated with l l the SEC and the Control Room to ensure that l l the contacts required are made in a timely l l manner. l I I IBM I

\ - , . , . - - - . - - - . - - , . -- -

F3-4 Rev. 7 Page 11 (9) Direct the Shift RPS to

.(a) perform the appropriate sampling and analysis as necessary, e.g. , primary system, containment air, steam generator liquid, shield building stack, etc., and/or (b) perform offsite dose calculations, if the high range effluent stack monitors (R-50) are in valid alarm mode.

(10) Direct the RPS and/or operator to conduct onsite and in plant radiation surveys, as necessary.

(11) If the first notification of an emergency is a General Emergency, call the County Sheriff and make the -initial Protective Action recommendation:

(a) Recommend activation of the public notification system, and (b) Recommend sheltering of the public within a two mile radius of the plant.

(12) Ensure that the NRC has been notified and designate an individual to maintain communications with the NRC via the ENS phone, as necessary.

I I l NOTE: Notification of the NRC via the ENS l l required within I hour. l I I (13) During plant evacuations, direct the evacuation of all non-essential personnel from the plant site to the desi;nated assembly point (per F3-9).

(a) Normally the Construction Office Building will be the designated assembly point. However, the Screenhouse can be used if conditions make the Construction Office Building uninhabitable.

(b) Direct the Security Force to warn all personnel within the Owner Controlled Area and outside the Protected Area.

(14) Monitor the habitability of the Auxiliary Building and order an evacuation of the Auxiliary Building Operators to the OSC if:

(a) General are'a radiation lAvels exceed 100 mR/hr; or IBM

F3-4 Rev. 7 Page 12 '

f (b) Based upon recommendations from the Radiation Protection Group.

(15) Account for all personnel (plant personnel, visitors and construction personnel) onsite, within 30 minutes following 4

the evacuation. (This responsibility may be delegated). See Procedure F3-9.

(16) Determine if the assembly point and guardhouse are safe and watch for changing conditions which would require further evacuation.

(17) Complete a turnover of Emergency Director responsibilities from the Shift Supervisor of the unaf fected unit to the designated Emergency Director when that individual arrives onsite. Ensure that both Shift Supervisors are aware of the turnover of the Emergency Director responsibilities. The Shif t Supervisor of the unaffected unit shall continue with the Emergency Responsibilities until a formal turnover occurs.

(18) During plant evacuations, direct monitoring of all personnel for contamination (adequate instrumentation is available at 3 both assembly points for this task). J (19) Direct the activatien of the Technical Support Centet and Operational Support Center per procedure F3-6, and F3-7, and ensure that coordinators are assigned to the emergency response centers.

(20) Verify that communications have been established between all i the onsite emergency operating centers. (Control Room, OSC, l and TSC). -

(21) If necessary, based on plant conditions, initiate monitoring of onsite and offsite areas. This responsibility may be delegated to the Radiation Protection Group.

(22) Tf offsite releases may or are occurring, direct tim calculation of projected offsite dose rates as per F3-13.

This responsibility may be delegated to the Radiological Emergency Coordinator.

(23) Make appropriate protective action recommendations to the offsite authorities. (See F3-8, " Recommendations for Offsite Protection Actions").

(24) Ensure that continuous updates (approximately every half-hour) are provided to the State EOC's (Wisc and Minn) which were actisated by the intial notification. (See F3-5)

IBM

4 F3-4 Rev. 7 Page 13 I

I l NOTE: When the EOF is activated, communications with l l the offsite authorities will be transferred to l l the EOF. l l

l (25) Authorize overexposures in accordance with F3-12', " Emergency Exposure Control".

(26) Direct opera.*ons at the assembly point via the Assembly Point Coordinator and arrange for any assistance required at the assembly area.

(27) If conditions indicate that further system degradation has cccurred, escalate to a more severe emergency classification and direct the notification of all offsite agencies and personnel of such action, per F3-5. Announce, or have announced, the re-classification and escalation to a higher emergency classification, over the public address system.

(28) As conditions permit, terminate the emergency condition or downgrade the emergency classification to a lower classification. Direct the notification of all offsite agencies and personnel, per F3-5. Announce or have announced the downgrading or termination of the emergency condition over the public address system.

(29) When the Near-Site EOF has been activated, the Emergency Manager will inform the Emergency Director. Ine Emergency

Director will then transfer centrol of all offsite activities over to the Emergency Manager.

(30) Coordinate with all group Superintendents to insure tha; plant manpower requirements for all subsequent workshifts are determined and that the necessary personnel are scheduled.

1 (31) When the emergency condition is terminated, ensure that all offsite and onsite personnel are notified of the termination of the emergency condition and initiation of recovery operations.

6.4 Operations Group (1) Utilize applicable operations manual procedures to respond to the Emergency Condition as appropriate, with the objective of returning the plant to a normal safe status (or cold shutdown, if necessary).

IBM

. l F3-4 Rsv. 7 Page 14 (2) Assist the Shift Supervisor as requested.

(3) Announce the location and nature of the Emergency over the public address system. Wneu an evacuation is declared, sound the evacuation alarm and direct all non-essential personnel to evacuate to the designated assembly point. Direct all personnel to remain clear of the affected area (if applicable). See F3-9, " Emergency Evacuation."

(4) Assist in the activation of onsite emergency centers and organization.

(5) Assist individuai performing the pe rsonnel accountabil'ity a check as necessary, per F3-10, " Personnel Accouncability".

(6) Continuously monitor the Control Room instrumentation, radiation monitors, or any other developments which could be indicative of further system degradation. Inform the Shift Supervisor immediately of any changes in plant status. ,

(7) Operators (Aux & B0P) should report to their duty station when the emergency is declared.

(a) Aux operators shall ensure that they have a low and ')

high range dosimeter and a dose rate indicating device '

for all further required operations in the Auxiliary Building.

(b) Aux & BOP operators should give consideration to terminating all non-essential plant operations. (e.g.,

shutdown evaporators).

1 (c) When a plant evacuation is declared, the aux & BOP operators should immediately establish a communi-cation channel with the OSC.

l l

i (d) If the Auxiliary Building general rad levels exceed 100mR/hr or upon recommendations from the Emergency Director or Radiation Protection Group, the Aux Operators shall evacuate to the OSC. For exposure control purposes, all further Auxiliary Building entries shall be controlled thru the OSC.

l l (8) Perform the necessary onsite and in plant radiation surveys l as requested by the Shift Supervisor.

(9) Relief Shift and Training Operators should proceed to the Operational Support Center for further instructions to j support operations in the Control Room.

IBM

F3-4 ,

Rev. 7 {

Page 15 (10) The Superintendent, Operations, if on site, should report to the Control Room and provide assistance where necessary.

6.5 Shift Technical Advisor (1) Report to the Control Room immediately upon notification of the Emergency Condition.

(2) Assist the Shift Supervisor and Emergency Director in assessing the emergency condition and safety related aspects of the plant.

6.6 Shift Emergency Communicator (1) Report to the Control Room immediately upon notification.

(2) Complete the Notification Report Focm, Figure 1 (PINGP #577),

F3-5, with assistance from the Emergency Director / Shift Supervisor of the unaffected unit.

(3) Complete the required notification of state and local authorities, and NSP personnel in accordance with F3-5,

" Emergency Notifications".

l l l NOTE: State and local authorities shall be notified l l within 15 minutes of the declaration of the l l emergency classification. l I I (4) Notify applicable offsite authorities if conditions escalate to a more severe emergency class or whenever the emergency class is downgraded in accordance with F3-5, "Energency Notifications".

(5) When the emergency classification has been terminated, .

close-out the emergency classification, by notifying the state, local, and NSP personnel in accordance with F3-5,

" Emergency Notifications".

! I l l NOTE: If the EOF has been activated, notifications l l of offsite agencies for an escalation, 1 l downgrade or termination of the emergency l l condition will be completed by EOF personnel.l l 1 IBM

t F3-4 -

Rev. 7 Page 16

)

6.7 Technical Support Center Coordinator The Technical Suppore Center Coordinator shall be responsible for the general activation, operation and coordination of activities in the Technical Support Center (TSC).

The TSC Coordinator shall:

1 (1) Report to the TSC and assume the position as TSC Coordinator.

Use Attachment C, Technical Support Center Coordinator Checklisc (PINGP #573).

(2) Coordinate activities of plant and non plant personnel located in the TSC.

(3) Designate an individual to maintain the Emergency Directors Log.

(4) Establish and verify radiological monitoring for the TSC, in accordance with F3-6.

(5) Ensure that the TSC doors are closed and initiate the TSC cleanup system.

(6) Designate an adividual to operate the Data Recall Computer.

(7) Assist the Emergency Director in performing the account-ability check as necessary as per F3-10.

(8) Establish or ensure that communications are established with all onsite emergency operating facilities (Control Room, OSC and assembly area).

(9) Periodically update personnel located in the TSC with appropriate information.

I

(10) Maintain any necessary status boards.

(11) Control the use of equipment located in the emergency locker.

(12) Provide technical guidance to the Emergency Director and Control Room operators on plant operations.

(13) Obtain and provide technical assistance as required to support the Technical Support Center and Control Room operations.

l (14) When the Near-Site EOF has been activated, establish communications between the TSC and the EOF.

IBM L

L i

F3-4 Rev. 7 Page 17 6.8 Operational Support Center Coordinator The Operational Support Center Coordinator shall be responsible for the general activation, operation, and coordination of activities in the Operational Support Center (OSC).

The OSC Coordinator shall:

(1) Report to the OSC and assume the role as OSC Coordinator.

Use Attachment D, Operational Support Center Coordinator Checklist (PINGP #574).

(2) Coordinate activities of plant personnel located in the OSC to support plant operations as requested by the Control Room and TSC.

I i l NOTE: The REC shall be responsible for control and l l direction for the Radiation Protection Spe- l l ialists located in the OSC. 1 I I (3) Establish and verify radiological monitoring for the OSC and the Control Room, as per F3-7.

(4) When a plant evacuation occurs, (a) Ensure all OSC personnel insert their badges into the OSC card reader. Inform the Emergency Director upon completion.

(b) Designate an individual to perform a Control Room accountability and transfer accountability sheet to the Emergency Director.

(5) Ensure that dosimetry is issued to all OSC and Control Room

, Personnel, in accordance with F3-7.

(6) Establish communications between the OSC, the TSC and the Control Room.

(7) Designate an individual to update and maintain the OSC Status Board.

l (8) Periodically update personnel located in the OSC with appropriate plant status information.

(9) Control the use of all food use in the OSC natil directed by the Radiation Protection Group.

(10) Control the use of equipment located in the emergency locker.

IBM

F3-4 Rov. 7 Page 18

)

6.9 Assembly Point Coordinator The Assembly Point Coordinator shall be responsible for the general operation of the assembly area.

'The' Assembly Point Coordinator shall:

(1) Verify that radiological monitoring has been established for the Assembly Point.

(2) Ccordinate activities of all personnel (plant and non-plant) located at the Assembly Point.

(3) Assist the Emergency Director in performing the accountability check, as necessary, per F3-10.

(4) Maintain the communication systems. A person may be designated as the communicator, if necessary.

(5) Control the use of. equipment located in the Emergency Locker.

. (6) Update all personnel with appropriate information when directed by the Emergency Director. -,

(7) Provide instructions to personnel when they are released from -)

the assembly point for reentry or transport offsite.

6.10 Radiological Emergency Coordinator (REC)

The Radiological Emergency Coordinator (REC) shall be responsible for accident assessment, onsite and offsite. The REC shall:

(1) Report to the Technical Support Center and assume responsibility for the Radiological Emergency Coordinator position. Use Attachment B, Radiological Emergency

Coordinator Checklist (PINGP #572).

[

(2) Determine the current plant status.

(3) If radiological releases are occurring, airborne or liquid, t verify that the Radiation Survey teams have been dispatched j in accordance with F3-15 or F3-16.

i (4) If radiological airborne releases may or are occurring, initiate offsite dose projections in accordance with F3-13.

(5) Assist the Emergency Director in performing the personnel t accountability check of the Radiation Survey Teams, as per 1

F3-10 " Personnel Accountability".

IBM

i .

F3-4 Rev. 7 Page 19 (6) Designate or ensure that an RPS is designated to proceed to the EOF Count Room to perform any required analysis in the backup countroom, as necessary.

(7) Maintain communications with the offsite survey teams. Based on current meteorological data, release data and survey team results, dispatch the survey teams in the affected areas of the plume.

(8) Ensure that all Radiation Survey Team Members (onsite &

offsite) are informed of the current plant status and are informed of any emergency condition changes.

(9) When the Radiation Survey Teams forward survey results to the TSC, log the data and supervise the development of the plume map.

(10) If the wind is from the East or West such that the plume is traveling towards the Minnesota or Wisconsin bluffs, consider that plume diversion is likely to occur. Deploy the survey teams to conduct a plume search both beyond the bluffs and up and down the valley, where plume diversion is likely to occur.

(11) Direct the activities of the onsite radiation survey teams, (i.e., samples required, surveys required, analysis, etc.).

(12) Based on the meteorological data, release data, and surveys (onsite and offsite), determine the necessary radiation protection for the various segments of the plant emergency organization.

(13) Monitor the habitability of the Auxiliary Building. If the radiation levels exceed 100 mR/hr or based on Rad Prot Group survey results, recommend to the Emergency Director that the Auxiliary Building Operators be evacuated to the OSC. All entries to the Aux Building shall be controlled thru the OSC.

(14) Verify that the Radiation Protection Status Board is periodically updated.

(15) Based on offsite dose projections and offsite survey results, provide the Emergency Director with recommendations for Protective Actions in accordance with F3-8, " Recommendations For Offsite Protective Actions".

(16) Periodically update the Minnesota Department of Health and the Wisconsin Section of Radiation Protection with infor-IBM

F3-4 Rsv. 7 Page 20 mation required by Figure 6 (F3-5) " Emergency Notification Followup Message" (PINGP #582).

f I l i NOTE: When the EOF is activated, this responsibil- l l ity will be transferred to the Radiation l l Protection Support Supervisor (RPSS). l l l (17) When.the Near-Site EOF is activated, transfer control of the offsite survey teams to the Radiation Protection Support Supervisor (RPSS).

I I l NOTE: Dose projections will still be a responsi- l l bility of the REC and dose projection infor-l l mation will be forwarded to the Radiation l l Protection Support Supervisor (RPSS). l l l (18) Periodically or as requested, update the NRC, via the HPN phone, with release data, dose projections and meteorological data, as required by Figure 6 (F3-5) " Emergency Notification Followup Message" (PINGP #582).

L

[)

6.11 Radiation Protection Group (1) The Shif t Radiation Protection Specialist shall provide assistance (e.g., sampling, chemistry, radio-chemistry, surveys, etc.) as requested by the Shift Supervisor.

4 (2) The Radiation Survey Teams shall be dispatched to initiate 1

offsite surveys as directed per F3-15 and/or F3-lo.

(3) All other Radiation Survey Team members shall report to the i

plant site for further instructions. The Radiation Survey Team members reporting to the plant site shall:

[

(a) Unless directed by the Emergency Director or Radio-logical Emergency Coordinator, proceed to the Oper-ational Support Center and wait for further instruc-tions.

(b) Supervise any checks for personnel contamination and i direct decontamination at the assembly point.

! (c) Provide recommendations to the Emergency Director regarding radiation exposure control to ensure that applicable limits are not exceeded.

IBM i

l .

F3-4 Rev. 7 Page 21 (d) Provide radiation protection coverage for:

(1) Damage control and repair teams (2) First aid j (3) Search and Rescue Teams (4) Reentry Teams (e) Perfona emergency sampling (air and liquid), chemistry, !

radio-chemistry, surveys, etc., as directed by the Emergency Director or the Radiological Emergency Coordinator.

6.12 Security Force (1) Continue with normal duties unless otherwise notified.

(2) When the evacuation alarm sounds, all guarda, with the exception of the SAS guard, evacuate to the guardhouse for further instructions.

I I l NOTE: The SAS guard will evacuate when directed l l by the Emergency Director. l l- 1 i

(3) Assist with the evacuation of personnel to the designated assembly point which will normally be the Construction Office Building, in accordance with F3-29, " Emergency Security Procedures".

IBM

F3-4 Rav. 7 Page 22 i'

I l l NOTE: (1) It will be necessary for personnel to exit l l quickly thru the portal monitor and turn- l l stile. Collect all I.D.'s and process l l badges so an Employee Onsite List of per- l l sonnel inside Protected Area can be ob- l l tained. l l l l (2) To speed evacuation from the Protected l l Area, it may be beneficial to open the l l vehicle gates and allow personnel to exit l l there. l l l l (3) The Security Force shall ensure that all l l personnel onsite, within the protected l l area, have heard the evacuation alarm. l l l (4) Perform a check of all areas immediately surrounding the Protected Area so that all personnel are notified of the evacuation in progress.

l l l NOTE: The owner Controlled Area vill be checked whenl l directed by the Emergency Director. l l l (5) Control access to Protected area per instructions from the Emergency Director. Be prepared to obtain a prir, tout for an accountability check in accordance with F3-10, " Personnel Accountability".

(6) Assist the Radiation Protection Group in establishing a secondary access control point when directed by the Emergency

-Director.

(7) Station a guard, with dosimetry, at the plant entrance, if conditions permit, to control access to the plant site.

6.13 Logistic Support Group The Logistic Support Group includes the Administrative Services Group, Eurchasing & Inventory Control Group and the Document Control Group.

During emergency conditions, the Logistics Support Group shall:

(1) Continue with normal duties unless directed otherwise.

l l IBM 1

+ - - *==+m =mwe

~

F3-4 Rev. 7 Page 23 (2) Immediately vacate any emergency operating center (Control Room, OSC, or TSC) when an emergency is declared.

(3) Remain clear of any areas, as announced over the public address system.

(4) When requested by the Shift Emergency Communicator (SEC),

transfer control of the telephone switchboard to the TSC.

I I l NOTE: The switchboard operator should report l l to the TSC to control the switchboard l l from the TSC until relieved by an l l alternate communicator. l l 1 (5) When the evacuation alarm sounds, proceed to the designated assembly point.

(6) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the site property.

6.14 Instrument & Control Group (1) The I&C Supervisor and Coordinators shall report to the Operational Support Center (OSC) to provide support for:

(a) Repair and corrective actions for instrument and control systems, and; (b) Search and rescue efforts.

(2) The I&C Specialists shall:

(a) Continue with normal duties unless directed otherwise.

(b) Immediately vacate any emergency operating center (Control Room, OSC or TSC) when an emergency is declared.

(c) Remain clear of any areas, as announced over the public address system.

(d) When the evacuation alarm sounds, proceed to the designated assembly point.

IBM

F3-4 Rev. 7 Page 24 (e) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the site property.

6.15 Maintenance Group The maintenance group consists of all maintenance personnel, plant electricians and plant helpers.

(1) The Maintenance Supervisors, Chief Station Electrician, and designated station electrician alternates shall report to the OSC to provide support for:

(a) Repair and corrective actions for mechanical and electrical systems and; 1

(b) Search and rescue efforts.

(2) All other maintenance personnel, electricians and plant helpers shall:

(a) Continue with normal duties unless directed otherwise.

(b) Immediately vacate any emergency operating center )

(Control Room, OSC, or TSC) when an emergency is declared.

(c) Remain clear of any areas, as announced over the public address system.

(d) When the evacuation alarm scunds, proceed to the designated assembly point.

(e) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the site property.

6.16 Engineering Group (1) All Superintendents, lead engineers and system experts (as requested by their supervisor) shall report to the Technical Support Center (TSC). The Engineering Group shall:

(a) Provide technical support for emergency repairs and corrective action on electrical and mechanical systems.

(b) Provide technical & engineering support for plant systems.

IBM

F3-4 Rev. 7 Page 25 (c) Provide technical & engineering support for operating radioactive waste systems.

(d) Provide technical & engineering support on core parameter analysis.

(2) All other engineers (unless specifically requested to remain in the TSC) shall:

(a) Continue with normal duties unless directed otherwise.

(b) Immediately vacate any emergency operating center (Control Room, OSC, or TSC) when an emergency is declared.

(c) Remain clear of any areas, as announced over the public address system.

(d) When the evacuation alarm sounds, proceed to the designated assembly point.

(e) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the i site property.

6.17 Contact, Temporary Personnel and Visitors (1) Continue with normal duties unless di;ucted otherwise.

(2) Immediately vacate any emergency operating center (Control Room, OSC, or TSC) when an emergency is declared.

(3) Remain clear of any areas, as announced over the public address system.

4 (4) When the evacuation alarm sounds, proceed to the designated assembly point.

(5) Follow instructions from the Assembly Point Coordinator for either reentry into the plant or departure from the site property.

IBM l- _

PINGP #571, Rrv. 2 F3-4 Rtv. 7 Page 26

.]

m cm , .

ATTACHMENT A hhh (

EMERGENCY DIRECTOR CHECKLIST

- 11 (1) Determine Plant Status MTTH1T BM M (2) Announce Emergency Class over PA Systein (3) Contact STA & SEC to report to Control Room (4) Assist SEC & sign notification report. Direct SEC to:

(a) Notify offsite authorities (F3-5)

(b) Augment onsite emergency organization (F3-5)

(5) If the first notification of an emergency is a General Emergency, call the County Sheriff immediately and recommend:

(a) Activation of Public Notification System, and; .

(b) Sheltering within 2 mile radius of plant (6) Assure communications established & maintained with NRC.

(7) Direct Shift RPS to:

a) conduct onsite sampling, as necessary.

b) perform dose calculations, if R-50 in alarm mode.

(8) Direct RPS/ Plant Operations to conduct onsite/in-plant surveys, as necessary.

(9) Determine need to evacuate nonessential personnel (F3-9)

(10) If evacuation is necessary, designate assembly point.

(a) Designate assembly point coordinator (b) Complete accountability within 30 minutes after evacuation (F3-10)

(c) Determine habitability of assembly area (11) Monitor Aux Building habitability and direct evacuation of Aux Operators to OSC if:

(a) General area rad levels >100 mR/hr; or (b) Based on Rad Protection Group recotwendations IBM

PINGP #571, Rav. 2 F3-4 Rev. 7 Page 27 ATTACHMENT A (Cont'd)

EXAMPLE ONLY -

EMERGENCY DIRECTOR CHECKLIST U w 1 (12) The Shift Supervisor of the unaffected unit should ,

complete a turnover to the designated Emergency Director at this point. Ensure that both Shift Supervisors are aware that a turnover of Emergency Director responsibilities has occurred. If the designated Emergency Director is not available, proceed with the checklist.

(13) Direct activation of TSC & OSC (F3-6 & F3-7) and assign the responsibility for TSC Coordinator, OSC Coordinator and REC to appropriate individuals.

(14) Establish communication links between onsite emergency centers (15) Dispatch offsite survey teams as necessary (F3-15 & F3-16)

(16) Direct offsite dose assessment activities (F3-13)

(17) Make protective action recommendations (F3-8)

(18) Provide continuing updates to State EOC's (19) Authorize overexposurcs as necessary (F3-12)

(20) Establish communications with EOF (21) Transfer offsite responsibilities to EOF (22) Determine long-term manning requirements (23) Escalate / downgrade emergency class, as appropriate (24) Review Emergency Director's responsibilities to ensure all required actions are complete.

Emergency Director Date/ Time IBM

PINGP #572, R:v. 2 F3-4 Rsv. 7 EXMPlYUNLY -.

4 Q').h ATTACHMENT B D 9 TU l '

m k. . .

RADIOLOGICAL EMERGENCY COORDINATOR CHECKLIST INIT (1) Determine Plant Status (2) Determine additional TSC support required for accident assessment functions & assign, as necessary.

(3) Designate Rad Protection Coordinator for OSC (4) Determine if releases are occurring (5) Obtain meteorological data (F3-13) & radiation monitor readings (6) Direct offsite dose projection calculations (F3-13)

(7) Recommend protective action recommendations for Emergency Director (F3-8)

_s (8) Instruct, dispatch & coordinate offsite radiation survey teams, as necessary in accordance with the following:

(a) F3-15 Airborne Release - Team #1 Plume Search

- Team #2 Plume Search & Sampling or (b) F3-15 Liquid Release - Team #1 Eisenhower Bridge Sampling

- Team #2 Intake / Discharge Canal &

Lock & Dam Sampling (9) Ensure an RPS is designated to operate the EOF countroom facility and perform the required analysis, as necessary.

(10) Consider plume diversion along valley if plume is traveling towards Minnesota or Wisconsin bluffs and instruct Survey Teams appropriately.

(11) Instruct, dispatch & coordinate onsite radiation survey teams, as necessary (F3-14) i (12) Monitor the habitability of the Auxiliary Building. Recommend to the Emergency Director that the Aux Operators evacuate to ;

the OSC if the general area rad levels are >100 mR/hr or '

based on Rad Protection Group surveys.

IBM

F PINGP #572, Rtv. 2 F3-4 Rev. 7 Pa e 29 D{i4MPLE ONLY ad -.

ATTACHMENT B (Cont'd)

WWW o

]D A3

]D JU g Q

.h U ~

y 1}

RADIOLOGICAL EMERGENCY COORDINATOR CHECKLIST QU ;

(13) Determine RPS sampling priorities per F3-23 (number in order) and specify protective clothing / respiratory protection require-ments for sampling team.

I I Primary Sample - Pressurized /Unpressurized n Secondary Sample

((] Shield Building Stack Sample Pi Containment Air Sample i I Liquid l I Filtered Gas l l Unfiltered Gas l I Iodine / Particulate i I Other (14) Update offsite survey teams with periodic plant status updates (15) Evaluate survey data and develop plume map (16) Request alternate meteorological data and weather forecast information as necessary (F3-13 Figure 4)

(17) Recommend overexposure limits to Emergency Director (F3-12)

(18) Update the Radiation Protection Status Board (19) Provide periodic updates to the Emergency Director & TSC Staff (20) Update the State Health Departments (Minn & Wisc)

(21) Establish / Maintain communications with the RPSS (22) Turnover the offsite survey responsibilities to the RPSS (23) Acknowledge the HPN phone and update the NRC as appropriate.

_ (24) Review the REC responsiblities (F3-4 Section 6.10) to ensure all required actions are complete Radiological Emergency Coordinator Date/ Time IBM

PINGP #573, R2v. 2 F3-4 Rtv. 7 Page 30 EMBLE GNLY ,

Ig]

ATTACHMENT C

<9 N 0 TECHNICAL SUPPORT CENTER C00RDIN i ,

U

]D ! !

tnu.% m IJui.h U u yI i INIT (1) Coordinate the activities of plant and non plant personnel located in the TSC.

(2) Shut TSC Door and Start TSC Clean Up System (3) Designate an individual (s) to establish communication between TSC, OSC & Control Room.

(4) Designate an individual to maintain the Emergency Director's Log.

(5) During a plant evacuation, assist the Emergency Director in overall plant accountability. (F3-10)

(6) Activate & verify proper operation of Vamp. (F3-6 Section 4.2.1)

(7) Activate & verify proper operation of CAM (F3-6, Section 4.2.2)

(8) Designate an individual to operate the Data Recall System (9) Update TSC personnel with plant status updates as requested by the Emergency' Director.

(10 Provide technical assistance and guidance to the Emergency Director and Control Room.

(11) Evacuate all unnecessary personnel, as requested by the Emergency Director.

l (12) Up-date Status Boards (13) Control use of equipment located in Emergency Locker (14) Establish appropriate office space for Emergency Personnel (15) Establish routine sampling & monitoring for the TSC as necessary.

(16) When the Near-Site EOF has been activated, ensure that com-munications are established between the TSC and EOF.

(17) Review F3-4 & F3-6 1

TSC Coordinator Date/ Time IBM

PINGP #574, R;v. 2 F3-4 Rev. 7 Page 31

< a m s u l A, u , A ?f i , . I y

"I E 9 IE!

ATTACHMENT D yO ra ,e 7 -

WS Es -Vi h

OPERATION SUPPORT CENTER COORDINATOR CHECKLIST INIT (1) Coordinate activities of plant personnel in the OSC.

(2) Designate an individual (s) to establish cammunication between OSC, TSC and Control Room.

(3) Activate and verify proper operation of Vamp (F3-7, Section 4.2.1)

(4) Activate & verify proper operation of the Control Room CAM (F3-7, Section 4.2.2)

(5) Issue dosimetry to OSC and Control Room Personnel.

, (6) Designate an individual (s) to control use of equipment in Emergency Lockers.

(7) When a plant evacuation occurs, (a) Ensure all OSC personnel insert their badges into the OSC card reader. Inform the Emergency Director upon completion.

(b) Designate an individual to perform a Control Room account-ability and transfer accountabiltiy sheet to the Emer-gency Director.

(8) Evacuate all unnecessary personnel.

(9) Control use of food in OSC until directed by Radiation Protection Group.

(10) Establish a routine sampling and monitoring of OSC and Control Room as necessary.

(11) Periodically update Status Board and Personnel.

(12) Review F3-4 & F3-7.

OSC Coordinator Date/ Time IBM

PAGE 1 OF 41 l l EMERGENCY PLAN IMPLEMENTING l r l PRAIRIE ISLAND NUCLEAR PROCEDURES l

\ l GENERATING PLANT l l NORTHERN STATES POWER COMPANY Number: F3-5 Rev: 7 l l History Copy l l /T , , _ Retention Time: Lifetime l l TITLE:

l Supt. Qd~ Protect 'n l l l Approved By: (c/ ) l EMERGENCY NOTIFICATIONS l ( ,o Plan FManager f)b i l

l l

l 1

/'

l l

l OC Date: 3- M T3 l l l l l l 1 l l l 1.0 PURPOSE l l l-l This instruction delineates the notification procedures to be used l l during emergency conditions, definen the various emergency communica- l l tions systems available at the plant, (primary and backup), and l l provides the necessary operating instructions for their proper use. l I l l 2.0 APPLICABILITY l l l

, l This instruction SHALL apply to all Radiological Emergency l l Coordinators, Shift Supervisors, Emergency Directors and Shift l l Emergency Communicators. l l l l 3.0 PRECAUTIONS l 1 l l 3.1 Always speak in a clear, distinct voice. l l l l 3.2 Make messages as short and concise as possible. l l l l 3.3 Always have the information repeated if it was not completely l l understood. l l 1 l 4.0 PROCEDURE l l l l 4.1 Shift Emergency Communicator (SEC) Responsibilities: l l l l 4.1.1 Report to the Control Room l l l l 4.1.2 Complete the " Emergency Notification Report Form", l l Figure 1, (PINGP #577) with assistance from the l l Emergency Director or Shift Supervisor. l l l l 4.1.3 Upon completion of the " Emergency Notification Report l l Form", (PINGP #577) report to the communications area l l of the Technical Support Center. l l l l l l l l .

l l !

l l IBM l

~

i , ,

, F3-5 j Rev. 7 PAGE 2 4.1.4 Request the telephone switchboard operator to transfer control of the switchboard to the TSC and request that individual to report to the TSC to control the switch-board until relieved by a backup communicator, or the emergency situation is terminated.

I I l NOTE: Refer to the Nuclear Emergency Preparedness l l Telephone Directory for specific telephone l l locations and numbers. l l l 4.1.5 Initiate and complete the notifications of state, local, and NSP personnel as listed on the Emergency Notification Call Lists, as follows:

(a) For a Notification of Unusual Event, use Figure 3, PINGP #579.

(b) For an Alert, Site Area, or General Emergency, use Figure 4, PINGP #580.

4.1.6 Request local offsite support as deemed necessary.

Coordinate these notifications with the control room.

(Refer to the Nuclear Emergency Preparedness Telephone Directory for local support telephone numbers.) ~

s J

4.1.7 If the emergency has been reclassified, (i.e.,

escalated, down graded,'or terminated) complete the Emergency Classification Change, Figure 2, PINGP #578 and complete the notifications of offsite authorities as follows:

(a) For a termination from a Notification of Unusual Event, use Figure 3, PINGP #579.

(b) For any classification change, use Figure 4, PINGP #580.

4.1.8 When the EOF becomes activated, transfer control of Offsite Notifications to the EOF.

4.2 Radiological Emergency Coordinator (REC) Responsibilities:

4.2.1 Complete the Emergency Notification Followup Message Form, Figure 6, PINGP #582.

l l l NOTE: This form does not need to be completed in l l its entirety prior to transmitting data to l l offsite authorities. I i l IBM

F3-5 Rev. 7 PAGE 3 I

4.2.2 Periodically update the Minnesota Department of Health and the Wisconsin Division of Radiation Protection with the information as recorded on Figure 6, PINGP #582 the

" Emergency Notification Followup Message".

I i

l NOTE: When the Nearsite EOF is activated, updates l l to the Minnesota Department of Health and l l

Wisconsin Division of Radiation Protection l l will be handled by EOF personnel. l l

l 4.2.3 Acknowledge the HPN phone when it rings and periodically, update the NRC with the information as recorded on Figure 6, PINGP #582 the " Emergency Notification Followup Message".

I I

l NOTE: Be prepared to provide continuous updates l l to the NRC, as requested over the liPN phone. l l

1 4

J d

IBM

PINGP #577, Rsv. 1 F3-5 Rev. 7 PAGE 4 FIGURE 1 INITIAL EMERGENCY NOTIFICATION REPORT /

Verify that the organization / person called is correct prior to relaying emergency information.

THIS IS , SHIFT EMERGENCY COMMUNICATOR AT THE (Name)

PRAIRIE ISLAND NUCLEAR GENERATING PLANT.

WE HAVE DECLARED A(N) AT HOURS.

(Emergency Class) (Time)

Pick one of the following:

I I WE HAVE NOT HAD A RADI0 ACTIVE RELEASE.

I I WE HAVE HAD A(N) RADI0 ACTIVE RELEASE.

(Liquid or Airborne)

ATMOSPHERIC CONDITIONS AT THE PRESENT TIME ARE AS FOLLOWS:

WIND DIRECTION IS FROM THE AT MPH.

(Direction) (Speed)

THE AFFECTED SECTOR (S) IS(ARE) .

9 (List sector (s) by letter designation)

THE PRCTECTIVE ACTION RECOMMENDED AT THIS TIME IS:

1 I NONE I I SHELTER IN SECTORS OUT TO MILES I I EVACUATE IN SECTORS OUT TO MILES I l ACTIVATE THE PUBLIC NOTIFICATION SYSTEM Give a brief description of the emergency. &l@l.E Ohi!.Y qq

($tul C 9 "Il It '2 Y O ';n ":)n n 7 m ,

S M 1.51 ~ id$WJM f,f, PLEASE RELAY THIS INFORMATION TO YOUR EMERGENCY ORGANIZATION PERSONNEL.

Emergency Director Approval

Name/Date Shift Emergency Communicator Name/Date

{

IBM

PINGP #578, Rev. 1 F3-5 Rev. 7 PAGE 5 FIGURE 2 EMERGENCY CLASSIFICATION CHANGE Verify that the organization / person called is correct prior to relaying emergency information.

THIS IS , SHIFT EMERGENCY COMMUNICATOR AT THE (Name)

PRAIRIE ISLAND NUCLEAR GENERATING PLANT.

WE HAVE RE-CLASSIFIED THE EVENT AND l l Escalated l I Down graded .

l l The Event May Be Terminated TO A(N): (Pick one below if escalated or down-graded is checked) l I Notification of Unusual Event

' ' ^'"'

I I Site Area Emergency EX. AMPLE 3E" I ! General Emergency u AT HOURS (Time)

Atmospheric Conditions at the Present Time Are as Follows:

Wind Direction is From the at MPH.

(Direction) (Speed)

The Affected Sector (s) is(are)

(List Sector (s) by Letter Designation)

Form of Precipitation (if applicable)

Give a brief description of the emergency:

PLEASE RELAY THIS INFORMATION TO YOUR EMERGENCY ORGANIZATION PERSONNEL.

Emergency Director Name/Date Shift Emergency Communicator Name/Date IBM

4 PINGP #579, Rsv. 3 F3-5 Rev. 7 PAGE 6 FIGURE 3 EMERGENCY NOTIFICATION CALL LIST FOR A ~'

NOTIFICATION OF UNUSUAL EVENT GENERAL INSTRUCTIONS (1) The Shift Emergency Communicator SHALL make notifications to the individuals and organizations listed on this Emergency Call List.

(2) Contact each organization or individual using the contact information listed in this Attachment.

(3) For those notifications made by telephone, make the call as follows:

I l l NOTE: All primary contacts <:ontained in this checklist have l 3 l pre-programed telephone numbers on the Touch-A-Matic l l l dialars. Alternate or backup telephone numbers must be l l manually dialed. l l l

a. When the party answers, read the text of the Initial Notification Report Form.

b. Note the name of the individual contacted and the time of the contact.

(4) For those notifications made by NAWAS, transmit only the information as specified in this procedure. Specific plant data, as specified on the Initial Notification Report Form, will be available to those authorities when they call back for a verification.

(5) Proceed to the next party on the call-list.

(6) If a party cannot be contacted in two attempts, use alternate or backup communication channels. If a party still cannot be reached, consider other means such as <'.ispatching a courier, relay through another party or similar actions.

(7) The Wisconsin Division of Emergency Government (DEG) and the Minnesota Division of Emergency Services (DES) are required to call back for verifi-cation and/or request further information. Other emergency organizations, e.g., Minnesota and Wisconsin Health Departments may call the plant for more information. Update these organizations, as appropriate. Use the Contact Report Log, PINGP #597 or the verification signoffs in this checklist to note the time and the names of the individuals calling.

(8) If a party not specified on the call list requests information, refer the party to the NSP Communications Department or to the local emergency services organization in his/her community, as appropriate.

EXAMPLE ggty IBM mr -

M1 b- '

PINGP #579, Rev. 3 F3-5 Rev. 7 PAGE 7 FIGURE 3 (Continued)

EMERGENCY NOTIFICATION CALL LIST FOR A t' NOTIFICATION OF UNUSUAL EVENT -

O ,_

NOTIFICATIONS

'%o 7O FD m

e '

f' WA lu bl (1) Notify the Minnesota Division of Emergency Services. The telephone , ,,

number iDEWEDiight or day. (Ask for the Duty Officer)

Contact Time Person Initial Verification Notification- Time /SEC Initials SEC INITIALS I ~

l l NOTE: (1) This notification shall be c:ade within 15 minutes l l of declaration of emergency class. l l (2) If NO verification is received within 30 minutes, l 1 contact the state again. l l (3) If the telephone system malfunctions, attempt to l I relay emergency notifications to the DES via the l l NSP system dispatcher. l l

1 (2) Using the NAWAS network, notify the Wisconsin authorities in accordance with the following procedure:

a. Pick up the NAWAS set, press the talk button and say:

"THIS IS PRAIRIE ISLAND NUCLEAR PLANT CALLING WISCONSTN WARNING CENTER ONE, WEST CENTRAL WARNING CENTER AND PIERCE COUNTf WARNING CENTER, ACKNOWLEDGE." '

b. When warning center one, west central warning center and Pierce ,

County warning centers acknowledge, press the talk switch and say:

PRAIRIE ISLAND NUCLEAR PLANT IS (Pick correct classification):

EXPERIENCING A NOTIFICATION OF UNUSUAL EVENT.

TERMINATING THE NOTIFICATION OF UNUSUAL EVENT.

RELAY THIS INFORMATION TO EMERGENCY GOVERNMENT IMMEDIATELY."

Warning Center I Time Initial Verification Notification- Time /SEC Initials SEC Initials West Central Warning Center Time Inital Notification-SEC Initials IBM

pit *GP #579, Rev. 3 F3-5 Rev. 7 -

, FIGURE 3 (Continued)

EXAMPLE DE.Y,,

~'

EMERGENCY NOTIFICATION CALL LIST FOR A h_ 3 NOTIFICATION OF UNUSUAL EVENT o Q') b Pierce County Warning h f Center Time * "; Tltt f ^ " ^ ' - uvA Notification-SEC Initials l l l NOTE: (1) This notification SHALL be made within 15 l l ainutes of declaration of emergency class. l l (2) If area or county warning centers do not l l acknowledge, Wisconsin Warning Center I, II or l l III will ring on the circuit and relay the l l message to appropriate warning centers. l l (3) If the NAWAS System should become disabled, l l alternate methods of notification to Wisconsin l l as follows: l l t authorities (a) Wisc. DEG should be attempted,DELETEDi

-- Telephone -- l l (b) West Central Warning Center -- Telephone -- l l

(c) l l

Pierce County or -- Telephone - DELETED { ll l l Radio - Channel 1 l l l T (3) Notify the local authorities by telephone as follows:

V

., (a) GOODHUE COUNTY SHERIFF ATDELETED Contact Time Initial Notification-SEC Initials l I l NOTES: (1) This notification SHALL be made within l l 15 minutes of declaration of emergency class. 1 I I l (2) Alternate means to communicate with the Goodhue l l County Sheriff is the Radio System - Channel 1. 1 I I (b) DAKOTA COUNTY SHERIFF AT Contact Time Initial Notification-SEC Initials V

IBM l

PINGP #579, Rev. 3 F3-5 Rev. 7 PAGE 9 FIGURE 3 (Continued)

EMERGENCY NOTIFICATION CALL LIST FOR A NOTIFICATION OF UNUSUAL EVENT I

I l NOTES: (1) This notification SHALL be made within 15 l l minutes of declaration of emergency class. l l

1 l

(2) Alternate means to communicate with the Dakota l l County Sheriff should be at. tempted in the l 1 following orderg g L g'j g g l l a. Telephone - l l b. Radio System - Channel 1 l l c. Point-t'o-Point relay via Goodhue Sheriff. l l

I (4) Notify the Plant Manager (or designee) if not already done so, to infor.n him of the situation (notify one of the following in the order shown):

Name Home Phone

~ DELETED /

~ ' .,

' Time / SEC Initials DELETED /

l Time /SECInitials 1

DELETED Time

/

/ SEC Initials

( DELETED

.f Time / sEC laitials l' l l NOTE: .The Plant Manager pager number is lThepager l l should be used as a backup means of notifying the Plant l l Manager. The pager is passed down the line of succes- l l l sion when the Plant Manager is unavailable. l l

1

! (5) Notify the NSP System Dispatcher ( DELETED ) and inform

him of the situation.

/

Time / SEC Initials l I l NOTE: Alternate means to communicate with the NSP System Dis- l l patcher should be attempted in the following order: l l (1) Telephone: I l (2) Telephone: DELETED ' l l l (3) Control Room Hotline l l (4) Low Band Radio Telephone l l I EXAM?M ONLY

! 181 OMl? BIT @R

e s PINGP #579, Rev. 3 F3-5

. e Rev. 7 .

PAGE 10

' FIGURE 3 (Continued)

EMERGENCY NOTIFICATION CALL LIST FOR A (

NOTIFICATION OF UNUSUAL EVENT (6) Notify ONE of the NRC Resident Inspectors: .

DELn.1ED 1 l /

or Time /SEC Initials DELETED l

/

Time SEC Initials (7) Contact

DELc. A EO l' District Manager to inform him of the emergeacy situation.

I t DELETED j f Time / SEC Initials (8) Update the Radio Alert Monitor System Message Cassette as follows:

(a) Insert a blank tape into the tape recording unit.

(b) Make sure that the remote control unit ' Mike Enable' & 3

' Transmit Enable' key switches are both off (Green).

(J (c) Set tape unit selector switch to ' Record Announcement'

- insert microphone in tape unit mike jack.

(d) Press tape unit ' Start' switch and record the prepared message.

l l l NOTE: (1) Information to be recorded should include the l l date, time and unit status. l l (2) When recording the message, speak slowly and l l clearly, about 3 inches from the microphone. l l l (e) Set tape unit selector switch to ' Check Announcement' press ' Start' switch and listen to recording. (Adjust volume to desired level with tape unit ' Monitor Volume' Control.) If satisfactory, proceed with (f).

(f) Now, remove the message cassette from the tape unit and insert it into the telephone answering unit. /

Time SEC Initials EXAMPLEm OM.Y

'ag k C)

IBM

PINGP #579, Rev. 3 F3-5 Rev. 7 PAGE 11

( FIGURE 4 EMERGENCY NOTIFICATION CALL LIST FCR_A NOTIFICATION OF UNUSUAL EVENT (9) Notify or verify the Control Room has established notification of the NRC Emergency Response Center via the ENS Hotline. /

Time / SEC Initials l l l NOTES: (1) Notification of NRC required to be made within l 1 one hour of event declaration. l l -

1 l (2) If the ENS Network should become disabled,' alternate l l methods of NRC notification should be attempted in l l the following order: l l l l (a) Commercial Telephone System 202/951-0550 l l to NRC Operations Center l 3

l (Via Bethesda Central Office) l g g l (b) Commercial Telephone System 301/427-4056 l l to NRC Operations Center l l (Via Silver Spring Central Office) l

(' l l l (c) Health Physics Network to l l NRC Operations Center 22 (Rotary Dial) l 1 l l (d) Commercial Telephone System 301/492-7000 l

] to NRC Operator l l (Via Bethesda Central Office) l 1 I (10) Inform the Shift Supervisor of the completion of the notifications. /

Time /SEC Initials CALL LIST COMPLETE: TIME DATE SHIFT EMERGENCY COMMUNICATOR

.t 1 IBM M B E si r Jd H H

i <

PINGP #580, Rev. 3 F3-5 Rev. 7 FIGURE 4 so.uvu.h . . . ,

fWU1' a

EMERGENCY NOTIFICATION CALL LIST FOR AN q TU7 t ALERT, SITE AREA, OR GENERAL EMERGENCY _ C GENERAL INSTRUCTIONS h (1) The Shift Emergency Communicator SHALL make notitications to the individuals and organizations listed on this Emergency Call List.

(2) Contact each organization or individual using the contact information listed in this Attachment.

(3) For those notifications made by telephone, make the call as follows:

I l

l NOTE: All primary contacts contained in this checklist have l l l pre-programed telephone numbers on the Touch-A-Matic l '

l dialers. Alternate or backup telephone numbers must be l l manually dialed. l l

l

a. When the party answers, read the text of the Initial Notification i Report Form.

b. Note the name of the individual contacted and the time of the ,

contact.

(4) For those notifications made by NAWAS, transmit only the information as specified in this procedure. Specific plant data, as specified on the Initial Notification Report Form, will be available to those authorities when they call back for a verification.

(5) Proceed to the next party on the call-list.

(6) If a party cannot be contacted in two attempts, use alternate or backup

. communication channels. If a party still cannot be reached, consider other means such as dispatching a courier, relay through another party or similar actions.

(7) The Wisconsin Division of Emergency Government (DEG) and the Minnesota Division of Emergency Services (DES) are required to call back for verification and/or request further information. Other emergency organizations, e.g., Minnesota and Wisconsin Health Departments may .

call the plant for more information. Update these organizations, as appropriate. Use the Contact Report Log, PINGP #597 or the verifica-tion signoffs in this checklist to note the time and the names of the individuals calling.

(8) If a party not specified on the call list requests information, refer the party to the NSP Communications Department or to the local emergency services organization in his/her community, as appropriate.

IBM

PINGP 1580, Rev. 3 F3-5 Rev. 7

(*.

FIGURE 4 (Continued) EXAM"#f* c.9 y

'"i '* m EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY fui ju f b

(1) Notify the Minnesota Division of Emergency Services. The telephone number iOELETEGight or day. (Ask for the Duty Officer) bkE? kh[Q Contact Time Initial Verification Person Notification- Time /SEC Initials SEC INITIALS I

I il NOTE:- (1) This notification whall be made within 15 minutes l of declaration of emergency class. l l (2) If NO verification is received within 30 minutes, I l contact the state again. I l (3) If the telephone system malfunctions, attempt to l l relay emergency notifications to the DES via the l I hSP system dispatcher. l l

l (2) Using the NAWAS network, notify the Wisconsin authorities in accordance k with the following procedure:

a. Pick up the NAWAS set, press the talk button and say:

I

! "THIS IS PRAIRIE ISLAND NUCLEAR PLANT CALLING WISCONSIN WARNING i CENTER ONE, WEST CENTRAL WARNING CENTER AND PIERCE COUNTY WARNING CENTER, ACKNOWLEDGE."

t

b. When Warning Center One, West Central Warning Center and Pierce County Warning Centers acknowledge, press the talk switch and say:

" PRAIRIE ISLAND NUCLEAR PLANT IS EXPERIENCING A(N) (Pick the correct class):

O ALERT, or O SITE AREA EMERGENCY, er O GENERAL EMERGENCY l

RELAY THIS INFORMATION TO EMERGENCY GOVERNMENT IMMEDIATELY."

Warning Center I Time Initial Verification j

Notification- Time /SEC Initial SEC Initials

(

IBM

i .

PINGP #580, R:v. 3 F3-5 Rev. 7 e .

PAGE 14

' FIGURE 4 (Continued)-

EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY

(

West Central Warning Center Time Initial Notification-SEC Initials

' Pierce County Warning Center Time Initial Notification-SEC Initials l NOTE: (1) This notification SHALL be made within 15 l l minutes of declaration of emergency class. l l (2) If area or county warning centers do not l l- acknowledge, Wisconsin Warning Center I, II or l l III will ring on the circuit and relay the l 1 message to appropriate warning centers. l l (3) If the NAWAS System should become disabled, l

, l alternate methods of notification to Wisconsin l l authorities should be attempted, as follows: l

l (a) Wisc. DEG -- Telephone - . DELETED I l (b) We , Warning Center -- Telephone -- l l

l (c) Pierce County -- Telephone - . DELETEC l 7

, l or l y' l Radio - Channel 1 l l

1 (3) Notify the local authorities by telephone as follows:

(a)

GOODHUE COUNTY SHERIFF AT' DELETED.{

Contact Time Initial Notification-SEC Initials l NOTES: (1) This notification SHALL be made within l l 15 minutes of declaration of emergency class. l l

(2) Alternate means to communicate with the Goodhue l 1 County Sheriff is the Radio System - Channel 1. l I I (b) DAKOTA COUNTY SHERIFF AT DELETED Contact Time Initial Notification-SEC Initials EXAMPLE OMLY t m h e

[Hir FN @ H .

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

PINGP #580, Rev. 3 F3-5 Rev. 7

.I PAGE 15

\ .

N.

FIGURE 4 (Continued)

EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY 1

1 l NOTES: (1) This notification SHALL be made within 15 l l minutes of declaration of emergencf class. l 1

l l

(2) Alternate means to communicate with the Dakota l l County Sheriff should be attempted in the l l following order: l l a. Telephone -OELETED l l b. Radio System - Channel 1 l l c. Point-to-Point relay via Goodhue Sheriff. l l

l l

l

, l NOTE: IF THE EMERGENCY RESPONSE ORGANIZATION HAS PREVIOUSLYl

., l- BEEN ACTIVATED BY THIS CHECKLIST, THE FOLLOWING STEPS l l NEED NOT LE COMPLETED FOR FURTHER ESCALATIONS. l

. l l

' (4) Notify the Plant Manager (or designee) if not already done so, to inform him of the situation (notify one of the following in the order shown):

Name H,eme Phone bELETEC '

/

p Time / SEC Initials DELETZP ! /

Time / SEC Initials D E Lt..1 E D } /

Time / SEC Initials DELETED /

Time / SEC Initials l

I l NOTE: The Plant Manager pager number isDELETEmThe pager I l should be used as a backup means of notifying the Plant l l Manager. The pager is passed down the line of succes- l l sion when the Plant Manager is unavailable. I l

l (5) Notify the NSP System Dispatcher (Telephone NooELETEPand inform him of the situation.

y, . : ., Time / SEC Initials

e. .,

p

'0I v l1

_L.

PINGP #580, Rev. 3 F3-5 Rev. 7 .

PAGE 16 FIGURE 4 (Continued).

EMERGENCY NOTIFICATION CALL LIST FOR AN k ALERT, SITE AREA, OR GENERAL EMERGENCY I

I l NOTE: Alternate means to communicate with the NSP System Dis- l l patcher should be attempted in the following order: l l (1) Telephone: g l l (2) Telephone: l l (3) Control Room Hotline l l (4) Low Band Radio Telephone l l

l (6) Notify ONE of the NRC Resident Inspectors:

DELETED > /

Time /SEC Initials or DELETED I

, i /

Time SEC Initials (7) Activate the Emergency Response Organization as follows:

(a) Normal Work Hours

', (1) Verify announcement to report to emergency response centers is made over public address system.

Time /SEC Initials (2) Contact the PI Training Center by telephonuELETED inform them of the emergency classification and request them to report to the EOF.

Time /SEC Initials l NOTE: Alternate numbers should be attempted in the l l following order:

gg l DELETED l 1

I (3) ContacttheNuclearTec_hycalServicesGroupby telephone (; 2LEThk ), inform them of the emergency c,lassification and request them to report to the EOF.

QfpF Time /SEC Initials bdvf ~ , nt M y pg

+

1

.a s

- ,. y g ... y d bblJi'3thJ d UUb Q yy[j IBM

PINGP #580, Rev. 3 F3-5 Rev. 7 PAGE 17

(

FIGURE 4 (Continued)

EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY I NOTE: Alternate numbers should be attempted in the l l following orderDELETED I I l l 1 (4) Contact DELETED .

designee by phone otstrict Manager, or his p g L g 7 E g ' inform him of the emergency classification.

Time /SEC Initials (b) Off-Normal Work Hours l I I NOTE: NSP personnel and Civil Defense personnel l l SHALL be. activated by this callout during l l off-normal work hours. I I

.'* I (1) Insert the pre-recorded tape designated "ERO Callout" into the tape unit.

, (2) Set the tape unit selector switch to " Answer".

(3) Turn the message transmitter control unit " Transmit

~

Enable" key switch to the ON position. The red "XMIT" lamp should light.

(4) Enter Code 04 on the encoder unit and press "P".

As soon as the tones.are completed, enter Code 06 and then press "P".

l NOTE: Several seconds after the last tone is I l heard, the tape will be transmitted i

! l 3 times - then the unit will shut off. l l l (5) Verify proper operation of the radio alert monitor

system by acknowledging that the TSC Radio Alert Monitor did activate.

If not, repeet steps (1) through (4).

f

' 4 h.I 8 (lT;' 2

. .Y IBM l.5LO I. b.l$1'/db)bd i

PINGP #580, Rev. 3 F3-5 Rev. 7 .

PAGE 18

' FIGURE 4 (Continued)

EMERGENCY NOTIFICATION CALL LIST FOR AN (~

ALERT, SITE AREA, OR GENERAL EMERGENCY (6) If the radio alert system failed to function after 2 attempts, use the Emergency Organization Call List, Figure 5 and call all Emergency Organization Members by telephone.

(7) When tne transmission has ended, turn the " Transmit Enable" key switch to the OFF position.

(8) Remove the message cassette from the tape unit and replace in cassette storage rack.

Time /SEC Initials (8) Notify the Local Residents as follows:

(a) . Insert the pre-recorded tape designated " Local Notifications" into the tape unit.

(b) Set the tape unit selector switch to " Answer".

(c) Turn the message transmitter control unit " Transmit Enable" key switch to the ON position. The red

, "XMIT" lamp should light.

(d) Enter Code 01 on the encoder unit and press "P". \m

'. 1 I I NOTE: Several seconds after the last tone is l l heard, the tape will be transmitted l l 3 times - then the unit will shut off. l '

I I (e) Verify proper operation of the radio alert monitor system by acknowledging that the TSC Radio Alert Monitor did activate. If not, repeat steps (a) through (d).

(f) If the Radio Alert System failed to function after 2 attempts, attempt to notify one of the following local residents by telephone:

DELETED !

or; f fM7.1 f pt1q 3 o- w . '

DELETED : , , .,

r.

(g) When the transmission has ended, turn the "Tracemit .

rg Enable" key switch to the OFF position. 'clGLglu; i

JO t'/lj IBM

PINGP 6580, Rev. 3 F3-5 Rev. 7 4

PAGE 19

( FIGURE 4 (Continued)

EMERGENCY NOTIFICATION CALL LIST FOR AN ALERT, SITE AREA, OR GENERAL EMERGENCY (h) Remove the message cassette from the tape unit and insert it into the telephone answering unit.

Time /SEC Initials (9) During Off Normal Work Hours ONLY, NOTIFY NSP RED WING SERVICE CENTER BY TELEPHONE AT DELET REQUEST THE RED WING NSP SUPERVISOR ON DUTY TO REPORT TO THE NSP RED WING SERVICE CENTER TO UNLOCK THE FACILITIES FOR TIC NSF RADIATION SURVEY TEAMS.

Time /SEC Initials (10) Notify or verify the Control Room has established notification of the NRC Emergency Response Center via the ENS Hotline.

Time /SEC Initials l

l NOTES: l.

(1) Notification of NR0 required to be made within l

' l one hour of event declaration. l I

i l (2) If the ENS Network should become disabled, alternate l 1 methods of NRC notification should be attempted in l l the following order:

l I

I l (a) Commercial Telephone System 202/951-0550 l l to NRC Operations Center l l (Via Bethesda Central Office) l l

l l (b) Commercial Telephone System 301/427-4056 l l to NRC Operations Center l l (Via Silver Spring Central Office) l l

l l (c) Health Physics Network to l l NRC Operations Center 22 (Rotary Dial) l I

I l (d) Commercial Telephone System 301/*92-7000 l l to NFC Operator l 1

(Via Bethesda Central Office) l l

I (11) Inform one Westinghouse contact, using the list in the order shown, to ensure early notification to W of an emergency occurring at the plant.

Be prepared to discuss as many facts as are available at the time of L , .

enre G.G

.r,a r; as, ,

FINGP #580, Rev. 3 F3-5 Rev. 7 -

FIGURE 4 (Continued)

EMERGENCY NOTIFICATION CALL LIST FOR AN

'EXFLe.1Ls.bM N--

ALERT, SITE AREA, OR GENERAL EMERGENCY r uum l NOTE: Unless indicated otherwise, all phone @ b dj A f d y c @

m-C j l 412. Where an area code other than 412 is shown, it l applies to the office, home, and HHL numbers. l 1 l Title Name Office /Home/HHL Site Services Representative !

Operating Plant Regional DEbN ,

Manager 1st Alternate 'OELETED l 2nd Alternate Service Response Manager l 1sc Alternate DELETED j

~

2nd Alternate Emergency Response Director DELETED I Emergency Response Deputy Director CELETED j

Emergency News k

Communications DELETED W Contact /

Time /SEC Initials (12) Notify American Nuclear Insurers (ANI) by Telephone -

DELETED ' (24-Hour Number) /

Time /SEC Initials l NOTES: (1) During Normal Office Hours (8:00 a.m. - 4:00 p.m.), j l this number will be answered by a receptionist who l l will transfer the call to an appropriate individual. l l l l l

l (2) During Off Normal Office Hours, an answering machine l l l will intercept the call and notify a designated l l l ANI Staff Member. Please leave your name, company, l l l and telephone number. The ANI member will return l l l the call to obtain further information. l l 1 (13) Inform the Emergency Director of the completion of the notifications. /

Time /SEC Initials CALL LIST COMPLETE: TIME DATE

(

SHIFT EMERGENCY COMMUNICATOR IBM

=-

\

PINGP #581, Rev. 1 F3-5 Rev. 7 1

PAGE 21 FIGURE 5 EMERGENCY ORGANIZATION CALL LIST INSTRUCTIONS (1) This call list SHALL be : sed to activate the ONSITE Emergency Response Organization during off-normal work hours, should the Radio Alert Monitor System Fail.

(2) Use the following notification guidelines:

(a) Contact each individual in the order shown; (b) When the individual answers, request that individual to report to the plant; (c) Proceed to the next individual on the call list; (d) If an individual cannot be contacted in two attempts, bypass that individual and proceed down the list. After the other individuals.

notifications are complete, re-attempt h., Q/ + to (@RSq p@':j bfhe y

[

NOTIFICATIONS Plant Management (OC Members) r p ;r p. . ,

l PLANT MANAGER DELETED,1 PLT SUPT ENGR & RAD PROT PLT SUPT OPER & MAINT OELETED SUPT RAD PROTECTION D-

- DELETED l SUPT MAINT SUPT OPER ENGR kg),

SUPT OPERATIONS ED f SUPT QUALITY ENGR l SUPT TECH ENGR I DELETED '

SUPT NUC ENGR Radiation Protection Group DE W ED' RAD PROT SPEC RAD PROT SPEC -

RAD PROT SPEC DELc1ED

'%AETdo ,

I RAD PROT COORD CHEMIST k,(7 RAD PROT SPEC kg '

DELETED [ RAD PROT SPEC

. RAD PROT SUPV DELETEDl TRAINING INSTRUCTOR Rf RADIO-CHEMISTRY SUPV CELETED I RAD PROT SPEC RAD PROT SPEC RAD PROT SPEC CELEAM RAD PROT COORD b- '

RAD PROT SPEC' r.5LETED RAD PROT SPEC RAD PROT SPEC IBM

PINGP #581, Rev. 1 F3-5 Rev. 7 -

FIGURE 5 (Continued)- EXAMR2 DRY ,

EMERGENCY ORGANIZATION CALL LIST Radiation Protection Group (Continued) "

d j Y 2 RAD PROT SPEC ,

i U U' d QUALITY SPEC C d

RAD PROT SPEC RAD PROT SPEC '

k'

$ ~ 'f, RAD PROT SPEC '

! RAD PROT SPEC '

SENIOR PROD ENGR 3 Maintenance / Electricians ,

i MAINT SUPV 1

MAINT SUPV i

,_ MAINT SUPV !

7E'E 8 C.D I MAINT SUPV

{

CHIEF STATION ELECT l'

?

g l}'

STATION ELECT

~~

l

STATION ELECT

. I & C Group

'T I & C SUPV V

DELETED ! I & C C00R DELETED l ?

I & C C@R Engineers J ENGINEER DEL.*TED a! ASSOC PROD ENGR ASSOC PROD ENGR I LEAD PROD ENGR .

I

- i ASST PROD ENGR ASST PROD ENGR T{ I ASSOC PROD ENGR ASSOC PROD ENGR l ;

) LEAD PROD ENGR i LEAD PROD ENGR l

EOF Coordinator W8"O LEAD PROD ENGR kg l OPERS INSTRUCTOR PROD ENGR kQ l

1

(

l IBM l

1

a .

PINGP #581, Rev. 1 F3-5 Rev. 7 PAGE 23 1

FIGURE 5 (Continued)

EMERGENCY ORGANIZATION CALL LIST I

ENGR ASSOC OPERS INSTRUCTOR Og[ INSTRUCTOR GENERAL SIMULATOR SUPERVISOR Q b gT60,'

SUPT NUC TECH SERVICES .

ENGR ASSOC ,

I TRAINING ENGR i !

- "I i SUPT TRAINING 4

,h gggQ ',

' LEAD PROD ENGR OPERS INSTRUCTOR ggk7 INSTRUCTOR SUPV l

- ,' 'i

'..3 ' 4 . , ,. . L., : )

A

, , pr : m r-~,r- . m - -. ...mp a .

k .

COMPLETED: DATE TIME SHIFT EMERGENCY COMMUNICATOR l

IBM

PINGP #582, Rev. 1 F3-5 Rev. 7 -

PAGE 24 FIGURE 6 '

EMERGENCY NOTIFICATION FOLLOWUP MESSAGE

Sample Time AM/PM

! l~~ - " :'

1. Locat' ion of incident.f Prairie Island ,.~,7,,-,,..,..,7., ',.y

2. Class of emergency: ljN -

C'.)J . 1.

3. Type of release ( ) actual or ( ) potential:

( ) airborne () waterborne ( ) surface spill

4. Height df release: () groand level Relative % Noble Gases uCi/sec Quantity: % Iodines uCi/sec

% Particulates uCi/sec Estimated quantity of radioactive material released or being released: curies e 5. Meteorological Conditions: Wind Velocity sph ,

V Wind Direction (from): degrees Temperature 'C

] Atmospheric Stability Class Form of precipitation

6. Release is expected to continue for hours.

7. Projected Whole Body Thyroid Sectors Affected dose rates: S.B. mrem /hr mrem 2 miles mrem /hr mrem 5 miles mrem /hr mrem i 10 miles mrem /hr mrem Project S.B. mrem mrem l integrated 2 miles mrem mrem l dose at: 5 miles mrem mres 10 miles mrem mrem l

Complete as much of the form as information availability and time allows.

l All blanks need not be completed.

L IBM

~

e PINGP #582, Rev. 1 F3-5 Rev. 7 PAGE 25

( FIGURE 6 (Continued)

EMERGENCY NOTIFICATION FOLLOWUP MESSAGE *

8. Survey Results SURVEY TIME POINT READING EYEMD5 E OME U E= H h..' ! !6% Qs);L [

. ,m -m li]!lliW liHF.Ev.T T

9. Estimate of any surface radioactive contamination: dps/100 cm

10. Chemical and physical form of released material:

. 11. Emergency response actions underway:

12. For liquid release to the river, estimate release volume, release activity and estimated time for concentration to reach public water:

13. . Recommended emergency actions, including protective actions:

14. Request for any_needed support by offsite organizations:

l

15. Prognosis for worsening or termination of event. based on plant information:

Emergency Director l

b l IBM 1

F3-5 Rev. 7 -

PAGE 26

. ATTACHMENT A

(

TELEPHONE COMMUNICATIONS NETWORK I. SITE TELEPHONE COMMUNICATIONS

1. Dimension 2000 PBX Normal communications are provided by a Dimension 2000 PBX.

Three separate Dimension PBX attendent consoles are used in the system. All have identical functions and only one ca'n be operational at a time. For normal business hours, all incoming calls are answered by the receptionist located on the 5th floor of the Administration Building. During backshifts and weekends, the console at the secondary alarm station is activated. The third console, located in the Technical Support Center Communications area, will be activated during emergency plan implementation.

The Dimension System controls approximately 265 main stations and 75 extensions. It is designed with a high degree of fault i

detection and diagnostic capabilities. Additional reliability is provided by a backup duplicate common control unit. If there are certain PBX failures or power failure, all stations would normally be inoperative. However, automatic operation of transfer relays in the emergency transfer panels bridge preassigned stations directly to the trunk lines. Assigned (;~)

stations are located in control rooms, shift supervisors office, access control, administrative office, and technical support center. A key switch to manually cut over these preassigned stations is located within the telephone equipment room if the need exists.

Terminated within the Dimension System are 7 trunk lines and 7 tie lines. The trunk lines are ' ' "hi*h CEDis incoming only, while OEb"iED '

have incoming E)pREE"outgoingcapabilities. The seven two-way tie lines connect the Dimension 2000 PBX to the general office exchange via the NSP microwave relay system.

Normal power for the system is provided by an instrument inverter which in turn is supplied by a diesel backed 480 VAC safeguards

~

j motor control center and a 125 VDC station battery. An alternate

! source is provided by a SKVA 480/120V transformer supplied by the 480 VAC diesel backed safeguards motor control center.

2. Gai-Tronics Page System Gai-Trouies paging system is also available and is used to call personnei over the plant and yard spear.ers as well ar to issue plantwide instructions from GTC sta_tions located throughout the (, .

plant. This system is tied to the' Dimension 2000 PBX, making access to the paging system possible from all telephone IBM

e 1 i

F3-5 ATTACHMENT A (Continued) Rev. 7

. PAGE 27

/

stations on site. Any one station tying up access to the paging system can be overridden with the executive override function from the operators console or the plant manager's office.

3. Phillips M100 Intercom System Additional communication capability is provided by the Phillips M100 Intercom System. Stations are installed throughout the plant with a two digit number identifying its location.

4. Sound Powered Phone System Sound powered phones are available for use within the plant'and are primarily used for operations and maintenance coordination.

Phone jacks are located throughout the Containment, Auxiliary Building, Turbine Building and Control Room.

II. TECHNICAL SUPPORT CENTER (TSC) TELEPHONE COMMUNICATIONS

1. Touch-A-Matic Dialer The TSC Communications area is equipped with two automatic dialers. They function as a 31 name and number directory with an automatic memory. Numbers are programmed into the memory as labeled on the face plate. Both Touch-A-Matics are connected

, directly to an outside line. The memory button needs only to be depressed once to automatically dial the complete number.

Unit #1 has numbers preprogrammed for all the State and County Agencies, plus the EOF Coordinators and Engineers, Maintenance, Electrical, and I&C personnel required for notification procedures. Unit #2 is programmed for Operations Committee members and all the Health Physics personnel.

The last number manually dialed is automatically recorded into the last number dialed position of the directory. Each number in this position is automatically replaced by the number previously manually dialed.

2. Dimension PBX Attendant Console Located in the communications area, the console once activated has complete control of all incoming communications. The console is activated by calling the console in operation and instructing them to unplug the handset receiver.

Operating Console on backshifts and weekends - Secondary Alarm Station Operating Console during normal working hours - Receptionist in Administration Bldg.

IBM

1 s 3 F3-5 ATTACHMENT A (Continued) Rev. 7 PAGE 28 The TSC console is then'made operational by plugging its handset "

into the board. At no time should two consoles be operated at the same time.

The console should only be operated by the Shift Emergency Communicator (SEC) or someone designated by the SEC.

3. Stations, Extensions, and Hot Lines Individual telephone communication from the TSC is provided for by fifteen separate plant stations with two extensions of these stations, four General Office extensions, and four Eau Clair FX lines. Three separate dedicated circuits (auto ringdown), are also available with points of connection as follows:

1. TSC - St. Paul State Capital EOC - (REC - Minn. Health Department)

2. TSC - EOF (ED to EM)

3. TSC - EOF - (REC - RPSS)

The auto ring down is initiated by picking up the receiver.

Ringine ceases when one other point picks up the line.

4. Phillips M100 Intercom Two stations of the Phillips M100 intercom station are located in the TSC. One is in the Radiation Protection Area while the other is in the communications area.

5. Emergency Notification System (ENS)

The ENS is a leased private line between Prairie Island and the NRC Incident Response Center. The ENS is the primary means for reporting emergencies and other significant events to the NRC/IC Headquarters. When the NRC Operations Center is activated, the ENS becomes the dedicated line to the NRC for the transmission of operational data.

Redphoneslabeled(GPO1504)arelocatedinthedontrolRoomand the Technical Support Center. To activate the ENS line, proceed as follows:

(1) Lift receiver. This causes the telephone console in the Operation Center in Bethesda, Maryland to ring automatically.

IBM

F3-5 ATTACHMENT A (Continued) Rev. 7 PAGE 29

( (2) The NRC Duty Officer will answer.

(3) Calmly identify yourself and give the NRC Duty Officer the required information.

(4) Designate an individual to maintain continuous communication with the NRC staff member in the Operations Center until the NRC decides that the event has been successfully terminated or additional communication is unnecessary.

l l l NOTE: If the incident has little potential for l l impacting the public health and safety, the NRC l l Duty Officer may only collect relevent infor- l l mation and then terminate the conversation. l l However, if the event is of a more serious l l nature, the Duty Officer will maintain an open l l and continuous line with the site until the l l matter is resolved. l l l

6. Health Physics Network (HPN)

The Health Physics Network (HPN) is a leased, private line system which connects all the nuclear power plants, the NRC Operations Center, and the NRC Regional Office (Glen Ellyn).

It is primarily intended for use during emergencies and will function as the dedicated line between the Health Physics personnel, the Operations Center in Bethesda, MD and the NRC Regional Office.

In the event of a site emergency, the NRC will activate the HPN.

Before NRC Health Physics specialists arrive on site, the NRC Operations Center communicator may request information from plant personnel.

1 I l NOTE: The HPN is a restricted network and may not be used l l by nongovernment employees at any time unless a l l significant event has to be reported and both the l l ENS and the commercial telephone lines are out of l l service. l l l IBM

F3-5 ATTACEMENT A (Continued) Rev. 7 PAGE 30 Extensions for the HPN are at the following locations:

(1) HP Office (2) Technical Support Center (3) NRC Resident Inspector's Office If necessary to use the HPN phone:

-(1) Lift receiver. NO DIAL TONE IS HEARD.

(2) Dial the required number:

22 - NRC Operations Center 23 - Region III Office i

I l NOTE: a. There will be audible ringing signal dial tone l l af ter dialing the desired code. Ringing is l l heard at the called station to indicate an l l incoming call. This ring stops when the tele- !

l phone is answered or at the end of thirty l l seconds. You may dial again if the call has l l not been answered in approximately 30 seconds. l l

1 l b. An automatic time-out period of six seconds is !

l provided on the HPN to prevent a tie-up if only l 1

, l one digit has been dialed. This means that the l l desired code must be dialed within six seconds l I or the call will not complete. l 1

I

7. National Warning System (NAWAS)

The National Warning System (NAWAS) is a private wire system provided by the Federal Government to disseminate emergency information of a National or International nature. The National Primary input location is the North American Air Defense (NORAD)

Command Center in the Cheyenne Mountains, Colorado. There are over 2000 terminals on this system in federal, military and state designated locations.

The Wisconsin Division of Emergency Government (DEG) is responsible for maintaining a 24-hour statewide warning system as part of the National Warning System (NAWAS). The Prairie Island NAWAS is part of the Wisconsin State National Warning System. In Wisconsin, there are three (3) state warning centers. These warning centers have operational control over all terminals serving Wisconsin (including Prairie Island). This system is so designated that only the State Warning Point can communicate with terminals outside of Wisconsin. All terminals within Wisconsin IBM

F3-5 ATTACHMENT A (Continued) Rev. 7 PAGE 31

s. are on a " Party Line" basis, in that any terminal talking on the circuit is heard by all other terminals on the Wisconsin circuit.

In Wisconsin, NAWAS terminals are located at all seven district State Patrol Headquarters radio dispatch rooms and Area Emergency Government EOC's, 26 county warning centers, the five nuclear power plants and six U.S. Weather Station Offices. The State Patrol and county warning centers relay to and from the other 46 county non-NAWAS centers by radio.

The Prairie Island NAWAS talks directly to the State Warning Centers, the Weather Station Offices, and to the county sheriffs. The State Warning Centers and the county sheriffs further disseminate information to emergency organizations and personnel by other communications systems.

The state-wide emergency telephone number DELETED is the alternate communications backup for notification to the Wisconsin Division of Emergency Government. ,

THE FOLLOWING WILL BE USED IN THE EVENT AN INCIDENT AT PRAIRIE ISLAND REQUIRES A RESPONSE FROM STATE AND LOCAL AGENCIES:

(1) DETERMINE THE CLASS OF EMERGENCY.

(2) PICK UP THE NAWAS SET, PRESS TALK BUTTON AND SAY:

"THIS IS PRAIRIE ISLAND NUCLEAR PLANT CALLING WISCONSIN WARNING CENTER ONE, WEST CENTRAL AREA WARNING CENTER AND PIERCE COUNTY WARNING CENTER, ACKNOWLEDGE."

(3) WHEN WARNING CENTER ONE, WEST CENTRAL AREA AND PIERCE COUNTY WARNING CENTERS ACKNOWLEDGE, PRESS TALK SWITCH AND SAY:

1 j

" PRAIRIE ISLAND NUCLEAR POWER PLANT IS EXPERIENCING A: '

" NOTIFICATION OF UNUSUAL EVENT" (least serious); OR

" ALERT"; OR

" SITE AREA EMERGENCY"; OR

" GENERAL EMERGENCY" (most serious)

" RELAY THIS INFORMATION TO EMERGENCY GOVERNMENT IMMEDIATELY."

l NOTES: a) IF AREA OR COUNTY WARNING CENTERS DO NOT ACKNOWLEDGE, WISCONSIN WARNING CENTERS I, II, OR III WILL RING ON THE CIRCUIT AND RELAY THE HESSAGE TO APPROPRIATE WARNING CENTERS.

b) DUTY OFFICERS AND EMERGENCY GOVERNMENT OFFICIALS AT STATE AND LOCAL AGENCIES WILL INITIATE RESPONSE IN ACCORDANCE WITH CURRENT PLANS AND SOP'S.

l t

l IBM

F3-5

Rsv. 7 Page 32 ATTACHMENT A (Continued)

NATIONAL WARNING SYSTEM

(

(NAWAS)

COLORADO 'SPRINOS ALTERNATE ,

PRIMARY NWC WARNING CENTER ~

OLNEY, MD

4 5

lI s s' /

i

e' / -

I / 3 E l - / :

- / 3 E

~ ll '

/

/ 5

/ 3 STATES / WISCONSIN FEDERAL AGENCIES / WISCONSIN WARNING CENTER III MILITARY POINTS / WARNING CENTER I ALT DEG EOC

/ STATE PATROL TOMAH

/ COMM CENTER

/

DISTRICT I MADISON /

/

f NUCLEAR -

/

/ 1 )

WISCONSIN

POWER V

, ,, /

WARNING CENTER II #, :, $

ee

PLANTS DEG COMMO ROOM -

s

5 l f'

HILL FARMS -

i i ,' e j8'8' MADISON N 8 '

e 8 7'SP DISTRICTS AREA EOC's U.S. WEATHER SERVICE j+#'j,/ , ,

/,e ,,

j'i g

g MILWAUKEE MADISON

/8 g*f ' /

/ '8 5l g

g GREEN BAY LA CROSSE g# '

, f ',8 ii g DUBUQUE

/ t MINNEAPOLIS 26 COUNTIES -- ----

18 COUNTIES l

/ RADAR NEENAH

\ RADAR MARSELLES

/S

, /$ \

i /8 I

/8 \

\

28 COUNTIES l DEDICATED TELEPHONE (NAWAS) fROL

- - - - -- - - RADIO OBI m oeeeeeeeeeWEATHER TELETYPE '

iniiiiiiiiiiiiiisis si TELETYPE (TIME)

(ALL POINTS, EXCEPT MOBILES, INTERCONNECTED BY COMMERCIAL TELEPHONE)

O $

e F3-5 ATTACHMENT A (Continued) Rev. 7 PAGE 33 I

SUMMARY

OF PRAIRIE ISLAND HOTLINE NETWORK NRC EOF

CONTROL (Eh3)

ROOM BETHESDA 3 2

) NRC

" ~

u

~

_ 1 (HPN)

TSC T 5 GLEN ELLYN j 7 g

WISC. -

NRC AUTHORITIES 4 5 --*

(HPN)

(NAWAS)

BETHESDA e e STATE EO*"

OFFICE Number Name Station

, 1 Emergency Primary means for reporting emergencies and Notification other significant events to the NRC Head-System quarters in Bethesda, Maryland. ENS phones (ENS) are located in the Control Room and TSC.

2 TSC - EOF (ED-EM) 2 point auto ring between the TSC and EOF.

Either station can activate the circuit.

3 TSC-EOF (REC-RPSS) 2 point auto ring between the TSC and EOF.

Each station can activate the circuit.

4 TSC - Minn 2 point ring on demand between the TSC State E0C and State EOC. Each station can activate the circuit.

5 Health Physics Multiple station line between the TSC, Plant Network (HPN) HP Office, NRC Glen Ellyn, & other utilities.

This is a two digit ring telephone.

6 TSC - National Dedicated Line to Wisc. Warning C' enter I, II, Warning System and III, Regional Warning Center, and County (NAWAS) Warning Center.

IBM

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ne . . , - . . . - - - . . , w- ----w., y- ==.

y -

a

. o F3-5 Rev. 7 PAGE 34 ATTACHMENT B '

RADIO COMMUNICATIONS NETWORK I. MOTOR 0I.A RADIO SYSTEM This radio system is capable of being operated in either a normal (clear-uncoded) mode or in a private (Coded-digital voice protection) mode.

In the clear mode, all communications can be monitored by scanner receivers. In the coded mode, a standard receiver or scanner cannot monitor your communications. In the coded mode, the audio quality is degraded due to the encoding / decoding process. This is a normal condition.

1. Motorola Radio Console Three radio consoles provide the heart of the radio system.

They are all identical with respect to function but not appearance. The consoles are located in the Control Room, TSC, and EOF. All contain the same channels and have an intercom feature between the consoles. Indication lights on the face of the console give the status of the transmitter / receiver mode, coded or clear operation.

Check the status lamp located beside the clear / coded switch on s the control units. Operate it as necessary to put the system into the clear or coded mode.

All consoles are able to monitor the selected channel as well as the unselected channels. Independent volume controls are provided for both. Frequency 1 and frequency 2 are banded together and are one in the same. Call lights on the verticle portion of the console indicate which channel information is

being receiven on. The second row of channel selection buttons t

on the TSC console are not connected.

I

! IBM t

F3-5 ATTACHMENT B (Continued) Rev. 7

, PAGE 35 I

8 Channels give communication ability for:

CHI (60 watt Simplex) Goodhue County EOC - Goodhue County Sheriff's office, Red Wing, MN Dakota County EOC - Dakota County Sheriff's office, Hastings, MN Pierce County EOC - Pierce County Sheriff's office, Ellsworth, WI CH2 (100 watt repeater) - 10 radiation monitoring team portables -

F1 or F2.

CH3 (100 watt repeater) - 10 plant portables - F1.

CH4 (60 watt Simplex) - 20 security portables - F1 (primary freq)

CHS (60 watt Simplex) - 20 security portables - F2 (secondary freq)

CH6 (60 watt Simplex) - Goodhue County Sheriffs office -

Red Wing, MN CH7 - (60 Watt Simplex) - System Dispatcher (proposed)

CH8 (12 watt Simplex) - Auxiliary Building F2 of the plant portables.

20 SECURITY PORTABLES 10 PLANT PORTABLES (F2)

AUXILIARY BLDG USE SECURITY

/

CAS

'4,

'N CONTROL 0

SEC ITY 5 ROOM SAS ~~-- '

TSC 3

RAD SURVEY 2 TEAM MEMBERS 10 PLANT PORTABLES (F1) 2 P.I. VEHICLES 10 PORTABLES EOF (Proposed) 1 SYSTEM DISPATCHER GOODHUE COUNTY GOODHUE EOC SHERIFF DAKOTA EOC RED WING, MN , PIERCE EOC

~~~~~~~~~

IBM RADIOWAVE HARDWIRE

F3-5 ATTACHMENT B (Continued). Rev. 7 PAGE 36

2. Motorola Portable Ha.', die,-Talkie (Model MX350) - '

i A. Special Instructioqs (1) Do not separat- br ttery pack from radio. This separation could cause loss of DVP feature and it would have to be coded. The encoder and instructions are located in 'ommunications area of the TSC if needed.

(2) Radios may be left in charger after full charge signal (grenn light) is on. You may leave volume turned "on" in charger; however, you must never transmit while radio is in the charger.

(3) External antenna jack located on " press to talk" switch side near the top of the radio provides an extended i range when an antenna is used with this set. All Radiation Monitoring Team radios are provided with external antennas.

(4) A compatable headset is available for use with this portable. When connected to the headphone plug (on top of set) the headset earphones and microphone displaces the built in speaker and microphone. This accessory provides noise control when required.

B. Radio Operation >

(1) Knob on top marked F1 and F2 is a frequency selector switch. On the plant portables F1 works on CH3 of I

radio console and should be used in the Turbine Bldg and outplant areas. F2 works on CH8 of the radio console and should be used in the Auxiliary Bldg.

The radiation monitoring portables have F1 and F2 banded together.

(2) sVV' is the squelch control - it should be positioned to just remove extraneous receiving noises.

(3) The knob marked VQ d31 C) provides a choice of the coded position (left), private line position (center) and clear position (right). To protect your messages, always use the coded position. NEVER USE THE CENTER POSITION!

(4) The red light on top will be on during transmitting.

It is also a check for battery status. (Weak indicates low battery power.)

(5) Operate radio similar to other portables, using the 2" distance between mouth and the microphone grill, speak clearly, and say when your transmission is complete.

Use reasonable volume and squelch.

IBM

ATTACHMENT B (Continued) Re 7

' PAGE 37

{

,' ILLUSTRATION MOTOROLA PORTABLE HANDIE TALKIE MODEL MX350 HEADSET CONTROL DO NOT USE!

SQUELCH CONTROL CO CLEAR ANTENNA \

N / eno To* _\.iD 8 's..

kSi IN x VOLUME g FREQUENCY f

TRANSMITTING LIGHT I

IBM

F3-5 ATTACHMENT B (Continued) Rev. 7 PAGE 38 II. LOW BAND PAGING SYSTEM ^

SYSTEM DISPATCHER I D. GILBERTS HQEC TSC AND ,

CONTROL ROOM 8 RED '

HANDSETS

/

/ NSP RICE ST.

1 RADIO !

I

- - - - - - - HARDWIRE i

MINN STATE EOC s

PROCEDURE

1. To contact the System Dispatcher:

Lift the handset, push the push-to-talk switch and say:

" PRAIRIE ISLAND TO SYSTEM DISPATCHER."

2. To contact the Minn. State E0C (See Note f):

Lift the handset, push the push-to-talk switch and say:

" PRAIRIE ISLAND TO EMERGENCY OPERATIONS CENTER."

l l l NOTES: (a) The System Dispatcher can activate the receiver l l at the plant. l l (b) The plant can activate the receiver at the System l l l Dispatcher and the HQEC (when connected). l l l (c) The state can activate the Prairie Island receiver. l l (d) Each station can monitor each channel. l l (e) The-HQEC can activate the receiver at the plant. l i

l (f) The State EOC must first be manned and the l l radio phone activated by the Duty Officer. l l l i

l IBM

F3-5 ATTACHMENT B (Continued) Rcv. 7 PAGE 39

(_. .

(

II'I. RADIO ALERT MONITOR SYSTEM k

N O,

~

5 4 $ 4

-4,. -$-

.r.

k s.,

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GENERAL The Radio Alert (RA) System is a one-way radio transmission system from the plant to the receiver. The transmitter is located in the onsite Technical Support Center with receivers installed in the homes and/or offices of the following three groups:

1. Local Residents

2. Civil Defense

3. Prairie Island Emergency Organization Personnel

( The transmitter unit consists of: (a) message recorder; (b) message transmitter; (c) microphone; (d) telephone answerins; unit; (e) telephone; and (f) code selector.

When the RA System is activated, a tone will be heard by the receiver. The pre-recorded message will then be automatically played three times by the Alert Radio Message Unit. Upon completion of the transmission, the pre-recorded tape is then placed into the telephone answering unit. If an individual is not home when the unit is activated, a red light on the receiv'er will indicate that a message has been transmitted via the Radio k Alert System. That individual may then call,.the number indicated on his receiverEl ETQud the pre-recorded tape will play the message over the phone.

IBM -

F3-5 ATTACHMENT B (Continued) Rev. 7 -

PAGE 40 The micropnone will allow plant personnel to transmit messages which are no't detailed and pre-recorded. k~

The code numbers for the various receiver groups are:

i

1. Local Residents - 01

2. Civil Defense - 04

3. Prairie Island Emergency Organization Personnel - 06 INSTRUCTIONS The following details some of the various specific operating instructions:

A. To Record the Message Cassette:

(1) Make sure that the remote control unit ' Mike Enable' and

' Transmit Enable' key switches are both off (Green).

(2) Set tape unit selector switch to ' Record Announcement' -

insert microphone in tape unit mike jack.

(3) Press tape unit ' Start' switch and record 45 second prepared messages.

j (4) When recording the message, speak slowly and clearly about 3 k inches from the microphone.

(5) Set tape unit selector switch to ' Check Announcement' -

press ' Start' switch and listen to recording. (Adjust volume to desired level with tape unit ' Monitor Volume' Control) - if satisfactory, proceed.

i B. To Test Entire Alert Sequence:

l l

(.1) Insert proper recorded cassette in tape unit.

(2) Set tape unit selector switch to ' Answer'.

(3) Set up desired group code on encoder - Press 'P' (Page) button. Tones will be heard on the remote control unit.

l Adjust its volume control to the desired level.

(4) 18 seconds after the 2nd tone is heard, the 45 second l recorded messaEe will be heard 3 times. Then the unit will i shut off.

! C. To Transmit an Alert Message:

(1) Insert the proper recorded message cassette into the tape unit. (

l l

l IBM l

F3-5 ATTACHMENT B (Continued) Rev. 7 PAGE 41

( (2) Set the tape unit selector switch to ' Answer'.

(3) Turn the remote control unit ' Transmit Enable' key switch on. (Red 'XMIT' lamp will light.)

(4) Set up desired group code on encoder press 'P' (Page) button. If other groups are to be alerted to receive the same message, enter the next code or codes as soon as the preceeding tones have finished.

The rest of the sequence is automatic caveral seconds after the last tone has been transmitted, the 45 second recorded message will be transmitted 3 times - then the system will shut off.

(5) Now, remove the message cassette from the tape unit and insert it into the telephone answering unit.

D. To Send a Live Microphone Transmission:

' (1) Turn the remote control unit ' Mike Enable' and ' Transmit Enable' key switches both on. (Red lamps will light.)

(2) Press ' Transmit' paddle on microphone and transmit desired message.

2 I I l NOTE: (1) Any message sequence, recorded or live, l

, l can be aborted at any time simply by l l turning the remote control unit ' Transmit l l Enable' key switch off. (Green ' Test' l l lamp will light.) l 1 l l (2) None of the volume controls on any of the l l units affect the volume of the transmitted l l message. They are for your convenience l l in monitoring the message. l l 1 l (3) In case the automatic alert sequence has l l been inadvertantly started without a tape l l in the message unit, simply press the l l blue ' Reset' button on the alert radio l l message unit - insert the proper. tape l l message, and start the sequence over. l l l IBM i

4

/ PAGE 1 OF 7 l l EMERGENCY PLAN 1MPLEMENTING l l PRAIRIE ISLAND NUCLEAR PROCEDURES l

{ l GENERATING PLANT l l NORTHEPE STATES POWER COMPANY Number: F3-9 Rev: 2 l ls History Copy I l A . ' Retention Time: Lifetime 1 l TITLE: I I Supt. grad Prptegtion i I l Approved By: EMERGENCY EVACUATION l

<{c/G,[$ M @t 1

l l

l Plaht Managerf' l l l OC Date: 3-M2 - D I I ! I I I l 1.0 PURPOSE l l l l This procedure provides instructions for implementing an emergency l l evacuation of affected areas within the plant buildings or areas l l within the site boundaries. This procedure does not apply to l l evacuation of the general public located in affected areas beyond the l l site boundaries. l l l l This instruction shall apply to evacuations caused by radiological l I hazards, fire, toxic gas, etc. 1 I I

t. l The Emergency Director has three options for evacuation determined by l l the type of emergency condition and/or magnitude of the release. The l l options are: l l l l 1. Local Evacuation i I I I This is an evacuation of a specific area of a plant building to a l I safe area within the building. l I l l 2. Plant Evacuation i I I l This is an evacuation of plant buildings to a designated assembly i I point onsite. I I I I 3. Site Evacuation l I I l This is an evacuation of the plant site to a designated area l l offsite. I I I l The Emergency Director (Shift Supervisor until relieved) is l l responsible for ensuring that an appropriate evacuation (local, plant I I or site) is implemented when radiological or other conditions warrant l l such action. l I I l The Emergency Director shall, based on the best information available, I l determine that evacuation is the protective action that will result in l l the lowest personnel exposure. I I I I I I I l IBM l

. ~

t F3-9 Rev. 2 Page 2 2.0 APPLICABILITY This instruction shall apply to all plant personnel.

3.0 PRECAUTIONS 3.1 This procedure does not apply to the evacuation of the general public located in affected areas beyond the site boundary.

3.2 The Emergency Director shall consider radiation shine from the containments as well as natural hazards when determining the habitability requirements of the assembly areas.

4.0 PROCEDURES 4.1 Local Evacuation A local evacuation of a specific area of the plant may be necessary because of local hazards. A local evacuation shall proceed as follows:

4.1.1 Alarms / indications or visual observations indicate unacceptable conditions in an area of the plant.

4.1.2 The Emergency Director / Shift Supervisor shall direct the Control Room operator to announce over the public address system the location of the problem and any evacuation instructions, as follows:

" ATTENTION, ALL PLANT PERSONNEL. THERE IS A (hazard)

OCCURRING IN (specify area) . ALL PERSONNEL SHOULD EVACUATE FROM THE (specify area) AND STAY CLE/R OF THAT AREA UNTIL FURTHER NOTIFIED.

Repeat the message to ensure that all personnel are warned. l l

l l NOTE: During a local evacuation, the evacuation l l alarm SHALL not be sounded. l l

l l 4.1.3 The Emergency Director / Shift Supervisor shall ensure that all personnel have exited the specified area by completing or directing the completion of a brief search of the area.

IBM

O b F3-9 e

Rev. 2 Page 3 4.1.4 The Radiation Protection Group shall assume control of entry into the area for exposure control purposes.

4'.1.5 The Radiation Protection Group shall complete surveys in the area and when conditions are returned to normal, the Radiation Protection Group shall recommend to the Emergency Director or Shift Supervisor that the area be returned to normal use or relax access control to that area.

4.1.6 When the affected area has been released for normal use,

, the Shift Supervisor or Emergency Director should announce over the public address system, that the affected area is

, now returned to normal use.

4.2 Plant Evacuation A plant evacuation may occur anytime during an Alert, Site Area, or General Emergency due to radiological or other conditions making or potentially making large areas of the plant buildings uninhabitable. All non-essential personnel shall evacuete to a designated onsite assembly area for monitoring, accountability, l

and dose assessment while energency response personnel proceed to their respective emergency operating centers.

t A plant evacuation shall proceed as follows:

4.2.1 The emergency has been classified as either an Alert, Site '

Area, or General Emergency. When conditions make large areas of the plant site uninhabitable, the Emergency Director shall then order a plant evacuation.

4.2.2 The Emergency Director shall determine the wind direction and possible habitability problems at the onsite assembly areas.

l l l

l NOTE: When considering.the habitability re- l 3 l quirements of the Construccion Office l l Building, consider the radiation levels l

, l resulting from direct shine from the l l

l containments. l l l 4.2.3 If conditions are acceptable, the Emergency Director shall inform the Control Room operator of the designated l assembly point and direct the operator to sound the plant l evacuation alarm.

4.2.4 Upon sounding the alarm, the operator shall announce the evacuation instructions over the public address system, as follows:

IBM

.r a ~

t t i F3-9 l Rev. 2 Page 4

" ATTENTION ALL PLANT PERSONNEL. A PLANT EVACUATION HAS BEEN DECLARED. ALL EMERGENCY ORGANIZATION PERSONNEL REPORT TO AND REMAIN AT YOUR EMERGENCY DUTY STATIONS. ALL OTHER PERSONNEL SHALL EVACUATE TO THE (specify assembly point)."

Repeat the message to ensure that all personnel are warned.

4.2.5 The Emergency Director shall monitor the habitability of the Auxiliary Building and order an evacuation of the Auxiliary Building Operators to the OSC if:

(a) General area radiation levels exceed 100 mR/hr, or (b) Based upon recommendations from the Radiation Protection Group.

4.2.6 The Emergency Director shall ensure that the onsite emer-gency operating centers remain activated in accordance with F3-6, " Activation of TSC" and F3-7, " Activation of OSC".

4.2.7 The Emergency Director shall implement F3-10, " Personnel Accountability". Personnel accountability should be completed within 30 minutes.

4.2.8 The Emergency Director shall designate the Radiation Protection Group responsible for supervising any required s monitoring or decontamination at the assembly point in accordance with F3-14.

4.2.9 The Emergency Director shall designate an Assembly Point Coordinator who will control operations at the Assembly paint.

4.1.10 If the completion of the accountability check results in missing persons, the Emergency Director shall direct a search of the plant buildings in accordance with F3-ll,

" Search and Rescue" and F3-12, " Emergency Exposure Control".

4.2.11 The Emergency Director shall continuously monitor conditions at the assembly point and take action if conditions deteriorate. The Radiation Protection Group shall be responsible for establishment of a sampling program.

4.2.12 When plant conditions have stabilized, the Emergency Director shall direct a reentry into selected areas of the plant in accordance with F3-5, " Reentry".

4.2.13 The Emergency Director shall release all personnel at the assembly area when conditions allow. The Radiation Protection Group shall monitor all vehicles departing the site if contamination is highly likely in accordance with F3-14. -

IBM

F3-9 Fev. 2

Page 5

(

l l l NOTE: Key personnel may be authorized reentry l l into the plant to augment the TSC and/or l l OSC staff when requested. l l l 4.3 Site Evacuation A Site Evacuation of non-essential personnal shall be required when unacceptable conditions extend outside the plant buildings to areas offsite making the normal assembly areas uninhabitable.

Personnel shall be directed to evacuate to the parking lot and then using personal cars or NSP vehicles, proceed to sa upvind remote assembly area which should be selected in cooperation with the Emergency Manager.

l l l NOTE: Monitoring of personnel and equipment prior to l l departure from site is not necessary because of l l probable offsite contamination. l l l A site evacuation is highly unlikely but may be necessary in

( cases of Site Area or General Emergency when conditions worsen.

A Site Evacuation shall proceed as follows:

4.3.1 An Alert, Site Area or General Emergency condition exists and the Emergency Director has ordered an evacuation of non-essential personnel from the plant site, and the primary onsite assembly points are uninhabitable.

4.3.2 When conditions indicate that the onsite assembly areas are not habitable, the Emergency Director shall designate an area offsite for congregating non-essential personnel evacuated from the plant site. A site should be chosen in cooperation with the Emergency Manager at the Near-site EOF. (Possible upwind assembly areas are the NSP Red Wing Service Center or the Prairie Island Near-site EOF).

4.3.3 The Emergency Director shall inform the Control Room operator of the designated assembly area and the traffic routes to use and direct the operator to sound the evacuation alarm.

4.3.4 The operator shall sound the alarm and announce over the public address system:

IBM l . .

F3-9 i

Rev. 2 .

Page 6

" ATTENTION, ALL PLANT PERSONNEL. ALL PERSONNEL WITHOUT '

EMERGENCY ASSIGNMENTS SHALL EVACUATE THE PLANT SITE IMMEDIATELY. EVACUATE TO THE PARKING LOT AND YOUR CAR OR NSP VEHICLES AND PROCEED TO THE (specify assembly area) VIA

~

(designated traffic route) FOR PERSONNEL MONITCRING. ALL EMERGENCY PERSONNEL SHOULD REMAIN AT YOUR EMERGENCY OPERATING CENTERS".

Repeat the message several times to ensure that all personnel are warned.

4.3.5 The Emergency Director shall provide additional .

' instructions to Guard Force personnel who will be able to advise the people as they exit the guardhouse on the proper traffic route and assembly area locations.

j Instruct the Guard Force to hand out evacuation instructions, Figure 1 (PINGP #602), to all personnel.

4.3.6 The Emergency Director shall implement F3-10, Personnel l

Accountability and direct any required follow-up actions in accordance with applicable procedures.

4.3.7 The Emergency Director shall ensure that the Guard Force has warned all personnel within the owner controlled area, including all trailers, warehouses and construction sites.

4.3.8 n The Emergency Director shall direct the Radiation a-Protection Group responsible for personnel monitoring and decontamination at the assembly area.

! 4.3.9 The Emergency Director shall coor.dinate arrival of the evacuated personnel at the assembly area.

i 4.3.10 The Radiation Protection Group shall supervise all l

monitoring and decontamination per the guidelines of F3-19, " Personnel and Equipment Monitoring and Decontamination".

4.3.11 When conditions allow, release personne~l from the assembly area or issue further instructions. Key personnel may be authorized reentry to the plant site upon request from the site emergency organization.

l IBM l

l

\

. ~

r PINGP #602, Rev. O F3-9 e Rev. 2 Page 7

( FIGURE 1 SITE EVACUATION INSTRUCTIONS HASTINGS EXAMPLE ONLY g, EHil? 21Kgg i

e 18

[1$ Y

~* INGP PI EOF E

g _

EVACUATION ROUTES 61

NSP Red Wing To Near-site EOF Senice Center

1. Exit Plant Parking Lot RED WING

2. Turn left on County 18

3. Proceed to PI Training Center

4. Use West Entrance INSTRUCTIONS To NSP Red Wing Service Center

1. Proceed to offsite Assembly

1. Exit Plant Parking Lot via Point along designated route.

County 18 to Hwy 61.

2. Turn Left on Hwy 61. 2.

3.

Keep windows rolled up; turn Proceed to Red Wing heaters and air conditioners off.

4. Turn left on Cannon River Road. 3. Do not smoke, eat or drink.

5. Turn Left on Pepin St. to NSP Service Center. 4. Do not leave Assembly Point until released.

l IBM l-

ML20073Q903

Text

SUMMARY

SUMMARY

SUMMARY

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