ML20100G295

Revised Radiological Emergency Response Plan Implementing Procedures,Including Issue 4 to RERP-CR Re Control Room Procedure & Issue 5 to RERP Section 10.B Re Radiological Emergency Response Plan

ML20100G295
Person / Time
Site:	Fort Saint Vrain
Issue date:	03/22/1985
From:	Gahm J PUBLIC SERVICE CO. OF COLORADO
To:	Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
P-85101, PROC-850322-01, NUDOCS 8504080168
Download: ML20100G295 (355)

Text

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RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATION ISSUE EFFECTIVE NO. SUBJECT NUM8ER DATE RERP CR-ALERT DELETED 04-25-84 l RERP CR Control Room Procedure 4 03-21-85 RERP-DOSE Offsite Dose Calculations Methodology 6 08-06-84 0

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TABLE OF CONTENTS Section Description Pace 1.0 C riteri a for Impl ementati on. . . . . . . . . . . . . . . . . . . . . . . . ........ 3 2.0 Procedure.................................................... 3 3.0 R e s p o n s i b i l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.0 References .................................................. 15 5.0 Re ferenced or Supporting Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . 16 Figure 1 Response Center Manning Requirements .................. 1 Figure 2 Visitor's Center Evacuation Routes .................... 1 Table 1 Non-Emergency Events: Four-Hour Reports .............. 1 Table 2 Non-Emergency Events: One-Hour Reports................ 1 Table 3 NOTIFICATION OF UNUSUAL EVENT. . . . . . . . . . . . . . . . . . . . . . . . . . 1 Table 4 ALERT.................................................. 1 Table 5 SITE AREA EMERGENCY.................................... 1 Table 6 GENERAL EMERGENCY...................................... 1 Table 7 Initiating Event Cross-Reference ...................... 1 Table 8 Emergency Condition Cross-Reference.................... 1 1

Table 9 Protective Action Guides .............................. 1 I

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Attachment 1 Phone Numbers for Notification.................. 1 Attachment 2 Non-Emergency Event Notification................ 1 Attachment 3 Notification of Unusual Event .................. 1 Attachment 4 Notification of Emergency Event ................ 1 Datasheet 1 Preliminary Assessment of Plant Conditions...... 1 Checklist 1 Emergency Coordinator / Control Room Director Checklist.............................. 1 Checklist 2 Emergency Coordinator /CR Director Checklist:

Part 2 - ALERT or Higher Event................... I Work /Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . If Forms Use Reporting Sheet *........................................ 2

• ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, p DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE V ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.

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O l General l During the occurrence of an emergency event at Fort St. Vrain, the l Shift Supervisor is initially assigned to be the Emergency l Coordinator. .This responsibility is transferred to the Control Room l Director when he arrives to take over direction of the Control Room, l and to the TSC Director upon his arrival and assumption of duties.

l This procedure describes the responsibilities of the Emergency l Coordinator while this function is performed by the Shift Supervisor i or CR Director. Responsibilities of the Control Room staff and l Technical Advisor are also presented.

1.0 Criteria for Imolementation This procedure is to be utilized by Control Room personnel in the event of an occurrence which is classified in Tables 1 through 6 of this procedure to be a Non-Emergency Event or an FSV Radiological Emergency Response Plan (RERP) event. Guidance to assist in the accident classification process can be found in Emergency Procedure EP CLASS. Initial accident classification is the responsibility of the Shift Supervisor, in the role of Emergency Coordinator.

2.0 procedure 2.1 General Responses 2.1.1 Under any emergency condition, the Shift Supervisor and onsite personnel will immediately- initiate those actions required to limit the consequences of the event and return the plant to a safe and stable condition.

2.1.2 Implementation of the FSV Radiological Emergency Response Plan (RERP) is required whenever any of the Initiating Events of Tables 3 through 6 of this procedure occurs. Additional guidance on accident classification is contained in Emergency Procedure EP Class, as well as in each individual Emergency Procedure. Initial accident classification is the responsibility of the Shift Supervisor.

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i 2.1.3 Notification of offsite authorities will be initiated within 15 minutes after the declaration l of an emergency. Notification to the NRC will be l made within one hour, except for certain non- 1 l emergencies requiring a report within four hours. I l Since prompt notification is extremely important, l provide offsite agencies with information that is l available for initial notification. Followup l l information will be provided as it becomes l available.

2.1.4 *#*Section 2.1.4 is a result of corrective actions made in response to CAR 84-118. Do not delete l Section 2.1.4 without issuance of comparable l controls.*#* Checklists I and 2 are for use by the l Emergency Coordinator (Shift Supervisor or Control l Room Director). These checklists present a brief l summary of actions, and are to be used for guidance l purposes to assist in verifying execution of l required responses. These responses are presented l as responsibilities of the Emergency Coordinator, l but are to be delegated to the Control Room staff l as much as possible.

A l 2.1.5 *#*Section 2.1.5 is a result of corrective actions V l made in response to CAR 84-117. Do not delete l Section 2.1.5 without issuance of comparable I controls.*#* The Control Room staff should be l briefed periodically regarding changes in plant and l emergency status that they would not necessarily be l aware of. This will ensure that staff actions are l most effective in responding to the incident.

l 2.1.6 If the RERP is to be implemented for an ALERT or higher classification, PSC personnel required to man the response centers (Figure 1) are notified by l telephone if the event occurs during non-working ,

hours. It is the responsiblity of the individual response center Alternate Directors (or the first individual contacted by the Director) to ensure that these notifications are made (see RERP-HOME).

Refer to RERP-PHONE LISTS for instructions aid personnel names and telephone numbers.

2.2 On-Shift Control Room Personnel - Procedure 2.2.1 Implement Emergency Procedure actions required to limit the consequences of the event and return the plant to a safe and stable condition.

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r-RERP-CR Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 19 0Public$9fVICe* PusuC SERVICE COMPANY OF COLORADO pd 2.2.2 If a radiological release is involved, make a preliminary assessment of the release utilizing implementing procedure RERP-DOSE to perform offsite dose calculations. Worksheets, Datasheets, and Checklists for dose calculations are contained in RERP-DOSE, as summarized below:

Worksheet 1 Monitored Release - Manual; Worksheet 2 Monitored Release - TI-59; Worksheet 3 Unmonitored Release - Manual; Worksheet 4 Unmonitored Release - TI-59; Datasheet 1 Monitored Datalogger; ,

Datasheet 2 Unmonitored Datalogger; and Checklist 1 Monitored Datalogger.

It is the Shift Supervisor's responsbility to ensure that the offsite consequence assessments are performed as required. Radiological Assessment will become the responsibility of the Technical Support Center after full facility activation.

2.2.3 As soon as possible, inform the Emergency l Coordinator (Shift Supervisor or Control Room l Director) of the results of the preliminary radiological assessment.

2.2.4 Maintain the plant in a safe and stable condition.

2.2.5 Implement corrective actions as directed by the l Emergency Coordinator. -

2.3 Technical Advisor - Procedure 2.3.1 Report to the Control Room immediately when the Plant Emergency Alarm sounds, or when directed by l Emergency coordinator (Shift Supervisor or Control l RoomDirector).

2.3.2 Datasheet 1, " Preliminary Assessment of Plant Conditions," is provided to assist in making initial assessment of plant status.

2.3.3 Provide technical support to Control Room staff, as required.

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V 2.4 Shift Supervisor (Emergency Coordinator) -

Initial Responses to all Events 2.4.1 Assume the position of the Emergency Coordinator until relieved by the Control Room Director (Primary: Superintendent of Operations; Alternate: Shift Supervisor, Training), or the TSC Director.

2.4.2 As Emeroency Coordinator, direct onsite emergency responses and initiate any required corrective actions to mitigate the consequences of the event. .

2.4.3 Checklist 1 is provided as guidance to verify execution of required responses. Checklist 2, a continuation of Checklist 1, is provided for use in the event of an ALERT or higher incident.

2.4.4 If a radiological release or potential radiological release is involved, preliminary radiological assessment may be delegated to a Reactor Operator.

l (This calculation should be performed within 15 l minutes after declaration of the emergency, if l possible, for notification purposes. Subsequent calculations should be performed at an average rate O l of approximately once every 30 minutes until this responsibility is assumed by the TSC or untti the offsite release is terminated.)

2.4.5 For additional assistance in assessing the magnitude of the release, attempt to contact the l Support Services Manager (seeAttachment1, Phone Numbers for Notification.)

2.4.6 Initiate radiological protective actions for station personnel.

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2.4.7 Classify the event as a Non-Emergency Event, Unusual Event, or an ALERT or more severe emergency event, utilizing event status and preliminary radiological assessment, if applicable. Additional guidance for classification is provided in l Emergency Procedure EP CLASS. Sound the plant l alarm and announce the level and nature of l emergency as soon as possible for an ALERT or l higher event. Do NOT wait for management l concurrence to classify the event.

Table 7, Initiating Event Cross-Reference, and Table 8. Emergency Condition Cross-Reference, are also provided for use in classifying the event category and summarizing emergency response actions.

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RERP-CR Issue 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 19 0SerVlCe* PusuC SERVICE COMPANY OF COLORADO 2.4.7.1 Non-Emergency Events This group of operating events comprises a series of occurrences for which, in the wake of Three Mile Island 2, there was a need to receive notification and data early-on in the situation's course of events. The reporting requirements for this group of events have been revised to include only reports of those events which are related to the operations of the NRC and which affect the safety of the operating power plant. The category has been changed from "Significant Events" to "Non-Emergency Events" and split into two categories -- those events which should be reported as soon as l possible but in all cases within four J

l hours, and those which should be reported as soon as possible but in all cases l within one hour. Table 1 summarizes those events and representative occurrences which would require a four-hour report and Table 2 summarizes O those report.

that would require a one-hour Refer to section 2.5, Non-Emergency Event Procedure, for actions required for this event classification. -

It should be noted that if an occurrence listed herein also falls under a higher level category, the actions required for the more severe category shall take

, precedence.

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2.4.7.2 NOTIFICATION OF UNUSUAL EVENT This classification is the least severe Emergency Class and applies to situations where unusual events are in process (or have occurred) which indicate a potential for degradation of the level of safety of the plant.

The plant is placed in a position of readiness for a possible cessation of routine activities and/or an augmentation of on-shift resources, however, the FSV Emergency Organization is not activated for the UNUSUAL EVENT.

l Notifications to State and Local 2

l officials is required to be initiated within 15 minutes after declaration of l the UNUSUAL EVENT, and to the NRC within l one hour after declaration.

4 Table 3 outlines initiating events and Emergency Action Levels for this class of

() incident. Required responses for this classification are presented in section 2.6, NOTIFICATION OF UNUSUAL EVENT.

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2.4.7.3 ALERT, SITE AREA EMERGENCY or GENERAL EMEPGENCY Declaration of an ALERT or higher Emergency Class will require implementation of the REP.P and activation of emergency response centers.

l Notificatian of State and Local l authorities is required to be initiated within 15 ' minutes after declaration of l the emergency, and NRC notifications are l required within one hour, in accordance l with 10CFR50.72.

If the event is an escalation of a previous emergency classification, followup notification to the NRC should be made immediately if an open line has not already been established.

Actions to take for these events are described in section 2.7, the procedure for ALERT or higher events. If the event is an escalation from a lower category, O proceed direct's to stea 2 7 3-Tables 4, 5, and 6 outline initiating events and Emergency Action Levels for the three classes of incidents:

• Table 4 - ALERT; *

• Table 5 - SITE AREA EMERGENCY; and, Table 6 - GENERAL EMERGENCY.

l l NOTE: In the event that a General Emergency is l declared, refer to RERP-PAG, Protective l Action Guidelines, for guidance in l recommending offsite protective actions l to offsite agencies. If the General l Emergency was declared due to l radiological release rates, it may be l desireable to contact the Support l Services Manager (Radiological Assessment l Coordinator at the Forward Command Post) l and request that he assess core damage l (see RERP-CORE).

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l NOTE: If the General Emergency was declared due l to loss of physical control of the I facility, a two-mile precautionary l evacuation is to be considered.

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• PUBLIC SERVICE COMPANY OF COLORADO 2.5 Non-Emergency Event Procedure 2.5.1 In the event of an occurrence believed to be defined by Table 1 or 2, the Shift Supervisor or his authorized delegate may contact one member of plant management listed in order of preference in Attachment 1, although the responsibility of initial event classification is that of the Shift Supervisor, and may not be delegated.

2.5.2 The Shift Supervisor shall inform the management l contact of the event classification. The Shift l Supervisor may request management advice regarding l the classification, but this shall not preclude his l ultimate responsibility.

l 2.5.3 The Shift Supervisor and the management contact, if l available, shall jointly fill out the "Non-Emergency Event Notification" Form (Attachment

2) to ensure that both have the same information.

l 2.5.4 The management contact shall contact other management personnel listed, as appropriate.

p 2.5.5 The Shift Supervisor shall notify the NRC U Operations center of the event as soon as possible, and in all cases, within one hour or four hours as applicable to the Non-Emergency Event category.

l Notification should be made via the NRC Emergency l Notification System, if possible. Alternative methods of notification are given in Attachment 1, should the " hot line" be unavailable.

2.5.6 Maintain an open, continuous communication channel with the NRC Operations Center, upon request by the NRC.

2.5.7 If an open line is not established, a followup notification should be made to report any of the following, if applicable:

= any further degradation of plant conditions; a results of evaluations or assessments of plant '

conditions;

=

effectiveness of response or protective l measures taken; or,

= information related to plant behavior that is g not understood.

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2.5.8 No further action is required unless there is an escalation to an RERp emergency classification as shown in Tables 3-6 of this procedure.

In case of an escalation, refer to the appropriate section:

• Section 2.6 - UNUSUAL EVENT;

• Section 2.7 - ALERT or higher event.

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2.6 NOTIFICATION OF UNUSUAL EVENT 2.6.1 In the event of an occurrence believed to be defined by Table 3, the Shift Supervisor shall assume the position of Emergency Coordinator until relieved by the Superintendent of Operations  ;

(alternate: Shift Supervisor, Training).

2.6.2 Notify the on-duty Technical Advisor. (Refer to Attachment 1, Phone Numbers for Notification.)

2.6.3 Contact one member of plant management listed in order of preference in Attachment 1, Phone Numbers l l for Notification and inform the management contact l of the classification of the event. If desired, l management advice regarding the classification may l be requested, but this shall not preclude the Shift l Supervisor's ultimate responsibilit) to classify l the event. ,

l 2.6.4 Jointly complete the " NOTIFICATION OF UNUSUAL l EVENT" form with the management contact, i

'f l available, to ensure that the same information is recorded by both parties.

O The management contact will then contact other management personnel as required, and the Resident NRC Inspector. (See Attachment 1.)

l 2.6.5 Notify the State of Colorado and the NRC Operations Center of the event by following the instructions l on the notification form (Attachment 3). State l notifications should be initiated within 15 minutes l after declaration of the emergency category. NRC l notifications are to be initiated within one hour l if event declaration. Alternate backup methods of contacting the NRC are given in Attachment 1, Phone Numbers for Notification.

l 2.6.6 Keep the on-duty Technical Advisor abreast of the event status.

2.6.7 Maintain an open, continuous communication line with the NRC upon request. Report any degradation of plant conditions, results of evaluations, or response actions and results.

2.6.8 No further action is required unless the event escalates to a higher RERP emergency classification as shown in Tables 4-6 of this procedure.

O Continue to step 2.7.3 if an escalation occurs.

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RERP-CA Issu2 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 19 0SerVICO* PUBLIC SERVICE COMPANY OF COLORADO 2.7 ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY 2.7.1 In the event of an occurrence believed to be definea as an ALERT or nigner emergency by Tables 4-6 of this procedure, the Shift Supervisor shall assume the position of Emergency Coordinator, until relieved by the Control Room Director (Primary:

Superintendent of Operations; Alternate: Shift Supervisor, Training), or the TSC Director.

I NOTE: The following order of steps is recommended; I however the Emergency Coordinator must remember l that timely announcement of the emergency and l notification of offsite authorities (within 15 l minutes of declaration) are of secondary importance l only to protecting the health and safety of the l public and to mitigating the consequences of the 1 event. The Emergency Coordinator is responsible to l classify the emergency; however, other functions l listed here are to be delegated as desired.

2.7.2 Notify the on-duty Technical Advisor if not already done. (Refer to Attachment 1, Phone Numbers for Notification.)

O 2.7.3 Contact one member of plant management listed in order of preference in Attachment 1, Phone Numbers l for Notification. If desired, the Emergency l Coordinator may consult with the management contact l regarding the classification of the event, but this l in no way precludes the Emergency Coordinator's l responsibility for classification.

I 2.7.4 Checklist 2 is provided as guidance to verify completion of required responsibilities.

l 2.7.5 Sound the Plant Emergency Alarm, if not already done, and announce the nature of the emergency.

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All onsite personnel will report to their Personnel Accountability Stations (refer to Administrative Procedure G-5, Personnel Emergency Response) for initial accountability.

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Rapid evaluation of departmental accountability will be accomplished using plant rosters and computer printouts delivered by Security to the accountability stations.

l 2.7.6 Complete the " Notification of Emergency Event" Form (Attachment 4).

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• PUBLIC SERVICE COMPANY OF COLORADO j 2.7.7 Initiate notifications to the PSC Company Operator

] and Weld County Communications Center, within 15 minutes after declaration of the emergency (these numbers are on the auto-dialer telephone in both the Control Room and Shift Supervisor's office).

l Initiate NRC notification within one hour of event I declaration via the Emergency Notification System.

Alternate enethods of contacting the NRC are listed in Attachment 1, Phone Numbers for Notification, and are to be used in the event that the NRC " hot line" cannot be used.

Read the information on the " Notification of l Emergency Event" Form (Attachment 4) to the above contacts. The information should also be conveyed to the Technical Advisor.

I 2.7.8 The PSC Operator will notify Emergency Response Center Directors, who will in turn notify their l Alternates. During an off-hours event; Alternate l Directors will contact the remainder of the personnel to report to each response center.

l 2.7.9 During normal working hours, inform the Visitor's l Center (VC) representive to instruct visitors at (U3 the VC to depart to the Fort Lupton Fire Station and, depending on the wind directica, specify the departure route (see Figure 2).

Wind from North Route #3-Wind from South Route #1 Wind from East Route #1 Wind from West Route #2 l l 2.7.10 Notify Security of the impending arrival of emergency personnel and provide adequate . clearance for Protected Area access, where required. (If access is required to activate TSC, refer to RERP-l Phone Lists or RERP-HOME, Attachment 9, TSC l Director's Call Li st, for a list of personnel requiring access.) <

( l 2.7.11 Establish communications with the TSC using l l extension 293. (See Attachment 1, Phone Numbers

! for Notification, for alternate numbers if l required.)

l l 2.7.12 Utilize the Fire Brigade or a team from the PCC to locate and/or rescue any unaccounted-for personnel

-as indicated by reports from Security (see RERP-TEAMS).

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l 2.7.13 Upon arrival at the Control Room, the CR Director shall request a briefing regarding incident status and actions currently in progress. After the briefing, ne may assume responsibility for Control Room actions and direct the control of plant operations. He shall notify the Shift Supervisor, duty Reactor Operators, and the TSC of his assumption of the role of CR Director.

I 2.7.14 Request supplemental Operations personnel from the TSC Director, as required, to control the I emergency. (The TSC will relay the request to the l PCC thus re-entry control will be maintained.)

l 2.7.15 Initiate corrective actions recommended by the TSC Director to minimize the consequences of the emergency. j l 2.7.16 Recovery The CR Director is responsible for recommending l termination or de-escalation of the emergency status, from a plant operaticr,al viewpoint, to the TSC Director. This recommendation shall be based

] upon the CR Director's determination that:

• Radiation levels are stable or decreasing with time;

• Releases of radioactive materials to the environment have ceased, or are controlled

, within Technical Specification Limits;

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• Fires, flooding, or similar hazards no longer pose a threat to plant environment or personnel; and

• Measures have been successfully instituted to repair or compensate for malfunctioning plant equipment.

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3.0 Responsibilities l 3.1 Shift Supervisor l The title of Emergency Coordinator is retained by the duty l Shift Supervisor until he is relieved by either the Control Room Director or the Technical Support Center Director, upon activation of the FSV Emergency Organization (see Figure 1). The Emergency Coordinator is responsible for:

• Initial accident classification; l

• Recommending protective actions;

• Initiating emergency actions to mitigate the accident; l

• Notifying offsite authorities (NOTE: State notifications are required to be initiated within l 15 minutes after declaration of an emergency and l NRC notifications must be initiated within one l hour);

• Diagnosing accident conditions;

• Estimating radiological exposures; and

• Establishing communications with the TSC should the FSV Emergency Organization be activated. -

l Responsibility for the decisions for accident I classification, offsite notification, and protective l action recommendations may not be delegated.

3.2 Control Room Director l The Control Room (CR) Director is responsible for control l

of plant operations, assessing plant operational aspects, l and for implementing rny recommended corrective actions.

l In addition, the CR Director may request any additional i operations personnel necessary through the TSC Director.

i 3.3 Technical Advisor l

l The Technical Advisor is responsible to provide technical analysis and advice as requested, and to provide recommendations of corrective actions necessary to restore the plant to a safe and stable condition.

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O l 3.4 Control Room Personnel Plant control and plant operations responsibilities are handled by personnel already on-shift and assigned those responsibilities.

4.0 References 4.1 FSV Radiological Emergency Response Plan 4.2 State Radiological Emergency Response Plan 5.0 Referenced or Supporting Procedures 5.1 RERP-TSC, Technical Support Center Procedure 5.2 EP CLASS, Event and Emergency Classification Overview 5.- 3 RERP-DOSE, Offsite Dose Calculation Methodology 5.4 RERP-PAG, Protective Action Guideline Recommendations 5.5 RERP-PCC, Personnel Control Center Procedure O s.s asae-sosa. some r cxet for off-Shift netifications 5.7 Station Security Plan and Procedures-5.8 RERP-PHONE LISTS 5.9 RERP-VC, Visitor's Center P ocedure 5.10 Administrative Procedure G-5, Personnel Emergency Response 5.11 RERP-TEAMS, Emergency Team Formation and Direction O

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FORMiCl372 22 3643

RERP-CR Figure 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0SerVIC9" PUBUC SERVICE COMPANY OF COLORADO 'Page I of I O

FIGURE 2 VISITOR'S CENTER EVACUATION ROUTES Colorado Hvv. 60 Johnstown Milliken

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Fort St.

Visitor's > w Vrain Center 'j2 _

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Platteville N

E Colorado hav. 52 [

\ ortF Lupton Exit t =g Fort Lupton b

• h Ath St.

e 9

• Tort Lupton y Municipal 31dg.

• • (618 4th St.)

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FORM (Cl772 22-3e43

RERP-CR Table 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 O

TABLE I NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiating Event

1. Any event, found while 1. Determination as result of the reactor is shut- surveillance testing of Plant down, that, had it Protective Systems (PPS) that been found while the failure of PPS modules would reactor was in oper- have prevented a required ation, would have re- reactor scram from occurring.

suited in the plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that significantly compromises plant safety.

() 2. Any event or condition that results in

2. Reactor scrams, loop shutdowns, and automatic starting and manual or automatic loading of diesel generators actuation of an only.

Engineered Safety Feature, including EXCEPTIONS:

the Reactor Protection .

System. a) Manual scram initiated at 2% during a normal shutdown.

b) Only one of three channels tripped manually or auto-matically, but no final protective action takes place, nor is required.

c) Actuation of the afore-mentioned systems which result from, and are a part of, the planned sequence during surveil-lance testing or reactor  ;

operation. l

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FORM 10372 22 3643 l

l

i RERP-CR Table 1 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 4 TABLE 1 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Tyoical Indication Initiatina Event

3. Any event or condition 3. a) During refueling operations, that alone could have a .Olap shutdown margin prevented the ful- is not maintained due to fillment of the safety incorrect rod removal function of structures sequence.

or systems that are needed to: b) Incorrect valve lineup which results in shut off a) shut down the reactor of secondary system decay and maintain it in heat removal sequence.

a safe shutdown condition; c) Liquid waste monitor setpoints raised for liquid waste release b) remove residual heat; completed. Reactor Building sump pumps taken out of pull-to-s c) control the release lock. Setpoints not reset.

of radioactive material; or d) Loss of HEPA filtration.

d) mitigate the con-sequences of an accident.

l l

l O

FORMIC 1372 22 3643

RERP-CR Table 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4  :

O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4 !

O TABLE 1 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiatina Event

4. a) Any airborne radio- 4. As determined by analysis active release that and evaluation.

exceeds 2 times the applicable concentra-tions of the limits specified in Appendix B, Table II of 10CFR20 in unrestricted areas when averaged over a time period of one hour, b) Any liquid effluent release that exceeds 2 times the limiting combined MPC (see Note 1 of Appendix p B of 10CFR20) at the U point of entry into the receiving water (i.e.,

unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.

NOTE: Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR20.403.

5. Any event requiring 5. As occurring.

the transport of a radioactively contam-inated person to an offsite medical facility for I treatment. 1 O

FORM tC1372 22 3643

RERP-CR Table 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 O service

• PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 O

TABLE I NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Tyoical Indication Initiating Event

6. Any event or situation, 6. a) Onsite fatality for which related to the health a news release will be made.

and safety of the public or onsite personnel, or b) Inadvertent release of protection of the environ- radioactive material not ment, for which a news in excess of 10CFR20 limits release is planned or for an unrestricted area, notification to other but requiring report to government agencies has the State.

been or will be made.

c) Oil or chemical spill which could reach the South Platte River or St. Vrain Creek and which is therefore reportable to the EPA.

O FORM (Cl372 22 3643

i i

RERP-CR Table 2 l

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 SerVIC9" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 l

O i TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Tyoical Initiatino Event

1. a) The initiation of 1. a) As occurring.

any plant shutdown required by Technical Specifications.

b) Any deviation from b) Any deviation from a Tech-Technical Specifica- nical Specification, when tions authorized the action _ is immediately pursuant to needed to protect the 10 CFR 50.54(x). public health and safety, and no action consistent with Technical Specifica-ions which can provide adequate or equivalent protection is immediately apparent. (The action should be approved, as a minimum, n

V by a senior licensed operator.)

~

i O

FoRMtCl372 22 3843

1 RERP-CR Table 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 S service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Tyoical Initiatino Event

2. Any event or condition during operation that results in the condi-tion of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:

a) In an unanalyzed 2. a) As determined.

condition that significantly compromises plant safety; b) In a condition b) 1. Reactor pressure in P that is outside excess of design

\ the design basis limits with failure of the plant; or 8 to trip plant.

2. Winds experienced in excess of FSAR design levels.

c) In a condition c) As determined.

not covered by the plant's operating and emergency procedures.

3. Any natural phenomenon 3. a) Toxic gas release in imme-or other external diate vicinity of plant.

condition that poses an actual threat to the b) Extremely high winds or safety of the plant or severe storm preventing significantly hampers plant personnel from i site personnel in the completing requisite )

performance of duties assignments. j necessary for the safe operation of the plant.

O l l

l FORMIC)372 22 3M3 l

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RERP-CR

. Table 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0SerylCe* PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 n.

O TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR rep 0RT Event Typical Initiatina Event

4. Any event that results 4. a) Loss of significant in a major loss of portion of Control Room emergency assessment indication, capability, offsite response capability, b) Loss of all offsite or communications communication systems.

capability.

5. Any event that poses 5. a) Fire posing undue an actual threat to the personnel hazard.

safety of the plant, or significantly hampers b) Severe chlorine release site personnel in the from chlorine cylinders.

performance of duties necessary for the safe c) Accidental gaseous radio-operation of the plant, logical release resulting including fires, toxic in onsite concentrations CJ "''' leases.

radioactive re Appendix B, Table I.

O FORM tC1372 22-3043

RERP-CR Table 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION. Issue 4 0 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 O

TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication

1. Any unplanned radio- 1. Alarms on:

logical release to RT 7312 the Reactor Building CAM (s) or its ventilation RT 7324-1 syster. RT 7324-2 RT 7325-1 RT 7325-2 RT 4801 RT 4802 RT 4803 RT 73437-1, 2

2. Any liquid waste re- 2. a) RT 6212 or 6213 alarm lease resulting in with inability to prevent offsite effluent in discharge offsite.

excess of Technical Specification limits, b) As determined by station personnel.

3. Indication of minor 3. a) 25% increase in fuel damage detected circulating activity in primary coolant. from previous equilibrium cond-itions at the same power level.

RT 9301 (RR 93256).

b) SR 5.2.11 results.

4. Serious fire at the 4. a) Any of various alarms plant lasting more on Fire Control Alarm than 10 minutes Panel; which could lead to substantial b) Fire Pump 1A auto degradation of plant start; safety systems, or which could result c) Verbal reports, in the release of radiologial or toxic materials.

O FORM (Cl372 22 3643

RERP-CR Table 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue d O $9tVIC9" PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 4 O

TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication

5. Abnormal coolant temp- 5. Violations of eratures or core region LCO 4.1.7 or LCO 4.1.9 temperature rises for region outlet to the extent mismatch, or region requiring shutdown in AT, respectively, accordance with to the extent that Technical Speci- shutdown per Station fications. Technical Speci-fications is required (SOP 12-04).

6. Natural phenomenon that 6. a) Seismic Recorder may be experienced Operate; or threatened that represent risks beyond b)-d) As visually observed normal levels; by, or reported to, a) earthquake station personnel.

s ) b) floods c) tornadoes d) extremely high winds

7. Unusual Hazards 7. As visually observed by, Experienced: or reported to, station personnel.

a) Aircraft crash on site or near the site that is subject to public concern because of possible detrimental effect on the plant; b) Onsite explosions or near site explosions that may be subject to public concern because of possible detrimental effect on the plant; or,

. O FORMICI372 22 3643

1 RERP-CR  !

Table 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 ,

O ServlCe*

i PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4

() i TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication

7. c) Onsite or near site plant related accidents that could result in the release of toxic material or spills of flammable materi al s.

8. Any serious radio- 8. As occurring.

logical exposure of plant personnel or the transportation to offsite facilities of contaminated personnel who may have beer.

injured.

O (Probably cannot be determined within two hours- call to be made in a timely fashion.)

9. Accidents within the 9. As occurring or state that may reported by shipper.

involve plant spent fuel shipments or plant radio- .

active waste shipments.

10. Loss of Engineered 10. Shutdown required in Safety Feature or Fire accordance with applicable Protection System to LCOs:

the extent requiring Shutdown a) Engineered Safeguards in accordance with station Technical Specifications. 1) Plant ventilation- l LCO 4.5.1

2) Steam / Water Dump System - LCO 4.3.3

(])

. FOftM tC3 372-ll2 3S43

RERP-CR Table 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 O

TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication 10.(Cont). 3) PCRV penetration flow restriction devices - LCO 4.2.7 and LCO 4.2.9

4) PCRV penetration secondary closures -

LCO 4.2.7 and LCO 4.2.9

5) PCRV Safety Valves -

LCO 4.2.8 ,

SL 3.2 LSSS 3.3.2.c b) Fire Protection System -

LCO 4.2.6, LCO 4.10.1-LCO 4.10.5

11. Indication or alarms 11. Data Logger Alarm / Alarm on radiological effluent Summary indication of non-monitors not functional. operational alarm or indication on:

a) RT 7324-1, 2 and RT 4803; or b) RT 73437-1, 2, RT 4802, and RT 7325-1; or c) RT 73437-2 and RT 4801; or d) RT 6212 and RT 6213.

NOTE: Use ELC0 8.1.1 Technical Specification Limits as basis.

()

i FWtht tCI TU .M .MC

RERP-CR Table 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue a 0 ServlCe" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 U,,

TABLE 4 ALERT Event Indication  !

1. Rapid, severe fuel 1. Coolant Inventory of particle coating a) >2.4 (CI) (Mev) Beta-Gamma failure. Ib b) circulating I-131 activity equivalent >24Ci c) plate out I-131 >1x10' Ci d) SR 5.2.6 or SR 5.2.11 results.

2. Rapid, gross failure of 2. Loop 1 Hot Reheat Header (HRH) one steam generator reheat activity high (5 mrem /hr);

section with loss of or, Loop 2 HRH activity offsite power. high (5 mrem /hr) accompanied by 230 Kv OCB trips g a_nd RAT undervoltage/ loss of power alarm.

3. Primary coolant pressure 3. PAL 9335 decay (to a value greater PAL 9347 than 100 psi less than PAL 9359 normal pressure, ad area monitor accompanied by area and or stack monitor alarm stack radiation monitor alarms).

4. High radiation levels or 4. RT 7312 high airborne contamination CAM (s) alarm which indicates severe RT 6212 degradation in control of RT 6213 radioactive materials. RT 93252-12 (Increase by factor Area Monitors of 1,000 over normal.)

e.g. lifting PCRV relief valve or abnormal release to cooling tower blowdown. Alarms with corresponding meter readings on area or process monitors.

O FORM (C)372 D 3M3

RERP-CR Table 4 FORT ST. VRAl.4 NUCLEAR GENERATING STATION Issue 4 0PublicService

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 4 n

U TABLE 4 ALERT Event Indication

5. Loss of offsite power ad 5. 230 KV OCB trips and RAT vital onsite AC power undervoltage/ loss of power alarm for up to 30 minutes. accompanied by 4 KV bus undervoltage, 480V bus under-voltage, ag Diesel Trouble alarms.

6. Loss of all vital 6. DC bus 1 < 10 volts and DC power for up to DC bus 2 < 10 volts 3 .0' minutes.

7. Loss of primary coolant 7. All He flow indicators read forced circulation for zero.

between 2 and 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.*

8. Loss of secondary coolant 8. All secondary coolant flow functions needed for indicators read zero.

removing residual heat.

9. Loss of normal ability 9. a) Indication of insufficient to place the reactor in rods inserted; or, a subtritical condition by scram of the control b) Neutron rods, count rate not decreasing.

10. Serious fire which could 10. a) Any of various alarms on lead to substantial Fire Control Alarm Panel degradation of plant .

safety systems. b) Fire Pump 1A auto start c) Verbal reports I

• These times are LOFC from 100Y, power. Times may be correspondingly longer for icwer power levels. (See LCO 4.2.18 for time available to initiate depressurization as a function of reactor power level.)

O G

1~ ame,m.n. a

4 RERP-CR Table 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4 4

o TABLE 4 ALERT Event Indication

11. Radiological effluents 11. a) RT 7324-1 indicating exceed 10 times technical 22.5 x 10 2 pCi/cc specifications instan-tenous limits, b) RT 7324-2 indicating

~

22.5 x 10 2 pCi/cc c) RT 7325-1 indicating

~

27.0 x 10 ' pCi/cc d) RT 7325-2 indicating 27.0 x 10 vCi/cc RT 73437-1 indicating e)

~

27.0 x 10 ' pCi/cc I-131.

O <> at 48o2 $adic *4=9 2 7.0 x 10

• yC1/cc I-131.

g) RT 4803 indicating

' ~

2 2.5 x 10 2 pCi/cc Utilize reading from above instruments and calculate dose rate per procedures

12. Ongoing security 12. a) As observed or reported.

compromise.

i 13. Severe natural phenom- 13. a) Seismic recorder operate

enon being experienced (2.05 g) or projected, such as

a) earthquake exceeding b) As Reported Operating Basis Earthquake levels; c) As Reported flood near design b) level; or, _

c) tornado striking facility.

O e

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Fonuici372 22.see

RERP-CR Table 4 ,

FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 I SPublicSerVlCe* PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 TABLE 4 ALERT Event Indication

14. Other hazards being 14. As reported by, or to, experienced or projected station personnel.

such as:

a) aircraft crash on facility; b) missile impact on facility; c) explosion damage affecting plant operation; or, d) entry into facility environs of toxic or flammable gas.

(Some effect on facility ex-perienced or anticipated.)

15. Evacuation of control 15. As deemed necessary by O room aaticipated or required, with control of shift sePervisor shutdown systems established from local stations.

(Control room integrity breached.)

16. All alarms 16. Control room observation.

(annunciators) lost for more than 15 minutes and reactor is not sfiutdown; or, plant tr'ansient experienced while all alarms lost.

(Parameter indication still functional.)

17. Other plant conditions 17. As deemed necessary by warranting precautionary Shift Supervisor.

activation of the PCC, TSC, and FCP.

O FORMtC1372 22 3643

RERP-CR Table 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 O

TABLE 5 SITE AREA EMERGENCY Event Indication

1. Loss of primary coolant 1. All He flow indicators read forced circulation for zero.

over 5 hr. from 100*4 power.

(Lower power levels preceeding LOFC extends time available before core damage is incurred.

See LCO 4.2.18) _. /

2. Non-isolable primary 2. Loop 1 or 2 HRH activity coolant leakage through a alarm-high with Shift steam generator reheat Supervisor determination section. that leakage is non-isolable.

3. PCRV relief valve remains 3. RT 93252-12 alarm and rapidly open. decreasing Reactor pressure.

O 4. Determination of inability 4. 230 KV OCB trips and RAT to restore onsite AC undervoltage/ loss of power power. alarm accompanied by 4Kv bus undervoltage, 480v bus undervoltage, and Diesel Trouble alarms. Standby Diesel Fail to Start.

5. Loss of functions needed 5. Inability to insert for plant hot shutdown. sufficient control rods accompanied by failure of emergency reserve shutdown system - resulting in inability to maintain .01Ap at 220 F.

6. Major damage to spent 6. a) Visual observation.

fuel due to severe cask damage resulting in release b) Area radiation monitor of radioactivity to plant alarms.

environs.

O j FORMICl372 22 3843 l

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RERP-CR l Table 5 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 4 O

TABLE 5 SITE AREA EMERGENCY Event Indication

7. Fire adversely affecting 7. a) Fire pump 1A start; safety systems.

b) Fire Control Alarm Panel c) Various alarms according to affected safety system.

d) Shift Supervisor determines fire beyond capability of station staff.

8. a) Effluent monitors 8. Stack monitor alarm with detect levels corresponding stack corresponding to concentration indications greater than 50 mrem / on:

hr,ctr greater than 500 mrem /hr a) RT 73437-1, RT 4802, whole body for two and RT 7325-1, 2 minutes at the 26.7 x 10 5 pCi/cc site boundary under I-131; or, adverse meteorology (or levels 5 times b) RT 7324-1, 2, the above for thyroid and RT 4803

~

dose rate). >6.6 x 10 2 pCi/cc b) These dose rates are mixed noble gasses.

projected based on other plant parameters or are measured in the environs.

9. Imminent loss of physical 9. Situation evident.

control of the plant due to security breach.

(Response detailed in Station Security Plan.)

i l .-

FORMtC1372 22 3643 1

1 RERP-CR Table 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4 O

v TABLE 5 SITE AREA EMERGENCY Event Indication l

i l

10. Severe natural phenomenon 10.

being experienced or projected (with plant not in cold shutdown), such as; a) earthquake greater a) Seismic Recorder Operate than Safe Shutdown alarm with indication of Earthquake ground motion greater than 0.10g horizontal or greater than 0.0679 vertical.

(

b) flood greater than b) As reported or observed.

design levels c) winds in excess of c) Average wind velocity s design levels greater than 90 mph or 10-second gusts exceeding 99 mph.

d) tornado in excess of d) Horizontal wind design levels velocity greater than 202 mph.

11. Other hazards being 11. As observed by or experienced or projected reported to station with reactor not shutdown, personnel.

such as: ,

a) aircraft crash affecting vital structures; b) severe damage to safe shutdown equipment; c) entry of toxic / flammable gas into vital areas.

12. Reactor building louvers 12. a) Louvers Open Alarm open due to building (3 inches water) being overpressurized by primary coolant. b) Reactor building O cos^ #2) ree4 4o# ier s.

1 i

FORMC372 22 3643

RERP-CR Table 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 OSerVlCe* PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 O 1 TABLE 5 SITE AREA EMERGENCY Event Indication

13. Evacuation of control 13. Remote shutdown room accompanied by

• instrumentation indications inability to locally (panel I-49).

control shutdown systems

, within 15 minutes.

14. Other plant conditions

14. As determined by warranting activation of Shift Supervisor. '^~ f FCP/EOCs, monitoring teams, and precautionary public notification.

O 1

i v

RERP-CR Table 6 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 OSerVlCe* PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 1 TABLE 6 GENERAL EMERGENCY Event Indication

1. a) Effluent monitors 1. Stack monitor RT-7324-1, 2 detect levels alarm, or corresponding to corresponding dose I rem /hr whole rates determined with body (or 5 rem /hr E-500 or cutie pie thyroid) at the detector per exclusion area procedure HPP-56 and boundary under associated graphs, actual meteoro-logical conditions.

b) These dose rates are projected based on other plant para-meters or are

- in the environs.

2. Loss of physical control 2. Situation evident.

of the facility (due to security breach).

3. Other plant conditions 3. As determined by exist that make release Shift Supervisor, of large amounts of radioactivity possible.

O' l

FORMICl372 22 3843 I

O O O RERP-CR inble 7 Issue f4 Page 1 00 2 TABLE 7 INITIATING EVENT CROSS-REFERENCE NOTlflCATION of S11E AREA GENERAL UNUSUAL EVENT. ALTRT EMERGENCY EHERGINCY rad ioac t ivi ty >1. unplanned release to 1. high radiation erfluent monitors errit*ent monitors event reactor building or levels indicate 50 mrom/hr indicate 1 rem /h r its vents (1000 x normal) WB for 1/2 hour WB ( 5 rem /hr

2. any liquid release 2. ef fluents 10 x ( 250 arem thyroid) or thyroid at exclusion Tech. Spec. limits Tech. Spec. limits 500 mrem /hr WB for 2 area boundary min. (2.5 rem thyroid) under actua l at site bounda ry under meteorology or adverse meteorology or similar dose ra te s similar dose rato p rojec ted )

projected fuel > 1. damago Indication or minor rapid and severe major duel damage damage in shipping cask

2. accidents within Colorado allor'r.g release to involving fuel / waste plant environs shipments fire > >10 minutes, possible' serious, possible arrects saroty systems

- safety system degradation; substantial safety possible release of r/a / system degradation toxic materials natural phenomena 4>severo, occurring or severe, component severe, component strains projected; risks strains nea r design levels (plant normal levels design levels not in cold shutdown) unusua l haza rds --i>on/nea r s i te; impact s racility impacted / vita l area impacted /

oxplosions/ accidents; explosion damage severe damage to shutdown could errect plant / release arrecting plant / entry equipment / vital a rea toxic / flammable material into racility/ entry of toxic /

envi rons of toxic / flammable flammable gas gas secu ri ty > on going security security breach causing security breach compromise imminent loss or plant causing loss physical control or plant physical control d

~O O O RERP-CR Table 7 issun 4-Page 2 of 2 4

TABLE 7 INITIATING EVENT CROSS-REFERENCE NotirlCATION Or - SITE AREA CINERAl.

UNUSUAL EVENT ALERT EMERGENCY ENERGENCY 4

a la rms >erfluent monitor problems all alarms lost for 15 (ELCO 8.1.1) minutes and reactor not

< shutdown or transient experienced while ala rms out i

electrical > 1. loss or orrsite inability to restore power coupled with onsite AC loss of vital AC power up to 30 minutes

2. loss or vital DC up to 30 minutes S/G > gross failure or Ril non-i so la tab le leak section coupled with through RH section orrsite power loss plant > 1. loss or engineered. 1. primary coolant 1. loss or primary coolant safety feature pressure decay circulation 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />

2. abnormal coolant / core coupled with ( mo re t i me f'o r l owe r temps, requiring shut- stack alarms powe r l eve l s )

down because or Tech. 2. loss or Forced 2. loss or functions Specs, primary coolant needed for hot

. circulation 2 to 5 shutdown hours .

3. PCRV relier valve

3. control rod inser- doesn't resen t tion problems 4. DBA #2

4. seconda ry coolant- 5. CR evacuation, Inability residual heat removal to control within 15 min.

system problems

5. ovacuation or CR/

shutdown from I-49 miscellaneous > serious radiological any other event any other event any other plant exposure to personnol/ warranting manning warranting manning or condition that ,

transportation or con- of response centers response centers and allows possible taminated person to precautiona ry public release or large orrsite racilities notification amounts nr r/a l

R E R P-CR .!

Table 8 -

lasue 4 Page 1 or 1 TABLE 8

[MERGENCY CONOITION CROSS-REFERENCE NOTirlCATION SITE AREA CENERAL UNUSUAL EVE NT ALERT EMERGENCY EMERGENCY events a re . in > have potentia l fo r have potential for involve actual or involve actual or progress or have - degradation or plant substatial degra- likely failure (s) Imminent occurred that level or safety dation or plant or plant protective substantia l core level or sarety equipment deg rada t ion exists radioactive > none requiring orr small f rac tions EPA PACS except may exceed EPA PACS- ,

releases site monitoring of EPA PAGs near site bounda ry notification > State / local /rederal Sta te/ loca l/redera l Sta te/loca l/redera l Sta te/ loca l/rede ra l emergency response not manned manned manned manned centers rad ia t ion > not dispatched could be dispatched dispatched dispatched monitoring teams protective actions none none cons ide red initlated onsite evacuation > no no could occur could occur sta tus upda tes --y> none If applicable p rovided p rov ided to orrsite authorities State monitoringd> not dispatched not dispatched dispatched dispatched teams j

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l RERP-CR Attach. 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0 SerVlCe* PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 1 p.

N.

PHONE NUMBERS FOR NOTIFICATIONS Plant Manaoement Contacts Page Plant Home Phone Ext. Phone W. J. Franek, Supt. of Operations 890-0558 218 9-532-3489 D. P. Hood, Alternate N/A 347 78-776-1843 C. H. Fuller, Station Manager 890-0810 202 8-303-663-2363 F. J. Novachek, Tech./ Admin.

Services Manager 890-1941 201 8-303-457-8034 J. W. Gahm, Manager Nuclear Production 890-6359 200 8-303-452-0507 F. J. Borst, Support Services Manager 890-1775 203 8-303-663-1230 l 0. R. Lee, Vice Pres., Prod. 890-2834 571-7105, 8-303-659-1180 Resident NRC Inspector Page Plant Home Office Phone Ext. Phone G. L. Plumlee 785-2282 890-2225 490 776-9541 Technical Advisors O Page Phone Plant Ext.

Home Phone J. Sills 890-2223 265 221-5059 A. Reed 890-1942 325 772-5312 l M. Joseph 890-2835 275 465-1248 Alternate Numbers for NRC Operations Center Notification l NOTE: The preferred method for notification is the Emergency l Notification System (ENS). These numbers, listed in order of l preference, should only be used if the ENS is not available.

Commercial Telephone System '(202)951-0550 (301)427-4056 (301)427-4259 (301)492-8893 (301)492-7000 Health Physics Network *22 (Touch-Tone) 22 (Rotary Dial)

Technical Support Center Preferred extension: 293 Alternate extensions: 291 or 294 FORM (C)372.*2 3643

RERP-CR Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 OSerVICO* PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 O

LJ NON-EMERGENCY EVENT NOTIFICATION Report No. -

Year . Sequence No.

IMPORTANT:

It is important that the time of all calls and names of people contacted be logged. Any further follow-up calls received or made should be logged as to time and identity of persons involved and the information transmitted or received shall also be logged.

1. Name and Identity of Caller:

2. Date of Event: Time of Event:

3. This notification appears to be required pursuant to 10CFR 50.72, paragraph ((b)(1), "One-Hour Report"; or (b)(2)

"Four-Hour Report")(circle one).

4. Description of Event:

Reactor power prior to event:

O 'ooa sauteo a7 scr =?

Initiating signal (s):

Was event result of an LCO Action Statement?

Other pertinent information:

5. Actions Taken:

m i .. ...

l Fomu(ci372 22 as43 l

RERP-CR Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 O $9fVlCe* PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 4

6. Status:

Reactor power at time of report:

Under control by onsite staff, no offsite assistance anticipated. Final report.

Under control by onsite staff. Will keep NRC advised.

Offsite assistance may be required. Will advise.

(See Item #7)

Offsite assistance required. (See Item #7)

7. If offsite assistance is anticipated or required, describe assistance that has been or may be requested:

O 1

8. Does the event involve offsite releases or the potential for offsite release that would affect the general health and safety of the public as the result of Fort St. Vrain conditions?

Yes No

9. If yes, provide a good description:

Contacts made by Shift Supervisor:

10.

a) Name of NRC contact:

O b) Time of NRC contact:

FORMIC 1372 22 3843

RERP-CR Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue d 0 ServiC9" PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4 f

0 Management Contact a) Name of management contact:

b) Time of management contact:

11. Contacts made by management:

a) Per attached call sheet log.

12. The Shift Supervisor and Management Contact shall send their copies of the completed forms directly to. Technical Services who will:

a) Determine if a Licensee Event Report is required and prepare a facsimile copy if a 30 day report is indicated.

b) Send a copy to the Superintendent, Operations.

2 c) Send a copy to PORC.

!O 4

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l FORMIC)372 22 3843 l

i

RERP-CR Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0 service

• PUBUC SERVICE COMPANY OF COLORADO Page 4 of 4  ;

l O  !

I I I I I I I CALL I TIME I DATE I CONTACT (NAME) l COMMENTS / REMARKS I I I I I I I I I I I I I I I I I I i 1 I i I I I I I l- 1 I I I I I I I I I I I I I I I I I I I l l l l l l l l 1 I I I I I I I I I I I l- 1 I I I I I I I I I I I I I I I I I I I i 1 I I I I I I I I I I i 1 1 I I I I I I I I I I I O i l

i i

I I

i I

i I

i I

I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 I I I I  ! I I I I I I I I I I l l l l l 1 I I I I I I I I I i 1 -l I I I I I I I I I I I I l l l l l l l l l l l l 1 1 l O

FORMIC 1372 22 3043 l

RERP-CR Datasheet 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4

0PublicService" PUBUC SERVICE COMPANY OF COLORADO Page 1 of 2 l

PRELIMINARY ASSESSMENT OF PLANT CONDITIONS i TECHNICAL ADVISOR

1. Brief description of event

2. Date/ Time of event

3. Date/ Time of assessment <

4. If the data logger is operating, obtain the Demand Function Printout (or print the specified displays):

NOTE: All screens and demand functions are accessible from Display 900.

DF 69-0-0 DF 76-0-0 O DF 77-1-0 Post Trip Review Helium Inventory PRIMARY SYSTEM

5. Current Reactor Power l 6. Rod Runback Occur (Y/N) i i If yes, record positions 2A 4F

7. If shutdown, are all rods fully inserted (Y/N)

8. Circulators Operating A B C D MODE:

Steam /Feedwater/Cond./ Firewater

9. Purification Train A B To: Storage, PCRV, or Ventilation

10. Is heat removal capability adequate at this time (Y/N)

FORMIC)372 22 3M3 L.

I RERP-CR i Datasheet 1 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 l 0 Service

• PUBUC SERVICE COMPANY OF COLORADO Page 2 of 2 O

SECONDARY SYSTEM

11. Loops Operating I II 4

12. Feed to S/G's: Norm FW Emer. FW Emer. Cond.

Firewater

13. Status of Aux. Boilers Remarks f

, Time Description lO e

t l

O FORM (Cl372 22 3M3 I

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

RERP-C2 Checklist 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0Public$9tVIC9" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 1 O

EMERGENCY C00RDINATOR'S CHECKLIST

1. Initiate Emergency Procedure actions.

2. Technical Advisor notified. (Not necessary for NON-EMERGENCY events.)

3. Assign preliminary assessment of radiological release taking place.

4. Initiate protective actions for station personnel.

5. Classify event, using preliminary radiological assessment, if applicable.

6. Contact management and confirm classification.

7. If event is classified as an ALERT or more severe emergency, turn to Checklist 2 for ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.

l DO NOT COMPLETE THE REMAINDER OF THIS CHECKLIST!

8. Complete Notifications Form.

O NON-EMERGENCY EVENT NOTtFICATION - Attachmeat 2 NOTIFICATION OF UNUSUAL EVENT - Attachment 3

. 9. Make Notifications NON-EMERGENCY EVENT NOTIFICATION NRC Operations Center NOTIFICATION OF UNUSUAL EVENT State EOC Governor's Office or Mansion NRC Operations Center l 10. Complete Forms Use Reporting Sheet '

l l

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RERP-CR Checklist 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 O$9fVIC9" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 2 (O)

EMERGENCY COORDINATOR /CR DIRECTOR CHECKLIST, PART 2:

ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY l 1. Sound Plant Emergency Alarm and announce nature of the emergency.

2. Select the PCC location based upon consideration of the dominant wind direction:

1) Training Center (Primary)

2) Engineering /QA Office Complex (Alternate)

NOTE: If both onsite locations are uninhabitable, alternate offsite locations are, in the O order of Johnstown preference.

County the Shops, Platteville Volunteer Fire Department, and Longmont PSCo

. Service Center.

3. For GENERAL EMERGENCY:

a) If radiological, contact Support i Services Manager to perform core damage evaluation.

b) If physical loss of control of facility, consider precautionary 2-mile evacuation.

' l 4. Complete Notifications form (Attachment 4).

i I

O PonMtC1372 22 3H3

RERP-CR Checklist 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 2 O l 5. Make notifications.

PSC Operator Weld County Communications Center NRC Operations Center l 6. Notify Visitor's Center and specify departura route 1, 2, or 3 (see Figure 2):

Wind from North Route #3 Wind from South Route #1 Wind from East Route #1 Wind from West Route #2 l '7. Notify Security to provide clearance O for Prot etee required.

r- access. <<

l 8. Receive initial personnel accountability reports.

i l 9. Dispatch Fire Brigade and/or Search and Rescue teams as necessary.

l 10. Establish communications with TSC (dial 293) and notify of PCC location.

a) Announce to Control Room Staff any changes in emergency status, b) Complete Forms Use Reporting Sheet.

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RERP-CR l

t!S/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 l O SerVlCe* PUBUC SERVICE COMPANY OF COLORADO Page 1 of 3 Work /Datasheet/ Checklist Control List NDTE: Extra attachments as listed are found in the working copy of this procedure in the Control Room.

Worksheet No. Title Number Copies None N/A N/A Datasheet No.

1 Preliminary Assessment of Plant Conditions 2 O ca c'iist "e.

1 Emergency Coordinator / Control Room 2 Director Checklist 2 Emergency Coordinator / Control Room 2 Director Checklist, Part 2: ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY Attachment No.

2 Non-Emergency Event Notification 2 3 Notification of Unusual Event 2 4 Notification of Emergency Event 2 O

FoAMICI372 22 3M3 r

RERP-CR WS/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 l 0 Service ~ PusuC senviCe COMPANY OF COLORADO Page 2 of 3 l t

O FORMS USE REPORTING SHEET Nuclear Documents Specialist:

This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at

. The following forms have been utilized from this copy:

Worksheet Numbers Copies Used O Datasheet Numbers Copies Used Checklist Numbers Copies Used i

i The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. Wnen this form is received, it will be necessary to replace O the noted number of forms, as well as this " Forms Use Reporting s PoRM(C)372 22 3043

RERP-CR WS/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 O

Sheet" for the affected procedure in the affected book.

FORMS USE REPORTING SHEET (Continued) l COMMENTS Reported By:

Date:

1 Nuclear Documents Specialist

• Date Received O Date Replaced Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.

1 I

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FORMIC)372 22 3843

RERP-CR Datuheet 1 Public FORT ST. VHA!N NUCLEAR GENtHATING STATION Issue 4 Page 1 of 2

$ SerVICO'" PUBLIC SERVICE COMPANY OF COLORADO O

V 4

PRELIMINARY ASSESSMENT OF PLANT CONDITIONS TECHNICAL ADVISOR

1. Brief description o.f event

2. Date/ Time of event

3. Date/ Time of assessment If the data logger is operating, obtain the Demand Function 4.

Printout (or print the specified displays):

NOTE: All screens ansi demand functions are accessible from Display 900.

DF 69-0-0 0F 76-0-0 O oF 77-1-0 Post Trip Review Helium Inventory PRIMARY SYSTEM l

5. Current Reactor Power -

6. Rod Runback Occur (Y/N)

If yes, record positions 2A 4F

7. If shutdown, are all rods fully inserted (Y/N)

8. Circulators Operating A B C D MODE:

Steam /Feedwater/Cond./ Firewater

9. Purification Train AB To: Storage, PCRV, or Ventilation

10. Is heat removal capability adequate at this time (Y/N) i =cim.m.no

RERP-CR Datasheet 1

,

• Public FORT ST. VRAIN NUCLEAR Gt NERAllNG STATION Issue 4 Page 2 of 2

' .) Service'" PUBLIC SERVICE COMPANY OF COLORADO O

SECONDARY SYSTEM

11. Loops Operating ,I II

12. Feed to S/G's: Norm FW Emer. FW Emer. Cond.

Firewater 4

13. Status of Aux. Boilers Remarks Time Description J

4 i O i

1 1

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RERP-CR Datasheet 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page I of 2 service

• PUBLIC SERV!CE COMPANY OF COLOFIADO O

PRELIMINARY ASSESSMENT OF PLANT CONDITIONS TECHNICALADVlq0R

1. Brief description o.f event

2. Date/ Time of event

3. Date/ Time of assessment

4. If the data logger is operating, obtain the Demand Function

' Printout (or print the specified displays):

NOTE: All screens and demand functions are accessible from Display 900.

DF 69-0-0 DF 76-0-0

( DF 77-1-0 i

Post Trip Review Helium Inventory PRIMARY SYSTEM

5. Current Reactor Power 4 6. Rod Runback Occur (Y/N)

If yes, record positions 2A 4F

7. If shutdown, are all rods fully inserted (Y/N)

8. Circulators Operating A B C 0 MODE:

, Steam /Feedwater/Cond./ Firewater

9. Purification Train AB To: Storage, PCRV, or Ventilation

10. Is heat removal capability adequate at this time (Y/N) __

)

PonMICl372 22 3M3

, ., .. . . , . - _--_..w-.

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

F.ERP-CR Datasheet 1 Public rORT ST. VRAIN NUCLEAR GENLiiATING STATION Issue 4 Page 2 of 2 SGIVICO'" PUBLIC SERVICE COMPANY OF COLORADO SECONDARY SYSTEM

11. Loops Operating I II

12. Feed to S/G's: Norm FW Emer. FW Emer. Cond.

Firewater

23. Status of Aux. Boilers Remarks I

i Time > Description i

, O 4

1 I

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RERP-CR

- Checklist 1

. . Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page 1 of 1 s ) SerVICO* PUBLIC SERVICE COMPANY OF COLORADO

,O i

EMERGENCY C00RDINATOR'S CHECKLIST

1. Initiate Emergency Procedure actions.

j 2. Technical Advisor notified. (Not necessary for NON-EMERGENCY events.)

I 3. Assign preliminary assessment of radiological release taking place.

4. Initiate protective actions for station personnel.

,! 5. Classify event, using preliminary radiological assessment, if applicable, j 6. Contact management and confirm classification.

1 i

7. If event is classified as an ALERT or more severe emergency, turn to Checklist 2 for ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY. .

t t

l DO NOT COMPLETE THE REMAINDER OF THIS CHECKLIST!

! 8. Complete Notifications Form.

NON-EMERGENCY EVENT NOTIFICATION - Attachment 2 ,

NOTIFICATION OF UNUSUAL EVENT - Attachment 3

9. Make Notifications NON-EMERGENCY EVENT NOTIFICATION i

NRC Operations Center -

NOTIFICATION OF UNUSUAL EVENT State EOC f

{ Governor'.s Office or Mansion NRC Operations Center l 10. Complete Forms use Reporting Sheet h

! O' pow.cim.n see

- . . . ,e, . ,- - ,% , - . - - _ , , _ _ . ,,,.3 -, y-- . . y,. .m,,... ,,y. , ,.. . , , .,,,-, , _ _ _-,,,___m,y .-.,,y. . --.e e,m .,m m,_

RERP-CR Checklist I Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page I of I

@ Service *PUBLIC SERVICE COMPANY OF COLORADO O

V EMERGENCY C00RDINATOR'S CHECKLIST l

I. Initia'te Emergency Procedure actions. '

2. Technical Advisor nptified. (Not necessary for 1

NON-EMERGENCY events.)

3. Assign preliminary assessment cf radiological release taking place.

4. Initiate protective actions for station personnel.

5. Classify event, using preliminary radiological assessment, if applicable.

6. Contact management and confirm classification.

7. If event is classified as an ALERT or more severe emergency, turn to Checklist 2 for ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.

l DO NOT COMPLETE THE REMAINDER OF THIS CHECKLIST!

8. Complete Notifications Form.

() NON-EMERGENCY EVENT NOTIFICATION - Attachment 2 NOTIFICATION OF UNUSUAL EVENT - Attachment 3

9. Make Notifications NON-EMERGENCY EVENT NOTIFICATION NRC Operations Center NOTIFICATION OF UNUSUAL EVENT State EOC Governor's Office or Mansion NRC Operations Center l 10. Complete Forms Use Reporting Sheet O

HMM tCs 3n.D. HQ l

l

RikP-CR Checklist 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 ServlCe* PUBLIC SERVICE COMPANY OF COLOllADO E890 I Of I O -

EMERGENCY COORDINATOR /CR DIRECTOR CHECKLISTu PART 2:

ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY l 1. Sound Plant' Emergency Alarm and announce nature of the emergency.

2. Select the PCC location based upon consideration of the dominant wind direction:

I

1) Training Center (Primary)

2) Engineering /QA Office Complex (Alternate)

NOTE: If both onsite locations are uninhabitable, alternate i

p v

offsite locations are, in the order of preference, the Johnstown County Shops, Platteville Volunteer Fire Department, and Longmont PSco Service Center.

3. For GENERAL EMERGENCY:

a) If radiological, contact Support Services Manager to perform core damage evaluation, b) If physical loss of control of facility, consider precautionary 2-m11e evacuation. ___

l 4. Complete Notifications form (Attachment 4).

l l

l O i i

I ronu ician.22. seas l

RERP-CR Checklist 2 Public FORT ST. VRAIN NUCL EAR GENERATING STATION Issue 4 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 2 O l 5. Make notifications.

PSC Operator Weld County C'ommunications Center 4

i NRC Operations Center l 6. Noti fy Visitor's Center and specify departure route 1, 2, or 3 (see Figure 2):

Wind from North Route #3 Wind from South Route #1 Wind from East Route #1 Wind from West Route #2 p l 7. Notify Security to provide clearance

'ss ,) for protected area access, if required.

l 8. Receive initial personnel accountability reports.

l 9. Dispatch Fire Brigade and/or Search and Rescue teams as necessary.

l 10. Establish communications with TSC (dial 293) and noti fy of PCC location.

a) Announce to Control' Room Staff any changes in emergency status. ___

b) Complete Forms Use Reporting Sheet.

l

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l ponuician 22.su

REM'-CR Checklist 2 1 Public FORT ST. VRA!N NUCLEAR GENFiRAllNG STATION I: Sue 4 i

( Service

• PUBLIC SERVICE COMPANY OF COLORADO I'69 3 UI 2 f3 __

\

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EMERGENCY COORDINATOR /CR DIRECTOR CHECKLIST, PART_2,:

l ALERT, SITE AREA EMERGENCY. or GENERAL EMERGENCY '

l 1. Sound- ' Plant' Emergency Alarm and announce nature of the emergency.

2. Select the PCC location based upon consideration of the dominant wind direction:

1

1) Training Center (Primary)

2) Engineering /QA Office Complex -

(Alternate)

NOTE: If both onsite locations are uninhabitable, alternate

, offsite locations are, in the order of preference, the Johnstown County Shops, Platteville Volunteer Fire l Department, and Longmont PSCo Service Center.

3. For GENERAL EMERGENCY:

a) If radiological, contact Support i Services Manager to perform core

• damage evaluation. ,

b) If physical loss of control of facility, consider precautionary 2-mile evacuation. ., ,.

l 4. Complete Notifications form (Attachment 4).

i FORM fCl372 22 3643

RERP-LR I

Checklist 2 Public FORT ST. VRAIN NUCLEAR Gt NERAllNG STATION Issue 4  !

Service ~ PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 2 l O

l 5. Make notifications.

PSC Operator Weld County C'ommunications Center NRC Operations Center l 6. Notify Visitor's Center and specify departure route 1, 2, or 3 (see Figure 2):

Wind from North Route #3 .

Wind from South Route #1 Wind from East Route #1 Wind from West Route #2

(~t

\

l 7. Notify Security to provide clearance for protected area access, if required.

l 8. Receive initial personnel accountability reports.

l 9. Dispatch Fire Brigade and/or Search and Rescue teams as necessaiy.

l 10. Establish communications with TSC (dial 293) and noti fy of PCC location.

a) Announce to Control Room Staff any changes in emergency status.

b) Complete Forms Use Reporting Sheet.

%/

FonMtCa372 22 393

.~

RERP-CR Attach. 2

/ s Public F09T ST. VRAIN NUCLEAR GENERATING STATION Issue 4 h , ServlCe* PtjBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 r

p ..

Q a

pN-EMERGEK;YEVENTNOTIFICATION 5

Report No. -

Year Sequence No.

IMPORTANT:

It is important that the time of all calls and names of people contacted be logged. Any further follow-up calls received or made should be logged as to time and identity of persons involved and the information transmitted or received shall also be logged.

1. Name and Identity of Caller:

2. Date of Event: Time of Event:

3. This notification appears to be required pursuant to 10CFR 50.72, paragraph ((b)(1), "One-Hour Report"; or (b)(2)

"Four-Hour Report")(circle one).

4. Description of Event:

Reactor power prior to event:

0 tcop shutdown 2 scram 2 Initiating signal (s):

Was event result of an LCO Action Statement?

Other pertinent information:

5. Actions Taken:

O l l

i Foauics:72 22 se43 l

l

REhP-CR Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page 2 of 4 4

) service

• PUBLIC SERVICE COMPANY OF COLORADO r

d

6. Status:

Reactor power at time of report:

Under. control by onsite staff, no offsite assistance anticipated. Final report.

Under control by onsite staff. Will keep NRC advised.

Offsite assistance may be required. Will advise.

(See Item #7)

Offsite assistance required. (SeeItem#7)

.. _ .A. If offsite assistance is anticipated or required, describe assistance that has been or may be requested:

O

8. Does the event involve offsite releases or the potential for offsite release that would affect the general health and safety of the public as the result of Fort St. Vrain conditions?

_ Yes No

9. If yes, provide a good description:

l

10. Contacts made by Shift Supervisor:

D a) Name of'NRC contact: l d~ l b) Time of NRC contact:  !

1 I

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RERP-CR Attach. 2

- FORT ST. VRAIN NUCLEAR GENERATING STATION Issue d ,

Page 3 of 4 k ) Public service

• PUBLIC SERVICE COMPANY OF COLORADO

.O .

Management Contact a) Name of management contact:

b) Time of management contact:

11. Contacts made by management:

a) Per attached call sheet log.

12. The Shift Supervisor and Management Contact shall send their copies of the completed forms directly to Technical Services who will:

a) Determine if a Licensee Event Report is required and prepare a facsimile copy if a 30 day report is indicated.

b) Send a copy to the Superintendent, Operations.

c) Send a copy to PORC.

O 1

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RERP-CR Attach. 2

( Public Service

• FORT ST, VRAIN NUCLEAR GENEllATING STATION ' Issue 4 PUBLIC, SERVICE COMPANY OF COLORADO Page 4 of 4

. 0; I I I I I I l CALL I TIME I DATE I CONTACT (NAME) I COMMENTS / REMARKS I I I I I I I l l I I I I I -l I .I I I I I I I I I I I I I I I I I I l l l l l l l 1 1 I I l- 1 I I I I -l l I I I I I I I I I I I I I I I l' I I I I I I i 1 -l I j' -

1 I I I I I I I I I I i l l I I I I

I I I I I I l I i I i I O l l l l l l I I I I I I I I I I I I 3 I I I I I I I I I 1 1 I I I I I I I I I I i l I I i i l i I

I I I I -l I t

i I I I I ~

I 1 1 1 I I l l- .1 F i l i i I i I I I 1 I I I i 1

I  ! I I I I I l~ l l I I I I I- 1 I I i .

.I I I 1- 1 I I I I I I I I I I

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. I i 1. I I I l- I- I -1 I l-1 I I -l i I I I l- 1 I I l

- DORM (Cf 372 22 3W3 a ..--r

- . - - , - - . . - , - - . , - . a m-. - , ,

RERP-CR Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page I of 4 NON-EMERGENCY EVENT NOTIFICATION Report No. -

Year Sequence No.

IMPORTANT:

It is important that the time of all calls and names of people contacted be logged. Any further follow-up calls received or made should be logged as to time and identity of persons involved and the information transmitted or received shall also be logged.

1. Name and Identity of Caller:

2. Date of Event: Time of Event:

3. This notification appis'r~s/ to be required pursuant to 10CFR 50.72, paragraph ((b)(1), "One-Hour Report"; or (b)(2)

"Four-Hour Report")(circle one).

4. Description of Event:

Reactor power prior to event:

() Leop Shutdown? Scram?

Initiating signal (s):

Was event result of an LCO Action Statement?

Other pertinent information:

5. Actions Taken:

l I

o FORMIC 1372 22 3M3

,-g--,

l RERP-CR Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page 2 of 4 s ) ServlCe* PUBLIC SERVICE COMPANY OF COLORADO O

6. Status:

Reactor power at time of report:

Under control by onsite staff, no offsite assistance anticipated. Final report.

Under control by onsite staff. Will keep NRC advised.

Offsite assistance may be required. Will advise.

(See Item #7)

Offsite assistance required. (See Item #7)

7. If offsite assistance is anticipated or required, describe assistance that has been or may be requested:

A V

8. Does the event involve offsite releases or the potential for offsite' release that would affect the general health and safety of the public as the result of Fort St. Vrain conditions?

Yes No i

9. If yes, provide a good description:

l J

10. ContactsmadebyShiftSupervisor:

i a) Nane of NRC' contact:

b'~T b) Time of NRC contact:

l l

FORM 4Cl372.*2 3643 1

+ l

RERP-CR Attach. 2

. 's PUDllC FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page 3 of 4 sd ' Service'- rustic seavice comeAuv or cotonAno O

V Management Contact a) Name of management contact: _

b) Time of management contact:

11. Contacts made by management:

a) Per attached call sheet log.

12. The Shift Supervisor and Management Contact shall send their copies of the completed forms directly to Technical Services who will:

a) Determine if a Licensee Event Report is required and prepare a facsimile copy if a 30 day report is indicated.

b) Send a copy to the Superintendent, Operations.

c) Send a copy to PORC.

O

. O i

ronuict3': 22-3643 e,

RLRP-CR Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Service'- eusuC scaviCE COMPANY OF COLORADO Page 4 of 4 O'

l l l l l 1 l- CALL l TIME I DATE I CONTACT (NAME) l COMMENTS /REVMKS I I I l l l l l l l l l l l l l l l l 1 I I I I I I I I I I I I I I l- 1 I I l l 1 I l l I I I I I l l ,

I I I I I I I I ..

I I I I l .L /

I I I I I l l l l l l l l l l l l l l l l l l l l l l l l l ,

1 I I I I I I I I I

. O i l

i I

i I

i l-i l

i l

l l l l l l 1 1 1. I I I I I I I I I l l 1 I I l l l l l l l 1 I I I I I I i 1 1 I I

. 1 I I I I i I I i l l l  ;

I i -1 i l I i i l I i i l 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I ,

I I I I I I l 1 il l I I l- l l l l 1 I I l 'l I I I I l l- 1 I I I I l- l- l' I 1 l l l l l l l l l I I: 1 I

, Fonv#Cl372 22 3843 v- w > + t w- 7-f v w=- w

RERP-CR Attach. 3 Public FORT ST. VRA!N NUCLEAR GENERATING STATION Issue 4 Page 1 of 3 9' Service- eusi.ic sanVICE COMPANY OF COLORADO O

NOTIFICATION OF UNUSUAL EVENT A. The Emergency Coordinator and first management contact will complete the following information jointly:

1. Name and ideritity of caller

2. Date of Event Time of Event

3. General Category of Event Unplanned Radiological Release to Reactor Building Fuel Failure Fire .

Natural Phenomenon (circle one)

Earthquake Flood Tornado Winds Unusual Hazards (circle one) .

O ^'"c' "*a' " ' "'c "''

Other(Specify)

Spent Fuel Incident

4. Description of Event

5. Actions Taken ,

6. Status:

Under control by onsite staff, no offsite assistance anticipatect.

Under control by onsite staff. Will keep State and NRC advised.

Offsite assistance may be required. Will advise.

(See Item 7.)

Offsite assistance required. (See Item 7.)

O a

FORM (01372 22 3643

RERP-CR Attach. 3

/

FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4

$g Public

• 7 Service PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 0 -

7. If offsite assistance is anticipated or required, describe assistance that has been or may be required:

8. At the present time, the event does not involve offsite release or the potential for offsite releases that would affect the general health and safety of the public.

B. The Emergency Coordinator will make notifications as follows:

l Contact with State E0C (279-8855) and Governor's Office (866-2471)l l or Mansion (837-8350) l l l

1. READ the following statement verbatim:

"THIS IS A NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION. THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF EMERGENCY RESPONSE CENTERS. THIS NOTIFICATION REQUIRES VERIFICATION OF RECEIPT BY THE STATE.

VERIFY BY CALLING 571-7436 or 785-2223."

2. READ all the information recorded in Step A (Page 1 of 3 this ATTACHMENT).

~

TOGM#Cl372 22 3fd3

RERP-CR Attach. 3 l I

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page 3 of 3 Service

• PUBLIC SERVICE COT.1PATJY OF COL ORADO O

I 3, RECORD the following information:

l Date Name of State EOC contact l Time Name of Governor's Office / Mansion Contact l Time Call back verification from State EOC l Time .

Call back verification from Governor's Office / Mansion

~

l Time l . I l Contact with NRC Operations Center (Hot Line or 202-951-0550) l O '

(Alternate means of notification are given in Attachment 1.)

1. READ the following statement verbatim:

"THIS IS NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION AT PLATTEVILLE, COLORADO. THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO 10CFR50.72, PARAGRAPH (a)(3). THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE ,

ORGANIZATIONS."

2. READ the NRC ' Operations Center all of the information recorded in Step A (Page 1 of this Attachement).

3. RECORD the following information:

-l Name of NRC Contact Time O

V FORMIC 4372 22 3643

'RERP-CR Attach. 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 sj ' SOTVICe* PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 NOTIFICATION OF UNUSUAL EVENT A. The Emergency Coordinator and first management contact will complete the following information jointly:

1. Name and identity of caller

2. Date of Event Time of Event

3. General Category of Event Unplanned Radiological Release to Reactor Building Fuel Failure Fire Natural Phenomenon (circle one)

Earthquake Flood Tornado Winds l Unusual Hazards (circle one)

Aircraft Explosion Toxic Material Other(Specify)

Spent Fuel Incident

4. Description of Event

5. Actions Taken J

6. Status:

Under control by onsite staff, no offsite assistance anticipated.

Under control by onsite staff. Will keep State and NRC advised.

Offsite assistance may be required. Will advise.

(See Item 7.)

Offsite assistance required. (See Item 7.)

FOAV(Ci372 22 3M3 -

P.ET.P-C R l Attach. 3 l

.- pyhllC FORT ST. VRAIN NUCLEAR GENFHATING STATION Issue 4 Page 2 of 3

\ ) SGIVice* PUCLIC SERVICE COMPANY OF COLORADO (3w/

7. If offsite assistance is anticipated or required, describe assistance that has been or may be required-l 1

8. At the present time, the event does not involve offsite release or the potential for offsite releases that would affect the general health and safety of the public.

B. The Emergency Coordinator will make notifications as follows:

l Contact with State EOC (279-8855) and Governor's Office (866-2471)l l or Mansion (837-8350) l l l

1. READ the following statement verbatim:

"THIS IS A NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION. THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF EMERGENCY RESPONSE CENTERS. THIS NOTIFICATION REQUIRES VERIFICATION OF RECEIPT BY THE STATE.

VERIFY BY CALLING 571-7436 or 785-2223."

2. READ all the information recorded in St:ep A (Page 1 of this ATTACHMENT).

t fomusC1372 22 X43

RERP-CR Attach. 3 i s Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page 3 of 3

) Service ~ PUBLIC SERVICE COMPANY OF COLORADO

3. RECORD the following information:

l Date Name of State EOC contact l Time Name of Governor's Office / Mansion Contact l Time Call back verification from State EOC l Time Call back verification from Governor's Office / Mansion l Time l I l Contact with NRC Operations Center (Hot Line or 202-951-0550) l 1 -

l (Alternate means of notification are given in Attachment 1.)

1. READ the following statement verbatim:

"THIS IS NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION AT PLATTEVILLE, COLCRADO. THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO 10CFR50.72, PARAGRAPH (a)(3). THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE ORGANIZATIONS."

2. READ the NRC Operations Center akloftheinformation recorded in Step A (Page 1 of this Attachement).

3. RECORD the following information:

l Name of NRC Contact Time .

O U

FORMtC1372 22 3643 L__._

, klRP-CR  :

Attach. 4 l

- /"' PUIJIIC FORT ST. VMIN NUCLEAR' GENERATING stall 0N Issue 4

( SGIVICO'"

~

PUCUC SERVICE COff.PANY OF COLORADO Page 1 of 5

- =

NOTIFICAll_CN OF EMERGENCY EVENT A. The Emergency Coordinator will complete Pages 1 and 2 of this attachment with. the assistance of the first management  :

contact. ,

I I

, l Required Information l 1 I

1. This is (Name) , Shift Supervisor at the Fort St.

Vrain Station.

~

l 2. At (Time) we declared an (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident.

r l .3. Refer to Protective Action Guidelines on page 3 of this l l attachment (item 15).

, I a) There is @ , repeat NO, radioactive release taking

place, and no specia Tprotective actions are recommended at this time.

i .OR-b) A small release IS taking place, but at this time

- @ protective actions are recommended and are not anticipated to be.

OR c) A radioactive release IS, repeat H , taking place, and we recommend that people in areas remain indcors with windows and coors closed.

0.3 j- d) A radioactive release IS, repeat I_S, taking place, and we recommend that evacuation of areas be cor.sidered.

4. Further information on incident conditions will be provided in' followup messages.

5. Personnel Control Center to be located d

_ _ _ = _.

POnMtc)3'2 22 3Gt3

hLhP-Gi Attach. 4

/ . ['t!bllC ~ FORT ST. VRAIN NUCLFAR GENERATING STATION I*. sue 4

',_ S G i*s'IC G* PunLIC OE;;VICE COfGPArJY OF COLORADO Page 2 of 5 V

l SUPPLEMENTAL INFORMATION l l l NOTE: This information 'is to be supplied to the NRC and the Colorado l Department of Health only when requested. The radiological data can be determined as specified in RERP-DOSE. ,

1. Date and Time of Incident

'2. Class of emergency (ALERT)(SITE AREA EMERGENCY)

(GENERAL EMERGENCY)

3. Type of release (airborne, waterborne, surface)

4. Estimated duration of release (Hours)

5. Current release rate:

Noble Gas Ci/sec; Iodine Ci/sec a

6. Estimated curies released:

~

O Noble Gas Ci; Iodine Ci O,

7. Wind Velocity MPH, from degrees.

to degrees, Air Temp 'F

8. Stability Category . Form of Precip.

9. Cose rate at EAB: WB rem /hr; Thyroid ,

_ rem /hr 2 Miles: WB rem /hr; Thyroid rem /hr 5 Miles: WB rem /hr; Thyroid rem /hr 10' . Pro,iected dose at EAB: 1lB __ _ rem; Thyroid rem 2 Miles: WB rem; Thyroid rem 5 Miles: WB rem; Thyroid rem

11. Estimated accur.ulated dose at EAB:

WB _ rem; Thyroid rem

12. Areas expected to be impacted by release W* $ G $

i;LRI-CR Attach. 4 PtiblIC FORT ST. VRAIN . NUCLEAR GENL H AllNG STADON Issue 4 rustic SF.nvics coff.PAIJY OF COLO.1 ADO Page 3 of 5

'[ $ O TVIC G'"

'v'

13. Estimate of any surface radioactive contamination __ _ _ _

14. On-site response. actions under way _

15. Recommended Protective Action based on the projected dose at che EAB (Read appropriate Protective Actions)

Projected Dose Recom. mended (rem) Protective Action Whole Body <1 I;o planned protective actions. State Thyroid <5 may issue advisory to seek shelter and await instructions. Monitor l radiation levels. (3.b. on page 1)

Whole Body 1 to 5 Take shelter and consider selective Thyroid 5 to 25 evacuation. Monitor radiation levels.

Establish Controlled Area and limit l access. (3.c. on page 1)

Whole Body 5 and above Conduct mandatory evacuation. Monitor

(~')

\_ Thyroid 25 and above - radiation levels and adjust area for mandatory evacuation based on these -

l 1evels Control Access. (3.d. on page 1)

16. Pro 5nosis for worsening of event l 17. ' Time of report

12.  !!ame of person providing report

< 19. Telephone number for call back i

20, Description of any requested off' site assistance - -

• umeme.

en >

- ' am > 4 6 ,,

b

.,. ...c

. m . a .,. 3

. _i.i oh Attech. 4

' [ j, lfUbllc FORT ST. VRAIN T4UCLEAR.GENLP Alff!G SI AllON },.;ue 4 Pc9e 4 of 5

. V./> Sorvico"' runne c.cnvice cor.se..rev of cotonAno h

B. The -Emergency Coordinator will make notifications in sequence as follows:

I .. 1

[ PSC Company Operator 8-571-4591 l l or 8-571-0111 l l l

1. INSTRUCT the -Operator to initiate the " Fort St. Vrain l Radiological Emergency Call List", and READ verbatim the e

. l .information- recorded in Part A (Page 1 of this

.l attachment).

l 2. RECORD the following information:

. Time PSC Operator Notified ,______

Time Operator Callback Received ____

I l l Weld County (911 Using Greeley Line) l l _ l READ verbatim the information recorded in Part A (Page 1

~

1.

of this attachment). ,

2. RECORD the following information: -

Time Weld County Notified _

Time Weld County Callback Received

<*? *. 372-?2,yA3

'j'.

_ . . _ . . _ . ._ _ _ . . _ . . _ m _ . _ __. >_.__. .

h:.St *i.T At. tach. 4

.- . FORT ST. VRAIN NUCl. EAR gel 4Lf1ATING SI AllOrl Is:ue 4

-}# PLII.. j{C

'? s;fh .CCi'/ICG"' PUELIC DE!!VICE COMPArJY 0." COLOFIADO Page 5 of 5

~

l tF OPERATICNS CENTER (HOT LINE OR (202) 951-0550) l I _ _ .I (Alternate means of notification are given in Attachment 1).

1. READ Items 1) through 4) from Part A.

2. READ the .following sentences verbatim. "THIS EVE'iT IS E'EING REPORTED PURSUANT TO 10-CFR50.72, PARAGRAPH (a)(3).

WE ARE PRESENTLY ACTIVATItiG STATE AND LOCAL EMERSEtiCY RESPCNSE CENTERS." -

3. READ the supplemental information (Page 2 of this

, attachment). *

4. RECCRD the following information:

NAME of NRC Contact

^

TIME of NRC Contact l l l l l RETURN TO CHECKLIST 2 l I I l t

a l

t j

G i CT 7,4,[ . 'gf} , ***}, y g n e.- , v p .we,- - -w,-r - w e

RLhP-CR )

                -_                                                                               Attach. 4 i              ~ IUI)llC       TORT ST. VRAIN NUCLEAR GENERATING STATION             Issue 4 Page 1 of 5

[ SG IVICG'" PUDUC SERVICE COT 4PArJY OF COLORADO O NOTIFICATION OF EMERGENCY EVENT A. The Emergency Coordinator will complete Pages 1 and 2 of this attachment with, the assistance of- the first management contact. I l l Required Information l l l 1 1. This is (Name) , Shift Supervisor at the Fort St. Vrain Station. l: 2. At (Time)- we declared an { ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident. l 3. Refer to Protective Action Guidelines on page 3 of'this l attachment (item 15). l a) There is N2, repeat NO, radioactive release taking place, and no speciaT protective actions are recommended at this time. _O_R b) A small release IS taking place, but at this time NQ protective actions are recommended and are not anticipated to be. 93 c) A radioactive relesse IS, repeat IS, taking pitce, and we recommend that people in areas remain indoors with - windows and doors closea. 93 d) A radioactive release IS, repeat IS, taking place,

                   >                          and we recommend that evacuation of areas be considered.

4. Further . information_ on incident conditiens will be provided in followup messages.

5. Personnel Control Center.to be located eOW'Ce372 22 YA3

kEtG-CR Attach. 4 p(;l)((C FORT ST. VRAIN NUCLEAR GENERATING STATION issue 4 Page 2 of 5 A [ $ 6 i'\'IC G"' PUOLIC SERVICr. COT.T/.UY OF COLOR ADO l

        ,m,                                                                                                                1

(_) I I l SUPPLEMENTAL INFORMATION l l l t'OTE: This information'is to be supplied to the NRC and the Colorado l Department of Health only when requested. The radiological data can be determined as specified in RERP-DOSE.

1. Date and Time of Incident

2. Class of emergency (ALERT)(SITE AREA EMERGENCY)

(GENERAL EMERGENCY)

3. Type of release (airborne, waterborne, surface)

4. Estimated duration of release (Hours)

5. Current release rate:

Noble Gas ,Ci/sec; Iodine C1/sec

6. Estimated curies released:

(- Noble Gas - Ci; Iodine C1

7. Wind Velocity MPH, from degrees.

to , _ degrees, Air Temp 'F

8. Stabiitty Categcry . . Form of Precip.

9. Cot,e rate at EAS: WB res/hr; Thyroid rem /hr 2 Miles: WB rem /hr; Thyroid rem /hr 5 Miles: WB rem /hr; Thyroid rem /hr 10', Projected cose at EAB: UB rem; Thyroid rem-2 Miles: WB. rem; Thyroid rem

                                                 .5 Miles: WB                       rem; Thyroid                     rem

11. Estimated accumulated do:e at EAB:

WB rem; Thyroid rem , 12. Areas expected to be impacted by release _

            ' ;' ' '. > - 1/2. N 143 L

RUil' t4 Attach. 4

             ~-

g ' pub llC FORT ST. VRAIN NtlCLEAR GENI' IIA 1!NG Sl ATION Issue 4 dy S0rvice* runue crr.VICE COT.TArJY OF COI.OHADO Page 3 of 5 V

13. Estimate of any surface radioactive contamination __

14. On-site response. actions under way

15. Recommended Protective Action based on the projected dose at the EAB (Read appropriate Protective Actions)

Projected Dose Recommended __[ rem) Protective Action Whole Body <1 No planned protective actions. State Thyroid <5 may issue advisory to seek shelter and await instructions. Monitor l radiation levels. (3.b. on page 1)

Whole Body I to 5 Take shelter and consider selective Thyroid 5 to 25 evacuation. Monitor radiation levels.

Establish Controlled Area and limit l access. (3.c. on page 1) i Whole Body 5'and above Conduct mandatory evacuation. Monitor (v] - Thyroid 25 and above radiation levels and adjust area for < mandatory evacuation based on these l . levels Control Access. (3.d. on page 1)

16. Prognosis for worsening of event l 17. . Time of report

18. Name of person prcviding report i

• j 19. Telephone number for call back

20. Descriotion of any requested off-site assistance _

I l- . , - - ... -.. . -

                                                    - - - -                 ._.m. - .

l 50M.nc 377 72 393

h:.hi -ik Atuch. 4

   /        Pub llC'         FORT ST, VRAIN NUCLEAR GENERATING STATION        Issue 4 rUBUC SERVICE COrdPArJY OF COLORADO Page 4 of 5
    . )[ S Gl \'ICG*

0,, B. The Emergency Coordinator will ma}e notifications in sequence as follows: I . l l PSC Company Operator 8-571-4591 l l or 8-571-0111 l l __I

1. INSTRUCT the Operator to initiate the " Fort St. Vrain l Radiological Emergency Call List", and READ verbatim the l information recorded in Part A (Page 1 of this I attachment).

I 2. RECORD the following information: Time PSC Operator Notified Time Operator Callback Received 4 l l l Weld County (911 Using Greeley Line) l l l

1. READ verbatim the_.information recorded in Part A (Page 1 of this attachment).

2. RECORD the following information: -

Time Weld County Notified Time Weld County Callback Received

   **X.<C %:2-12 3M3

                                                           -,                                             1 i 1.,:i-- .4 At.t.ich. 4

[ Il!DllC FORT ST. VRAIN NUCLEAR GENERATING STATION l<.sve 4

         ' j} SOrVICG'"
           .                       i'Ucuc Otisvice cor.TANY OF COI.OT: ADO                 1%ge 5 of 5
    )

i I i NRC OPERATIONS CEl'TER (HOT LINE OR (202) 951-0550) i I l (Alternate means of notification are given in Attachment 1).

1. READ Items 1) through 4) frcm Part A.

2. READ the following sentences verbatim. "THIS EVENT IS BEING REPORTED FURSUANT TO 10-CFR50.72, PARAGRAPH (a)(3).

WE ARE ~ PRESENTLY ACTIVATING STATE AND LOCAL EMERGENCY RESPCNSE CENTERS."

3. READ the supplemental information (Page 2 of this attachment).

4. RECORD the following information:

NAME of NRC Contact TIME of NRC Contact O i l I i l l RETURN TO CHECKLIST ~2 I I I l

         ;;...,.,,.-;1.;--

l RERP-CR Attach. 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue A 0 service" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 l () U NOTIFICATION OF UNUSUAL EVENT A. The Emergency Coordinator and first management contact will complete the following information jointly:

1. Name and identity of caller

2. Date of Event Time of Event

3. General Category of Event Unplanned Radiological Release to Reactor Building Fuel Failure

                        ~.)#'

Natural Phenomenon (circle one) , Earthquake Flood Tornado Winds Unusual Hazards (circle one) Aircraft Explosion Toxic Material O Other (Specify) Spent Fuel Incident

4. Description of Event

5. Actions Taken

6. Status:

Under control by onsite staff, no offsite assistance anticipated. Under control by onsite staff. Will keep State and NRC advised. Offsite assistance may be required. Will advise. (See Item 7.) Offsite assistance required. (See Item 7.) O FonMic)372 22 3M3

l RERP-CR Attach. 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 . l SerVlCe* PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 l 1 O

7. If offsite assistance is anticipated or required, describe assistance that has been or may be required:

8. At the present time, the event does not involve offsite release or the potential for offsite releases that would affect the general health and safety of the public.

B. The Emergency Coordinator will make notifications as follows: l Contact with State EOC (279-8855) and Governor's Office (866-2471)l 1 or Mansion (837-8350) l l l

1. READ the following statement verbatim:

                               "THiS IS A NOTIFICATION OF AN UNUSUAL EVENT AT THE O'                              FORT ST. VRAIN NUCLEAR GENERATING STATION.      THIS NOTIFICATION     DOES  NOT    REQUIRE ACTIVATION OF EMERGENCY RESPONSE CENTERS.      THIS   NOTIFICATION REQUIRES VERIFICATION OF RECEIPT BY THE STATE.

VERIFY BY CALLING 571-7436 or 785-2223."

2. READ all the information recorded in Step A (Page 1 of this ATTACHMENT).

O FORM (C)372 22 3043

I RERP-CR Attach. 3 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue'4 1 I O SerVlCe*PUBLIC SERVICE COMPA'NY OF COLORADO Page 3 of 3 l O

3. RECORD the following information:

l Date Name of State EOC contact l Time Name of Governor's Office / Mansion Contact l Time Call back verification from State EOC l Time _ Call back verification from Governor's Office / Mansion l Time l l l Contact with NRC Operations Center (Hot Line or 202-951-0550) l l l QL (Alternate means of notification are given in Attachment 1.)

1. READ the following statement verbatim:

                             "THIS IS NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION             AT PLATTEVILLE, COLORADO.      THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO 10CFR50.72, PARAGRAPH (a)(3).      THIS   NOTIFICATION   DOES NOT REQUIRE ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE 0RGANIZATIONS."

2. READ the NRC Operations Center all of the information recorded in Step A (Page 1 of this Attachement).

3. RECORD the following information:

l Name of NRC Contact Time FORM (Cl372 22 3643

l l RERP-CR Attach. 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 5

                                   . NOTIFICATION OF EMERGENCY EVENT A.       -The Emergency Coordinator will complete Pages I and 2 of this attachment with the assistance of the first                 management contact.

I I l Required Information l l l

1. This is (Name) , Shift Supervisor at the Fort St.

Vrain Station.

  ~ ~

l 2. At (Time) we declared an (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident. l 3. Refer to Protective Action Guidelines on page 3 of this l attachment (item 15). I a) There is NO, repeat NO, radioactive release taking

  ]                              -place, and no speciaTprotective actions are recommended at this time.

pR b) A small release H.taking place, but at this time N0 protective actions are recommended and are not anticipated to be. 0.3 c) A radioactive release I_S, repeat IS, taking place, and we recommend that people in areas remain indoors with windows and doors closed. ). 0_3 d) A radioactive release H, repeat H, taking place, and we recommend that evacuation of areas be considered.

4. Further information on incident ' conditions -will be provided in followup messages.

5. ' Personnel Control Center to be located

( FoRMtC1372 22 3643

RERP-C.:i Attach. 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 (.,-) 0 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 5 l I l SUPPLEMENTAL INFORMATION l l l NOTE: This information is to be supplied to the NRC and the Colorado l Department of Health only when requested. The radiological data can be determined as specified in RERP-DOSE.

1. Cate and Time of Incident

2. Class of emergency (ALERT)(SITE AREA EMERGENCY)

(GENERAL EMERGENCY)

3. . Type of release (airborne, waterborne, surface)

4. Estimated duration of release _ (Hours)

5. Current release rate:

                                   . Noble Gas            C1/sec; Iodine          Ci/sec

6. Estimated. curies released:

                                   . Noble Gas            Ci; Iodine           Ci

7. ' Wind Velocity MPH,'from degrees.

to- degrees, Air Temp- F

8. Stability Category . Form of Precip.

9. Dose rate at EAB: WB rem /hr; Thyroid rem /hr

2. Miles: WB rem /hr; Thyroid rem /hr 5 Miles: WB rem /hr; Thyroid rem /hr

10. Projected dose at EAB: WB rem; Thyraid rem 1

2 Miles: WB rem; Thyroid rem 5 Miles: WB rem; Thyroid rem

11. Estimated accumulated dose at EAB:

WB - rem; Thyroid rem p 12. Areas expected to be impacted by release

V 4

o l

FoHMIC)372 22 3643

l l RERP-CR Attach. 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 OSerylCG* PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 5 p%.)

13. Estimate of any surface radioactive contamination

14. On-site response actions under way

15. Recommended Protective Action based on the projected dose at the EAB (Read appropriate Protective Actions)

Projected Dose Recommended (rem) Protective Action Whole Body <1-- - -

                                               - No planned protective actions. State Thyroid <5                          may issue advisory to seek shelter and await instructions. Monitor l                                     radiation-levels. (3.b. on page 1)

Whole Body 1 to 5 Take shelter and consider selective Thyroid 5 to 25 evacuation. Monitor radiation levels. Establish Controlled Area and limit l -access. (3.c. on page 1) (]} Whole Body 5 and above Conduct mandatory evacuation. Monitor Thyroid 25 and above radiation levels and ' adjust area for-mandatory evacuation based on these' l levels Control Access. g(3.d. on_page 1)

16. Prognosis 'for worsening of event l 17. Time of report

18. Name of person providing report

19. Telephone. number for call back

20. Description of any requested off-site assistance Y s FORMfC1372 22 3643 -

RERP-CR Attach. 4 Public - FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 Page 4 of 5 OSerVlCe* PUBLIC SERVICE COMPANY OF COLORADO B. The Emergency Coordinator will make notifications in sequence as follows: 1 I l PSC Company Operator 8-571-4591 l l or 8-571-0111 l l l

1. INSTRUCT the Operator to initiate the " Fort St. Vrain l Radiological Emergency Call List", and READ verbatim the l information recorded in Part A (Page 1 of this l attachment).

l 2. RECORD the following information: Time PSC Operator Notified Time Operator Callback Received ' l l-Weld County (911 Using Greeley Line) l

1. READ verbatim the information recorded in Part A (Page 1 of this attachment).

2. RECORD'the following information: -

Time-Weld County Notified Time Weld County Callback Received O FORMtCl372 22 3643 Li

RERP-CR Attach. 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 '

        *' SGIVICe*               PUBLIC SERVICE COMPANY OF COLORADO          Page 5 of 5 O                                                                             .

I I

                     ~ l NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l l                                                     l (Alternate means of notification are given in Attachment 1).

1. READ. Items I) through 4) from Part A.

2. READ the following sentences verbatim. "THIS . EVENT IS BEING REPORTED PURSUANT TO 10-CFR50.72, PARAGRAPH (a)(3).

WE ARE PRESENTLY ACTIVATING STATE AND LOCAL EMERGENCY RESPONSE CENTERS."

3. READ the supplemental information (Page 2 of this attachment).

                                                  ~

4. RECORD the following information:

                                  ~

NAME of NRC Contact

                          ~ TIME ~ of NRC Contact i

I I I I l RETURN.TO CHECKLIST 2 l l.. _ l I 4 O l

                             \

FORM (C3372 22 3643 - r

                           '                 o                   ,

d.C Ecmo rog t ihm.m sT PA rare Public FORT ST. VRAIN NUCLEAR GENERATING STATION p O service

• PUBLIC SERVICE COMPANY OF COLORADO 2/21/85

 .Q RADIOLOGICAL EMERGENCY RESPONSE PLAN - PLANT ISSUE    EFFECTIVE NO.               SUBJECT                           NUMBER      DATE Table of Contents                          3       10-08-82 Introduction                               3       10-08-82 Section 1        Definitions                                4      07-24-84 Section 2        Scope and Applicability                    4      01-03-83 Section 3        Summary of the Radiological

, Emergency Response Plan 4 07-24-84 Section 4 Emergency Conditions 5 08-21-E4 Section 5 Organizational Control of Emergencies 7 01-15-85 Section 6 Emergency Measures 8 01-15-85 Section 7 Emergency Facilities and Equipment 6 08-21-84 Section 8 Maintaining Emergency Preparedness 3 10-08-82 Section 9 Recovery 5 01-15-85 Section 10.A Agreement Letters and Summary-of Referenced Interfacing Emergency Plans 7 07-02-84  ; i Section 10.B Sample Dose Calculations 5 03-21-85 Section 10.C Maps of Exclusion Area, Low Population Zone, Environmental Dosimetry, Population Densities 3 10-08-82 Section 10.0 Titles of Written Procedures that Implement or Supplement the Plan 6 07-24-84 i Section 10.E Listings of Emergency Kits, ' Protective Equipment and Supplies 1 Stored and Maintained for ) p

 .xj Emergency Purposes 5       11-28-83 Section 10.F     Cross Reference to NUREG-0654, Rev. 1                                     4      01-03-83 FORM (C)372 22 3643

PUBLIC SERVICE COMPANY OF COLORADO RERP Section 10.B Issue 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 11 i ; ppmem eg v if FORT ST,; <VQtAIN ej m

h. MONiCONTROLLED

                                                                              . . ,,                  3 TITLE:     RADIOLOGICAL EMERGENCY RESPONSE PLAN, SECTION 10.8
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                                                                        #4.       ? Whius usTN .      Ul IN ' oosuusur cantan T lj V, o;;m gg ISSUANCE                  ,
                                                                         }                         ' ]j, AUTHORIZED              /                                                                    gg j                                  -ygg.3 PORC           /                                              EFFECTIVE REVIEW                      PORC 612 MAR 14:1985              DATE      3-il-ST APPENDIX B SAMPLE DOSE CALCULATIONS l The following pages are taken from RERP Implementing Procedure l RERP-DOSE, Offsite Dose Calculation Methodology, Worksheet 1, l Monitored Release - Manual Calculations. All Attachments and Tables l referred to in this Appendix may be found in RERP-DOSE.

I') v [ s k v FORM 372 - 22 3642

A RERP Section 10.8 Issue 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 11 0 SOTVICe* PUBLIC SERVICE COMPANY OF COLORADO bs WORKSHEET I ASSESSMENT OF RELEAS5 MONITORED RELEASE This attachment is to be used only if the TI-59 calculator program is not used. If the TI-59 is used, Worksheet 2 is to be used. This attachment is used to determine the following: a) Estimated noble gas and iodine release and release rate; b) The estimated whole body and thyroid gamma dose and dose rate at the EAB; c) Classification of the release; d) Projected whole body and thyroid gamma dose at the EAB; and e) Recommended protective action for the general- population.

1. Date/ Time of beginning of release.

2. Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calctllation.

3. Hours between 1. and 2.

4. Collect the following data:

a) Maximum CPM, RIS-7324-1: (RR-93539, red pen) cpm b) Sensitivity, RIS-7324-1: (I-14,403-P7) pCi/cc/ cpm c) Maximum CPM, RIS-7324-2:

                         .(RR-93539, blue pen)                             cpm d)      Sensitivity, RIS-7324-2:

(I-14,203-P7) pCi/cc/ cpm i e) Maximum CPM / Min, RIS-73437-1: cpm / min NOTE: Maximum CPM / Min must be calculated as:

(Maximum CPM - Initial or Intermediate CPM) ( Elapsed Time (min) ) from strip chart.

                                                                                                    - l romienn n.aso

RERP Section 10.8 Issue 5 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION SerVlCe* - ' PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 11 f) Sensitivity, RIS-73437-1: pCi/cc/ cpm / min g) Site Area Emergency Limit (as posted):

1) 6.6E-2 pCi/cc noble gas

2) 6.7E-5 pCi/cc222I h) Ten Times Technical Specification Limits (as posted):

1) 2.5E-2 pct /cc noble gas

2) 7.0E-8 pCf/cc282I i) Exhaust Stack Flow (cfm):

(I-15,FI-7320) cfm j) Exhaust Stack Flow (cc/sec): (Step 41 x 4.72E + 2) cc/sec k) Average Wind Speed . , at 10 meters: mph

1) Wind Direction at 10 meters:

From Degrees NOTE: North = 0* increasing degrees - c.w. m) Differential Temperature: *F (60m Tower) I n) os = From Data Logger, or square root of l (maximum fluctuation in wind direction over l period of 15 minutes to one hour). l -(OPTIONAL CALCULATION)

5. Determine Stability Category using Table 1 and l Step 4m)or4n).

Stability Category

6. Determine potential sectors affected within 5 mile EPZ using Table 2 and Site Sector Map (Figure 2).

Sectors l I i (q> l l Noble Gas Concentration l l FORM (C1372 22 3643

RERP Section 10.8 Issue 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 11 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO

7. Calculate the exhaust stack noble gas concentration.

a) RIS-7324-1 concentration = (step 4a) x (step 4b)

                                                                                                                                =(                )x(            )
                                                                                                                                =                      pCi/cc b)    RIS-7324-2 concentration = (step 4c) x (step 4d)                                                         l 1
                                                                                                                                =(             -) x (            )

I

                                                                                                                                =                      pCi/cc c)    If either RIS-7324-1 or RIS-7324-2 is off-scale high, record the stack concentration as obtained by local, portable . instrument (refer to HPP-56 or Figure 1 for instructions).

l If readouts are not available for RIS-7324-1 or RIS-7324-2 l due to power loss, etc., record the stack concentration as I obtained -from RT-4803, located on level 11 of the Turbine l l~ Building adjacent to _the reactor plant exhaust ~~ stack _

                                                                                                                                                     ~
                                                                                                                                                              ~~

l (refer to_HPP-13 for instructions).' Loca1 Indicated Concentration = pCi/cc d) Enter the highest of 7a), 7b), or 7c) pC1/cc l - l l Noble Gas Release Rate l l l

8. Calculate the Source Term, Q (i.e., Noble Gas Release Rate).

Q ='(step 7d) x (step 4j) x (1 E -6 C1/pci)

                                                                                     =(                        )x(             ) x (1 E -6)
                                                                                     =                              Ci/sec FORMICl372 22 3643 -

r RERP Section 10.8 Issue 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 11 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO I i

[ Classification of Event i I i l 9. Determine the EAB dilution factor from Attach-l ment 1, Table IA, using the Stability Category l (Step 5) and wind speed (Step 4k). Dilution Factor = sec/m' General Emergency Determination l 10. Determine whole body dose rate at the EAB. l Dose P.4te = (step 8) x (7.5 E+2 Rem / hour) x (step 9) l ( ci/m ) 3 l =( )*x (7.5 E+2) x ( )

                                      =              Rem / hour p              If the resulting dose rate at the EAB is 2 1 Rem / hour, the d              classification of the event is GENERAL EMERGENCY.               Inform the Shift Supervisor of the General Emergency condition. Then go l        directly to Step 13 of this attachment.

Site Area Emergency Determination l 11. Criteria for Site Emergency: If Step 7d) is greater than or equal to 6.6 E-2 pCi/ce, the classification of the event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site l Emergency Condition. Then go directly to Step 13 of thi.s attachment. Radiological Alert Determination l 12. Criteria for Radiological Alert: If Step 7d) is greater than or l equal to 2.5 E-2 pCi/cc (ten times the Technical Specification l limit), the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. l Then proceed with Step 13. O l FoRMfCl372 22 3643

RERP Section 10.B 1 Issue 5 l Public- FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 11 l 0 Service'" PUBLIC SERVICE COMPANY OF COLORADO I l I I l Curies of Noble Gas Released l

I I l_13. Calculate the curies of noble gas released to present time.

Curies released = (step 8) x (step 3) x (3.6 E +3 s/hr)

                                            =(         )x(         ) x (3.6 E +3)
                                            =               Curies i

l l l Accumulated Whole Body Gamma Dose at EA8 l l l t l 14. Calculate the 6 s'e received at the EAB. l Dose = (step 10) x (step 3) O)

                                     =(             )x(        )
                                     =                 Rem NOTE:           This calculation assumes the recipient was at the EAB for the entire duration of the release.

I l-l Projections l I l l 15. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue l (i.e., from beginning to end). A projected release duration of l two hours may'be reasonable if no better estimate is available. , If the release has terminated, enter value from step 3. Preiirrinary estimate of release hours hours. v~ i FORM (C)372 22 3643 d

r . RERP Section 10.B Issue 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 11 0 ServlCe* PUBUC SERVICE COMPANY OF COLORADO l 16. Project the total whole body gamma dose at the EAB. l Projected dose at EA8 = (step 10) x (step 15)

                                              =(        )x(         )
                                              =            Rem I                         I l   131 I Concentration   l e l                           I l 17. Calculate the exhaust stack 2'2I concentration.

l a) RIS-73437-1 concentration = (step 4e) x (step 4f)

                                                 =(        )x(          )
                                                 =             pCi/cc l        b)     If RIS-73437-1 is off-scale high or if a readout is not l               available due to power loss, etc., record the stack
 \    l               concentration as obtained from RT-4802, located on level l               11 of the Turbine Building adjacent to the reactor plant l               exhaust stack (Refer to HPP-13 for -instructions).

l Local Indicated Concentration = pCi/cc I I l 131I and Total Radiotodine Release Rate l l l l 18. Calculate the source term Q (2221 release rate). l Q = (step 17) xL(step 4j) x (1 E-6 Ci/pCi)

                   =(       )x(          ) x (1 E-6)
                   =           Ci/sec O

FoRMtCl372 22 3643

RERP Section 10.8 Issue 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 11 0 service

• PUBLIC SERVICE COMPANY OF COLORADO v'

l 19. Calculate QT f r total radiotodine release. l QT = (step 18) x (1.05 E + 2)*

                                =(          ) x (1.05 E + 2)*
                                =               C1/sec

• Ratio of total radiof odines to ** *I in design inventory.

I I l Classification of Event l

>                                    I                                 I General Emergency Determination l 20. Determine the thyroid dose rate at the EAB.

l Dose Rate = (step 19) x (5.3 E+4 Rem / hour) x (step 9) l ( C1/m*) l =( ) x (5.3 E+4) x ( ) O = Rem / hour If the resulting dose rate at the EAB is a 5 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency Condition. Then go l directly to Step 23 of this attachment. Site Area Emergency Determination l 21. Criteria for Site Area Emergency: If Step 17 is greater than or equal to 6.7 E-5 pCi/ce, the classification of the event is SITE l AREA EMERGENCY. Inform the Shift Supervisor of the Site Area l Emergency Condition. Then go directly to Step 23 of this attachment. Radiological Alert Determination l 22. Criteria for Radiological Alert: If Sten 17 is greater than or l equal to 7.0 E-8 pC1/cc (ten times the Technical Specification l limit), the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. , Then proceed with Step 23. l O G FORM iC1372 + 22 3643 i.

                                                                                          ..             _     .=_-

RERP Section 10.8 Issue 5 Public -FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 11 0 service

• PUBLIC SERVICE COMPANY OF COLORADO I .

l l Curies of Radioiodine Released l l 1 . l 23. Calculate the curies of radioiodine released to present time. i Curies Released = (step 19) x (step 3) x (3.6 E+3 sec/hr)

                                                =(             )x(        ) x (3.6 E+3)
                                                =                  curies l                                               I l      Accumulated Thyroid Dose at EAB          I I                                               I l 24. Calculate the dose received at the EAB.

I Dose = (step 20) x (step 3)

                                       =(               )x(          )

! = Rem , NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release. , I I ! l Projections l l l I l 25,- If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue l (i.e., fr5in b. ginning to end). Use two hours if no better l estimate is available. If the release has terminated, enter value from step 3. , _ Preliminary estimate of release hours hours. l 26. . Project the total thyroid dose at the EAB. - l Projected Dose at EAB = (step 20) x (step 25)

                                                                 =(        )x(          )
                                                                 =              Rem FORM tC1372 22 3643 '

1 RERP Section 10.8 Issue 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 'Page 10 of 11 m SGTVlCe* PUBUC SERVICE COMPANY OF COLORADO U l 27. Determine the recommended protective action for the general l population based on the results of steps 16 and 26. (Refer to l -RERP-PAG.) l 28. The whole body gamma dose rate at the EAB is (step 10): Rem / hour l 29 The classification of the event based on noble l gases is (step 10 or step 11 or step 12): l 30. The noble gas release rate is (step 8): Ci/sec l 31. The accumulated whole body gamma dose at the EA8 l _is (step 14): Rem l 32. The total number of curies of noble gas release l to the present time is (step 13): Curies l 33. The projected whole body gamma dose at the EAB is l- (step 16): Rem l Based on projected release duration of (step 15): hours l 34. The thyroid dose rate at the EAB is (step 20): Rem / hour t O FORM (C)372 22 3643

( RERP Section 10.B Issue 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 11 0SerVlCe* PUBUC SERVICE COMPANY OF COLORADO l 35. The classification of the event based on radio- [ iodines is (step 20 or step 21 g step 22):

• l 36. The radioiodine release rate is (step 19): C1/sec l 37. The accumulated. thyroid dose at the EAB is l (step 24): Rem l 38. The total number of curies of radioiodine l ~ released to the present time is (step 23): Curies l 39. The projected thyroid dose at the EAS is l (step _26): Rem l . Based on projected release duration of (step 25): hours

/

         .            *If this classification differs from the classification in step l         29, the higher (i.e., more severe) classification is to be used l         to determine recommended ;;rctective actions.

O

                                                                         ~

3 0 . FoRMICl372 22+3643

w e r L ,o m l b .n. reaczl 800K 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION O service

• PUBUC SERVICE COMPANY OF COLORADO 2/21/85 0 .

RADIOLOGICAL EMERGENCY RdSPONSE PLAN - STATION ISSUE EFFECTIVE NO. SUBJECT NUMBER DATE RERP-ECP Executive Command Post Procedure 9 10-10-84 RERP-EXP Emergency Exposure Guidelines 2 08-06-84 RERP-FCP Forward Command Post Procedure 11 08-06-84 RERP-FIELD Field Monitoring Procedure 6 08-06-84 l RERP-HOME Home Packet for Off-Shift l Notifications 14 03-21-85 RERP-ORG FSV Emergency Organization and Responsibilities 7 10-10-84 l RERP-PAG Protective Action Guideline

 ]     l                   Recommendations                           4      03-21-85 l RERP-PCC          Personnel Control Center Procedure       15      03-21-85 RERP-SE0C        State Emergency Operations Center Procedure                                 9      10-10-84 RERP-SURVEY      Inplant/Onsite Radiological Monitoring                                4      08-06-84 Thyroid Blocking Agent RERP-THYROID Administration                            4      10-10-84

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o PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Issue 14 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 5

                                                                                                                            ,cmm eq                                                                                                         f,ly yORT 8' VEA8 5 f-f O                                                                                                                         CONTROLLED M TITLE:     HOME PACKET FOR OFF-SHIFT NOTIFICATIONS                                              ((

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ISSUANCE 9 AUTHORIZED iM 2) BY h 'yN _f $-<,/- t f G " A ' **"* " REV EW AI l 4:N ATE 7S~ Sections Description Pace 1.0 Cri te ri a for Impl ementa tion . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Procedure.................................................... 3 3.0 Re s p o n s i b i l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4.0 References .................................................. 5 5.0 Ref erenced or Supoorti ng Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . 5 g Figure 1 Notification Fanout................................... I t  ? Figure 2 Facility Staffing Requirements ...................... 1 Checklist 1 Management Contact Notification List for an UNUSUAL EVENT........................................ 1 Table 1 Plant Management Contacts............................ 1 Table 2 Non-Emergency Event: Four-Hour Report .............. 1 Table 3 Non-Emergency Event: One-Hour Report................ 1 Table 4 NOTIFICATION OF UNUSUAL EVENT Table.................. 1 Table 5 ALERT Tab 1e.......................................... 1 Table 6 SITE AREA EMERGENCY Tab 1e............................ 1 Table 7 GENERAL EMERGENCY Tab 1e.............................. 1 Attachment 1 Impaired Fire Protection Notice (ANI) .......... 1 Attachment 2 Initial Notification, Non-Emergency Event . . . . . . 1 Attachment 3 NOTIFICATION OF UNUSUAL EVENT (Notification Form) ............................ 1 Attachment 4 Notification of Emergency Event ................ 1 FORM 372 22 3642 \

P RERP-HOME Issue 14 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 5 0 Service ~ rusuc sanvece comeamy or cotonaoo j O . l Attachment 5 ECP Director's Call List......................... 1 Attachment 6 FCP Di rector's (CEDs) Call Li st . . . . . . . . . . . . . . . . 1 Attachment 7 PCC Di rector's Call L1 st. . . . . . . . . . . . . . . . . . . . . . . . 1 Attachment 8 State EOC Call List ............................. I Attachment 9 TSC Director's Call List........................ 1 Attachment 10 Facility Directors / Alternates .................. 1 O l I O ro w ici m . m . nes , (

RERP-HOME Issue 14 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 5 OSerVlCe* PUBUC SERVICE COMPANY OF COLORADO O-v General This procedure is provided for use, at home, by plant management contacts, RERP facility directors and alternates, and by the first individual on each facility director's call list. The purpose of this procedure is: (1) To assist plant management in determining the severity of an occurrence when contacted at home by the FSV duty Shift Supervisor; (2) To provide plant management contacts with copies of notification forms to assist the the duty Shift Supervisor in their completion; (3) To provide required telephone numbers for facility activation if required; and, (4) To assure that individuals who may potentially be required to call-in individuals for off-shift emergency facility activation are clearly identified. 1.0 Criteria for Implementation This procedure may be utilized under virtually any off-normal off-shift situation where consultation regarding reportability or activation requirements must be addressed. 2.0 Procedure 4 2.1 ANI Notifications Notification to American Nuclear Insurers (ANI) is O rea#iree uader five (s) seaer i catesories iisted beio : a Losses believed to be near, or above, the deductible ($50,000); Incidents where fixed fire protection systems have operated under other than test conditions;

• Incidents where prompt assistance could help prevent further loss or expense, 'or where assistance is otherwise desireable; Incidents where incendiarism or malicious mischief is suspected; or

                        =

Emergency impairments to fire protection equipment. Whenever the on-duty Shift Supervisor believes an occurrence matches one of these circumstances, he will contact a plant management contact for consultation (where possible). The Shift Supervisor and plant management contact will jointly complete Attachment 1 to this procedure. Additional plant management contacts may be made utilizing Table 1 for reference. n FOAMICl372 22 3M3

RERP-HOME Issue 14 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5 service

• PUBUC SERVICE COMPANY OF COLORADO 2.2 Non-Emergency Event Notifications Notification to the NRC operations center within four (4) hours is required for events which fall under the general descriptions shown in Table 2, and within one hour for events as described in Table 3. When these events transpfre, or when the on-duty Shift Supervisor believes an event may require such reporting, he may contact one of the plant management contacts listed in Table 1.

Together, where possible, they will jointly complete the "Non-Emergency Event Notification Form," Attachment 2 of this procedure. Additional plant management contacts may be made at the Shift Supervisor's discretion utilizing . Table 1. 2.3 Radiological Emergency Response Plan (RERP) Notifications Notification to offsite authorities within fifteen (15) minutes and to the NRC within one hour of event classification is required when a situation has arisen that meets classification criteria set forth in Tables 4-7 of this procedure. Events classified as a NOTIFICATION OF UNUSUAL EVENT are reported to the state utilizing the notification format of Attachment 3. The plant management contact shall assist the completion of this form. If the O event is an ALERT, or higher, RERP event, Attachment 4 shall be completed. The Shift Supervisor may consult with plant management regarding incident classification, I although this does not preclude classification from being l his responsibility. 2.3.1 NOTIFICATION OF UNUSUAL EVENT For a NOTIFICATION OF UNUSUAL EVENT, where appropriate, the initial management contact shall notify other contacts per Checklist 1 and forward the completed form to the Technical Services Department. 4 l lO FORM (C)372 22 3643 k

RERP-HOME Issue 14 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 5 , O Service

• PUBUC SERVICE COMPANY OF COLORADO  !

2.3.2 ALERT or Higher RERP Event For an ALERT or higher RERP event, the notification fanout shown in Figure 1 of this procedure shall occur to assure prompt facility activation and staffing. Under these conditions, Facility Directors will be contacted by the PSCo Telephone Operator. The Facility Director will in turn contact his alternate. The alternate, or the next person contacted, is then responsible for performing the additional notifications specified herein. Each facility's call list is reproduced as l Attachments 5-9 to this procedure. The Facility Director primary and alternates are shown on Attachment 10. 3.0 Responsibilities 3.1 Duty Shift Supervisor Classify the situation, contacting a plant management contact for assistance in accordance with existing Operations Orders, Notification Procedures, or RERP-Implementing Procedures, where possible. () 3.2 Plant Management Contacts Assist the Shift Supervisor, as required, and perform additional notifications, as appropriate to a given situation. 4.0 References 4.1 FSV Radiological Emergency Response Plan l 5.0 Referenced or Supporting Procedures 5.1 RERP-PHONE LISTS

               , 5.2   RERP-CR, Control Room Procedure S

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1 RERP-Home , Checklist 1 i Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBUC SERVICE COMPANY OF COLORADO Page 1 of 1 O

MANAGEMENT CONTACT NOTIFICATION LIST FOR AN UNUSUAL EVENT The first management contact will make the following notifications, and forward the completed form to the Technical Services D.epartment. l Subsequent l Date/ l l l Contacts l Time l Remarks l l Plant Management l l l l(Contact 1) l l l l Supt. of Oper. l l l l218: 532-3489 l l l l Station Manager l l l l202: 663-2363 l l l l Administrative / l l l l Tech. Serv. Mgr. l l l l201: 457-8034 l l l l Manager, Nuclear l l l l Production l l l l200: 452-0507 l l l l Support Services l l l l Manager l l l l203: 663-1230 l 1 l Os lVice President, l , l l Production l l l 1571-7105 l l l l659-1180 l l l Media Relations l l l Bob Burns l l l l571-7726 l l l l759-9740 l l l 1 or l l l l Gary Reeves l l l l571-7726 l l [ l424-4958 l 1 l l or l l l lMarily Mora l l l l571-8462 l l l l694-2369 l l l l NRC l l l lG.L. Plumlee, IIIl l l l490; 776-9541; I l l lPager: 890-2225 l l l

• Calls to PSC ' phones from outside of the PSC telephone system may require use of a different telephone exchange. In these cases, utili a the exchange in parentheses.

O FORMiCl372 22 3043

RERP-HOME Table 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service ~PusuC ssRviCE COMPANY OF COLORADO Page 1 of 1 O TABLE 1 PLANT MANAGEMENT CONTACTS

• Page Plant Home Phone Ext. Phone Supt. of Operations 890-0558 218 532-3489 Station Manager 890-0810 202 663-2363 Tech./ Admin.

Serv. Manager 890-1941 201 457-8034 Mgr. Nuclear Prod. 890-6359 200 452-0507 Support Services Manager 890-1775 203 663-1230 l Vice Pres., Prod. 890-2834 571-7105 659-1180 0 Listed in order of pref erred contact sequence. O FORMICl372 22 3M3

RERP-HOME Table 2 i Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 ,

O TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiating Event

1. Any event, found while 1. Determination as result of the reactor is shut- surveillance testing of Plant down, that, had it Protective Systems (PPS) that been found while the failure of PPS modules would reactor was in oper- have prevented a required ation, would have re- reactor scram from occurring.

suited in the plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that significantly compromises plant safety. q G

2. Any event or condition that results in

2. Reactor scrams, loop shutdowns, and automatic starting and manual or automatic loading of diesel generators actuation of an only.

Engineered Safety Feature, including EXCEPTIONS: the Reactor Protection System. a) Manual scram initiated at 2% during a normal shutdown. b) Only one of three channels

                                              ,     tripped manually or auto-matica11y, bu*. no final protective act en takes place, nor is required.

c) Actuation of the afore- , mentiened systems which result from, and are a part of, the planned sequence during surveil- , lance testing or reactor l operation. l . I vomc> m.n.ms t

l RERP-HOME I Table 2 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBLIO ofRVICE COMPANY OF COLORADO Page 2 of 4 O

V TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Tyoical Indication Initiating Event

3. Any event.or condition 3. a) During refueling operations, that alone could have a .0 lap shutdown margin prevented the ful- is not maintained due to fillment of the safety incorrect rod removal function of structures sequence.

or systems that are needed to: b) Incorrect valve lineup which results in shut off a) shut down the reactor of secondary system decay and maintain it in heat removal sequence. a safe shutdown condition; c) Liquid waste monitor setpoints raised for liquid waste release b) remove residual heat; completed. Reactor Building sump pumps taken out of c) control the release pull-to-lock. Setpoints not of radioactive reset. , material; or d) Less of HEPA filtration. d) mitigate the con-sequences of an accident. b v FORMIC)372 22 3643

RERP-HOME Table 2 Public . FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4 O

TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event _ Typical Indication Initiatina Event

4. a) Any airborne radio- 4. As determined by analysis active release that and evaluation.

exceeds 2 times the applicable concentra-tions of the limits specified in Appendix B, Table II of 10CFR20 in unrestricted areas when averaged over a time period of one hour. b) Any liquid effluent release that exceeds 2 times the limiting combined MPC (see Note 1 of Appendix B of 10CFR20) at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour. NOTE: Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR20.403.

5. Any event requiring 5. As occurring.

the transport of a [ radioactively contam-inated person to an offsite medical l facility for ! treatment. . FORM tCl372 22 3643

c i RERP-HOME Table 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 l OPublic Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 O

TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiating Event

6. Any event or situation, 6. a) Onsite fatality for which related to the health a news release will be made.

and safety of the public or onsite personnel, or b) Inadvertent release of protection of the environ- radioactive material not ment, for which a news in excess of 10CFR20 limits release is planned or for an unrestricted area, notification to other but requiring report to government agencies has the State. been or will be made. c) Oil or chemical spill which could reach the South Platte River or St. Vrain Creek and which is therefore reportable to the EPA. O FORM (C1372 22 3643

RERP-HOME Table 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 i 0SerVlCe* PUBLIC SERVICE COMPANY OF COLORADO Pags 1 of 3 O TABLE 3 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event hoical Initiating Event

1. a) The initiation of 1. a) As occurring.

any plant shutdown required by Technical Specifications. b) Any deviation from b) Any deviation from a Tech-Technical Specifica- nical Specification, when tions authorized the action is immediately pursuant to needed to protect the 10 CFR 50.54(x). public health and safety, and no action consistent with Technical Specifica-ions which can provide adequate or equivalent protection is immediately apparent. (The action should be approved, as a (~ s minimum, by a senior

    \

licensed operator.)

O 1

l - FORM (C)372 22 3843

RERP-HOME Table 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 OSerVICe* PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 TABLE 3 NON-EMERGENCY EVENTS: ONE-HOUR rep 0RT Event Typical Initiatina Event

2. Any event or condition during operation that results in the condi-tion of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:

a) In an unanalyzed 2. a) As determined. condition that significantly compromizes plant ~ safety; b) In a condition b) 1. Reactor pressure in that is outside excess of design J the design basis limits with failure of the plant; or to trip plant.

2. Winds experienced in excess of FSAR design levels, c) In a condition c) As determined.

not covered by the plant's operating and emergency procedures.

3. Any natural phenomenon 3. a) Toxic gas release in imme-or other external diate vicinity of plant.

condition that poses an actual threat to the b) Extremely high winds or safety of the plant or severe storm preventing significantly hampers plant personnel from site personnel in the completing requisite performance of duties assignments. necessary for the safe operation of the plant. 0 v l FORMtC)372 22 3643 I l  ! I , _ _

RERP-HOME Table 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 SerVlCe* PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 O TABLE 3 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical Initiating Event

4. Any event that results 4. a) Loss of significant in a major loss of portion of Control Room emergency assessment indication.

capability, offsite response capability, b) Loss of all offsite or communications communication systems. capability.

5. Any event that poses 5. a) Fire posing undue an actual threat to the personnel hazard.

safety of the plant, or significantly hampers b) Severe chlorine release site personnel in the from chloiine cylinders. performance of duties necessary for the safe c) Accidental gaseous radio-operation of the plant, logical release resulting including fires, toxic in onsite concentrations ] gas releases, or radioactive releases. in excess of 10 CFR 20 Appendix B, Table I.

~.

1

                                                                                            )

(% 1 b I omc> m.m. l l

                                                                .        ..           . _ .i

RERP-HOME Table 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 TABLE 4 NOTIFICATION OF UNUSUAL EVENT Event Indication

1. Any unplanned radio- 1. Alarms on:

logical release to RT 7312 the Reactor Building CAM (s) or its ventilation RT 7324-1 system. RT 7324-2 RT 7325-1 RT 7325-2 RT 4801 RT 4802 RT 4803 - RT 73437-1, 2

2. Any liquid waste re- 2. a) RT 6212 or 6213 alarm lease resulting in with inability to prevent offsite effluent in discharge offsite.

excess of Technical Specification limits. b) As determined by station personnel.

3. Indication of minor 3. a) 25% increase in

~~ fuel damage detected circulating activity in primary coolant. from previous equilibrium cond-itions at the same power level. RT 9301 (RR 93256). b) SR 5.2.11 results.

4. Serious fire at the 4. a) any of various alarms plant lasting more on Fire Control Alarm

             'than 10 minutes                           Panel; which could lead to substantial                      b)    Fire Pump 1A auto degradation of plant                      start; safety systems, or which could result-                 c)    verbal reports.

in the release of radiologial or toxic materials. FoRMICI372-22 3643

l i RERP-HOME Table 4 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 , 0 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 4 ;

(~) l (_/ I l TABLE 4 NOTIFICATION OF UNUSUAL EVENT Event Indication

5. Abnormal coolant temp- 5. Violations of eratures or core region LCO 4.1.7 or LCO 4.1.9 temperature rises for region outlet to the extent mismatch, or region requiring shutdown in AT, respectively, accordance with to the extent that Technical Speci- shutdown per Station fications. Technical Speci-fications is required (SOP 12-04).

6. Natural phenomenon that 6. a) Seismic Recorder may be experienced Operate; or threatened that represent risks beyond b)-d) as visually observed normal levels: by, or reported to,

(' a) b) earthquake floods tornadoes station personnel. c) d) extremely high winds

7. Unusual Hazards 7. As visually observed by, Experienced: or reported to, station personnel, a) Aircraft crash on site or near the site that is subject to public concern because of possible detrimental effect on the plant; b) Onsite explosions or near site explosions that may be subject to public concern because of possible detrimental effect on the plant; or, O

FORM (Cl372 22 3643

RERP-HOME Table 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4 O TABLE 4 NOTIFICATION OF UNUSUAL EVENT Event Indication

7. c) Onsite or near site plant related accidents that could result in the release of toxic material or spills of flammable materials.

8. Any serious radio- 8. As occurring. '

logical exposure of plant personnel or the transportation to offsite facilities of contaminated personnel who may have been injured. s (Probably cannot be determined within two hours- call to be made in a timely fashion.)

9. Accidents within the 9. As occurring, or state that may reported by shipper.

involve plant spent fuel shipments or plant radio-active waste shipments.

10. Loss of Engineered 10. Shutdown required in Safety Feature or Fire accordance with applicable Protection System to LCOs:

the extent requiring Shutdown a) Engineered Safeguards in accordance with station Teghnical Specifications. 1) Plant ventilation-LCO 4.5.1 s 2) Steam / Water Dump

j. System - LCO 4.3.3 ,

FORMICl372 22-3843

l RERP-HOME , Table 4  ! Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 l OSerVIC9" PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 l TABLE 4 NOTIFICATION OF UNUSUAL EVENT Event Indication

10. (Cont). 3) PCRV penetration flow restriction devices - LCO 4.2.7 and LCO 4.2.9

4) PCRV penetration secondary closures -

LCO 4.2.7 and LCO 4.2.9

5) PCRV Safety Valves -

LCO 4.2.8 SL 3.2 LSSS 3.3.2.c b) Fire Protection System -

                                                                              ~

t t' ' O 11. Indication or alarms 11. Data Logger Alarm / Alarm on radiological effluent Summary indication of non-monitors not functional. operational alarm or indication on: a) RT 7324-1, 2 and RT 4803; or b) RT 7325-1, 2, RT 4802, and RT 73437-1; or c) RT 73437-2 and RT 4801; or d) RT 6212 ag RT 6213. NOTE: Use ELCO 8.1.1 Technical Specification Limits as basis. FORM (Cl372 22 3M3

RERP-HOME Table 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 5  !

o l TABLE 5 i ALERT Event Indication  !

1. Rapid, severe fuel 1. Coolant Inventory of particle coating a) >2.4 (CI) (Mev) Beta-Gamma failure. Ib b) circulating I-131 activity equivalent >24Ci c) plate out I-131 >1x10' Ci d) SR 5.2.6 or SR 5.2.11 results.

2. Rapid, gross failure of 2. Loop 1 Hot Reheat Header (HRH) one steam generator reheat activity high (5 mrem /hr);

section with loss of or, Loop 2 HRH activity offsite power. high (5 mrem /hr) accompanied by 230 Kv OCB trips P

 \

and RAT undervoltage/ loss of power alarm.

3. Primary coolant pressure 3. PAL 9335 decay (to a value greater PAL 9347 than 100 psi less than PAL 9359 normal pressure, and area monitor accompanied by area and or stack monitor alarm stack radiation monitor alarms).

4. High radiation levels or 4. RT 7312 high airborne contamination CAM (s) alarm

              'which indicates severe             RT 6212 degradation in control of          RT 6213 radioactive materials.             RT 93252-12 (Increase by factor               Area Monitors of 1,000 over normal.).

e.g. lifting PCRV relief valve or abnormal release to cooling tower blowdown. Alarms with corresponding meter readings on area or process monitors. FORM (C)372 22-3843 L

RERP-HOME Table 5 . Public FORT ST. VRAIN NUCLEAR GEN iRATING STATION Issue 14 l O ServlCe* PUBUC SERVICE COM?ANY OF COLORADO Page 2 of 5 o V TABLE 5 ALERT Event Indication

5. Loss of offsite power and 5. 230 KV OCB trips and RAT vital onsite AC power undervoltage/ loss of power alarm for up to 30 minutes, accompanied by 4 KV bus undervoltage 480V bus under-voltage, and Diesel Trouble alarms.

6. Loss of all vital 6. DC bus 1 < 10 volts and DC power for up to DC bus 2 < 10 volts 30 minutes. /

7. Loss of primary coolant 7. All He flow indicators read forced circulation for zero.

between 2 and 5 hours.*

8. Loss of secondary coolant 8. All secondary coolant flow functions needed for indicators read zero.

removing residual heat.

9. Loss of normal ability 9. a) Indication of insufficient to place the reactor in rods inserted; or, a subcritical condition by scram of the control b) neutron rods. count rate not decreasing.

10. Serious fire which could 10. a) any of various alarms on lead to substantial Fire Control Alarm Panel degradation of plant safety systems. b) Fire Pump 1A auto start c) verbal reports These times are LOFC from 100% power. Times may be correspondingly longer for lower power levels (See LCO 4.2.18).

.O FORM (C)372 22-3643

RERP-HOME Table 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 133ye }4 OSerVICO" PUBLIC SERVICE COMPANY OF COLORADO Page~3 of 5 TABLE 5 ALERT Event Indication II. Radiological effluents 11. a) RT 7324-I indicating

                                                               ~

exceed 10 times technical 22.5 x 10 2 pCi/cc specifications instan-tenous limits. b) RT 7324-2 indicating

                                                               ~

22.5 x 10 2 pCi/cc c) RT 7325-1 indicating

                                                               ~

27.0 x 10 ' pCi/cc d) RT 7325-2 indicating

                                                               ~

27.0 x 10 ' pCi/cc e) RT 73437-1 indicating

                                                               ~

27.0 x 10 ' pCi/cc I-131. O f) a1 48o2 indicatins

                                                                 ~

2 7.0 x 10 ' pCi/cc I-131. g) RT 4803 indicating

                                                                 ~

2 2.5 x 10 2 pCi/cc Utiliza reading from above instruments and calculate dose rate per procedures

12. Ongoing security 12. As observed or reported, compromise.

O FORM (C)372 22-3643

RERP-HOME Table 5 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 j O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 5 ' i O TABLE 5 ALERT Event Indication

13. Severe natural phenom- 13. a) Seismic recorder operate enon being experienced or (2.05 g) or projected, such as:

b) As Reported a) earthquake exceeding Operating Basis c) As Reported Earthquake levels; b) flood near design level; or, c) tornado striking facility.

14. Other hazards being 14. As reported by, or to, experienced or projected station personnel.

such as: a) aircraft crash on facility; b) missile impact on facility; c) explosion damage affecting plant operation; or, d) entry into facility environs of toxic or flammable gas. (Some effect on facility ex-perienced or anticipated)

15. Evacuation of control 15. As deemed necessary by room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations.

(Control room integrity breached). O  ! l l FORM (C)372 22 3643

RERP-HOME Table 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 Service PUBLIC SERVICE COMPANY OF COLORADO Page 5 of 5 O TABLE 5 1 ALERT Event Indication

16. All alarms 16. Control room observation.

(annunciators) lost for more than 15 minutes and reactor is not shutdown; or, plant transient experienced while all alarms lost. (Parameter indication still functional.)

17. Other plant conditions 17. As deemed necessary by warranting precautionary Shift Supervisor, activation of the PCC, TSC, and FCP.

O 1 O

          . FORMIC)372 22 3643 l

RERP-HOME Table 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 Public service

• PUBLIC SERVICE COMPANY-OF COLORADO Page 1 of 4 O

TABLE 6 SITE AREA EMERGENCY Event Indication

1. Loss of primary coolant 1. All He flow indicators read forced circulation for zero.

over 5 hr from 100% power. (Lower power levels preceeding LOFC extends time available before core damage is incurred. See LCO 4.2.18.)

2. Non-isolable primary 2. Loop 1 or 2 HRH activity coolant leakage through a alarm-high with Shift steam generator reheat Supervisor determination section. that leakage is non-isolable.

3. PCRV relief valve remains 3. RT 93252-12 alarm and rapidly Q open. decreasing Reactor pressure.

4. Determination of inability 4. 230 KV OCB trips and RAT to restore onsite AC undervoltage/ loss of power power. alarm accompanied by 4Ky bus undervoltage, 480v bus undervoltage, and Diesel Trouble alarms. Standby Diesel Fail to Start.

5. Loss of functions needed 5. Inability to insert for plant hot shutdown. sufficient control rods accompanied by failure of emergency reserve shutdown system - resulting in inability to maintain .01Ap at 220 F.

6. Major damage to spent 6. a) Visual observation.

fuel due to severe cask damage resulting in release b) area radiation monitor of radioas.'ivity to plant alarms. environs. 1 1 O l omeim.m. l

RERP-HOME Table 6 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O service

• PUBUC SERVICE COMPANY OF COLORADO Page 2 of 4 O

TABLE 6 SITE AREA EMERGENCY Event Indication

7. Fire adversely affecting 7. a) Fire pump 1A start; safety systems.

b) Fire Control Alarm Panel c) Various alarms according to affected safety system. / d) Shift Supervisor determines fire beyond capability of station staff.

8. a) Effluent monitors 8. Stack monitor alarm with detect levels corresponding stack corresponding to concentration indications O greater than 50 mrem / on:

hr,y greater than 500 mrem /hr a) RT 73437-1, RT 4802, whole body for two and RT 7325-1, 2 minutes at the

                                                                      ~

site boundary under 26.7 x 10 5 uC1/cc l adverse meteorology I-131; or, (or levels 5 times the above for thyroid b) RT 7324-1, 2, dose rate), and RT 4803

                                                             >6.6 x 10 2 pCi/cc b)      These dose rates are                 mixed noble gasses.

projected based on other plant parameters or are l measured in the environs.

9. Imminent loss of physical 9. Situation evident, control of the plant due to security breach.

(Response detailed in Station Security Plan.) O FORM (C)372 22 3M3

RERP-HCME Table 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0Public Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4 O

TABLE 6 SITE AREA EMERGENCY Event Indication

10. Severe natural phenomenon 10.

being experienced or projected (with plant not in cold shutdown), such as; a) earthquake greater a) Seismic Recorder Operate than Safe Shutdown alarm with indication of Earthquake ground motion greater than 0.10g horizontal or greater than 0.0679 . vertical. b) flood greater than b) As reported or observed. design levels f') v c) winds in excess of design levels c) average wind velocity greater than 90 mph or 10 second gusts exceeding 99 mph. d) tornado in excess of d) horizontal wind design levels velocity greater than 202 mph.

11. Other hazards being 11. As observed by or experienced or projected reported to, station with reactor not shutdown, personnel.

such as;

           'a)      aircraft crash affecting vital structures; b)      severe damage to safe shutdown equipment; c)      entry of toxic / flammable gas into vital areas.

12. Reactor building louvers 12. a) Louvers Open Alarm open due to building (3 inches water) being overpressurized p by primary coolant. b) Reactor building d (DBA #2) radiation alarms.

FORMICl372 22 3543

RERP-HOME Table 6 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O service

• PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 l

TABLE 6 l SITE AREA EMERGENCY Event Indication

13. Evacuation of control 13. Remote shutdown room, accompanied by instrumentation indications inability to locally (panel I-49).

control shutdown systems within 15 minutes.

14. Other plant conditions 14. As determined by warranting activation of Shift Supervisor.

FCP/EOCs, monitoring teams, and precautionary public notification. O I FORMIC)372 22 3843

RERP-HOME Table 7 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14

      ) SerVIC9"             PUBLIC SERVICE COMPANY OF COLORADO              Page 1 of 1 O

TABLE 7 GENERAL EMERGENCY Event Indication

1. a) Effluent monitors 1. Stack monitor RT-7324-1, 2 detect levels alarm, or corresponding to Corresponding dose 1 rem /hr. whole rates determined with body (or 5 rem /hr E-500 or cutie pie thyroid) at the detector per exclusion area procedure HPP-56 and boundary under associated graphs.

actual meteoro-logical conditions. b) These dose rates are projected based on other plant para meters, or are measured Q in the environs.

2. Loss of physical control 2. Situation evident.

of the facility. (due to security breach).

3. Other plant conditions 3. As determined by exist that make release Shift Supervisor.

of large amounts of radioactivity possible. O FORMtCl372 22 3843

RERP-HOME Attachment 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4

(/t ATTACHMENT I IMPAIRED FIRE PROTECTION NOTICE Report No. - Year Sequence No. NOTE: It is important that the time of all calls and names of people contacted be logged. Any futher followup calls received or made should be logged as to time and identity of persons involved and the information transmitted or received shall also be logged. GIVE THIS INFORMATION AS SHOWN

1. Facility Name: Public Service Comoany of Colorado Unit No. One

2. Location: Fort St. Vrain, Platteville, Colorado Below Is the Information Which Will Be Requested Of The Caller

3. Caller's Name: Phone:

4. Date and time of occurrence:

5. Details and extent of impairment:

6. Did impairment result from a loss? l((l*Yes l(([lNo If yes, details:

• Loss would be a fire, accidental system operation, windstorm damage, etc.

7. Restoration (of system) begun? l(( lyes l((lNo ,

l f Restoration work to be continuous? l(([Yes l((lNo

8. Impaired area or equipment operable? l(( lyes l((lNo o

l -) Estimated restoration time: FORMICl372 22 3843

RERP-HOME Attachment 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 4 O

9. Precautions: l[lValvestaggedout l[lDiscontinuedwelding, cutting,andhotwork l[l Discontinued smoking l l[lNotifyControlRoom(Shift) Supervisor,or other applicable management.

((l Notify Fire Department / Fire Brigade l[lIncreasedwatchmanserviceto hourly l[lExtraextinguishers/firehoseinarea Other:

10. Contacts made by Shift Supervisor:

a) Name of ANI contact: b) Time of ANI contact: O sanasement

Contact:

a) Name of management contact: b) Time of management contact:

11. Additional contacts made/ received:

a) Per attached call sheet log. I I l 12,. RESTORED l l l l a) Repeat Steps 1 and 2 above l l l l b) Caller's Name: l l l l c) Date and time of restoration: l l l l d) Name of ANI contact: l l l l e) Time of ANI contact: l l l

13. The Shift Supervisor shall send the completed copies of the O co aietee forms eirectiv to Teca#4cai services.

FORM tC)372 22-3643

RERP-HOME Attachment 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Service" PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4

14. If Notification was a Fire /All-Ri sk Emergency, Technical Services will:

a) Determine if a Reportable Occurrence is required, and prepare a facsimile copy if a 14 day report is indicated. b) Assign a sequential number and send a copy to the  ! Superintendent, Operations and a copy to PORC. i O l i

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i O  ! Fo#M C 372 22 3643

RERP-HOME l FORT ST. VRAIN NUCLEAR GENERATING STATION y O Public service

• PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 l O

I I I I I I l CALL I TIME I DATE I CONTACT (NAME) l COMMENTS / REMARKS I I I I I I i i I I I I I I I I I I I I I I I I l l 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l l l l 1 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 I I I I I I I I I I I I I I I I I ~1 O i i i l i i i I i I i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 I I I I I I I I I I I I I - 1 I I I I I I I I I I I I I- 1 I I I I I I I I I I I I I I I I I I I I I -1 I I I I I I l I I I I I I I I I I I I I I I O FORMC372 22 3643

RERP-HOME Attachment 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 OSerVICO PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 4 im

 \

Initial Notification, Non-Emergency Event Report No. - Year Sequence No. IMPORTANT: It is important that the time of all calls and names' of people contacted be logged. Any further follow-up calls received or made should be logged as to time and identity of persons involved and the information transmitted or received shall also be logged.

1. Name and Identity of Caller: ,

2. Date of Event: Time of Event:

3. This notification appears to be required pursuant to 10CFR 50.72, paragraph ((b)(1), "One-Hour Report"; or (b)(2),

                "Four-Hour Report") (circle one).

4. Description of Event:

Reactor power prior to event: _ Q Loop Shutdown? Scram? Initiating signal (s): Was event result of an LCO Action Statement? Other pertinent information:

5. Actions Taken:

O FORM (C)372 22 3643 l

RERP-HOME Attachment 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 4

6. Status: ,

Reactor power at time of report: Under control by on-site staff, no off-site assistance anticipated. Final report. l Under control by on-site staff. Will keep NRC advised. Off-site assistance may be required. Will advise. (See Item #7) Off-site assistance required. (See Item #7)

7. If off-site assistance is anticipated or required, describe assistance that has been or may be requested: j

8. Does the event involve off-site releases of the potential for off-site release that would affeact the general health and safety of the public as the result of Fort St. Vrain conditions?

Yes No

9. If yes, provide a good description:

10. Contacts made by Shift Supervisor:

a) Name of NRC conta::t: b) Time of NRC contact: A V FORM (C)372 22-3643 J

                                              -                                    _                      ---       -- ,-   r

I RERP-HOME Attachment 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 4 1 O l Management Contact a) Name of management contact: b) Time of management contact:

11. Contacts made by management:

a) Per attached call sheet log.

12. The Shift Supervisor and Management Contact shall ser.d their copies of the completed forms directly to Technical Service; who will:

a) Determine if a Licensee Event Report is required and prepare a facsimile copy if a 30 day report is indicated. b) Send a copy to the Superintendent, Operations. c) Send a copy to PORC. O O FORM tC)372 22 3643

l ! RERP-HOME Public FORT ST. VRAIN NUCLEAR GENERATING STATION ye O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 4 I I I i i l l CALL l TIME I DATE I CONTACT (NAME) i COMMENTS / REMARKS l l l 1 1 I I I I I I I I I I I I I I I I I I I I I I I I I i l l I I I I I I I I I I I I I I I I I I I I I '

I I I I I l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I O l l l l l l l l 1 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l l I I I I I I I I I I I I I I I -1 I l l I I I I I I I I I I I I I I I I I I I I I I

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I I I I I l I I I I I I I I I i 1 I I I I I I I I I I I I I I I I I I I I I -1 I I I I I I I I I I I I' I I I I I I I I I I I I I I I O j FORMtCl372 22 3043 ,.,

RERP-HOME Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O

NOTIFICATION OF UNUSUAL EVENT I A. The Emergency Coordinator and first management contact will complete the following information jointly:

1. Name and identity of calier l

2. Date of Event Time of Event

3. General Category of Event Unplanned Radiological Release to Reactor Building Fuel Failure

_ Fire Natural Phenomenon (circle one) Earthquake Flood Tornado Winds Unusual Hazards (circle one) Aircraft Explosion Toxic Material Other (Specify) Spent Fuel Incident

4. Description of Event

5. Actions Taken

6. Status:

Under control by onsite staff, no offsite assistance anticipated. Under control by onsite staff. Will keep State and NRC advised. Offsite assistance may be required. Will aovise. , (See Item 7.) Offsite assistance required. (See Item 7.). O v 4 FORMIC 1372 22 3643

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RERP-HOME Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 OSerVICe* PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 O '

7. If offsite assistance is anticipated or required, describe assistance that has been or may be required:

4

8. At the present time, the event does not involve offsite release or the potential for offsite releases that would affect the general health and safety of the public.

B. The Emergency Coordinator will make notifications as follows: l Contact with State E0C (279-8855) and Governor's Office (866-2471)l l or Mansion (837-8350) l l l

1. READ the following statement verbatim:

O TaIS IS ^ NOTIFIC^rr0N OF AN UNUSUAL EVENT AT TsE FORT ST. VRAIN NUCLEAR GENERATING STATION. THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF EMERGENCY RESPONSE CENTERS. THIS NOTIFICATION REQUIRES VERIFICATION OF RECEIPT BY THE STATE. VERIFY BY CALLING 571-7436 or 785-2223."

2. READ all the information recorded in Step A (Page 1 of this ATTACHMENT).

l FORMtC)372 22 3643 l J

RERP-HOME Attachment 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 OPublic Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3

3. RECORD the following information:

l Date Name of State E0C contact l Name of Governor's Office / Mansion Contact l Time l Call back verification from State EOC, Time Call back verification from Governor's Office / Mansion l Time

                                                                                  '~
                                                                          ~ ../

l l l Contact with NRC Operations Center (Hot Line or 202-951-0550) l l l (Alternate means of notification are described in Attachment 1 of RERP-CR.) O 1. RE^o the foiio ias statement verbatim:

                             "THIS IS NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING- STATION AT PLATTEVILLE, COLORADO. THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO 10CFR50.72,      PARAGRAPH    (a)(3). THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF FEDERAL OR          -

STATE EMERGENCY RESPONSE ORGANIZATIONS."

2. READ the NRC Operations Center all of the information recorded in Step A (Page 1 of this Attachement).

3. RECORD the following information:

l Name of NRC Contact Time v FORM (C1372 22-3643

l RERP-HOME l Attachment 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 service

• PUBUC SERVICE COMPANY OF COLORADO Page 1 of 5 NOTIFICATION OF EMERGENCY EVENT A. The Emergency Coordinator will complete Pages 1 and 2 of this attachment with the assistance of the first management corttact.

I i l Required Information l l l

1. This is (Name) , Shift Supervisor at the Fort St.

Vrain Station. l 2. At (Time) we declared an (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident. l 3. Refer to Protective Action Guidelines on page 3 of this l Attachment (item 15). l a) There is @, repeat @, radioactive release taking place, and no special protective actions are O recommemeed et this ti e-a b) A small radioactive release I_S taking place, but @ protective actions are recommended at this time and are not anticipated to be. c) A radioactive release I_S, repeat IS, taking place, and we recommend that people in areas remain indoors with

          ,                  windows and doors closed.

d) A radioactive release IS, repeat IS, taking place, and we recommend that evacuation of areas be considered.

4. Personnel Control Center to be located

5. Further information on . incident conditions will be provided in followup messages.

FORM tC1372 22-3643

RERP-HOME Attachment 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBUC SERVICE COMPANY OF COLORADO Page 2 of 5 l l l SUPPLEMENTAL INFORMATION l 1 1 I l l

NOTE: This information is to be supplied to the NRC and the Colorado l Department of Health only when requested. The radiological data can be determined as specified in RERP-DOSE.

1. Date and Time of Incident

2. Class of emergency (ALERT)(SITE AREA EMERGENCY)

(GENERAL EMERGENCY)

3. Type of release (airborne, waterborne, surface)

4. Estimated duration of release (Hours)

5. Current release rate:

Noble Gas Ci/sec; Iodine Ci/sec

6. Estimated curies released:

O "obie a = ci todiae c'

7. Wind Velocity MPH, from degrees.

to degrees, Air Temp F

8. Stability Category . Form of-Precip.

9. Dose rate at EAB: WB rem /hr; Thyroid rem /hr 2 Miles: WB rem /hr; Thyroid rem /hr 5 Miles: WB rem /hr; Thyroid rem /hr

10. ' Projected dose at EAB: WB rem; Thyroid rem 2 Miles: WB rem; Thyroid rem 5 Miles: WB rem; Thyroid rem

11. Estimated accumulated dose at EAB: WB rem; Thyroid rem l 12. Areas expected to be impacted by release l

FORMtC1372 22 3643

RERP-HOME Attachment 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 I OSerVICe* PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 5 l

13. Estimate of any surface radioactive contamination

14. On-site response actions under way

15. Recommended Protective Action based on the projected dose at the EAB (Read appropriate Protective Actions)

Projected Dose Recommended (rem) Protective Action Whole Body <1 No planned protective actions. State Thyroid <5 may issue advisory to seek shelter and await instructions. Monitor l radiation levels. (3b on page 1.) Whole Body 1 to 5 Take shelter and consider selective Thyroid 5 to 25 evacuation. Monitor radiation levels. Establish Controlled Area and limit l access. (3c on page 1.) () Whole Body 5 and above Thyroid 25 and above Conduct mandatory evacuation. Monitor radiation levels and adjust area for mandatory evacuation based on these l levels Control Access. (3d on page 1.)

16. Prognosis for worsening of event l 17. Time of report

18. Name of person providing report

19. Telephone number for call back

20. Description of any requested off-site assistance O)

FORMtC1372 22 3643 J

RERP-HOME Public FORT ST. VRAIN NUCLEAR GENERATING STATION e O SerVlCe*PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 5 B. The Emergency Coordinator will make notifications in sequence ) as follows: 1 I i 1 PSC Company Operator 8-571-4591 [ l or 8-571-0111 l l l

1. INSTRUCT the Operator to initiate the " Fort St. Vrain l Radiological Emergency Call List" and READ verbatim the l information recorded in Part A (Page 1 of this l attachment).

l 2. RECORD the following information: Time PSC Operator Notified Time Operator Callback Received i I I Weld County (911 Using Greeley Line) l Q l i

1. READ verbatim the information recorded in Part A (Page 1 of this attachment).

2. RECORD the following information:

Time Weld County Notified Time Weld County Callback Received I 1

                           .                                                      1 0

1 FORMC372 22 364

RERP-HOME Attachment 4 l Public FORT bT. VRAIN NUCLEAR GENERATING STATION Issue 14 i 0 SerVlCe PUBLIC SERVICE COMPANY OF COLORADO Page 5 of 5 O I l l NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l l l (Alternate means of notification are described in Attachment 1 of RERP-CR.)

1. READ Items 1) through 4) from Part A.

2. READ the following sentences verbatim. "THIS EVENT IS BEING REPORTED PURSUANT TO IOCFR50.72, PARAGRAPH (a)(3).

WE ARE PRESENTLY ACTIVATING STATE AND LOCAL EMERGENCY RESPONSE CENTERS."

3. READ the supplemental information'(Page 2 of this attachment).

4. RECORD the following information:

NAME of NRC Contact q TIME of NRC Contact v . i O FORMIC)372 22 3843

RERP-HOME Attachment 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 133ye 14 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 2 O ECP DIRECTOR'S CALL LIST INTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the folfowing telephone calls:

1. If you are the response center / post Director:

a. Call your response center / post Alternate Director (the alternate will complete the calls on the attached list).

b. If you cannot contact your Alternate Director, call the first person on the attached list and inform him to complete the call list.

2. If you are the response center / post Alternate Director and are contacted by the Director:

a. Complete the attached call list.

3. If you are the response center / post Alternate Director and are contacted by the PSC Operator:

a. Call the first person on the attached list and-inform him to complete the call list.

O FoRMtC)372 22 3643

RERP-HOME Attachment 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service" PUBUC SERVICE COMPANY OF COLORADO Page 2 of 2 O ECP DIRECTOR'S CALL LIST Fir call all primaries, then call all alternates. PSC Extension Home Time Manager - Technical Support l Primary - J. R. Reesy 571-8406 755-1720 l Alternate - M. E. Niehoff 785-1403 690-3879 Manager - Media Relations Primary - R. T. Person, Jr. 571-7323 753-9292 Alt. - W. D. Fitzmaurice 571-7713 424-8053 O Manager - Resources Primary - D. D. Hock 571-7211 394-3063 Alternate - J. Bumpus 571-78E1 388-7645 Manager - Security Pr71 mary-E.O'Neal 571-7709 757-0038 Alternate - E. Lane 571-8533 321-4016 l Alternate - D. Amick 571-7898 772-9378 O FORMtC1372 22 3843

RERP-HOME Attachment 6 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 SerVICG" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 2 O v CORPORATE EMERGENCY DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:

1. If you are the response center / post Director:

a. Call your response center / post Alternate Director.

b. If you cannot contact your Alternate Director, call the first person on the attached list and inform him to complete the call list.

2. If you are the response center / post Alternate Director and are contacted by the PSC Operator or the center / post Director:

a. Call the first person on the attached list and inform him to complete the call list.

(]) 3. If you are the first person on the attached list and are contacted by the Alternate Director or the Director:

a. Complete the attached list.

o O FonMtc)sn 22 3643

RERP-HOME Attachment 6 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O SOTVICe* PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 2 O CORPORATE EMERGENCY DIRECTOR'S CALL LIST (FCP) First contact all primaries, then call all alternates. Extension Home Time Station Technical Liaison (One of the Station Technical Liaisons is also contacted by the

 ,              PSC Operator.)

Primary - F. J. Novachek 785-1201 457-8034 Alternate - D. W. Warembourg 571-8419 833-4092 Alternate - L. W. Singleton 785-1350 772-1018 Radiological Assessment O Primary - T. Borst 785-1203 663-1230 (Pager) 890-1775 Clerical Assistance Primary - D. Merritt 785-1271 737-2339 Primary - D. Reichardt 785-1272 776-7435 Alt.ernate - S. Katcher 785-1212 356-0351 Media Relations Primary - M. Mora 571-8462 694-2369 Alternate - S. Volsted 571-7242 750-1785 l Security Support l The following individuals report to the Executive Command l Post but require access to the Forward Command Post. One l of these individuals will report to the FCP, in most cases. l If needed, contact the ECP at 571-8461. pd l Primary - D. Amick 571-7898 772-9378 l Alternate - E. Lane 571-8533 321-4016 l FOAM (C)372 22 3643 i

RERP-HOME Attachment 7 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O V PCC DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:

                                                                                         ]

1. If you are the response center / post Director:

a. Call your response center / post Alternate Director (the alternate will complete the calls on the attached list).

b. If you cannot contact yeur Alternate Director, call the first. person'on the attached list aM inform him to complete the call list.

2. If you are the response center / post Alternate Director and are contacted by the Director: -

a. Contact persons to set up the facility by calling those individuals with asterisks (*) after their

-Q names and by noti fying four (4) Health Physics Technicians listed. Inform all persons of the location of the PCC. Call the remainder of personnel upon arrival at the PCC. (This responsibility may be delegated.)

3. If you are the response center / post Alternate Director and are contacted by the PSC Operator:

a. Call the first person on the attached list ag inform him to complete the call list as specified in 2.a. above.

O FoflM(C)372 22 3M3

RERP-HOME Attachment 7 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3  !

/~\ V PCC DIRECTOR'S CALL LIST NOTE: The following are preferred assignments only; actual personnel assignments at the PCC may differ. PTant Extension Home Time Personnel Assignment Controller R. Rivera* 453 8-303-667-1906 Recorder / Communications S. Lehr 451 8-303-422-1280 T. Shafer 457 8-303-663-4862 D. Horihan* 250 78-776-7976 l D. Belgard* 445 78-678-0355 Personnel Accountability M. Blossom

• 261 9-785-6302 l G. Powers 252 9-356-5256 Decontamination R. Hooper
• 458 8-303-452-3614 M. Murphy 454 8-303-279-6762 Drivers P. Bearly* 455 8-303-669-6636 R. Hamblin* 254 8-303-667-1703 H. Wiedrich 452 8-303-732-4494 First Aid C. Harding 311 9-785-2398 J. Switzer* 452 9-587-4134 D. Reed 314 9-785-2159 Friskers R. Moler* .

456 78-772-9357 K. Hays 319 8-303-778-7702 W. Holcomb" 312 9-330-2068 O FORMtC1372 22 3643

l 1 RERP-HOME Public FORT ST. VRAIN NUCLEAR GENERATING STATION O SerVlCe*PUBUC SERVICE COMPANY OF COLORADO Page 3 of 3 A '

 \ ,)

Access Control R. Erwin* 315 9-330-7178 R. Teel

• 261 8-303-288-1959 R. Widows 314 8-303-663-1080 Maintenance, Repair, and Damage Control R. Webb* 229 78-776-8219 (Pager) 855-7257 R. Lamb
• 336 78-772-0757 C. Schmidt* 286 8-303-666-6955 Monitoring Teams - Health Physics (Notify four of the following initially.)

P. Glahn 245 8-303-450-5292 L. Hutchins 245 9-330-7187 G. Madison 245 8-303-833-2278 K. Morse 245 9-353-6163 K. Nasveschuk 245 78-651-6254 E. J. O'Donoghue 245 8-303-452-3514 S. Sherrow 245 9-353-1338

 ]-
 \

S. Sieg G. Valentine 245 245 8-303-663-3468 8-303-223-7674 Radiochemistry V. McGaffic (P)* 278 9-587-2752 l D. Miller (A)* 348 8-303-663-3595 S. Poet (A) 279 78-652-2297 l M. Prochownik (A) 280 9-785-6010 , S. Rima (A) 279 78-772-4068 i l (2) FORMIC 1372+22 3843

I RERP-HOME Attachment 8 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 Service

• PuBUC SERVICE COMPANY OF COLORADO Page 1 of 2 rm

(_) . l STATE EOC CALL LIST INSTRUCTIONS l (For Contacts by PSC) In the event you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:

1. If you are the PSC primary contact:

a. Call the PSC alternate contact and instruct him to complete the call list.

b. If you cannot reach the PSC alternate contact, call the first person on the attached list and inform him to complete the call list.

2. If you are the PSC alternate contact and are notified by the PSC primary contact:

! a. Complete the attached call list. I 3. If you are the PSC alternate contact and are notified by {-} the PSC operator:

a. Call the first person on the attached list and inform him to complete the call list.

a O-FORMIC)372 22 FA3

RERP-HOME Attachment 8 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 2 O

STATE EOC CALL LIST (For Contacts by PSC) Extension Home Time Technical Assistance H. L. Brey (Primary) 571-8404 469-4238 M. H. Holmes (Alt.) 571-8409 988-4522 Radiological Consultant l F. Ward Whicker 491-5343 221-3870 Media Relations Q R. A. Burns (Primary) G. Reeves (Alt.) 571-7726 571-7726 759-9740 424-4958 O 1 O FORM (C)372 22 3s43

RERP-HOME Attachment 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 O Service" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O TSC DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at . Fort St. Vrain, complete the following telephone calls:  !

1. If you are the response center / post Director:

a. Call your response center / post Alternate Director (the alternate will complete the calls on the attached list).

b. If you cannot contact you Alternate Director, call the first person on the attached list - andinform

                            - him to complete the call list.

2. If you are the response center / post Alternate Director and are contacted by the Director:

a. Complete the attached call list.

3. If you are the response center / post Alternate Director and O are contacted by the PSC Operator:

a. Call the first person on the attached list and inform him to complete the call list.

9 O FootM tC1372 22 3843

I RERP-HOME Attachment 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issyg 34 0 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 O

v TSC DIRECTOR'S CALL LIST First call all primaries, then call all alternates. Engineering and Plant Technical Analysis Extension Home Time Primary - J. Eggebraten 270 651-1523 (Pager) 890-2220 Alternate - R. Heller 284 772-1093 Radiological Assessment Primary - J. Sills 265 221-5059 (Pager) 890-2223 l Alternate - S. Johnson 285 587-4278 Technical Support' Contact three persons listed below in order of preference: A. Reed" 325 772-5312 (Pager) 890-1942 O l M. Joseph

• 275 (Pager) 465-1248 890-2835 O. Clayton 277 663-3939 D. Stuart 274 651-1927 -

R. Gappa 283 484-2306 l J. Wojtisek 268 364-2855 Plant Condition Assessment Call two off-duty Shift Suparvisors M. Deniston 219 776-3776 D. Evans 219 776-9672 J. Hak 219 776-1904 - D. Hood ** 219 or 347 776-1843 J. Hunter 219 330-1411 H. O'Hagan 219 776-8232 G. Reigel 219 330-4235 l J. Vandyke 444 772-2476 Reed or Joseph may not be available if either is the on-duty Technical Adv.isor. Also contacted as alternate to Control Room Director by PSC operator. O FORM (Cl372 22 3843

RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION e OPublic Service

• PUBUC SERVICE COMPANY OF COLORADO Page 3 of 3 O

Emergency Maintenance Primary - W. Craine 222 667-5427 Alternate - J. Petera 233 427-6273 instrument and Control Primary - B. Burchfield 249 351-0373 Alternate - J. McCauley 248 667-0635 Health Physics / Health Physicist Primary - T. Schleiger 242 785-6314 Alternate - B. Woodard 244 678-0818 Administration / Logistics Primary - A. Kitzman 206 737-2578 Primary - P. Collins 207 587-2172 Primary - P. Bollig 204 339-3972 Alternate - D. Cornelly 210 353-4575 Telephone Console Operators O Primary - D. Ed.ards 217 ee9-1680 l Alternate - D. Libal 208 651-1404 Computer Support

• Primary - D. Klaus 437 466-5046
• Alternate - D. Haloin 376 353-1993
• Computer Services Page Number: 855-3234 ,

1 O FORM tC1372 22 3M3

7 0 . O 0 . RERP-HOME . Attachment 10 issue 14 Page 1 of 1 ATTACHMENT 10 . Facility Directors / Alternates Extension Clly P40me Time TechniceI Suppgrt Center -

c. Primary: J. W. Cahm 5-785-1200 No rthg lenn 5-303-452-0M7 Alternate: C. H. Fuller 5-785-1202 l_oveland 5-303-663-2363 Control Rage Di rec to r

b. Prima ry: W. J. F ranek 5-785-1218 Berthoud 5-303-532-3489 Alternate: D. P. Hood 5-785-1347 Longmont 5-303-776-1843 Personnel Control Center

  - c. Primary: J. Class                            5-785-1253    Brighton      5-303-659-4118 Alternate:      S. R. Wi l l ro rd       5-785-1327    Brighton      5-303-659-5258 Forwa rd Co_amand Post

d. Prima ry: F. J. leovachek - 5-785-1201 Thornton 5-303-457-8034 Alternate: D. W. Wa rembourg 5-571-8419 Frede rick 5-303-833-4092 Al te rna te: L. W. Singleton 5-785-1350 Longmont 5-303-772-1018 Co_rygrate Emergency Directqr

( a t f o rvald _C _ .d Post)

o. Prima ry: O. R. Lee _571-7105, 571-7305 Brighton- 9-659-1180 i Alternate: J. K. Fuller 329-1104 Denver 9-779-1109 i

hecutive Command Poat

r. Primary: R. F. Wa l ke r 571-7333' Denver 9-234-9298 Atternato: 8. O'DonneiI 571-7381 Denver 9-388-0211 i

i Slaje Emergency Operations Center .

g. Prima ry: D. McNellis 571-7254 Donver 9-321-3142 Alternate: H. L. Brey 571-8404 Broomrield 9-469-4238 l

i (

RERP-PAG PUBLIC SERVICE COMPANY OF dOLORADO Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 6

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   ,m                                                                                                                         W,fiI                     5 L)         TITLE:                                                                                                     b NON2 CONTROLLEDM PROTECTIVE ACTION GUIDELINE RECOMMENDATIONS                                                     U' - ?COPYr               - i n

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ISSUANCE h "" AUTHORIZED / b r '** -o -' BY h1 J J-/-/f" U"*" PORC EFFECTIVE REVIEW / PORc 612 MAR 14d385 DATE 3- 3-33" Section Description Page General ........................................................... 2 1.0 Criteria for Implementation................................... 2 2.0 Procedure..................................................... 2 3.0 Re s p o n s i bi l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4.0 References ................................................... 5

   ,        5.0 Referenced or Supporti ng Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . . 5

( ) Table 1 Protective Action Guidelines ........................... 1 Table 2 Estimated Evacuation Time of the Permanent Population Within the Plume Exposure and Emergency Planning Zone................................. 1 Figure 1 Population Di stribution Summary. . . . . . . . . . . . . . . . . . . . . . . . . 1 Datasheet 1 ....................................................... 1 Work /Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e Re p o rti n g S he et* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ANYTIME A kORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE. Ol l Lj l PORM 372 22 3642 +

RERP-PAG l Issue 4 I FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 6 OPublic Service PUBUC SERVICE COMPANY OF COLORADO General This procedure discusses the mechanism for making recommendations of offsite protective actions to state authorities during a radiological emergency at Fort St. Vrain. This procedure also discusses the l mechanism for decision-making regarding protective action i recommendations. The decision as to the appropriate protective actions to recommend rests, initially, with the Emergency Coordinator and, after facility activation, with the Corporate Emergency Director. The Corporate Emergency Director is assisted in this task by the Radiological Assessment Coordinator and the Technical Support Center Director. The decision should be based upon dose projections, field monitoring results, plant system parameters, expected duration of release, weather conditions, and, most importantly, dose avoidance. 1.0 Criteria For Imolementation This procedure is intended for use by the Emergency Coordinator or by Radiological Assessment personnel at the Technical Support Center (TSC) and the Forward Command Post (FCP) for determination of the most practical method of protecting the general public. This information shall be relayed to the TSC Director and the Corporate Emergency Director. Additionally, (' this procedure may be used for reference information by the TSC Director and the Corporate Emergenc/ Director to assist in decision making. This procedure is to be implemented whenever there is an ALERT or higher emergency class event in progress. 2.0 Procedure Protective action recommendations are to be based upon the U.S. EPA Protective Action Guidelines. These Protective Action Guides (PAGs) are summarized in Table 1 of this procedure. The PAGs presented in Table 1 refer to avoidable doses, not simply to projected doses. In other words, for a protective action to provide any benefit, a substantial dose avoidance must be realized. The PAG values in no way imply an acceptable dose; they are simply values of dose avoidance where the benefit of taking a orotective action is highly likely to exceed the risks associated with taking that action. Utilize Table 1 as the basis for making protective action recommendations. The following subsections of this procedure describe the various factors to consider in making a protective action recommendation. Datasheet 1 is provided as a central place to record the appropriate data.

RERP-PAG i Issue 4 Page 3 of 6 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service PUBUC SERVICE COMPANY OF COLORADO O 2.1 Evacuation effectiveness The effectiveness of evacuation in limiting the radiation dose received is a function of the time available to complete evacuation prior to plume arrival. If the public can be evacuated prior to the plume's arrival, then the evacuation is totally effective in dose avoidance. The

                    " Evacuation Time Study of the 10-Mile Radius Area About the Fort St.      Vrain Nuclear Generating Station," April 1981, states that the entire two mile radial area around the plant can be evacuated in approximately one (1) hour after notification, and that the entire plume exposure Emergency Planning Zone (EPZ) can be evacuated within 2.75 hours. These numbers are good weather estimates based upon notification by Weld County Sheriff's personnel.

More detailed estimates, including adverse weather estimates and credit for use of the Early Warning Alert (EWA) system, are available in Table 2 for reference purposes. Figure 1 provides a reference map showing sector boundaries and summarfzes the population distribution around the plant. The above stated values should be utilized in conjunction with a stated value for plume arrival delay, in order to assess the effectiveness of an evacuation in dose O avoieance. 51 911 statee. 91ume arrivai eeiax (T A ) is the sum of the time available before a projected release begins (TB ) and the time prcjected for plume travel (TT) for a given windspeed and downward distance once the release has begun. TA (hours) = TB+TT 2.2 Sheltering Effectiveness Sheltering will always provide a measure of protection to the public, whenever carried out as instructed. It is extremely difficult, however, to quantify any specific protection factor that this will provide for all members of the public in all types of structures. Sheltering should be advised in any case where a definite hazard exists, but there are constraints against evacuation. l Sheltering as a protective action includes the following actions: , 1) Seeking shelter indoors near the center of the j lowest floor of the structure; l O l FomM@372 22 3043 u 1

RERP-PAG Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 6 0Public Service pusLiC senviCE COMPANY OF COLOMADO O l O 2) Securing all intake / exhaust ventilation to the structure during passage of the cloud; l

3) Sealing door cracks and window ledges with wet towels or rags;

4) Covering mouth and nose with moistened handkerchief or cloth; and

5) Restoring structure ventilation as quickly as possible after passage of the cloud.

I 2.3 General Emergency Considerations l 2.3.1 During a General Emergency, radiation levels, if I any, are expected to be high enough that evacuation l recommendations must be made with care. If l evacuation cannot be completed before the plume l arrives at the areas that evacuees must travel

,     I                        through, sheltering should be recommended as it l                       will provide a higher level of dose avoidance.

l (.5ee sections 2.1 and 2.2) l I? evacuation is to be considered, consider l ev6cuation only within about 2 miles of the site O l I boundary unless these site boundary levels are exceeded by a factor of 10 or projected to continue l for 10 hours or EPA Protective Action Guideline l exposure levels are predicted to be exceeded at l longer distances. As release information becomes l available, adjust these actions in accordance with l dose projections, time available to evacuate and l estimated evacuation times given current l conditions. l 2.3.2 A General Emergency is also declareo in the event l of physical loss of control of the plant. If this , l occurs, a two-mile precautionary evacuation is to l be considered. l 2.3.3 Factors to be considered whenever evacuation is l imminent include: l a) the magnitude and characteristics of the l event; j l b) availability of routes of evacuation, l transportation and the time required for the l actions; 1 i FOAM (Bl372 22.N43

RERP-PAG Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 6 0Public SerVlCe PUBLIC SERVICE COMPANY OF COLORADO f3 U l c) availability of reception centers (check with l Fort Lupton Fire Station and Colorado l Department of Health), and l d) prevailing weather conditions. 3.0 Resoonsibilities 3.1 Corporate Emergency Director After the full activation of the FSV emergency organization, the Corporate Emergency Director has the authority and responsibility to make all protective action recommendations. The Corporate Emergency Director should confer with the Radiological Assessment Coordinator and the Technical Support Center Director in this decision. 3.2 Radiological Assessment Coordinator After activation of the FSV emergency organization, make assessments of protective action needs based upon the current radiological conditions and the considerations contained herein. Inform the Corporate Emergency Director of the results of this appraisal and submit an assessment of recommended protective actions. Q U 3.3 Emergency Coordinator Prior to the activation of the FSV emergency organization, the Shift Supervisor, in the role of Emergency Coordinator, has the authority and responsibility to recommend protective actions to offsite authorities. 3.4 Technical Support Center Director Confer with the Corporate Emergency Director, as requested, with respect to current plant conditions and the need for offsite protective actions. 3.5 Radiological Assessment (TSC) Assist the TSC Director and Radiological Assessment Coordinator with this evaluation as requested. Confer with the Radiological Assessmer,t Coordinator regarding persistance or prospect of conditions worsening. l l l

RERP-PAG Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 6 0PublicService PUBLIC SERVICE COMPANY OF COLORADO O V 4.0 References 4.1 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, U.S.E.P.A., June, 1980. 4.2 Reactor Safety Study, Appendix VI, WASH-1400, October 1975. 4.3 Examination of Offsite Radiological Emergency Protective Measures for Nuclear Reactor Accidents Involving Core Melt, NUREG/CR-1131, D. C. Aldrich, P. McGrath, N. C. Rasmussen, October, 1979. 4.4 " Evacuation Time Study of the 10-Mile Radius Area About the Fort St. Vrain Nuclear Generating Station," Public Service Company of Colorado, April,1981. l 4.5 Annals of the ICRP: Statement from the 1984 Stockholm l Meeting of the ICRP: Protection of the Public in the Event l of Major Radiation Accidents: Princples for Planning, l Appendix B: Risks, Benefits and Difficulties Associated l with Countermeasures. l 4.6 NUREG 0654, Revision 1, Appendix I O s o aerere#ced or s#aaort4"a Proceevres 5.1 RERP-DOSE, Offsite Dose Calculation Methodology. 5.2 RERP-CR, Control Room Procedure 5.3 RERP-ORG, FSV Emergency Organization and Responsibilities 5.4 RERP-FIELD, Field Monitoring Procedure i

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TABLE.1

                                            .                                           PROTECTIVE ACTION CUIDELINES Rocommended' protective actions to reduce whole body and thyroid dose f rom exposure to a gaseous plume Projected Dose >(Rem) to the_fopulation                                e Recommended        Actions fa)                     Rosenn Wsole Body less than i                              No planned protective actions                      Previously recommended
                                    -                   4          (b). State may-issue an                        protective actions may Thyroid less than 3                                 advisory to seek shelter and                       he reconsidered or                                                       '

await further instruct icns, te rm i na ted . Mon i to r envi ronmenta t radiation levels. Woole Body 1 to 5' Seek shelter as a minimum. It' constraints exist, Consider evacua tion. Evacuate speciaI consideration Thyroid 5 to 25 s unless constraints make should be given for it imp rac t ica l , evacuation or childenn Monitor envirofunental and pregnant women. radiation levels. Control access. Whole body 5 and above Conduct mandatory ovacuation. Seeking shelter would be  ! Monitor environmentaI an alternative ir Thyroid 25 and above radiation levels evacuation were not aruf adjust area ror immediately possible, mandatory evacuation based on these levels. Control access. , s e jn m <O 7. These actions are recommended ror planning purposes. . Protective action decisions at the time or the incident attst take

                           . existing conditions into consideration, v    g_                                       .c                                                                 -

(b). At the time pr tho incident, orricials may implement low-impact protective actions in keeping with the principle or

               , % maintaining radiation exposures as low as reasonably achievable.

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l Worksheet No. Title Number Copies None N/A N/A Datasheet No. 1 Protective Action Recommendations 20 Checklist No. None N/A N/A O O FORMtCl372 22-3643 i

RERP-PAG t!S/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 O Public service" PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 FORMS USE REPORTING SHEET Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a controlled copy of the Emergency Plan Implementing Procedures, BOOK NO. , located at . The following forms have been utilized from +21s copy: Worksheet Numbers Copie Used Datasheet Numbers Copies Used O Checklist Numbers Copies Used l I l The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting l Sheet" for the affected procedure in the affected book. i FORM tC)372.*2 3643 l

RERP-PAG WS/DS/CL - Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 4 G service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 FORMS USE REPORTING SHEET (Continued)

COMMENTS l l l Reported By: Date: Nuclear Documents Specialist

• Date Received Date Replaced Nucle:r Documents Specialist will transmit this form to the originating individual / department upon completion of this form to

.h, noti fy users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies. v FORM (C)372 22 3843

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                                                                                  .            RERP-PAG Datasheet 1 Public                    FORT ST. VRAIN NUCLEAR GENERATING STATION          Issue 4                 j 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 1 '

Datasheet 1 - Protective Action Recommendations . l l Date / / Time  : Initials "h a pd Response Center Comments l0 't l i l l . I L l O F0mM(Cl372 22 3043

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PUBLIC SERVICE COMPANY OF COLORADO RERP-PCC Ssue M FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 15 pmes % ,y_ , [u ' PORT sT. VftAIN d /~ i r NON CONTM0~0. Epi a TITLE: PERSONNEL CONTROL CENTER PROCEDURF .Ibi, o,Mn. c .hsy@ ,r h J g VERsPV seus47 srAtus h j oldgj {[ Ay occuugsp. b l ,g Q . ISSUANCE AUTHORIZED

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                /                      E 61 sT, N14:M EFFECTIVE DATE ~3 - 2 l - 7fg TABLE OF CONTENTS                                                                  -

Section Description Page , 1.0 C ri te ri a for Impl eme nta ti on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Procedure............ ............ ................. ........ 3 3.0 R e s p o n s i bi l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 4.0 References ........................................... ...... 13 5.0 Referenced or Supoorting Procedures.................. ....... 13 Figure 1 (v") Training Center Floor Plan ............................. I Figure 2 QA/ Engineering Comple> Floor P1an...................... 1 Figure 3 Route to Johnstown County Shops.. ..................... 1 Figure 4 Route to Platteville VFD .............................. 1 Figure 5 Route to Longmont Sen ice Center . . . . . . . . . . . . . . . . . . . . . . 1 l Figure 6 Emergency Organizatior. ............................... 1 l Datasheet 1 Briefing Sheet for Field Monitoring Teams . . . . . . . . . . 1 l Datasheet 2 Briefing Sheet for Inplant Monitoring Teams ........ 1 l Datasheet 3 Briefing Sheet for Emergency Teams...........'....... 1 Checklist 1 PCC Director's Checkli st. . . . . . . . . . . . . ............. 1 , l Checklist 2 Personnel Assignment Controller's Checklist . . . . . . . . 1 l Attachment 1 Personnel Accountability and Exposure .............. 1 l Attachment 2 R e c o rd e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 ( U FnfnM 373 33.Se&3

RERP-PCC

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Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 2 of 15 service

• PUBLIC SERVICE COMPAW OF COLORADO

'       '.)                  l Attachment 3                             Communications..................................                .
                                                                                                                                                     ..        1-l Attachment 4 Decontamination ................ ...................                                                               1 l Attachment.5 Fort St. Vrain Security Deparment. . . . . . . . . . . . . ...                                                     1
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l Attachu.ent 6 Drivers ......... ..... ............................ 1 l Attachment 7. F'.rst Aid .......................................... 1 l Attachment 8 Maintenance, Repair and Damage Centro 1.............. 1 ,

                            "l.Jttachment 9                             Habitability....................            ...................                        1 ork/Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . .                          1 Fo rm s U s e R e p o rt i n g S h e e t* . . . '. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 4

• ANYTIME A ~WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRi. '

ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS 'N THE PRC*EDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE 'TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE. O v s

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i RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 15 ) 0 SerVICG' PUBLIC SERVICE COMPANY OF COLORADO l O 1.0 Criteria for Imolementation When the FSV Radiological Emergency Response Plan (RERP) requires augmentation of onsite resources, the Personnel Control Center (PCC) shall be activated. 2.0 Procedure The PCC shall be activated by the Personnel Control Center Director at the direction of the Shift Supervisor (see RERP-CR). The Shift Supervisor prior to ordering PCC activation, shall determine the PCC location. There are two designated onsite PCC locations, and three designated offsite PCC locations. The preferred location is the Training Center and the preferred alternate location is the Engineering /QA Complex. Facility locations are as follows: a) Onsite (in order of preference) (1) Training Center; (2) Engineering /QA Complex; b) Offsite (in order of preference) (1) Johnstown County Shops; (2) Platteville Volunteer Fire Departments; (3) Longmont.Public Service Company Service Center. O' The decision of PCC location will be made based upon prevailing l wind conditions and site access :bility to offsite respondents. l In the event that the PCC must ce established offsite, the PCC l Director is responsible for tha transport of emergency - l equipment, including decontamination supplies, necessary to I establish the offsite PCC. Personal vehicles are to be used as l needed to establish or relocate the PCC offsite. l 2.1 Locating or Relocating the Personnel Control Center l Offsite l In the event that the Personnel Control Center must be I located or relocated offsite, one of the three locations l listed below, in order of preference, will be used. An l Emergency Kit and Instructions from a site facility will l be utilized and must be transported to the alternate PCC. l It is the PCC Director's responsibility to assure l transport of Emergency Kit supplies. Privately owned l vehicles will be used for transportation. O V FORM (C)372 22 3643

RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 4 of 15 0 service

• PUBUC SERVICE COMPANY OF COLORADO h l 2.1.1 Johnstown County Shop i The Johnstown County Shop keys are located with l the Emergency supplies in the PCC Emergency Kit.

l During business hours, the county should be l notified of an anticipated use of the facility. l (See RERP PHONE LIST, Centers / Posts Phone Numbers) l During non-business hours, the County shall be l notified by calling one of the individuals listed l in RERP PHONE LIST, at home. The physical l location of the Johnstown County Shop is shown on l Figure 3. l 2.1.2 Platteville Volunteer Fire Department l The Platteville Fire department should be notified l of an anticip~ated use of the facility (See RERP l PHONE LIST). Location of the facility is shown on l Figure 4. I 2.1.3 Longmont PSCo Service Center l The Longmont Service Center should be notified of l an anticipated use of the facility (See RERP PHONE j l LIST). I Keys (two) to the gate and side door of the l Service Center are located with the emergency l supplies. Access to the building shall be via the l east side door. One key opens the yard gate and l the other key opens the building door. Light l switches are located on the east wall, just south l of the overhead door, and on the north wall by the l entrance. Physical location of the facility is l shown on Figure 5. l 2.2 Emergency Equipment l Emergency kits are stored at both the Training Center and i the Engineering /QA Complex (see HPP-37). The kits l include: I a) Emergency radiological monitoring equipment l b) First-aid and decontamination equipment l c) Protective clothing O FORM (C)372-22-3043

RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 15 0 SerylCe* PUBUC SERVICE COMPANY OF COLORADO l d) Communications equipment I e) Portable lighting l f) Protective breathing apparatus l 2.3 Personnel reporting to the PCC l 2.3.1 If not during normal working hours, those l personnel required to man the PCC are notified by l telephone (see RERP-HOME). It is the l responsibility of the PCC Alternate Director, or l the first individual contacted by the Director, to l ensure that the notifications are made. l 2.3.2 Individuals assigned to the PCC must enter at the l entrances designated on Figure 1 (Training Center) l or Figure 2 (Engineering /QA Complex) and remain in l the FRISKING (or, waiting) area until monitored for l contamination. l 2.3.3 If contamination is found, proceed to the i decontamination area as directed and initiate l decontamination procedures (see HPP-11). q L/ l 2.3.4 If contamination is not found, proceed to a clean l area of the PCC as directed. l 2.4 Personnel Assignments l The PCC Director shall assign one member of his staff l responsibility for maintaining control over personnel l assignments to teams or tasks. This individual is the l Personnel Assignment Controller, and his responsibilities l are summarized in section 3.2 of this procedure, and in l Checklist 2, Personnel Assignment Controller's Checklist. l NOTE: Prior to dispatching any personnel from the l Personnel Control Center, the senior Health l Physics representative at the Technical Support l Center and the TSC Director shall be consulted. I 2.5 The Personnel Assignment Controller shall inform thu PCC l Director when all basic assignments have been made and l that the' initial manning requirements of the PCC have been l met. l 2.6 Communications personnel shall establish initial l communications with the Technical Support Center (TSC)'and l verify that primary and seundary communication links are g l available. Constant communication should be maintained t) l with the TSC. FORM (C)372 22 3643 l

RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 15 0ServlCe* PUBLIC SERVICE COMPANY OF COLORADO O l 2.7 PCC Habitability l Initially, and throughout the period that the PCC is l activated, the PCC director is responsible for assurance l of facility habitability. Health Physics shall l periodically monitor the area (approximately every 15-20  ; I minutes). Habitability is aetermined using an RM 14/15  ; l set to alarm at 500 cpm, or if radiation levels are l l greater, by periodic air sampling. The HP Technician '

i performing habitability checks shall inform the PCC l Director of each survey's results, and assure that the l Recorder enters results in PCC Log.

I 2.8 Personnel Accountability and Exposure Control l After initial personnel accountability is completed at l emergency stations (see G-5, Personnel Emergency l Response), each facility director assumes responsibility l for continued personnel accountability of the personnel l assigned to him. This task is most challenging at the l PCC, where repair / damage control teams, survey teams, l reserve operating staff, and search and rescue teams are l assembled and dispatched into the plant. l A member of the PCC staff shall be assigned responsibility O- l for maintaining records of personnel accountability nd l personnel exposure records for those individuals assigned i to the PCC. This individual, the Personnel Accountability l and Exposure Cor. troller, reports directly to the PCC l Director, who maintains ultimate responsibility for l continued Personnel Accountability. Additionally, the PCC l Director has the responsibility for authorization of I selected volunteers to receive emergency exposures in l excess of occupational limits (only with joint concurrence l of TSC Director and the. senior Health Physics l representative at the TSC). These responsibilities are i described in detail in RERP-EXP, and include specific l requirements for record keeping and job briefings. l Responsibility for record keeping of personnel l accountability and exposure is assigned to the Personnel l Accountability and Exposure Controller. He is provided l Attachment I to assist him in maintaining the required l records. FORMICl372-22 3643

RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 7 of 15  : 0 SerVICG" PUBUC SERVICE COMPANY OF COLORADO l

 /D Gl l      2.9   Radiological Monitoring Teams l            Radiological monitoring teams are dispatched from the PCC        l l            upon approval of the TSC Director, and under the overall l            direction of the senior Health Physics representative at         .

l the TSC. Protective clothing and equipment requirements I l along with maximum stay times, are determined by the l l senior Health Physics representative at the TSC and l l relayed to the PCC Director for use in the briefing of the  ! l monitoring teams (see Datasheets 1 and 2). ' l l 2.9.1 Field Survey Teams l Field Survey Teams to survey both the Exclusion l Area Boundary (EAB) and the plume exposure l Emergency Planning Zone ,(EPZ) are dispatched as l required (see RERP-FIELD). Field Teams consist of l a Health Physics Technician and a Driver. Keys l for the two site assigned Emergency Response l vehicles and for two site assigned vehicles I generally located at the Engineering /QA complex l are stored in the PCC Emergency Kits. l 2.9.2 Inplant/Onsite Monitoring Teams O l l Monitoring teams to survey the plant and protected areas consisting of at least- a Health Physics l Technician and an assistant shall be dispatched as l required (see RERP-SURVEY). l 2.10 Notification of Persons Living on Plant Property l Notification of individuals living on plant property is to l be completed within 30 minutes of PCC activation. l Notification may be made by telephone by Communications , l Personnel (see Attachment 3), or by personal contact (see  ! l Attachments 3 and 6). l 2.11 Medical Transport l Transport of injured or contaminated individuals is to be l performed in accordance with the FSV Medical Emergency l Plan. The TSC Director shall be notified of all such l transport. n 1 l

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RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 15 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO O l 2.12 Site Access Control / Security l 2.12.1 PCC Guard l Upon notification to activate the PCC, the Lead l Security Officer (LS0) shall dispatch one security l guard to the PCC. Security responsibilities at I the PCC are as follows:

l

• Assist in gate control of authorized 1 personnel and vehicles at the PCC, where l applicable.

l

• Ensure that the outer perimeter gate is l secured and that non-PCC personnel are not l admitted to the PCC without proper l authorization.

I

• Assist with radio communications and access l authorizations in cooperation with the LSO.

l 2.12.2 Site Response Guards l After activation of the Personnel Control Center l the PCC Director will coordinate access of

 , .)  l                          personnel and vehicles into the protected area or i                          vital areas with the LSO. Site response security l                          personnel will:

l Check all site visitors out through the l Search and Identification Facility. l

• Facilitate the exit of onsite personnel I reporting to the PCC.

l

• Assist in personnel accountability (in l particular. the Central Alarm Station as l specified in Procedure G-5).

l

• Assist with personnel and vehicle l ingress / egress to and from protected and

       !                                vital areas.

i O FORM (C)372 22 3843

RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 15 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO O

C/ 2.13 Decontamination / Controlled Areas Areas for the decontamination of site personnel and for control of radiologically contaminated equipment shall be established on an as-needed basis in accordance with existing Health Physics Procedures (see HPP-9, Establishing and Posting Controlled Areas; HPP-10, Area and Equipment Decontamination; HPP-11, Personnel l Decontamination; and HPP-21, Surface Radioactive 1 Contamination Surveys). ' 2.14 Re-entry and Egress It is the responsibility of the PCC Director to coordinate re-entry into the plant for support plant operations personnel, emergency teams, or corporate resources personnel when directed to do so by the TSC Director. The PCC Director is also responsible for accountability of personnel leaving the plant after re-entry or being relieved. 2.14.1 Re-entry Guidelines c For entry or re-entry cf support plant operations () l l personnel, and corporate resources personnel: l a) The PCC Director shall conduct briefings for the personnel to appraise them of personnel protective equipment requirements as advised - by the senior Health Physics representative at the TSC and the TSC Director. l b) The Personnel Accountability and Exposure [ Controller shall record accountability and exposure information. l- c) The PCC Director shall inform the LSO of the personnel arriving and prepare to clear them through security. 2.14.2 Emergency Teams (see RERP-TEAM 5) a) The PCC Director will select individuals with the appropriate qualifications in Health Physics, First Aid, Operations, or Maintenance to make up a re-entry team and appoint a team leader. O FORM (C)372 22-3643

RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 15 Service

• PUBLIC SERVICE COMPANY OF COLORADO A

V b) Conduct a briefing of the personnel to appraise them of conditions affecting them and personnel protective equipment requirements as advised by the senior Health Physics representative at the TSC. (See , l Datasheet 3). The PCC Director must clear all Emeroency Team re-entry with the senior Health Physics representative at the TSC, and request assessment of protective equipment, clothing requirements, thyroid prophylaxis needs, and any Emergency Exposure limitations as specified by RERP-EXP. c) Furnish team leaders with ccmmunication equipment and have the Personnel Accountability and Exposure Controller record information. d) Have the LSO inform Security of the personnel arriving and prepare to clear them through Security. e) The re-entry team will enter the area, O establish communication with the TSC, perform the duties in the most safe and efficient manner possible, and inform the TSC of completion of duties and intent to leave the area. f) Once their operations have been completed, the team personnel will follow self-monitoring and personnel decontamination procedures as specified by the team leader. g) Return to the PCC to be screened through the Personnel Accountability and Exposure . Controller and report to the PCC Director. l h) PCC Communications personnel will inform the TSC of the return of the emergency team. 2.14.3 Personnel Leaving the Plant After Re-Entry or Being Relieved a) Report to the PCC for accountability. b) The PCC Director informs the TSC. fm V FORM (C1372 22 3643

RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 15  ; 0SOTVICe* PUBLIC SERVICE COMPANY OF COLORADO O 3.0 Responsibilities The Personnel Control Center (PCC) serves as manpower marshalling location to provide a pool of personnel available for emergency assignment. Personnel are assigned to perform functions consistent with their routine job classification. 3.1 Personnel Control Center Director l *#*Section 3.1 is a result of corrective actions made in I response to CAR 84-121. Do not delete Section 3.1 without l issuance of comparable controls.*#* The PCC Director is l ultimately responsible for continued personnel accountability, assembling personnel for repair / damage control or radiological survey teams, search and rescue teams, reserve operating staff, and establishing

    ]                   radiological control areas as directed. These duties are i                   to be delegated as much as possible, however, so that the l                   PCC Director may concentrate          efforts    on    providing l                   direction      for    the    Center. In    particular,     his
                       .responsiblities include the following:

• Continued personnel accountability; Assuring that all emergency workers at-risk are O evaluated by the Senior Health representative at the TSC with regard to a need Physics for thyroid blocking;
• Coordinates with Security personnel to control access to the owner controlled area (Shift Supervisor, in the capacity of Emergency Coordinator, may perform before PCC activation);

Dispatches personnel to notify any individuals living in the owner controlled area who were unable to be contacted by telephone;

• Coordinates medical transport for injured personnel; Coordinates access for personnel arriving from outside the plant with Weld County Sheriff's Department;

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Coordinates entry /re-entry of required personnel l with the Lead Security Officer; Relocates the PCC to an alternate onsite or l offsite location, as required; FORMIC 1372 22 3643 L

RERP-PCC PubilC FORT ST. VRAIN NUCLEAR GENERATING STATIO;J Pa 1 of 15 0 $9fVIC9" PUBLIC SERVICE COMPANY OF COLORADO O

• With the concurrence of the TSC Director, authorizes volunteer emergency workers to receive doses in excess of 10 CFR 20 limits (see RERP-EXP);

                      =       Receives    reports   of accidental or emergency exposure in excess of occupational     limits, and informs the TSC Director of these occurrences; and,

• Refers any requests for outside assistance to the TSC Director.

l 3.2 Personnel Assignment Controller l The Personnel Assignment Controller is responsible to l assign personnel to perform duties required to activate l and maintain operation of the PCC. Checklist 2 is l provided as guidance to the Personnel Assignment l Controller. l 3.2.1 The following is a summary of the responsibilities l of the Personnel Assignment Controller. l Distribute equipment and appropriate Attachments Os l or Datasheets of the PCC Procedure and record on I the assignment board as personnel arrive and are l available. I a) Personnel Accountability and l Exposui> Controller Attachment 1 l b) Recorde- Attachment 2 l c) Cot.aunication Attachment 3 l d) Decontamination Attachment 4 l e) Security Attachment 5 1 l f) Drivers Attachment 6 l g) First Aid Attachment 7 l h) Maintenance Repair and l Damage Control Attachment 8 l i) Habitability Attachment 9 O FORM (C)372 22 3643

RERP-PCC Issue 15 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 of 15 0Publicservice

• PUBUC SERVICE COMPANY OF COLORADO O l j) Assign an individual the duty of directing i addition 1 personnel to their areas and l retrieving them as necessary.

l k) Additional Personnel l 3.2.2 Make every effort to ensure all arriving persons I are assigned to each group in accordance with l individual qualifications or, if not immediately 1 assigned, assembled in an out-of-the-way place for l further instructions. l 3.2.3 Provide. each group with additional manpower as l required. l 3.2.4 Record all data for the master log. (See l Checklist 2.) l 3.2.5 List all available personnel on the control board l from the Emergency Kit so that, if additional l assistance is needed, personnel can be called in. l 3.2.6 Keep records of additional personnel assignments l for master log. O i 3.3 Senior Heaith Physics Representative (TSC) l The senior Health Physics representative at the TSC is l responsible for the direction of radiological monitoring l teams dispatched from the PCC. He is also responsible for l assessment of protective clothing, dosimetry, and l equipment requirements and maximum stay times for the l teams. l 3.4 Personnel Accountability and Exposure Control l Personne.1 Accountability personnel are responsible for l maintaining continued personnel accountability and l exposure estimates, handling search and rescue l assignments, performing first aid and personnel l decontamination, and assisting in the medical transport of l injury victims. l The initial personnel accountability assessment prior to l activation of the PCC shall be handled in accordance with l Administrative Procedure G-5 and Security Instruction l 6.10. l 3.5 Maintenance, Repair, and Damage Control l Perform mechanical and electrical repair / damage control, O i e=erseacv 4# tea >#ce. >#a te=Porerv oeiricat4oas. FORM (Cl372-22 3643 -

RERP-PCC Issue 15 Public FO .T ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 15 0 SerVICO PUBUC SERVICE COMPANY OF COLORADO o ks l 3.6 Hazards Control l Extinguish fires, purge hazardous gases, and combat l natural emergencies. l 3.7 Other Personnel l Detailed responsibilities of personnel assigned functions I of Recorder, Communications, Decontamination, Security, l Drivers, First Aid, and Habitability may be found in the l Attachments to this pr::edure. 4.0 References 4.1 FSV Radiological Emergency Response Plan 4 . 2- State Radiological Emergency Response Plan

            ./

l 4.3 PPC-83-1336, Woodard to Schleiger, 05/20/83, Eberline l RM 14/15 Sensitivity to Noble Gas Activity 5.0 Referenced or Supporting Procedures 5.1 RERP-ORG, FSV Emergency Organization and Responsibilities O 5.2 RERe-stEto. Fieie Monitorins erocedure 5.3 RERP-SURVEY, Inplant/Onsite Monitoring Teams 5.4 RERP-THYROID, Thyroid Blocking Agent Administration 5.5 RERP-EXP, Emergency Exposure Guidelines 5.6 RERP-TSC, Technical Support Center Procedure 5.7 RERP-CR, Control Room Procedure . 5.8 RERP-HOME, Homa Packet for Off-shift Notifications 5.9 RERP-PHONE LIST 5.10 RERP-SUPORG, Use and Coordination of Non-PSC Support Organizations 5.11 MEP, FSV Medical Emergency Plan 5.12 HPP-9, Establishing and Posting Controlled Areas 5.13 HPP-10, Area and Equipment Decontamination 5.14 HPP-11, Personnel Decontamination U 5.15 HPP-12, Portable Air Sample Collection and Analysis FORM (C)372 22 3843

RERP-PCC Issue 15 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 15 0 service

• PUBLIC SERVICE COMPANY OF COLORADO O 5.16 HPP-21, Surface Radioactive Contamination Surveys i

5.17 HPP-37, RERP Inventory List 5.1P HPP-57, Radiation and Airborne Radioactivity Monitoring During Abnormal Releases in the Plant 5.19 Security Instructions, Section 6.10, Personnel Accountability for Station Emergencies 5.20 G-5, Personnel Emergency Response O 1 O FoftM(C)372 22 3843 l

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RERP-PCC Figure 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 SerVICO PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 1 O FIGURE 3 l l MAP: JOHtiSTOWN COU?iTY SHOP l l State Eww 60 g (r4uner St. e'*~~ South Second Ave.J ' Wi

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RERP-PCC Public FORT ST. VRAIN NUCLEAR GENERATING STATION e1 0SerVlCO* PUBUC SERVICE COMPANY OF COLORADO Page 1 of 1 O FIGURE 4 MAP: FIREHOUSE, FLATTEVILLE irehouse E300MainSt. . Grand Ave,

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e d to Ft. St. Vrain O i ! E g D 0 l l Jr o . o FORMtCl372 22-3843 i

RERF-PCC i Figure 5 l FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 l 0 Public service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 1 O

FIGURE 5 i I MAP: PSC SERVICE CENTER. LONGMONT l 2 n 5 w uu u ;g euen k i k O h IIIl 4,w: < , - .:. - , , ,

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RERP-PCC Datash et 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 service" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 6 O l Datasheet 1 Briefing Sheet for Field Monitoring Teams (To be completed by senior HP represonative at the TSC) l

1) Area to be surveyed l 2) Route to be taken (mark on appropriate map):

3) Calculated or estimated parameters a) General Radiation Level (mrem /hr) b) Airborne Activity Level (uci/cc) l

                                                                                       )

4) Projected Time to complete survey (hr)

5) Projected Exposure 1

3)a) x 4) x 1.25 = (mrem)  ;

6) Maximum Stay . Time (based upon 10CFR20 limits or, with the TSC Director's Concurrence, the guidelines of RERP-EXP, Emergency Exposure Guidelines)

(br) i b\ U l FORMIC)372 22,3M3

s RERP-PCC Datasheet 1 , Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 l 0 service

• PUBUC SERVICE COMPANY OF COLORADO Page 2 of 6 i

7) Team Members:

8) Dosimetry requirements:

Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range i Other:

9) Protective Equipment requirements -

(Circle required equipment): Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator l Scott Air Pack f Thyroid Blocking Agent (see RERP-THYROID) No Respiratory Protection Required O 1 i FORM (C)372 22 3043 I

   ..                                                                                     y

RERP-PCC f Datasheet 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 OPublicService" PUBUC SERVICE COMPANY OF COLORADO Page 3 of 6 l O

10) Comments:

a) Save used filters and cartridges for Radiochemistry analysis. b) Leave the emergency vehicle running while in the field and l upon return to avoid battery discharge. O 1 O

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RERP-PCC Datasheet 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Service" PUBUC SERVICE COMPANY OF COLORADO Page 5 of 6 O

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RERP-PCC Datasneet 2 , Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 l O Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O l l Datasheet 2 Briefing Sheet for Inplant/Onsite Monitoring Teams (To be completed by senior HP representative at the TSC)

1) Area to be surveyed

2) Known parameters a) General Radiation Level (mrem /hr)

Detector RIS-O b) Airborne Activity Level- (uct/cc) Detector c) Surface Contamination Levels

• DPM/100cm2

3) Projected Time to complete survey (hr)

4) Projected Exposure 2)c) x 3) x 1.25 = (mrem) 4

5) Maximum Stay Time (based upon 10CFR20 limits or, with the TSC Director's Concurrence, the guidelines of RERP-EXP, Emergency Exposure Guidelines)

(br) i This parameter may be unknown prior to team deployment. FORM (C)372 22 3M3

RERP-PCC Datasheet 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 1 0 SerVIC9" PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 O

6) Team Members: 1

7) Briefing of HP Technician Team Leader By:

(PCC Director).

8) Dosimetry requirements:

Pocket Dosimeter - High Range (required) Other dosimetry requirements (circle): Film Badge Pocket Dosimeter - Low Range TLD Finger Ring

9) Protective Equipment requirements (Circle required equipment):

Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator Scott Air Pack Thyroid Blocking Agent (see RERP-THYROID) No Respiratory Protection Required FOAM (C)372 22 3643

RERP-PCC Datasheet 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0Public Service

• PUBUC SERVICE COMPANY OF COLORADO Page 3 of 3 O

10) Comments:

a) Save used filters and cartridges for Radiochemistry analysis. O i ) i O FORMIC 3372 22 3043

RERP-PCC Datasheet 3 i Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 l 0 ServlCe* PUBUC SERVICE COMPANY OF COLORADO Page 1 of 3 O v l Datasheet 3 I Briefino Sheet for Emeroency Teams

1) Area (s) to be entered

2) Known parameters:

a) General Radiation Level (mrem /hr) Detector RIS-l b) Airborne Activity Level (yci/cc) Detector c) Surface Contamination Levels

• DPM/100cm2

3) Projected Time to complete task (hr)

O 4) erosected Exposure 2)a) x 3) x 1.25 = (mrem)

5) Maximum Stay Time a Based upon 10CFR20 limits (3 rem / quarter whole body with completed NRC Form 4, 3 E-09pci/cc unidentified airborne contamination) or, with the TSC Director's Concurrence (NOTE:

Prior to activation of emergency organization, the Shift Supervisor may authorize exposures in excess of 10CFR20 limits), the guidelines of RERP-EXP, Emergency Exposure Guidelines (hr) This parameter may be unknown prior to team deployment. l O [ FoRMtCl372 22 3843

RERP-PCC Public FORT ST. VRAIN NUCLEAR GENERATING STATION 0 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 O

6) Team Members:

7) Briefing of Team By:

8) Dosimetry requirements:

Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range TLD Finger Ring

9) Protective Equipment requirements (Circle required equipment)

Full Arti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator Scott Air Pack Thyroid Blocking Agent (see RERP-THYROID) FORMICl372 22 3H3

RERP-PCC l Datasheet 3 I FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0Public Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 No Respiratory Protection Required

10) Comments:

l O i l l l O FORM (C)372 22-3843

RERP-PCC Checklist 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O PCC DIRECTOR'S CHECKLIST TIME NOTE: All information is to be logged by the Recorder.

l 1. Personnel Control Center (PCC) location: l 2. Habitability confirmed at PCC. l 3. Notification to Visitor's Center confirmed. l (May have been performed by Emergency Coordinator.) l 4. Fort Lupton Fire Department notified to receive Visitor's Center occupants (See RERP O eHoNE LIST). l S. (Normal working hours) make announcment by using telephone. Dial 6-0-4 and announce l "PCC Personnel, report to Personnel Control l Center located at ." Repeat l message. l 6. Verify with the Visitor Center (extension l 475) and the Lunchroom (extension 264) that I the announcement was received. l l 7. Controlled area established. All doors locked except the one being utilized .for controlled entry into the PCC. P) m FORM tC)372 22 3043

RERP-PCC Checklist 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3

(^) v l PCC DIRECTOR'S CHECKLIST l TIME l 8. Manning requirements adequately met. Request l that individual at the TSC (if activated) or I the Control Room notify the Emergency l Coordinator (TSC Director, Control Room l Director, or Shift Supervisor, depending on l level of activation) that the PCC is manned l and monitoring teams are ready to be l dispatched. l 9. Personnel dispatched to establish road blocks to the North and South of the plant along County Road 1915 (IF NOT ALREADY DONE BY COUNTY / STATE LAW ENFORCEMENT AGENCIES.) l 10. Persons living within property boundary l notified and/or drivers dispatched. r' l 11. Indicate transported individuals, if l transport to St. Luke's is required. I I l a) Notify TSC of need to transport l injured / contaminated personnel offsite l for treatment.) 1 - l 12. Field Monitoring Teams a) Briefing Sheets completed (Datasheet 2).

1) EAB

2) EPZ b) Briefing of teams conducted.

1) EAB O 2) EPZ

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RERP-PCC Checklist 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0Public service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 O

PCC DIRECTOR'S CHECKLIST TIME c) Teams dispatched.

1) EAB

2) EPZ l 13. Inplant/Onsite Monitoring Teams a) Briefing sheet completed (Datasheet 3).

b) Briefing of team (s) conducted. c) Team (s) dispatched. l 14. Emergency Teams a) Briefing sheet completed (Datasheet 4). b) Briefing of team (s) conducted. c) Team (s) dispatched. l 15. Personnel accountability verification completed - TSC notified. l 16. Colorado State University Personnel arrived at PCC and TSC Director informed. O l i i FORM (C)372 22 3843

RERP-PCC Checklist 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0Public Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 2 O

l PERSONNEL ASSIGNMENT CONTROLLER'S CHECKLIST l 1. Assign individuals to perform required functions. Distribute l attachments as indicated. l NAME(S) TIME l a) Personnel Accountability I and Exposure l (Attachment 1) l b) Recorder (Attachment 2) l c) Communications l (Attachment 3) l d) Decontamination

      ]                 (Attachment 4) l         e)      Security Guards l                 (Attachment 5) l         f)      Drivers (Attachment 6) v l         g)      First Aid (Attachment 7) l         h)      Maintenance, Repair and Damage Control i

l (Attachment 8) l i) Habitability l (Attachment 9)

   ,  l         j)      Friskers (No Attachment) l         k)      Access Control l                 (No Attachment) l         1)      Monitoring Team Members (EAB) l                 (Refer team members to l                 RERP-FIELD) l I

i O l ro m ici m .22.aec

RERP-PCC Checklist 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0SerylCe* PUBUC SERVICE COMPANY OF COLORADO Page 2 of 2 1 q J l m) Monitoring Team Members (EPZ) l (Refer team members to l RERP-FIELD) l I l n) Monitoring Team Members (In Plant) l (See RERP-SURVEY) l I l o) Emergency Team Members I (See RERP-TEAMS) l . I l 2. Assign an individual to direct and retrieve additional personnel l to/from holding areas as required. l l 3. Inform the PCC Director when all necessary assignments are made I as this signifies that the manning requirements of the PCC are l met. I l 4. Inform Exposure Controller of team assignments and l responsibilities. l l S. Provide each group with additional manpower as required. l l 6. List available personnel on the control board from the E-Kit. I O FORMtC)372 22 3M3 I

RERP-PCC Public FORT ST. VRAIN NUCLEAR GENERATING STATION O Service

• PUBUC SERVICE COMPANY OF COLORADO Page 1 of 3 l PERSONNEL ACCOUNTABILITY AND EXp0SURE CONTROLLER l 1. Assume the duty of maintaining accountability and recording i personnel exposure for evacuated personnel and for emergency l team personnel leaving the PCC on assignments.

1 l 2. Issue film badge and dosimeter (s) (at least a high range l dosimeter is required) for all team members. Record initial dosimeter readings, name and SSN number on film badge.

3. When personnel leave the PCC, record the time out and indicate their destination. It is the responsibility of the Personnel Assignment Controller to notify the Personnel Accountability and 4

Exposure Controller of team assignments and destinations. It is 1 the individual's responsibility to report to the Personnel Accountability and Exposure Controller upon their return / arrival to the PCC.

4. Logged Exposure is Final Dosimeter Reading minus Initial i Dosimeter Reading.

O 5. Current Exposure is Previous Exposure plus Logged Exposure.

6. Each time an individual is sent out on a team assignment, there should be a separate entry on the Personnel Accountability and -

Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.

7. Maintain records of all dos' metry and assignments for master log.

8. Assist the Personnel Assignment Controller in maintaining the status of all personnel on-site and at the Personnel Control Center.

9. Maintain accountability and recording of personnel contamination.

O FoRMtC)372 22 3H3

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RERP-PCC Attachment 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 OPublicservice

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of I l RECORDER l 1. Assist Communications personnel in notifying remainder of l personnel to man the PCC.

l 2. Keep a running log of all actions taken. a) These notes must be complete. The log could be used as an evaluation of the incident and could serve as a legal document. b) Any corrections by person recording the events must be initialled. l 3. Collect all data sheets and work sheets and give to PCC Director when PCC operations are terminated. l 4. After PCC operations have been terminated: a) Collect PCC Director's Checklist. j b) Collect Personnel Accountability and Exposure Controller Datasheets (Datasheet #1) O c) Collect any Emergency Exposure Job

Briefing Datasheets utilized (RERP-EXP, j Datasheat #1) d) Attach Recorder Logs of PCC events and activities e) Forward a3 Documents to the

FSV Nuclear Documents Supervisor for disposition, f) Complete Forms Use Reporting Sheet.

l O FOAM (C1372 22 3843

RERP-PCC Attachment 3-Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 $9fVICe* PUBUC SERVICE COMPANY OF COLORADO Page 1 of 5 O COMMUNICATIONS l 1. Notify remainder of personnel to man the PCC. (Obtain list from ' l Alternate Director or call individuals on the Call List that are l not marked with an asterisk (*) and all HP Technicians not l previously notified.)

                                                          ~

l 2. Establish communications with the Technical Support Center (TSC) and verify primary and secondary communication links are operaole. a) If PCC is Onsite Primary Telephone (0 pen Line) PSC Radio Secondary PSC Gai-Tronics Telephone

O 6) tr ecc is orrsit-Primary Telephone Secondary PSC Radio l 3. When instructed to do so, inform the TSC that the PCC is manned and ready and prepared to receive personnel.

l 4. Receive status of plant and emergency and assessment of l condition and inform PCC Director, who will then brief the PCC personnel. l S. With the PCC Director, fill out the STANDARD MESSAGE Form (Page 3). l 6. Within 30 minutes of ACC activation, notify all persons living within the property boundary of the plant emergency. Record the time notified and intial the CALL SHEET (Page 4). If unable to contact persons by phone, notify PCC Director. The PCC Director will dispatch personnel to inform persons. Record time Driver (s) dispatched. ponocim.m.as.:

RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 SOrVICO'"PUBUC SERVICE COMPANY OF COLORADO Page 2 of 5 () l 7. If event occurs during normal working housr, confirm Visitor l Center's notification of emergency. Confirm that Ft. Lupton Fire Station has been notified to receive Visitor Center evacuees. Record time verified or notified. l 8. Notify St. Luke's Hosptial in accordance with Medical Emergency Plan to prepare to receive injured and contaminated person (s) if required. l 9. Notify a medical facility to prepare to receive injured '

 =

person (s) if required. l 10. If necessary to relocate PCC, call facility as directed by PCC Director. Record the time of notification (See RERP PHONE LIST, l Centers / Posts Phone Numbers for telephone numbers). l 11. Inform tha TSC of the departure and return of Monitoring Teams I and Emergency Teams. l 12. Maintain communications flow between PCC and the TSC. l 13. Keep records of all pertinent information for master log. !( I h ] i

                                                                                                   ~

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RERP-PCC l Attachment 3 FORT ST. VRAIN NUCLEAR GENERATING 9TATION Issue 15 ePublic Service

• PUBUC SERVICE COMPANY OF COLORADO Page 3 of 5 O

V STANDARD MESSAGE l t 1 FILL IN THE BLANKS OF THE FOLLOWING STATEMENT, WHICH WILL BE READ VERBATIM TO THE PERSONS ON THE FOLLOWING LIST. At (TIME) there was an incident at the Fort St. Vrain Nuclear Power Generating Plant. The precautionary protecf.tve ~ measures we are taking for the populace in the affected area are: (EVERYONE STAY INDOORS), (SELECTIVE EVACUATION OF CHILDREN AND PREGNANT WOMEN), (EVACUATION OF AFFECTED AREA TO FT. LUPTON O etas osa^atse"T). O FORMIC 1372 22 3043

RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 5 O CALL SHEET Persons Living Within Property Boundary (Nu.bers correspond to Map, Pg. 5)

Name Phone No. Time Notified Driver Dispatched

1. Ben Houston 785-2408

2. Randy Russell 785-6326

3. Bill Pitt 785-6274

4. Raymon Marin 785-2862

5. Vacant No Phone

6. Scott Houston 785-2358

7. Keith Russell 785-2589

8. Dave LaChance 785-6303 0

FORMICl372 22 3M3

RERP-PCC Attachment 3 l ORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0Public Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 5 of 5 O

V Site Resident Notification Map i 27 Pet N

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RERP-PCC Attachmrnt 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 A) service

• PUBUC SERVICE COMPANY OF COLORADO Page 1 of 2 n

DECONTAMINATION

1. Survey all portions of the body.

2. Remove contaminated clothing.

3. Decontaminate the contaminated portions of the body using waterless hand cleaner (or mild soap and water if waterless hand '

cleaner is unavailable). Put a small amount of hand cleaner on the contaminated area (s) and lightly rub it around. Using Terry Towels or a similar soft paper towel, wipe the cleaning solution off of the victim. If mild soap is used, care should be taken to minimize the amount of rinse water, and the area should be patted dry.

4. Resurvey the area and determine the effectiveness of the decontamination effort.

;      5.      Continue this method of decontamination until the levels of contamination are reduced below allowable limits" or until the area is free of contamination.

6. If contamination cannot be removed by above methods, proceed to the following steps:

a) If a person is injured and requires evacuation to a medical center, outline contaminated areas on skin. Tag person with infnrmation on radiatian levels in these areas. Tags are in the Emergency Kit. b) Inform PCC Director of the need to transport injured person to St. Luke's Hospital so that he may coordinate move. c) If a person is uninjured, follow the decontamination instructions included in the Emergency Kit under Health Physics Procedure for Personnel Decontamination (HPP-11). Utilize HPPs-9, 10, 11, and 21 as reference, if required.

                   < 10 OPM/100 cm 2 alpha and < 100 DPM/100 cm8 beta gamma activity removable contamination outside radiological controlled areas.

FoRMICl372 22 3M3

RERP-PCC Attachment 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

0. service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2,of 2 A

V SAMPLE BODY TAG -

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1. Mark areas that are contaminated.

2. Number the areas.

3. Record levels of contamination in spaces given on back of card.

4. Secure tag to the individual.

O FORMIC 4372 22 3843

RERP-PCC Attachment 5 g PublicServlCe* FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 PUBUC SERVICE COMPANY OF COLORADO Page 1 of 1 n" FORT ST. VRAIN SECURITY DEPARTMENT PERSONNEL CONTROL CENTER RESPONSE GUARD

1. One guard reports to the Personnel Control Center.

l 2. Assist in gate control, if applicable, of authorized personnel and vehicles at the Personnel Control Center for equipment or support called to assist, if necessary.

3. Keep records of all PCC security actions taken for master log.

v l 4. Assist with radio communications and access authorizations with the LSO. _

                                                                         ,,r SITE RESPONSE GUARDS

1. Check all site visitors out through Search & Identification Facility.

2. Facilitate exiting of onsite personnel to PCC.

O 3. Ass'st in personnel accountability as requested. 4 Assist with personnel and vehicle ingress / egress to/from the protected and vital areas as required by the PCC Director. NOTE: PCC> Director or Emergency Coordinator coordinates access of personnel and vehicles into the protected area or vital areas with the LSO (i.e., names of drivers, vehicle types). i O row teim.m.sna 1

RERP-PCC Attachment 6 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 l 0 service

• PusuC SERVICE COMPANY OF COLORADO Page 1 of 1 )

O DRIVERS

1. Drive vehicles and assist teams. (Health Physics, Roadblock, l Door-to-door notification of Residents on site property.)

2. Obtain personnel dosimetry, instructions, maps, and l communications equipment before leaving the PCC.

l NOTE: Personal vehicles may be used to perform functions as l requ' red if RERP-assigned vehicles are in use. I i O O PodMICl372 22 3843

RERP-PCC Attachment 7 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 Service" PUBUC SERVICE COMPANY OF COLORADO Page 1 of 2

  .O                                                                                        1 FIRST AID

• I i

1. Establish first aid area.

2. Administer first aid to injured utilizing HP assistance as l needed. '

3. Inform PCC Director of the need to transport injured person (s) to a medical facility in order that he may coordinate the move.

4. Assist Decontamination personnel when tagging injured personnel to be transported off-site.

5. Keep records for master log of injured personnel, and extent of injuries.

i 4 i 1 O

• Utilize Fort St. Vrain Medical Emergency Plan as reference.

I lO I I - . PORMIC1372 23 300 l i

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RERP-PCC l Attachment 8 , Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 Service ~ pusuC ssRviCE COMPANY OF COLORADO Page 1 of 1 O l MAINTENANCE, REPAIR AND DAMAGE CONTROL l 1. Perform mechanical / electrical repair / damage control, emergency l maintenance, and temporary modifications as required. l 2. Keep records of all actions taken. i O i 1 l !o i conwician.za.ases l

RERP-PCC Attachment 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Page 1 of 1 0$9tVlC9" PUBUC SERVICE COMPANY OF COLORADO 0 l HABITABILITY

l 1. Perform habitability checks e~very 15-20 minutes.

l 2. Perform surveys and take air samples as required. (Contact l Health Physics individual if required.) l 3. Establish decontamination areas and/or radiologically controlled l areas as required. j a 4 J

 ,         O l                              .

O FoMMICl372 22 3843 l . - - . - . _ - , -

RERP-PCC US/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0SerylCe* PUBUC SERVICE COMPANY OF COLORADO Page 1 of 3 Q l WORK /DATASHEET/ CHECKLIST CDNTROL LIST Worksheet No. Title Number Copies None N/A N/A Datasheet No. l 1 Briefing Sheet for Field Monitoring Teams 2 l 2 Briefing Sheet for Inplant Monitoring Teams 2 l 3 Briefing Sheet for Emergency Teams 2 Checklist No. O 1 PCC Director's Checklist 2 l 2 Personnel Assignment Controller's Checklist 2 Attachment No. l 1 Personnel Accountability and Exposure 10 l 2^ Recorder 2 l 3 Communications 2 l 4 Decontamination 2 l 5 Security 2 l 6 Drivers 2 l 7 First Aid 2 l l 8 Maintenance, Repair and Damage Control 2 l 9 Habitability 2 . V 1 l l FORMtC1372 22 3043 l

RERP-PCC US/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 0 Service" PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 O FORMS USE REPORTING SHEET Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at

                                                                       . The following forms have been utilized from this sopy:

Worksheet Numbers Copies Used O Datasheet Numbers Copies Used Checklist Numbers Cooies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace the noted number of forms, as well as -this " Forms Use Reporting

                        ]

FORM (Q372 22 3143 l

RERP-PCC WS/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Page 3 of 3 0 SerVIC9" PUBUC SERVICE COMPANY OF COLORADO O Sheet" for the affected procedure in the affected book. FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: Nuclear Documents Specialist

• Date Received O Date Replaced Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.

1 O l FoMM(C)372 22 3843

RERP-PCC Public FORT ST. VRAIN NUCLEAR GENERATING STATION 5u SOIVice" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 6 l Datasheet 1 Briefing Sheet for Field Monitoring Teams (To be completed by senior HP representative at the TSC)

1) Area to be surveyed l 2) Route to be taken (mark on appropriate map):

O- 3) Ceicoi tea or estimetea n remeters a) General Radiation Level (mrem /hr) b) Airborne Activity Level (uci/cc)

4) Projected Time to complete survey (br)

5) Projected Exposure-3)a) x 4) x 1.25 = (mrem)

6) Maximum Stay Time (based upon 10CFR20 limits or, with the TSC Director's Concurrence, the guidelines of RERP-EXP, Emergency Exposure Guidelines)

(hr) O FoRMICl372 22 3643

kLkP-PCC' l Datasheet 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

         @ Service ~               pusLic sERvlCE COMPANY OF COLORADO        Page 2 of 6 i

7) Team Members: i

8) Dosimetry requirements:

Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range l Other:

9) Protective Equipment requirements -

(Circle required equipment): Full. Anti-C's Shoe Covers and Gloves No Protective Clothing Required 4 Full-Face Respirator Scott Air Pack Thyroid Blocking Agent (see RERP-THYROID) l No Respiratory Protection Required l O FoAMICl372 22 3643

RERP-PCC l Datasheet 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 l service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 6 O

10) Comments:

a) Save used filters and cartridges for Radiochemistry analysis. b) Leave the eme'gency r vehicle running while in the field and upon return to avoid battery discharge. O O FORM (C)372 22 3843

i.EhF-FCC Datasheet 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Service ~ PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 6 O I I e _J , I 1 o' v / ' '

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idid -PCC Data,heet 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION } sue 15 . Service

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1 RERF-PCC 8 Datasheet 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 1 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 6 of 6 O

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l RERF-PCC l Public FORT ST. VRAIN NUCLEAR GENERATING STATION ue

                         ' ) ' ServlCe           PUBLIC SERVICE COMPANY OF COLORADO            Page 1 of 6 l O

l Datasheet 1 Briefing Sheet for Field Monitoring Teams (To be completed by senior HP representative at the TSC)

1) Area to be surveyed l 2) Route to be taken (mark on appropriate map):

O 3)- Caicu,ated or estimated parameters a) General Radiation Level (mrem /hr) b) Airborne Activity Level (vci/cc)

4) projected Time to complete survey (hr)

5) Projected Exposure 3)a) x 4) x 1.25 = (mrem)

6) Maximum Stay Time (based upon 10CFR20 limits or, with the TSC Director's Concurrence, the guidelines of RERP-EXP, Emergency Exposure Guidelines)

(hr) n v f FORMICl372 22 3843

RERP-PCC Datasheet 1

    / siPublic               FORT ST. VRAIN NUCLEAR GENERATING STATION          Issue 15
       )) Service"           PUBLIC SERVICE COMPANY OF COLORADO                 Page 2 of 6

7) Team Members:

8) Dosimetry requirements:

             -Pocket Dosimeter - High Range (required)

Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range Q l Other:

9) Protective Equipment requirements -

(Circle required equipment): Full. Anti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator Scott Air Pack Thyroid Blocking Agent (see RERP-THYROID) \ No Respiratory Protection Required O V I FORMICl372 22 3643 I

RERP-PCC I Datasheet 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 SerVICO* PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 6 G V

10) Comments:

a) Save used filters and cartridges for Radiochemistry analysis. b) Leave the emergency vehicle running while in the field and upon return to avoid battery discharge. l O i 1 S O FomM tCl372 22 3043

l KERP-PCC 8 Datasheet 1

              .Public                                                   FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                     Issue 15 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 4 of 6 l O

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RERP-PCC Datasheet 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION . Issue 15

      @ Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 ja O

l Datasheet 2 Briefing Sheet for Inolant/Onsite Monitoring Teams (To be completed ,by senior HP representative at the TSC)

1) Area to be surveyed l

2) Known parameters a) General Radiation Level (mrem /hr)

Detector RIS-O b) Airborne Activity Level (vci/cc) Detector . c) Surface Contar.ination Levels

• DPM/100cm"

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3) Projected Time to complete survey (hr)

4) Projected Exposure 2)a) x 3) x 1.25 = (mrem)

5) Maximum Stay Time (based upon 10CFR20 limits or, with the TSC Director's Concurrence, the guidelines of RERP-EXP, Emergency Exposure Guidelines)

(br) This parameter may be unknown prior to team deployment. l FORMfC1372 22 3843 i l I

RERP-PCC Public FORT ST. VRAIN NUCLEAR GENERATING STATION u

       @ $9fVICe*PUBLIC SERVICE COMPANY OF COLORADO                                                                    Page 2 of 3 O

6) Team Members:

7) Briefing of HP Technician Team Leader By:

(PCC Director).

8) Dosimetry requirements:

Pocket Dosimeter - High Range (required) Other dosimetry requirements (circle): Film Badge Pocket Dosimeter - Low Range , TLD Finger Ring Other:

9) Protective Equipment requirements i

(Circle required equipment): Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator Scott Air Pack Thyroid Blocking Agent (see RERP-THYROID) No Respiratory Protection Required O FoRMICl372 22 3M3

RERP-PCC Datasheet 2 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 l Page 3 of 3 4 Service" PUBLIC SERVICE COMPANY OF COLORADO f i O

10) Cemments:

a) Save used filters and cartridges for Radiochemistry analysis. O e l l O i

ronvicam n.3m

l<r.lil'-l'LC Dat.isheet 2 , Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 e

(,s l Datasheet 2 Briefing Sheet for Inolant/Onsite Monitoring Teams (To be completed py senior HP representative at the TSC)

1) Area to be surveyed __

I

2) Known parameters a) General Radiation Level (mren/hr)

Detector RIS-b) Airborne Activity Level (uct/cc) Detector c) Surface Contamination Levels

• DPM/100cm8

3) Projected Time to complete survey (hr)

4) Projected Exposure 2)a) x 3) x 1.25 = (mrem)

5) Maximum Stay Time (based upon 10CFR20 limits or, with _the T5C Director's Concurrence, the guidelines of RERP-EXP, Emergency Exposure Guidelines)

(br) This parameter may be unknown prior to team deployment. (N

 %.)

FORMCl372 22 3543

l REkP-PCC Datasheet 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 service" PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 i O

6) Team Members: _ _ _ __

7) Briefing of HP Technician Team Leader By:

(PCC Director).

8) Dosimetry requirements:

Pocket Dosimeter - High Range (required) / Other dosimetry requirements (circle): Film Badge Pocket Dosimeter - Low Range TLD Finger Ring O Other:

9) Protective Equipment requirements (Circle required equipment):

Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator Scott Air Pack Thyroid Blocking Agent (see RERP-THYROID) No Respiratory Protection Required ponuicim 22 was

RERP-PCC Datasheet 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 O

10) Comments:

a) Save used filters and cartridges for Radiochemistry analysis. 9 i O l FORM tC1372-22 3643 l

RERP-PCC Datasheet 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

 @ SerVICO*               PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O

l Datasheet 3 Briefina Sheet for Emeroency Teams

1) Area (s) to be entered

2) Known parameters:

a) General Radiation Level (mrem /hr) Detector RIS-l b) Airborne Activity Level (pci/cc) Detector c) Surface Contamination Levels

• DPM/100cm2

3) Projected Time to complete task (br)

4) Projected Exposure 2)a) x 3) x 1.25 = (mrem)

5) Maximum Stay Time -

• Based upon 10CFR20 limits (3 rem / quarter whole body with completed NRC Form 4, 3 E-09 pct /cc unidentified airborne contamination) or, with the TSC Director's Concurrence (NOTE:

Prior to activation of emergency organization, the Shift Supervisor'may authorize exposures in excess of 10CFR20 limits), the guidelines of RERP-EXP, Emergency Exposure Guidelines (hr) This parameter may be unknown prior to team deployment. FORMtCl372 22 3043

RERP-PCC Datasheet 3 Public FORT ST. VRAIN NUCLEAR. GENERATING STATION Issue 15

       @ ServiCO                  PUBLIC S'ERVICE COMPANY OF COLORADO          Page 2 of 3 O

6) Team Members:

7) Briefing of Team By:

8) Dosimetry requirements:

Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range O TLD Finger Ring

9) Protective Equipment requirements (Circle required equipment):

Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required i Full-Face Respirator , Scott Air Pack O Thyroid Blocking Agent (see RERP-THYROID) FORMIC 1372 22-3843 -

RERP-PCC Datasheet 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15-Page 3 of 3

              @ SerVIC9"PUBLIC SERVICE COMPANY OF COLORADO O

No Respiratory Protection Required

10) Comments: .

i I 4 O s 9 4 O ronuici m . n . m a l 4

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

RERP-PCC Datasheet 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 i SerVICO" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 1 l O l Datasheet 3 Briefing Sheet for Emeroency Teams

1) Area (s) to be entered  !

2) Known parameters:

a) Ceneral Radiation Level (mrem /hr) _ Detector RIS- . ..,,._ / l b) Airborne Activity Level (yci/cc) Detector c) Surface Contamination Levels

• DPM/100cm8

3) Projected Time to complete task (br)

4) Projected Exposure 2)a) x 3) x 1.25 = (mrem)

5) Maximum Stay Time -

Based upon 10CFR20 limits (3 rem / quarter whole body with completed NRC Form 4, 3 E-09pci/cc unidentified airborne contamination) or, with the TSC Director's Concurrence (NOTE: Prior to activation of emergency organization, the Shift Supervisor'may authorize exposures in excess of 10CFR20 limits), the guidelines of RERP-EXP, Emergency Exposure Guidelines (hr) This parameter may be unknown prior to team deployment.

 'f O

1 FORMIC)372 22 3043

RERP-PCC Public FORT ST. VRAIN' NUCLEAR GENERATING STATION su service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 O  !

6) Team P abers:

7) Briefing of Team By:

8) Dosimetry requirements:

Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range O TLD Finger Ring

9) Protective Equipment requirements (Circle required equipment): "

Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator Scott Air Pack O Thyroid Blocking Agent (see RERP-THYROID) 70RMICl372 22 3043

RERP-PCC Datasheet 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 , Service" PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 l . O No Respiratory Protection Required

10) Comments: .

O I 6 i l l O l FORMIC)372 22 3643

                          .~                                _.      _.

RERP-PCC Checklist 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

         @. Service Public*              PUBLIC SERVICE COMPANY OF COLORADO         Page 1 of 3 PCC DIRECTOR'S CHECKLIST TIME
             -NOTE:          All information is to be logged by the Recorder.

l 1. Personnel Control Center (PCC) location: l 2. Habitability confirmed at PCC. i l 3. Notification to Visitor's Center confirmed. l (May have been performed by Emergency Coordinator.) l 4. Fort Lupton Fire Department notified to receive Visitor's Center occupants (See RERP O PHONE LIST). l 5. (Normal working hours) make announcment by using telephone. Dial 6-0-4 and announce , l "PCC Personnel, report to Personnel Control l Center located at ." Repeat l message. 1 l 6. Verify with the Visitor Center (extension l 475) and the Lunchroom (extension 264) that l the announcement was received. ! l.

l l 7. Controlled area established. All doors locked except the one being utilized for controlled entry into the PCC.

O FOMMtCl372 22 3M3

RERP-PCC Checklist 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

      - ) service"             PUBLIC SERVICE COMPANY OF COLORADO          Page 2 of 3 O                                    PCC DIRECTOR'S CHECKLIST TIME l 8.      Manning requirements adequately met. Request l         that individual at,the TSC (if activated) or l         the    Control    Room      notify the Emergency l         Coordinator (TSC Director,           Control    Room l         Director, or Shift Supervisor, depending on l         level of activation) that the PCC is manned l         and    monitoring     teams     are ready to be l         dispatched.

l 9. Personnel dispatched to establish road blocks to the North and South of the plant along

   .             County Road 1915        (IF NOT ALREADY DONE BY COUNTY / STATE LAW ENFORCEMENT AGENCIES.)

l 10. Persons living within property boundary l notified and/or drivers dispatched. O l 11. Indicate transported individuals, if l transport to St. Luke's is required. 1 I l a) Notify TSC of need to transport l injured / contaminated personnel offsite i for treatment.) l l 12. Field Monitoring Teams a) Briefing Sheets completed (Datasheet 2).

1) EAB  ;

i

2) EPZ b) Briefing of teams conducted.

l

1) EAB l Q 2) EPZ l

FORMIC)372 22 3643

RERP-PCC Checklist 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

    @ service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 3 4

o PCC DIRECTOR'S CHECKLIST TIME c) Teams dispatched.

1) EAB

2) EPZ l 13. Inplant/Onsite Monitoring Teams a) Briefing sheet completed (Datasheet 3).

b) Briefing of team (s) conducted." - - 4 c) Team (s) dispatched. l 14. Emergency Teams i a) Briefing sheet completed (Datasheet 4). b) Briefing of team (s) conducted. c) Team (s) dispatched. l 15. Personnel accountability ~ verification completed - TSC notified. l 16. Colorado State University Personnel arrived at PCC and TSC Director informed. O F0AMIC)372 22 3643

RERP-PCC Checklist 1 ' M Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

                -07 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 l l

(2) PCC' DIRECTOR'S CHECKLIST l TIME NOTE: All information is to ba logged by the Recorder. l 1. Personnel Control Center (PCC) location: l 2. Habitability confirmed at PCC. I i l 3. Notification to Visitor's Center confirmed.

!              l         (May have been         performed       by                     Emergency i

Coordinator.) i l 4. Fort Lupton Fire Department notified to receive Visitor's Center occupants (See RERP Q PHONE LIST). l 5. (Normal working hours) make announcment by

                       -using telephone.       Dial 6-0-4 and announce l         "PCC . Personnel, report to Personnel Control l         Center located at                                     .

Repeat l message. J l 6. Verify with the Visitor Center (extension 1 475) and the Lunchroom (extensten 264) that l the announcement was received. l-l 7. Controlled area established. All doors locked except the one being utilized for controlled entry into the PCC. i O FORMICl372 22 3MS

RERP-FCC Public FORT ST. VRAIN NUCLEAR GENERATING STATION ue SerVICO" PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 3 PCC DIRECTOR'S CHECKLIST TIME l 8. Manning requirements adequately met. Request l that individual at.the TSC (if activated) or ) l the Control Room notify the Emergency l Coordinator (TSC Director, Control Room l Director, or Shift Supervisor, depending on l level of activation) that the PCC is manned l and monitoring teams are ready to be l dispatched. l 9. Personnel dispatched to establish road blocks to the North and South of the plant along County Road 19 . (IF NOT ALREADY DONE BY COUNTY / STATE LAW ENFORCEMENT AGENCIES.) l 10. Persons living within praperty boundary l notified and/or drivers dispatched. O l 11. Indicate transported individuals, if i l transpcrt to St. Luke's is required. I I l a) Notify TSC of need to transport l injured / contaminated personnel offsite i for treatment.) I l 12. Field Monitoring Teams a) Briefing Sheets completed (Datasheet 2).

1) EAB

2) EPZ b) Briefing of teams conducted.

, 1) EAB Q 2) EPZ l FORM (C)372 22 3843

RERP-PCC

     & Public                        FORT ST. VRAIN NUCLEAR GENERATING STATION      u Page 3 of 3 WI Service

• PUBLIC SERVICE COMPANY OF COLORADO O PCC DIRECTOR'S CHECKLIST TIME c) Teams dispatched.

1) EAB

2) EPZ l 13. Inplant/Onsite Monitoring Teams a) Briefing sheet completed (Datasheet 3).

1 i

               -b)      Briefing of team (s) conducted.

I c) Team (s) dispatched. O l 14. Emergency Teams a) Briefing sheet completed (Datasheet 4). b) Briefing of team (s) conducted. c) Team (s) dispatched. l 15. Personnel accountability verification completed - TSC notified. I l 16. Colorado State University Personnel arrived

at PCC and TSC Director informed.

I l O FoRMICl372 22 3843

RERT-PCC , ! Public FORT ST. VRAIN NUCLEAR GENERATING STATION u ' Page 1 of 2 ! ) service PUBLIC SERVICE COMPANY OF COLORADO l l O V l PERSONNEL ASSIGNMENT CONTROLLER'S CHECKLIST l 1. Assign individuals to perform required functions. Distribute l attachments as indicated. l NAME(S) TIME l a) Personnel Accountability I and Exposure l (Attachment 1) l b) Recorder (Attachment 2) l c) Communications l (Attachment 3) l d) Decontamination l (Attachment 4) l e) Security Guards l (Attachment 5) I f) Drivers (Attachment 6) l g) First Aid (Attachment 7) l h) Maintenance, Repair l and Damage Control

• l (Attachment 8) l i) Habitability l (Attachment 9) l, j) Friskers (No Attachment) l k) Access Control l (No Attachment) i 1) Monitoring Team Members (EAB) l (Refer team members to - --

l RERP-FIELD) l I O FORMICl372 22 3SO

RERP-PCC Checklist 2 Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 2 O

l m) Monitoring Team Members (EPZ) l (Refer team members a ' l RERP-FIELD) l l l n) Monitoring Team Members (In Plant) l (See RERP-SURVEY) l l Emergency Team'Me'bers

                                                           ~J l         o)                               m l                 (See RERP-TEAMS)

I l n l 2. Assign an individual to direct and retrieve additional personnel V l to/from holding areas as required. I l 3. Inform the PCC Director when all necessary assignments are made l as this signifies that the manning requirements of the PCC are l met. I l 4. Inform Exposure Controller 'of team assignments and l responsibilities. l l 5. Provide each group with additional manpower as required. 4 l 1 6. List available personnel on the control board from the E-Kit. I O POAM(C)372 22 3843

RERP-PCC Checklist 2 Public - FORT ST. VRAIN NUCLEAR GENER ATING STATION Issue 14

    @ SerylC9"                 PUBLIC SERVICE COf/iPANY OF COLORADO        Page 1 of 2 l                   PERSONNEL ASSIGNMENT CONTROLLER'S CHECKLIST l 1. Assign individuals to perform required functions. Distribute l        attachments as indicated.

l NAME(S) TIME l a) Personnel Accountability l and Exposure l (Attachment 1) l b) Recorder (Attachment 2) l c) Communications i l (Attachment 3) l d) Decontamination , l (Attachment 4) l e) Security Guards l (Attachment 5) l f) Drivers (Attachment 6) l g) First Aid (Attachment 7) l h) Maintenance, Repair I and Damage Control - l (Attachment 8) l i) Habitability l (Attachment 9) l, j) Friskers (No Attachment) l k) Access Control l (No Attachment) i 1) Monitoring Team Members (EAB) l (Refer team members to l RERP-FIELD) l ., l . O FORMtCl372 22 3M3

RERP-PCC Checklist 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issus I4 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 2 of 2 j l m) Monitoring Team Members (EPZ) l (Refer. team members to i l RERP-FIELD) l I

i l n) Monitoring Team Members (In Plant) l (See RERP-SURVEY) I i l o) Emergency Team Members I (See RERP-TEAMS) i I Q l 2. . Assign an individual to direct and retrieve additional personnel I to/from holding areas as required. I l 3. Inform the PCC Director when all necessary assignments are made I as this signifies that the manning requirements of the PCC are l met. l l 4. Inform Exposure Controller of team assignments and l responsibilities. ,

          .                                                                                                    l l S.      Provide each group with additional manpower as required.

I 1 l 6. List available personnel on the control board from the E-Kit. I O FoRMICl372 22 3083

RERP-PCC Attachment 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 ServlC9" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O 1 l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER , l 1. Assume the- duty of maintaining accountability and recording l- personnel exposure for evacuated personnel and for emergency ' [ team personnel leaving the PCC on assignments. l 2. Issue film badge and dosimeter (s) (at least a high range l dosimeter is required) for all team members. Record initial dosimeter readings, name and SSN number on film badge. < 3. When personnel leave the PCC, record the time out and indicate , their destination. It is the responsibility of the Personnel l Assignment Controller to notify the Personnel Accountability and l Exposure Controller of team assignments and destinations. It is >

.                    the individual's responsibility to report to the Personnel i

Accountability and Exposure Controller upon their return / arrival i to the PCC.

4. Logged . Exposure is Final Dosimeter Reading minus Initial  !

O '' "d'"'-

5. Current Exposure is Previous Exposure plus Logged Exposure. l i 6. Each time an individual is sent out on a team assignment, there should be a separate entry on the Personnel Accountability and -

Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.  ;

7. Maintain records of all dostmetry and assignments for master

log.

8. Assist the Personnel Assignment Controller in maintaining the status of all personnel on-site and at the Personnel Control Center.

9. Maintain accountability and recording of personnel contamination.

l i i O FoRMtClF12 22 3M3 i

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l RERP-PCC Public FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O

l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER l 1.- Assume the duty of maintaining accountability and recording l personnel exposure for evacuated personnel and for emergency l team personnel leaving the PCC on assignments. l 2. Issue film badge and dosimeter (s) (at least a high range l dosimeter is required) for all team members. Record initial dosimeter readings, name and SSN number on film badge.

3. When personnel leave the PCC, record the time out and indicate their destination. It is the responsibility of the Personnel Assignment Controller to notify the Personnel Accountability and Exposure Controller of team assignments and destinations. It is the individual's responsibility to report to the Personnel Accountability and Exposure Controller upon their return / arrival to the PCC.

4. Logged Exposure is Final Dosimeter Reading minus Initial

{ Dosimeter Reading.

5. Current Exposure is Previous Exposure plus Logged Exposure.

6. Each time an individual is sent out on a team assignment, there should be a separate entry on the Personnel Accountability and -

Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.

7. Maintain records of all dosimetry and assignments for master log.

8. Assist the Personnel Assignmen't Controller in maintaining the status of all personnel on-site and at the Personnel Control -

Center.

9. Maintain accountability -- and- -- recording .. of personnel contamination.

O FonMicl372 22 3M3

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l I RERP-PCC p Public FORT ST. VRAIN NUCLEAR GENERATING STATION u Service

• PUBLIC SERVICE COr.1PANY OF COLORADO Page 1 of 3 O

l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER l 1. Assume the duty of maintaining accountability and recording l personn>1 exposure for evacuated personnel and for emergency l team per sonnel leaving the PCC on assignments. l 2. Issue film badge and dosimeter (s) (at least a high range l dosimeu r is required) for all team members. Record initial dost.r.atre readiaqs, name and SSN number on film badge.

3. When personnel leave the PCC, record the time out and indicate their destination. It is the responsibility of the Personnel Assignment Controller to notify the Personnel Accountability and Expo >ure Controller of team assignments and destinations. It is the individual's responsibility to report to the Personnel Accountability and Exposure Controller upon their return / arrival to the PCC.

4. Logged Exposure is Final Dosimeter Reading minus Initial Dosimeter Reading.

O 5. Current Exposure is Previous Exposure plus Logged Exposure.

6. Each time an individual is sent out on a team assignment, there should be a separate entry on the Personnel Accountability and -

Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.

7. Maintain records of all dosimetry and assignments for master log.

8. Assist the Personnel Assignment Controller in maintaining the .

status of all personnel on-site and at the Personnel Control Center.

9. Maintain - secountability - and . . recording - of._. personnel .

contamination. l l . O Fohutel372 22 3H3

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RERP-PCC Attachment 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

        @ service *PUBLIC               ' SERVICE COMPANY OF COLORADO                  Page 1 of 3 O

l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER l 1. Assume the' du'ty of maintaining accountability and recording l personnel exposure for evacuated personnel and for emergency 4 l team personnel leaving the PCC on assignments. l 2. Issue film badge and dosimeter (s) (at least a high range

l dosimeter is required) for all team members. Record initial dosimeter readings, name and SSN number on film badge.

 >          3.      When personnel.. leave the PCC,. record the-time out and indicate-                    - - -

their destination. It is the responsibility of the Personnel Assignment Controller to notify the Personnel Accountability and Exposure Controller of team assignments and destinations. It is the individual's responsibility to' report to the Personnel l Accountability and Exposure Controller upon their return / arrival 1 to the PCC.

4. Logged Exposure is Final Dosimeter Beading minus Initial Dosimeter Reading.

      )

. 5. Currect Exposure is Previous Exposure plus Logged Exposure. , 6. Each time an individual is sent out on a team assignment, there ! should be a separate entry on the Personnel Accountability and

• Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.

7. Maintain records of all dosimetry and assignments for master i log.

l 8. Assist the Personnel Assignment Controller in maintaining the status of all personnel on-site and at the Personnel Control i Center.

9. Maintain accountability and recording of personnel contamination. - - - - - - -

i ( l () FoPMIci372 22 3843

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RERP-PCC Attachment 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 I service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O

V l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER l 1. Assume the du'ty of maintaining accountability and recording l personnel exposure for evacuated personnel and for emergency l team personnel leaving the PCC on assignments. I 2. Issue film badge and dosimeter (s) (at least a high range i dosimeter is required) for all team members. Record initial dosimeter readings, name and SSN number on film badge.

3. When personnel leave the FCC, record the time out and indicate their destination. It is the responsibility of the Personnel Assignment Controller to notify the Personnel Accountability and Exposure Controller of team assignments and destinations. It is the individual's responsibility to report to the Personnel ,

Accountability and Exposure Controller upon their return / arrival to the PCC.

4. Logged Exposure is Final Dosimeter Reading minu's Initial Dosimeter Reading.

O 5. Current Exposure is Previous Exposure plus Logged Exposure.

6. Each time an individual is sent out on a team assignment, there should be a separate entry on the Personnel Accountability and -

3 Exposure Record Fo rm. It will be necessary to review the form for any previous exposure that an individual may have received. l

7. Maintain records of all dosimetry and assignments for master log.

1 .

8. Assist the Personnel Assignment Controller in maintaining the status of all personnel on-site and at the Personnel Control

• Center.

accountability

                                                                                                 ^

9. Maintain and recording of personnel contamination.

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i RERP-PCC i Attachment 1

 !-                             ,       . Pub llC               FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                     I$$y,}$

I SerVICO* Pusuc ssRVlCa COMPANY OF COLORADO Page 1 of 3 O , l PERSONNEL ACCOUNTABILITY AND EXp0SURE CONTROLLER  ! I t l -

                                                                                                                                                                                                                                  !r i

l l 1. Assume the du'ty of maintaining accountability and recording i personnel exposure for evacuated personnel and for emergency l team personnel leaving the PCC on assignments. l 3 1 l ' 2. Issue film badge and dosimeter (s) (at least a high range  ! l dosimeter is required) for all team members. Record initial j dosimeter readings, name and SSN number on film badge. l 3. When personnel leave the PCC, record the time out and indicate -  ! l their destination. It is the responsibility of . the Personnel  ! Assignment Controller to notify the Personnel Accountability and l Exposure Controller of team assignments and destinations. It is the individual's responsibility to report to the Personnel , i Accountability and Exposure Controller upon their return / arrival , to the PCC. j 4.- Logged Exposure is Final Dosimeter Reading minus Initial Dosimeter Reading. 1 1 O 5. Current Exposure is Previous Exposure plus Logged Exposure. i

+                                                                                                                                                                                                        -

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6. Each time an individual is sent out on a team assignment, there  !

should be a separate entry on the Personnel Accountability ~and

• Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.  ;

I 7. Maintain records of all dosimetry and assignments for master i log.  ;

8. Assist the Personnel Assignment Controller in maintaining the ,  !

status of all personnel on-site and at the Personnel control > i Center, , i

9. Maintain accountability. and recording of personnel  !

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RERP-PCC Attachment 1

 ;                            Public                      FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                               Issue 15 i           0 Service ~PUBLIC SERVICE COMPANY OF COLORADO                                                                                                                         Page 1 of 3 O

i l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER Assume the duty of maintaining accountability and recording

                                                                      ~

l 1. l personnel exposure for evacuated personnel and for emergency l team personnel leaving the PCC on assignments.

j 2. Issue film badge and dosimeter (s) (at least a high range l dosimeter is required) for all team members. Record initial

,i dosimeter readings, name and SSN numoer on film badge.

3. When personnel leave the PCC, record the time out and indicate i their destination. It is the responsibility of the Personnel

Assignment Controller to notify the Personnel Accountability and

] Exposure Controller of team assignments and destinations. It is j the individual's responsibility to report to the Personr.el i Accountability and Exposure Controller upon their return / arrival

to the PCC.

i 4 Logged Exposure is Final Dosimeter Reading minus Initial Dosimeter Reading. j 5. Current Exposure is Previous Exposure plus Logged Exposure. , 6. Each time an individual is sent out on a team assignment, there i should be a separate entry on the Personnel Accountability and - l Exposure Record Form. It will be riecessary to review the form i for any previous exposure that an individual may have received. I

7. Maintain records of all dosimetry and assignments for master log.

l 8. Assist the Personnel Assignment Controller in maintaining the

status of all personnel on-site and at the Personnel Control j Center, i

9. Maintain accountability and recording of personnel i contamination.

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RERP-PCC l Attachment 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Service ~ PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER l 1. Assume the duty of maintaining accountability and recording l personnel exposure for evacuated personnel and for emergency l l team personnel leaving the PCC on assignments. l 2. Issue film badge and dosimeter (s) (at least a high range

                  -l        dosimeter is required) for all    team members. Record initial dosimeter readings, name and SSN number on film badge.

3. When personnel leave the PCC, record the time out and indicate s .. _/, their destination. It is the responsibility of the Personnel Assignment Controller to notify the Personnel Accountability and Exposure Controller of team assignments and destinations. It is the individual's responsibility to report to the Personnel Accountability and Exposure Controller upon their return / arrival to the PCC.

4. Logged Exposure is Final Dosimeter Reading minus Initial Dosimeter Reading.

5. Current Exposure is Previous Exposure plus Logged Exposure.

6. Each time an individual is sent out on a team assignment, there should be a separate entry on the Personnel Accountability and -

Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.

7. Maintain records of all dostmetry and assignments for master log.

8. Assist the Personnel Assignment Controller in maintaining the l status of all personnel on-site and at the Personnel Control Center.

9. Maintain - accountability and recording-- of- personnel contamination.

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RERP-PCC Attachment 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Service" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER l 1. Assume the du'ty of maintaining accountability and recording l personnel exposure for evacuated personnel and for emergency l team personnel leaving the PCC on assignments. 4 l 2. Issue film badge and dosimeter (s) (at least a high range i dosimeter is required) for all team members. Record initial dosimeter readings, name and SSN number on film badge.

3. When personnel leave the PCC, record the time out and indicate their destination. It is the responsibility of the Personnel Assignment Controller to notify the Personnel Accountability and Exposure Controller of team assignments and destinations. It is the individual's responsibility to report to the Personnel Accountability and Exposure Controller upon their return / arrival to the PCC.

4. . Logged Exposure .i s Final Dosimeter -Reading minus Initial Dosimeter Reading.

5. Current Exposure is Previous Exposure plus Logged Exposure.

6. Each time an individual is sent out on a team assignment, there

should.be a separate entry on the Personnel Accountability and -

Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.

7. Maintain records of all dosimetry and assignments for master log.

8. Assist the Personnel Assignment Controller in maintaining the status of all personnel on-site and at the Personnel Control Center.

9. Maintain accountability and recording of personnel contamination.

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FomM(C)372 22 3tM3

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l RERP-PCC  ; Attachment 1 - Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 O SerVICO"PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 3 O l PERSONNEL ACCOUNTABILITY AND EXPOSURE CONTROLLER l 1. Assume the duty of maintaining accountability and recording  ! l personnel exposure for evacuated personnel and for emergency l team personnel leaving the PCC on assignments. l 2. Issue film badge and dosimeter (s) (at least a high range l dosimeter is required) for all team members. Record initial dosimeter readings, name and SSN number on film badge.

3. When personnel leave the PCC, record the time out and indicate their destination. It is the responsibility of the Personnel Assignment Controller to notify the Personnel Accountability and Exposure Controller of team assignments and destinations. It is the individual's responsibility to report to the Personnel Accountability and Exposure Controller upon their return / arrival to the PCC.

4. Logged Exposure is Final Dosimeter . Reading minus Initial Dosimeter Reading.

5. Current Exposure is Previous Exposure plus Logged Exposure.

6. Each time an individual is sent out on a team assignment, there should be a separate entry on the Personnel Accountability and -

Exposure Record Form. It will be necessary to review the form for any previous exposure that an individual may have received.

7. Maintain records of all dosimetry and assignments for master log.

8. Assist the Personnel Assignment Controller in maintaining the status of all personnel on-site and at the Personnel Control Center.

9. Maintain accountability and recording - of personnel -

contamination. l O FomM(C)372 22 3M3 h

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RERP-PCC ) Attachment 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

   @ Service ~Pustic SERVICE COMPANY OF COLORADO                           Page 1 of 1 O                                         RECORDER                                                     l l 1. Assist     Communications personnel    in noti fying remainder of l        personnel to man the PCC.

l 2. Keep a running log of all actions taken. a) These notes must be complete. The log could be used as an evaluation of the incident and could serve as a legal document. b) Any corrections by person recording the events must be initia11ed. l 3. Keep records of distribution of all contents of Emergency Kit. l 4. Log records kept by all other PCC personnel into master 109 l 5. Assure that all data sheets and work sheets are collected and given to PCC Director when PCC operations are terminated (Checklist 2). l 6. After PCC operations have been terminated: O V a) Collect PCC Director's Checklist. b) Collect Personnel Accountability and Exposure Controller Datasheets (Datasheet #1) c) Collect any Emergency Exposure Job Briefing Datasheets utilized (RERP-EXP, Datasheet #1) d) Attach Recorder Logs of PCC events and activities , e) Forward all Documents to the FSV Nuc1 E Documents Supervisor for disposition. f) Complete Forms Use Reporting Sheet. O FoRMfC1372 22 3843 i

RERP-PCC Attachment 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

  @ Service *PUBLIC SERVICE COMPANY OF COLORADO                                 Page 1 of 1 RECORDER l 1.      Assist     Communications personnel        in notifying remainder of l         personnel to man the PCC.

l 2. Keep a running log of all actions taken. a) These notes must be complete. The log could be used as an evaluation of the incident and could serve as a legal document. b) Any corrections by person recording the events must be initialled. l 3. Keep records of distribution of all contents of Emergency Kit. l 4. Log records kept by all other PCC personnel into master log. l 5. Assure that all data sheets and work sheets are collected and given to PCC Director when PCC operations are terminated (Checklist 2). l 6. After PCC operations have been terminated: a) Collect PCC Director's Checklist. b) Collect Personnel Accountability and Exposure Controller Datasheets (Datasheet #1)

• c) Collect any Emergency Exposure Job Briefing Datasheets utilized (REi?-EXP, Datasheet #1) d) Attach Recorder Logs of PCC events i

and activities _ e) Forward all Documents to the FSV Nuclear Documents Supervisor for disposition. , f) Complete Forms Use Reporting Sheet. a F08tMqC)372 22 3843 ,

!                                                                                             RERP-PCC Attachment 3 Public                    FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15
     @ service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 5 COMMUNICATIONS l 1. Notify remainder of personnel to man the PCC. (Obtain list from l Alternate Director or call individuals on the Call List that are l not marked with an asterisk (*) and all HP Technicians not l previously notified..)

l 2. Establish communications with the Technical Support Center (TSC) and verify primary and secondary communication links are operable. a) If PCC is Onsite Primary Telephone (0 pen Line) PSC Radio Secondary PSC Gai-Tronics Telephone b) If PCC is Offsite Primary Telephone Secondary PSC Radio } l 3. When instructed to do so, inform the TSC that the PCC is manned

and ready and prepared to receive personnel.

l 4.- Receive ' status of plant and emergency and assessment of l condition and inform PC" Director, who will then brief the PCC l personnel. ' l 5. With the PCC Director, fill out the STANDARD MESSAGE Form (Page 3). [ 6. Within 30 minutes of ACC activation, notify all persons living within the property boundary of the plant ' emergency. Record the

time notified and intial the CALL SHEET (Page 4). If unable to contact persons by phone, notify PCC Director. The PCC Director will dispatch personnel to inform persons. Record time Driver (s) dispatched.

FORM (C)372 22 3M3 1

RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Page 2 of 5 Service

• PUBLIC SERVICE COMPANY OF COLORADO O- i 7. If event occurs during normal working housr, confirm Visitor Center's notification of emergency. Confirm that Ft. Lupton l

Fire Station has been notified to receive Visitor Center evacuees. Record time verified or notified. I 8. Notify St. Luke's.Hosptial in accordance with Medical Emergency Plan to prepare to receive injured and contaminated person (s) if required. l 9. Notify a medical facility to prepare to receive injured person (s) if required. l 10. If necessary to relocate PCC, call facility as directed by PCC Director. Record the time of notification (See RERP PHONE LIST, l Centers / Posts Phone Numbers for telephone numbers). l 11. Inform the TSC of the departure and return of Monitoring Teams l and Emergency Teams. I 12. Maintain communications flow between PCC and the TSC. l 13. Keep records of all pertinent information for master log. O O FORMtCl372 22 3843 l

RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 SOfVICO'" PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 5 STANDARD MESSAGE FILL IN THE BLANKS OF THE FOLLOWING STATEMENT, WHICH WILL BE READ VERBATIM TO THE PERSONS ON THE FOLLOWING LIST. At (TIME) there was an incident at the Fort St. Vrain Nuclear Power Generating Plant. The precautionary protective 4 measures we are taking for the populace in the affected area are: (EVERYONE STAY INDOORS), (SELECTIVE EVACUATION OF CHILDREN AND PREGNANT WOMEN), (EVACUATION OF AFFECTED AREA TO FT. LUPTON FIRE DEPARTMENT), t O FCRMIC3372 22 3M3

 ,f

RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

  @ service *PUBLIC SERVICE COMPANY OF COLORADO                        Page 4 of 5 O-                                        CALL SHEET Persons Livine Within Property Ecundary (Numbers correspond to Map, Pg. 5)

Name Phone No. Time Notified Driver Dispatched

1. Ben Houston 785-2408

2. Randy Russell 785-6326

3. Bill Pitt 785-6274

4. Raymon Marin 785-2862

5. Vacant No Phone

6. Scott Houston 785-2358

7. Keith Russell 785-2569

8. Dave LaChance 785-6303 0

gs d FohMICl372 221643

RERP-PCC Attachment 3 Public FORT ST VRAIN NUCLEAR GENERATING STATION Issue 15 Service'" PUBLIC SERVICE COMPANY OF COLORADO Page 5 of 5 O Site Resident Notification Map

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RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 4 service" PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 5 O- COMMUNICATIONS l 1. Notify remainder of personnel to man the PCC. (Obtain list from l Alternate Director or call individuals on the Call List that are l not marked with an asterisk (*) and all HP Technicians not l previously notified..) l 2. _ Establish communications with the Technical Support Center (TSC) and verify primary and secondary communication links are operable. a) If PCC is Onsite Primary Telephone (0 pen Line) PSC Radio Secondary PSC Gai-Tronics Telephone If PCC is Offsite Q b) Primary Telephone Secondary PSC Radio l 3. When instructed.to do so, inform the TSC that the PCC is manned and ready and prepared to receive personnel. l 4.- Receive status of plant and emergency and assessment of l condition and inform PCC Director, who will then brief the PCC personnel. l 5. With the PCC Director, fill out the STANDARD MESSAGE Form (Page 3). l S. Within 30 minutes of ACC activation, notify all persons living within the property boundary of the plant emergency. Record the time notified and intial the CALL SHEET (Page 4). If unable to contact persons by phone, notify PCC Director. The PCC Director will dispatch personnel to inform persons. Record time Driver (s) dispatched. . O FORM (Cl372 22 3M3

RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

 @ Service *PUBLIC SERVICE COMPANY OF COLORADO                           Page 2 of 5 O   l 7.       If event occurs during normal working housr, confirm Visitor l          Center's notification of emergency.      Confi rm that Ft. Lupton Fire Station has been notified to receive Visitor Center evacuees. Record time verified or notified.

l 8. Notify St. Luke's.Hosptial in accordance with Medical Emergency Plan to prepare to receive injured and contaminated person (s) if required. l 9. Noti fy a medical facility to prepare to receive injured person (s) if required. l 10. If necessary to relocate PCC, call facility as directed by PCC Director. Record the time of notification (See RERP PHONE LIST, l Centers / Posts Phone Numbers for telephone numbers). l 11. Inform the TSC of the departure and return of Monitoring Teams I and Emergency Teams. l 12. Maintain communications flow between PCC and the TSC. I 13. Keep records of all pertinent information for master log. O FORM tCl372 22 3M3

RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 service

• PUBLIC SERVICE COMPANY OF COLORADO Page 3 of 5 O STANDARD MESSAGE l

l FILL IN THE BLANKS OF THE FOLLOWING STATEMENT, WHICH WILL BE READ VERBATIM TO THE PERSONS ON THE FOLLOWING LIST. At (TIME) there was an incident at the Fort St. Vrain Nuclear Power Generating Plant. The precautionary protective measures we are taking for the populace in the affected area are: (EVERYONE STAY INDOORS), (SELECTIVE EVACUATION OF CHILDREN AND PREGNANT WOMEN), (EVACUATION OF AFFECTED AREA TO FT. LUPTON O stas ose^atas"T). W O

     . tORM tCl372 22 3%3

RERP-PCC Attachment 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Service ~ pustiC SERVICE COMPANY OF COLORADO Page 4 of 5 O V CALL SHEET Persons Living Within Property Boundary (Numbers correspond to Map, Pg. 5) Name Phone No. Time Notified Driver Dispatched

1. Ben Houston 785-2408 __

2. Randy Russell 785-6326

3. Bill Pitt 785-6274

4. Raymon Marin 785-2862

5. Vacant No Phone

6. Scott Houston 785-2358

7. Keith Russell 785-2589

8. Dave LaChance 785-6303 0

e e O FORMICl372 22 3M3 i

     -                                                                                                                                                                                                           RERP-PCC Attachment 3 Public                                  FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                             Issue 15 Page 5 of 5 0 Service

• PUBLIC SERVICE COMPANY OF COLORADO O Site Resident Notification Map 4

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RERP-PCC Attachment 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 2 f3 U DECONTAMINATION

1. Survey all portions of the body.

2. Remove contaminated clothing.

3. Decontaminate the contaminated portions of the body using waterless hand cleaner (or mild soap and water if waterless hand cleaner is unavailable). Put a small amount of hand cleaner on the contaminated area (s) and lightly rub it around. Using Terry Towels or a similar soft paper towel, wipe the cleaning solution off of the victim. If mild soap is used, care should be taken to minimize the amount of rinse water, and the area should be patted dry.

4. Resurvey the area and determine the effectiveness of the decontamination effort. '- #

5. Continue this method of decontamination until the levels of contamination are reduced below allowable limits

• or untti the area is free of contamination.-

6. If contamination cannot be removed by above methods, proceed to the following steps:

a) If a person is injured and requires evacuation to a medical center, outline contaminated areas on skin. Tag person with information on radiation levels in these areas. Tags are in the Emergency Kit, b) Inform PCC Director of the need to transport injured person to St. Luke's Hospital so that he may coordinate move, c) If a person is uninjured, follow the decontamination instructions included in the Emergency Kit under Health

 ,                  Physics Procedure for Personnel Decontamination (HPP 11).

Utilize HpPs-9, 10, 11, and 21 as reference, if required.

                 < 10 DPM/100 cm 8 alpha and < 100 DPM/100 cm2 beta-gamma activity removable contamination outside radiological controlled areas.

O Fonu4cim 22-aso

RERP-PCC Attachment 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

                  $9tVICO'"                   PUBLIC SERVICE COMPANY OF COLORADO                                                                         Page 2 of 2 0             -

SAMPLE BODY TAG O- ', O

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1. Mark areas that are contaminated.

2. Number the areas.

3. Record levels of contamination in spaces given on back of card.

4

4. Secure tag to the individual.

FonMtCl372 22 3M3

RERP-PCC Attachment 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Page 1 of 2

           @ Service *PUBLIC SERVICE COMPANY OF COLORADO O

DECONTAMINATION ! 1. Survey all portions of the body.

2. Remove contaminated clothing.

3. Decontaminat'e the contaminated portions of the body using ,

, waterless hand cleaner (or mild soap and water if waterless hand cleaner is unavailable). Put a.small amount of hand cleaner on ! the contaminated area (s) and lightly rub it around. Using Terry - Towels or a similar soft paper towel, wipe the cleaning solution

off of the victim. If mild soap is used, care should be taken to minimize the amount of rinse water, and the area should be

patted dry.

4 4

4. Resurvey the area and determine the effectiveness of the

decontamination effort.

5. Continue this method of decontamination until the levels of

! contamination are reduced below allowable limits

• or until the area is free of contamination.

i If contamination cannot be removed by above methods, proceed to 6.

the'following steps

i a) If a person is injured and requires evacuation to a medical center, outline contaminated areas on skin. Tag person with information on radiation levels in these , areas. Tags are in the Emergency Kit. ! b) Inform PCC Director of the need to transport injured . ' person to St. Luke's Hospital so that he may coordinate move. c) If a person is uninjured, follow the decontamination I instructions included in the Emergency Kit under Health Physics Procedure for Personnel Decontamination (HPP-11).

  ~

j Utilize HPPs-9, 10, 11, and 21 as reference, if required. i ! * < 10 DPM/100 .cm8 alpha and < 100 DPM/100 cm8 beta gamma activity removable contamination outside radiological controlled areas. I i i ! O 4 l P0meAICl3P2 22 N el

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_. - __ - _ = . Fw *.- 4 RERP-PCC Attachment 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Page 2 of 2

          ) SerVICO*                     PUDLIC SERVICE COMPANY OF COLORADO O

SAMPLE BODY TAG i O' '.

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1. F. ark areas that are contaminated.

4

2. Number the areas.

3. Record levels of contamination in spaces given on back of card.

Q 4. Secure tag to the individual. FOAMtC1372 22 3sas

RERP-PCC Attachment 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 , Page 1 of 1

                ) service

• PUBUC SERVICE COMPANY OF COLORADO O

FORT ST. VRAIN SECURITY DEPARTMENT PERSONNEL CONTROL CENTER RESPONSE GUARD

1. One guard report's to the Personnel Control Center.

l 2. Assist in gate control, if applicable, of authorized personnel and vehicles at the Personnel Control Center for equipment or support called to assist, if necessary.

3. Keep records of all PCC security actions taken for master log.

l 4. Assist with radio communications and access authorizations with the LSO. SITE RESPONSE GUARDS 4 l 1. Check all site visitors out through Search & Identification Facility. ([) 2. Facilitate exiting of onsite personnel to PCC.

3. Assist in personnel accountability as requested.

4. Assist with personnel and vehicle ingress / egress to/from the protected and vital areas as required by the PCC Director.

NOTE: PCC Director or Emergency Coordinator coordinates access

of personnel and vehicles into.the protected area or vital areas with the LSO (i.e., names of drivers, vehicle types).

I 9 O FoRMtCl372 3 3543

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RERP-PCC Attachment 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Page 1 of 1 SerVIC9" PUBLIC SERVICE COMPANY OF COLORADO O FORT ST. VRAIN SECURITY DEPARTMENT PERSONNEL CONTROL CENTER RESPONSE GUARD

1. One guard report's to the Personnel Control Center.

      ] 2. Assist in gate control, if applicable, of authorized personnel and vehicles at the Personnel Control Center for equipment or support called to assist, if necessary.

3. Keep records of all PCC security actions taken for master log.

l 4. Assist with r:dio communications and access authorizations with the LSO. SITE RESPONSE GUARDS

1. Check all site visitors out through Search & Identification Facility.

2. Facilitate exiting of onsite personnel to PCC.

()

3. Assist in personnel accountability as requested.

4. Assist with personnel and vehicle ingress / egress to/from the protected and vital areas as required by the PCC Director.

NOTE: PCC Director or Emergency Coordinator coordinates access of personnel and vehicles into the protected area or vital areas with the LSO (i.e., names of drivers, vehicle types). 4 L C:) FORMIC 1372 22 3MB

l

                                                                       -                                              RERP-PCC                                 l Attachment 6                             l Public           FORT ST. VRAIN NUCLEAR GENERATING STATION    Issue 15                                 )

s Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 1 i

DRIVERS J i i

1. Drive vehicles and assist teams. (Health Physics, Roadblock, l l Door-to-door notification of Residents on site property.) -  ;

l

2. Obtain personnel dosimetry, instructions, maps, and l communications equipment before leaving the PCC.

l NOTE: Personal vehicles may be used to perform functions as l required if RERP-assigned vehicles are in use. O 9 O FORM tQ 372 22 3643

RERP-PCC Attachment 6

             . Public         FORT ST. VRAIN NUCLEAR GENERATING STATION          Issue 15 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 1 O

DRIVERS i

1. Drive vehicles and assist teams. (Health Physics, Roadblock, ~

l Door-to-door notification of Residents on site property.)

2. Obtain personnel dosimetry, instructions, naps, and l communications equipment before leaving the PCC.

I NOTE: Personal vehicles may be used to perform functions as l required if RERP-assigned vehicles are in use. l O l l Fonute 3n.22.ase

RERP-PCC Attachment 7 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 2 O FIRST AID *

1. Establish first aid area.

2. Administer first ' aid to injured utilizing HP assistance as needed.

3. Inform PCC Director of the need to transport injured person (s) to a medical facility in order that he may coordinate the move.

4. Assist Decontamination personnel when tagging injured personnel to be transported off-site.

5. Keep records for master log of' injured personnel, and extent of injuries.

O

• Utilize Fort St. Vrain Medical Emergency Plan as reference.

FORM (Cl372 22 3843

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RERP-PCC Attachment 7 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 l

     @ service

• PUBLIC SERVICE COMPANY OF COLORADO Page 1 of 2 O

b. FIRST AID *

1. Establish first aid area.

2. Administer first aid to injured utilizing HP assistance as needad.

3. Inform PCC Director of the need to transport injured person (s) to a medical facility in order that he may coordinate the move.

4. Assist Decontamination personnel when tagging injured personnel to be transported off-site.

5. Keep records for master log of injured personnel, and extent of injuries.

O 1 1

• Utilize Fort St. Vrain Medical Emergency Plan as reference.

( O FonMiCl372 22 3643 - I

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RERP-PCC Attachment 8 Public FORT ST VRAIN NUCLEAR GENERATING STATION Issue 15

         @ service"              PUBLIC SERVICE COMPANY OF COLORADO                 Page 1 of 1 O

l MAINTENANCE, REPAIR AND DAMAGE CONTROL l 1. Perform mechanical / electrical repair / damage control, emergency l maintenance, and temporary modifications as required. l 2. . Keep records of all actions taken. O l . i 1 1 O . FCMtCl372 22 3M3

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

RERP-PCC l Attachment 8 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15

        @ Service ~            pusuC SERVICE COMPANY OF COLORADO                Page 1 of 1

O I- MAINTENANCE, REPAIR AND DAMAGE CONTROL i

l 1. Perform mechanical / electrical repair / damage control, emergency l maintenance, and temporary modifications as required. I 2. Keep records of'all actions taken. h i O i l l i O sonu icim.22.ms

RERP-PCC Attachment 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Page I of 1

       @ SeTVICO'"                 PUBLIC SERVICE COMPANY OF COLORADO O

l HABITABILITY l 1. Perform habitability checks every 15-20 minutes. l 2. Perform surveys and take air s ples as required. (Contact l Health Physics individual if required.) l 3. Establish decontamination areas and/or radiologically controlled l areas as required. 4 i i O. i I O F0fWICI372 22 384 \

RERP-PCC Attachment 9 i Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 15 Page 1 of I O SerVICO'" PUBLIC SERVICE COMPANY OF COLORADO O l HABITABILITY l 1. Perform habitability checks every 15-20 minutes. I 2. Perform surveys and take air samples as required. (Contact l Health Physics individual if required.) l 3. Establish decontamination areas and/or radiologically controlled 1 -areas at required. O

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i O t FORMICI372 22 3M3 l

    ~                                                            --

M Public Service Company T Ocknds ) 1 16805 WCR 19 1/2, Platteville, Colorado 80651 March 22, 1985 Fort St. Vrain Unit No. 1 P-85101 Regional Administrator * @ @ 3 D M [2 R'; j Region IV ' U.S. Nuclear Regulatory Commission NAR 2 91985

                                                                                                                                      )

611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011 - Attention: Mr. Eric H. Johnson Docket No.: 50-267

Subject:

Radiological Emergency Response Plan (RERP)

Dear Mr. Johnson:

We are transmitting herein revisions to Fort St. Vrain's Station RERP Implementing Procedures. One copy of the RERP-HOME Issue 14, RERP-PAG Issue 4, RERP-PCC Issue 15, RERP-CR Issue 4, RERP-PLANT Section 10.B Issue 5 procedures is being transmitted for filing. Attachments, data sheets, checklists, and control lists should immediately follow the procedure. If difficulties or questions arise in filing this procedure, please contact Ms.Sharilyn Johnson at (303) 785-2224, extension 285. Sincerely,

                                                                                            ./

J. W. Gahm Manager, Nuclear Production JWG/dal

                                                                                                                                )

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