ML20099H747
| ML20099H747 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/06/1984 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20099H716 | List: |
| References | |
| PROC-840806, NUDOCS 8411280284 | |
| Download: ML20099H747 (636) | |
Text
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PUZLIC SERVICE COMPANY OF COLORADO BOOK 1 .
' I FORT ST. VRAIN NUCLEAR GENERATING STATION i 8/6/84 '
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RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATION
' ISSUE EFFECTIVE NO. SUBJECT NUMBER DATE RERP CR-ALERT DELETED 04-25-84 l RERP CR Control Room Procedure 2 08-06.-84 l RERP-DOSE Offsite Dose Calculations Methodology 6' 08-06-84 l
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PUBLIC SERVICE COMPANY OF COLOR ADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION O s TITLE: CONTROL ROOM ALERT, SITE EMERGENCY, GENERAL EMERGENCY PROCEDURE ISSUANCE p pjf AUTHORIZED BY I PORC EFFECTIVE REVIEW PORC 5 [5 APR 181904 DATE 4-:L5-85f DELETED WITH ISSUE 22 0;
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RERP-CR PUZLIC SERVICE COMPANY OF COLORADO Issue 2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 1 of 17 O)
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TITLE: CONTROL ROOM PROCEDURE ISSUANCE AUTHORIZED O"" M"'* A*f BY h *yY1lf/ A9ps : 0.
r PORC / EFFECTIVE REVIEW EDRc 5 8 0 AUG 2- 1984 DATE b- b- b
_ TABLE OF CONTENTS Section Description Page 1.0 Cri te ri a for Impl ementati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Procedure.................................................... 3 3.0 R e s o o n s i bi l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.0 References .................................................. 15 5.0 Referenced or Supportino Procedures.......................... 16 -
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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 NOTI FICATION 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 l Table 9 Protective Action Guides .............................. 1
.Attacnment 1 Phone Numbers for Notification.................. 1 Attachment 2 Non-Emergency Event Notification................ 1 Attachment 3 Notification of Unusual Event .................. 1' l
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FORM 372- 22 3642 l .
PUBLIC SERVICE COMPANY OF COLORADO $CR
. FORT ST. VRAIN NUCLEA.~t GENERATING STATION Page 2 of 17 O
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Attachment 4 Notification of Emergency Event ................ 1 Datasheet 1 Preliminary Assessment of Plant Conditions. . . . . . 1 Checklist 1 Emergency Coordinator / Control Room Di re ctor Cnec kl i st. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Checklist 2 Emergency Coordinator /CR Director Checklist:
Part 2 - ALERT or Higher Event................... I Work /Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e Re p o rt i n g S h e e t " . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ANYTIME. A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FGRWARD 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.
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'., PUBLIC SERVICE COMPANY OF COLORADO tj FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 17 O
V 1.0 Criteria for Implementation 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
{s) 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.
2.1.3 Notification of offsite authorities will be initiated within 15 minutes after the declaration of an emergency.
2.1.4 Checklists 1 and 2 are for use by the Emergency Coordinator and/or the CR Director. These checklists present a brief summary of actions, and are to be used for guidance purposes to assist in i verifying execution of required responses.
2.1.5 If the RERP is to be implemented for on ALERT or higher classification, PSC personnel required to man the response centers (Figure 1) are notified by telephone, if +he event occurs during non-working hours. It is the responsiblity of '.he individual response center Alternate Directors (or the first individual contac+.ed by the Director) to ensure that these notifications are made (see RERP-HOME).
Refer to RERP-PHONE LISTS for instructio,s and personnel names and telephone numbers.
FORM 372 22 3643 l
CR PUBLIC SERVICE COMPANY OF COLORADO 2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 4 of 17 O
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 cor.dition.
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- n SE, 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 oo, sequence assessments are performed as required. Radiological Assessment p will become the responsibility of the Technical
\ Support Center after full facility activation.
2.2.3 As soon as possible, inform the Emergency Coordinator 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 Emergency Coordinator or CR Director.
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 the Shift Supervisor (Emergency Coordinator).
2.3.2 Datasheet 1, " Preliminary Assessment of Plant Conditions," is provided to assist in making -
l initial assessment of plant status.
2.3.3 Provide technical support to Control Room staff, as required.
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C PUBLIC SERVICE COMPANY OF COLORADO 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 17 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: Superintendant of Operations; l Alternate: Shift Supervisor, Training), or the TSC Director.
2.4.2 As Emergency 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.
(This calculation should be performed at an average rate of approximately once every 30 minutes until relieved of this responsibility by the TSC or until
-the offsite release is terminated.)
2.4.5 For additional assistance in assessing the magnitude of the release, attempt to contact the Radiation Protection Manager (see Attachment 1, Phone Numbers for Notification.)
2.4.6 Initiate radiological protective actions for station personnel.
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 Emergency Procedure EP CLASS.
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 I
actions.
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v 2.4.7.1 Non-Emergency Events This group of operating events comprises l a series of occurrences for which, in the wake of Three Mile Island 2, there was a need to receive notification and data early-o- 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 possible but in all cases within one hour, and those which should be reported as soon as possible but in all cases within four hours. Table I summarizes those events and representative -
occurrences which would require a four-hour report and Table 2 summarizes
-- those - - that- would -- requi re a one-hour O- .
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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 I 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.
Notifications to State and Federal officials should be initiated within 15 minutes after declaration of the UNUSUAL EVENT.
Table 3 outlines initiating events and Emergency Action Levels for this class of incident. Required responses for this
~c-lassification are presented in - section- - - - - - ---
()) 2.6, NOTIFICATION OF UNUSUAL EVENT.
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FORT ST. VRAIN NUCLEAR GENERATING STATION page 8 of 17 i
(V~'y 2.4.7.3 ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY Declaration of an ; ALERT or higher ,
i Emergency Class iwill :equire implementation of the RERP and activation of emergency respcnse cenvers.
Notification of State and Federal authorities should be initiated within 15-minutes after declaration Sf the emergency. -
3 If the event is an escalation of >i previous emergency classification, followup notification to the NRC should be made immediately if an open line has not already been establisbed.
Actions to take for these events are described in section 2.7, the procedure for ALERT or higher events. If the event '
l is an escalation from a lower category, proceed directly to step 2.7.3. .
f-~s Tables 4, 5, and 6 outline initiatirg- --- - , - --
\m,/ events and Emergency Action Levels for -l the three classes of incidents:
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- Table 4 - ALERT; y
- Table 5 - S TE AREA EMERGENCY; and,
- Table 6 - GENERAL B4EDAEP;Y.
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RERP-CR PUBLIC SERVICE COMPANY OF COLORADO Issue 2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 9 of 17 a '
r 2.5 Non-Emergency Event Procedure 2.5.1 In the event of an occu'trence believed to be defined by Table 1 or 2, the Shift Supervisor or his authorized delegate may. contact one, member of 1 plant management listed in order of preference in l Attachment 1, although the responsibility of I initial event clusification is that of the Shift l Supervisor, and may not be delegated.
2.5.2 The Shift Supervisor shall inform the management contact of the event classification, or may request
, r anagement advice regarding t e classification.
2.5.3 The Shift Supervisor and the management contact shall jointly fill c' the "Non-Emergency Event Notification" Form pt schment 2) to ensure that both have the same information.
2.5.4 The management contact shall then contact edher
-management personnel listed, as appropriate.
2.5.5 The Shift Supervisor shall notify the MCC Operations center of the event as soon as possible, A and in all cases, within one hour or four hours as Cj applicable to the Non-Emergency Event category.
Notification should be made via the NRC " hot line,"
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 degradetion of plant conditions; results of evaluations or assessments of plant
- - conditions; effectiveness of response or protective measures taken; or, information related to plant behavior that is
, not understood.
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PUBLIC SERVICE COMPANY OF COLORADO (Pu FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 17 G
O 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;
- 5ection 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 I defined by Table 3, the Shift Supervisor shall assume the position of Emergency Coordinator until relieved by the Superintendent of Operations l (alternate: Shift Supervisor, Training).
2.6.2 Notify the on-duty Technical Advisor. (Refer to Attachment 1, Phone Numbers for Notificatien.)
2.6.3 Contact one member of plant management listed in order of preference in Attachment 1, Phone Numbers for Notification.
l NOTE: In the event that no management person l listed can be contacted, it is the Shift l Supervisor's responsibility to classify I the event and make notifications as l required.
2.6.4 Inform the management contact of the classification
! of the event, or if desired, request management advice regarding the classification.
h 2.6.5 Jointly complete the " NOTIFICATION OF UNUSUAL EVENT" form with the management contact to ensure that the same information is recorded by both parties.
The management contact will then contact other management personnel as required, and the Resident NRC Inspector. (See Attachment 1.)
2.6.6 Notify the State of Colorado and the NRC Operations Center of the event by following the instructions on the notification form (Attachment 3).
Notifications should be initiated within 15 minutes after declaration of the emergency category.
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Alternate backup methods of contacting the NRC are given in Attachment 1, Phone Numbers for Notification.
The on-duty Technical Advisor shoult' be kept abreast of the event status.
2.6.7 Maintain an open, continuous ccmmunication line with the NRC upon request. Report any degradation of plant conditions, results of evaluations, or response actions and results. '
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FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 17 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.
Continue to step 2.7.3 if an escalation occurs.
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RERP-CR PUBLIC SERVICE COMPANY OF COLORADO Issue 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 of 17 2.7 ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY 2.7.1 In the event of an occurrence believed to be defined as an ALERT or higher 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 l Supervisor, Training), or the TSC Director.
2.7.2 Notify the on-duty Technical Advisor if not already done. (Refer to Attachment 1, Phone Numbers for Notification.)
2.7.3 Contact one member of plant management listed in order of preference in Attachment 1, Phone Numbers for Notification.
l NOTE: In the event that no management person l can be contacted, it is the Shift l Superviser's responsibility to classify l the evera, and make notifications as I required.
2.7.4 Inform the management contact of the classification O or the eve #t. or << eesired. reaoest advice regarding the classification.
emese e=t 2.7.5 Checklist 2 is provided as guidance to verify completion of required responsibilities.
l 2.7.6 Sound the Plant Emergency Alarm, if not already l done, and announce the nature of the emergency.
All onsite personnel will report to their Personnel Accountability Stations (refer to Administrative Procedure G-5, Personnel Emergency Response) for initial accountability.
, Rapid evaluation of departmental accountability will be accomplished using plant rosters and computer printouts delivered by Security to the accountability stations.
2.7.7 In cooperation with the first management contact, l complete the " Notification of Emergency Event" Form (Attachment 4).
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PUBLIC SERVICE COMPANY OF COLORADO RERP-CR Issur 2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 14 of 17 Q
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l 2.7.8 Initiate notifications to the PSC Company Operator, Weld County Communications Center, and the NRC Operations 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). Alternate methods of contacting the NRC aro listed in Attachment 1, Phone Numbers for Notification, and are to be used in the event that the NRC " hot line" cannot be used.
l Read the information on the " Notification of l Emergency Event" Form (Attachment 2) to the above contacts. The information should also be conveyed to the Technical Advisor.
2.7.9 The PSC Operator will notify Emergency Response Center Directors, who will in turn notify their Alternates. During an off-hour event, Alternates will contact the remainder of the personnel to report to each response center.
2.7.10 Inform Visitor's Center (VC) to instruct visitors at the VC to depart to the Fort Lupton Fire Station and, depending on the wind direction, specify the D.
s,y 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 2.7.11 Notify Security of the impending arrival of emergency personnel and provide adequate clearance l for Protected Area access, where required. (If l access is required to activate TSC, refer to RERP-l Phone Lists or RERP-HOME, Attachment 9, for TSC l Director's call list for personne1' requiring l access.) ,
2.7.12 Establish communications with the TSC after l facility activation using extension 292. (See Attachment 1, Phone Numbers for Notification, for alternate numbers if required.)
l 2.7.13 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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PUBLIC SERVICE COMPANY OF COLORADO (P;CR FORT ST. VRAIN NUCLEAR GENERATING STATION page 15 of 17 2.7.14 Upon arrival at the Control Room, the CR Director shall request a briefing regarding incident status and actions currently in progress. After the briefing, he may assume responsibility for Control Room actions and direct the control of plant operationc. He shall notify the Shift Supervisor, duty Reactor Operators, and the TSC of his assumption of the role of CR Director.
2.7.15 Request supplenental Operations personnel from the TSC Director, as required, to control the emergency. (The TSC Director will relay the request to the PCC Director and thus maintain re-entry control).
2.7.16 Initiate corrective actions recommended by the TSC Director to minimize the consequences of the emergency.
2.7.17 Recovery The CR Director is responsible for recommending a termination or de-escalation of the emergency status, from a plant operational viewpoint, to the TSC Director. This recommendation shall be based
% upon the CR Director's determination that:
- Radiation levels are stable or decreasing with l time;
- Releases of radioactive materials to the environment have ceased, or are controlled l within Technical Specification Limits;
- Fires, flooding, or similar hazards no longer pose a threat to plant environment ar l personnel; and
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- Measures have been successfully instituted to repair or compensate for malfunctioning plant equipment.
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PUBLIC SERVICE COMPANY OF COLCRADO hEu FORT ST VRAIN NUCLEAR GENERATING STATION page 16 of 17 O :
3.0 Responsibilities 3.1 Emergency Coordinator The Emergency Coordinator is the on-duty Shift Supervisor.
The title of Emergency Coordinator is retained by the duty Shift Supervisor until he is relieved by either the Control Room Director or the Technical Support Center Director, upon activation of the FSV Emergency l Organization (see Figure 1). The Emergency Coordinator is responsible for:
- Initial accident classification;
- Recommending protective actions;
- Initiating emergency actions to mitigate the accident;
- Notifying offsite authorities (NOTE: Notifications are required to be initiated within 15 minutes after declaration of an emergency);
- Diagnosing accident conditions; O -
Estimatins reeieiosical exResures: ar.e
- Establishing communications with the TSC should the FSV Emergency Organization be activated.
Responsibility for the decision for offsite notification and protective action recommendation may not be delegated.
3.2 Control Room Director The Control Room (CR) Director is responsible for control of plant operations, assessing plani. operational aspects, and for implementing any recommended corrective actions.
In addition, the CR Director may request any additional operations personnel necessary through the TSC Director.
l 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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CR PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION page 17 of 17 O
GJ 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 l 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 5.6 RERP-HOME, Home Packet for Off-Shift Notifications 5.7 Station Security Plan and Procedures 5.8 RERP-PHONE LISTS 5.9 RERP-VC, Visitor's Center Procedure 5.10 Administrative Procedure G-5, Personnel Emergency Response 5.11 RERP-TEAMS, Emergency Team Formation and Direction O
FORM 372 22 3643
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RE'O-CR PUBLIC SERVICE COMPANY OF COLORADO Figure 2 FORT ST VRAIN NUCLEA9 GENERATING STATION Issue 2 Page 1 of 1 O
FIGURE 2 VISITOR'S CENTER EVACUATION ROUTES Colorado Hvv. 60 Johnstown Milliken i
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Visitor's m Fort St.
Canter 7; _
Vrain 5 e.
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Colorado Hvv. 66 ,f Platteville N N
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Colorado Hww. 52
% ort F Lwton Exit .=; ,
"* Fort Lupton
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$ Fort Lupton 3 Humicipal B1dg.
- (618 4th St.)
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CR PUBLIC SERVICE COMPANY OF COLORADO (E FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 4 A
g TABLE I NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Tyoical Indication Initiatino 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.
A tg 2. Any event or condition 2. Reactor scram:;, loop shutdowns, that results ti, 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 l sequence during surveil-
[
lance testing or reactor operation.
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V TABLE 1 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiatino Event
- 3. Any event or condition 3. a) During refueling operations, that alone could have a .01Ap 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 l condition; c) Liquid waste monitor setpoints l raised for liquid waste release l b) remove residual heat; completed. Reactor Building l sump pumps taken out of pull-to-
- l. c) control the release- lock. Setpoints not reset.
A of radioactive material; or d) Loss of HEPA filtration.
d) mitigate the con-sequences of an accident.
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. PUZLIC SERVICE COMPANY OF COLORADO (t Issue 2
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\j TABLE 1 l
NON-EMERGENCY EVENTS- FOUR-HOUR REPORT Event Tyoical Indication Initiatino 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 .
Q' 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 l treatment.
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. 1 CR PUBLIC SERVICE COMPANY OF COLORADO (E FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 ,
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~s TABLE I NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiatino 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 e chemical spill which could reach the South Platte River or St. Vrain Creek and which is therefore
- reportable to the EPA. -
I U
FORM 372 22 3bu
CR PU LIC SERVICE COMPANY OF COLORADO f,E FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 3 TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical 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 l apparent. (The action shou'ld l be approved, as a minimum, l--- - - . - - - by a senior licensed
,s l operator.)
e nv .
PORM 372 - 22 3643
CR PUBLIC SERVICE COMPANY OF COLORADO (E
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FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 3 I l
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TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical Initiating 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 q _'_ _ _ _ that is outside - - -
- - ---- -- excess of design b the design basis limits with failure of the plant; or to trip plant.
- 2. Winds experienced in *xcess of FSAR design levels.
c) In a condition c) As determined, not covered by the plant's operating and energer,cy procedures. .
- 3. Any natural phenomenon 3. a) Toxic gas release in imme-or other external diate vicinity of plant.
concition that poses an actual threat to the b) Extremely high winds or safety of the plant or severe storm preventing significantly hampers plant personnel '.am
- site personnel in the completing requisite performance of duties assignments, necessary for the safe operation of the plant.
P OR M 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO h-CR ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 3 of 3 TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Tyoical 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 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 gas releases, or .,,- -in excess of 10 CFR 20- -
O radioactive releases. Appendix B, Table I.
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1 FORM 372 22 3643
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FORT ST VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 4 I
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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 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 s station personnel. ,, ---- -- --
J Indication of minor
- 3. 3. a) 25% increase in fuel damage detected circulating activity in primary coolant. from previous equilibrium cond-itions at the same power level.
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 radiologia1 or toxic materials.
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P OR M 3 M
- 22 + M43
RE C PUBLIC SERVICE COMPANY OF COLORADO , 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 4 O
V TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 5. Abnorrni 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, tespectively, accordance with to the extent that Technical Speci- shutdown per S7.ation 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.
O ' 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; 9
b) Onsite explosions or near site
( explosions that may be subject to public concern because of possible detrimental effect on the plant; or, O
PORM 372 22 3643
-C PUl'LIC SERVICE COMPANY OF COLORADO
(,E e FORT ST, VRAIN NUCLEAR GENERATING STATION lssue 2 f Page 3 of 4
('M V
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 niaterial 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.
(Probably cannot be
[J- '- 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-LCO 4.5.1
- 2) Steam / Water Dump System - LCO 4.3.3 O
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RE CR PUZLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 4 of 4 i Q
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l TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 4) PCRV penetration secondary closures -
- 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 Sumtrary indication of non-monitors not functional. operational alarm or indication on:
a) RT 7324-1, 2 and-RT 4803; or l b) RT 73437-1, 2, RT 4802, l a_rtd RT 7325-1; or c) RT 73437-2 and RT 4801; or-d) RT 6212 d RT 6213.
NOTE: Use ELCO 8.1.1 Technical Specification Limits as basis.
l 1
_ .' F o R M 3 72 ' 22 3643 - ---'--
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... . -._,,..,.-n. -- . - . . - - . . . . - - - - - - - - - - - .
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RE CR PUT.LIC SERVICE ' COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 4 TABLE 4 ALERf 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 Ky OCB trips p) and RAT undervoltage/ loss -
C F 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, an_d area monitor accompanied by area and or stack monitor alarm stack radiation monitor alarms).
.which indicates severc 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 372 22 3643
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d TABLE 4 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 l undervoltage, 480V bus under-voltage, and Diesel Trouble alarms.
- 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 suberitical 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 l correspondingly longer for lower power levels. (See LCO 4.2.18 l for time available to initiate depressurization as a function of l reactor power level.)
O POMM 3M . 23 3843
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-C PUBLIC SERVICE COMPANY OF COLORADO y,E 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 i Page 3 of 4 l O
V l 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 pC1/cc c) RT 7325-1 indicating 27.0 x 10 yC1/cc d) RT 7325-2 indicating
~
27.0 x 10 ' pC1/cc e) RT 73437-1 indicating 27.0 x 10 pCi/cc I-131.
f) RT 4802 indicating 2 7.0 x 10
- uC1/cc I-131.
g) RT 4803 indicating
~
2 2.5 x 10 2 vC1/cc Utilize reading from above instruments and calculate dose rate per procedures l 12. Ongoing security 12. a) As observed or reported.
l compromise.
- 13. Severe natural phenom- 13. a) Seismic recorder operate enon being experienced (2.05g) or projected, such as:
a) earthquake exceedinj b) As Reported Operating Basis Earthquake levels; c) As Reported b) flood near design level; or, c) tornado striking f acility.
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O FORM 372 22 3843 I
RE -CR PUBLIC SERVICE COMPANY OF COLORADO , ,4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2
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NJ' 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 Q ronm anticipated or required, with control of Shift Supervisor -
shutdown systems established from local statiens.
(Control room integrity breached.)
- 16. All alarms 16. Control room observation.
(annunciators) lost for more than 15 minutes and reactor is not siiutdown; or, plant transient experienced
.hile w all alarms lost.
(Parameterindication still functional.)
- 17. Other plant conditions 17. As deemed necessary by warranting precautionary Shift Supervisor, activation of the PCC, TSC, and FCP.
O P OR M 372 22 364*
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RE CR PUBLIC SERVICE COMPANY OF COLORADO , ,
FORT ST. VRAIN NUCLEAR GENERATING STATION lsSue 2 Page 1 of 4 O
v 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% power.
(Lower power levels preceeding LOFC extends time available before core damage is incurred.
l 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.
- 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 Diese)
Fail to St .t.
- 5. Loss of functions needed 5. Inability to insert for plant hot shutdown. sufficient control rods ,
accompantei by failure of emergency reserve shetdovn 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 radu a monitor of radioactivity to plant alarms, environs.
PORM 372 22 3643 I
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PUBLIC SERVICE COMPANY OF COLORADO T FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 4 n
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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 beyor.d capability of station staff.
- 8. a) Effluent monitors 8. Stack monitor alarm with '
detect levels corresponding stack corresponding to concentration indications g)
( greater than 50 mrem / on:
he,or 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 ' 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 8 pC1/cc b) These dose rates are mixed noble gasses, projected based on other plant para. meters or are measured in t'.e environs.
- 9. Imminent loss of p?ysical 9. Situation evident.
control of the plar.t due to security breach.
(Response detailed in Station Security Plan.)
O POftM 372 22 3643
R CR PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Issu 2 Page 3 of 4 n
s TABLE 5 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 0.067g vertical.
b) flood greater than b) As reported or observed.
design levels c) winds in excess of c) Average wind velocity design 1evels greater than 90 mph or 10-second gusts --
bm) 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 j shutdown' equipment; l
c) entry of toxic / flammable gas into vital areas.
- 12. Reactor building louvers 12. a) Louvers Open Alarm l open due to building (3 inches water) being overpressurized by primary coolant, b) Reactor building (DBA #2) radiation alarms.
O -
FORM 372 22 3643
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RER CR
. PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 4 of 4 )
3 (G
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. .
FCP/EOCs, monitoring teams, and precautionary public notification.
O
(
O 1 1
1 Ponu 272 22 3642 l T-- - - - - - - ,.---__m _ . , _ _ _ , , _ _ , _ , , _ , _ _, _ _ _
RE CR
/ PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 j Page 1 of 1 I
TABLE 6 l l
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 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 FORM 372 22 - 3643
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i JAplE 7 INITIAilNG EVENT CROSS-REFERtiff4 NOTirtCATION OF SITE AREA C[NERAL UMUSUAL EVENT ALERT EMERGENCY f."ERGENCY j storms P erriuent monitor problems all alarms lost for 15 i
I (ELCO 8.1.1) minutes and reactor not shutdown or transient experienced while alarms
- out l
electrical & 1. loss or orrsite inability to restore power coupled with onsite AC loss or vital AC power up to 30
, minutes J 2. loss or vital DC up l
to 30 minutes
- S/C ; gross failure or RH non-Isolatable leak 1 section coupled with through MH section l orrsite power loss
'i plant r 1. loss or engineered 1. primary coolant 1. loss of primary coolant safety resture pressure decay c i rcula t ion > 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> j 2. abnormal coolant / core coupled with (more time for lower i
temps. requiring shut- stack storms power leve l s )
l down becauso or Tech. 2. loss of forced 2. loss or functions Specs. primary coolant needed for hot circulation 2 to 5 shutdown hours 3. PCRV reller valve 3
- 3. control rod Inser- doesn't reseat tion problems 4. DBA #2
- 4. seconda ry coolant- 5. CR evacuation. 8nability I residual heat removal to contros st!ttsin 15 min.
system problems
- 5. evacuation or CR/
t shutdown from I-49 I
miscellaneous : serious radiological any other event any other event any other plant i exposure to personnel / warranting manning warranting manning of condition that
- transportation or con- or response centers response centers and allows possible l taminated person to precautionary public release or large j l orrsite racilities notification amounts or r/a i
O O O RERP-CR imbio 8 lesue 2 Page 1 of 1
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l
- TABLE _8 iMLRGlitCY C08801 TION CRQ113 ([LRLJQ[
NOTlrICATION StTE AREA CENIRAL U88 USUAL EVENT ALERT EHERCEllCY EM(RCINCY events are in d have potential for have potential for involve actual or leivolve actuni or progress or have degraustion or plant substatial degra- likely rallute(s) Imml esosit
- i occurred that level or safety dation of plant level or safety or plant protective equipment substantial core deg rada t ion l
i exists l a'
radioactive ? none requiring orr small fractions < EPA PACS except may exceed EPA PACS l site monitoring or EPA PACS near site boundary releases notification Sta te/loca l/ redera l Sta te/loca l/redera l Sta te/loca l/redera l Sta te/ loca l/rede ra l f
I emergency responseenot asnned manned i manned manned centers rad la t ion r not dispatched coold be dispatched dispatched dispatched monitoring teams
! protective actions +none none conside red initiated onsite evacuation-eeio rio could occur could occur j status updates ? none ir applicable provided p rovided i to orrsite i authorities 1
State monitoring e t dispatched not dispatched dispatched dispatched teams j
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O O O RERP-CR
(
Table 9
, Issue 2 Page I of 1 TABLE 9 Pft0TECTIVE ACTIOll CUIDL3 Recommended protective actions to reduce whole body and thyroid dose from exposure to a gaseous plume
{ 9enerei Pu(1. LLC
! Projected Dose (Rem)
.to the Population Regggjggg[gd Actions f el Comments
- Whole Body less than 1 No planned protective actions Previously recommended
( b ) .* State may issue an protective actions may j thyrold less than 5 advisory to seek shelter and be reconsidered or await further Instructions. terminated.
1 Monitor environmental i radiation levels.
j .
} Whole Body 1 to 5 seek shelter as a minimum. Ir constraints exist,
, Consider evacuation. Evacuate spclat consideration
' Thyroid 5 to 25 unless constraints make snould be given for 1 It lep rac t ica l . evacuation or children j Munitor envi rotusental and pregnant women.
- radletion levels. Control j eccess.
Whole body 5 and above conduct mandatory evacuation, seeking shelter would be l
Mnnitor environmental an alternative ir j Thyroid 25 and above radiation levels evacuation were not 2
and adjust area for immediately possible.
1 mandstory evacuation based on
! these levels. Control access.
1 (a) These actions a re recommended limits for planning purposes. Protective action decisions at the time of the incident must take existing conditions into consideration (refer to RERP laplementing p rocedure RERP-PAC, "P ro tec t ive Action Culdeline Recommendetions").
1 (b) At the time or the incident, orricials may implement low-Impact protective actions In keeping with the principle or l
maintaining radiation exposures as low as reasonably achievable.
4 I
i i
i
PUZLIC SERVICE COMPANY OF COLOR ADO RERP-CR FORT ST. VRAIN NUOLEAR GENERATING STATION Page 1 of 1 O
PHONE NUMBERS FOR NOTIFICATIONS Plant Manacement Contacts Page Plant Home Phone Ext. Phone l W. J. Franek, Supt. of Operations 890-0558 218 9-532-3489 i D. P. Hood, Alternate N/A 347 78-776-1843 l L. M. McBride, Station Manager 890-0698 201 8-303-442-3829 1 C. H. Fuller, Tech./ Admin.
I Services Manager 890-0810 202 8-303-663-2363 l D. W. Warembourg, Manager l Nuclear Production 890-0699 200 8-303-833-4092 I F. J. Borst, Radiation i . Protection Manager 890-1775 203 8-303-663-1230 l 0. R. Lee, Vice Pres., Prod. N/A 797-4122, l 8-571-7305 8-303-659-1180 Resident NRC Insoector l Page Plant Home l Office Phone Ext. Phone i G. L. Plumlee 785-2282 890-2225 490 776-9541 O T canic 1 ^ovisor-Page Plant Home Phone Ext. Phone 1 J. Sills 890-2223 265 221-5059 I J. Eggebraten 890-2220 285 651-1523 A. Reed 890-1942 325 772-5312 Alternate Numbers for NRC Operations Center Notification NOTE: The preferred method for notification is the " hot line."
These numbers, listed in order of preference, should only be used if the " hot line" 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) l Technical suoport Center Preferred extension: 292 O
U Alternate extensions: 291 or 294 r
PORM 372 22 3843
PUBLIC SERVICE COMPANY OF COLORADD [gR 2
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 4 O
v 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) l "Four-Hour Report")(circle one).
- 4. Description of Event:
Reactor power prior to event:
) Loop Shutdown? Scram?
Initiating signal (s):
Was event result of an LCO Action Statement?
Other pertinent information:
- 5. Actions Taken:
G V
i r om u 372 22. as43 l
PUZLIC SERVICE COMPANY OF COLORAD3 $,P 2
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 4 c/
- 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:
- 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:
- 10. Contacts made by Shift Supervisor:
a) Name of NRC contact:
O'
'- b) Time of NRC contact:
P OR M 372 - 22 2443
PUBLIC SERVICE COMPANY OF COLORADO [,P 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 3 of 4 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.
W O V
O FORM 372 23 3643
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PUZLIC SERVICE COMPANY OF COLORADS hRP, 2 i FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 l Page 4 of 4
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I I I I I I l CALL 1 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 l l I I I I i 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 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 I I I I I I I I l l I I I l l l l l l l
'O k> I I I I I I I I I I I I I I i i l I i l i l l 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 l l l l l l l l l l I I I I I I l l 1 l I l l l l l l l l l l l 1 I I I I I I I I I I I i 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 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 l .
1 I I I I l l l I I I I O
PORM 372 22 3443
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PUBLIC SERVICE COMPANY OF COLCRAD9 cf 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 3 O)
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 Unusual Hazards (circle one)
() Aircraft Explosion Toxic Material v
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.) l O
v Pomu 372 22 34*3
PUBLIC SERVICE COMPANY OF CSLORADO [fa h 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 3 p
Q ,l
- 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 witn 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:
O k- / "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 this ATTACHMENT).
9 0RM 313
- 23 34L3
R PUBLIC SERVICE COMPANY OF COLORADO kga 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 3 of 3 I) v
- 3. RECORD the following information:
Name of State EOC contact Date/ Time Name of Governor's Office / Mansion Contact Date/ Time Call back verification from State EOC, Date/ Time Call back verification from Governor's Office / Mansion Date/ Time 1 l l Contact with NRC Operations Center (Hot Line or 202-951-0550)l l l (Alternate means of notification are given in Attachment 1.)
-~s 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 I of this Attachement).
- 3. RECORD the following information:
Name of ,NRC Contact Date/ Time O
PORM 372 22 M43
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R PUZLIC SERVICE COMPANY OF COLSRADO (ga 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 5 O
'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 I l Required Information l l l
- 1. This is (Name) , Shift Supervisor at the Fort St.
Vrain Station.
- 2. At (Time) we experienced an (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident.
- 3. a) There is @ , repeat NO, radioactive release taking place, and no speciaT protective actions are recommended at this time.
0B l b) A small release LS taking place, but at this time l @ protective actions are recommended and are not l anticipated to be.
I E l c) A radioactive release M, repeat LS, taking place, and we recommend that people in areas remain indoors with windows and doors closed.
Q.
l d) A radioactive release M , repeat LS, 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 PORM 373 32 3643
PUBLIC SERVICE COMPANY OF COLORADD $a h 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 5 (3
V l l l 1 l l l SUPP'_EMENTAL INFORMATION l l l l l NOTE: This information is to be supplied to the NRC and the Colorado l Department of Health when requested. The radiological data j can be determined as specified in RERP-DOSE.
l 1. Date and Time of Incident l 2. Class of emergency (ALERT)(SITE AREA EMERGENCY) l (GENERAL EMERGENCY) l l 3. Type of release (airborne, waterborne, surface) l 4. Estimated duration of release (Hours) l S. Current release rate:
l l Noble Gas C1/sec; Iodine C1/sec l G. Estimated curies released:
( l Noble Gas Ci; Iodine C1 l 7. Wind Velocity MPH, from degrees.
l to degrees, Air Temp 'F l 8. Stability Category . Form of Precip.
l 9. Oose ratt at EAB: WB rem /hr; Thyroid rem /hr l .' Miles: VB rem /hr; Thyroid rem /hr l 5 Miles: kB rem /hr; Thyroid rem /hr l 10. Projected dose at EAB: WB rem; Thyroid rem ,
l 2 Miles: WB rem; Thyroid rem l 5 Miles: WB rem; Thyroid rem l 11. Estimated accumulated doser at EAB:
l O
G l
PORM 372 22 3443
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PUBLIC SERVICE COMPANY OF COLORADO A a 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 3 of 5 p
l 12. Areas expected to be impacted by release l
I l 13. Estimate of any surface radioactive contamination l
l 14. On-site response actions under way I
l 15. Recommended Protective Action based on the projected riose at l the EAB (Read appropriate Protective Actions) l Projected Dose Recommended l (rem) Protective Action l Whole Body <1 No planned protective actions. State l Thyroid <5 may issue advisory to seek shelter i and await instructions. Monitor l radiation levels.
l Whole Body I to 5 Take shelter and consider selective l Thyroid 5 to 25 evacuation. Monitor radiation levels.
l Establish Controlled Area and limit l access.
l Whole Body 5 and above Conduct mandatory evacuation. Monitor l Thyroid 25 and above radiation levels and adjust area for l mandatory evacuation based on these l levels Control Access.
l 16. Prognosis for worsening of event l 17. Date and time of report l 18. Name of person providing report l 19. Telephone number for call back 0;
v P O m W 372 22 3643
i PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION
[4 Issue g I Page 4 of 5 i
,/
l 20. Description of any requested off-site assistance i
I I
I I
I B. The Emergency Coordinator will make notifications in sequence as follows:
I I I I PSC Company Operator 8-571-4591 I I or 8-571-0111 l l l
_n 1. INSTRUOT the Operator to initiate the " Fort St. Vrain
()
Radiological Emergency Call List."
- 2. READ verbatim the information recorded in Part A (Page 1 of this attachment).
- 3. RECORD the following information:
Time PSC Operator Notified Time Operator Callback Received 1 -
1 I 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 l
l 0 -
1 POmW 372 22 3643 l
R PUZLIC SERVICE COMPANY OF COLORADO [g,P g FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 5 of 5
(-
v i l I NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l I I (Alternate means of notification are giver in Attachment 1).
- 1. READ Items 1) 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 PORM 372 22 3643 1
l
PUBLIC SERVICE COMPANY GF COLORADO Dat et 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 2 g
L; PRELIMINARY ASSESSMENT OF PLANT CONDITIONS TECHNICAL ADVISOR
- 1. Brief description of event
- 2. Date/ Time of event
- 3. Cate/ 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.
OF 69-0-0 DF 76-0-0 Gq OF 77-1-0 Post Trip Review Helium Inventory PRIMARY SYSTEM
- 5. Current Reactor Power
- 6. Rod Runback 0: cur (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 A B To: Storage, PCRV, or Ventilation
- 10. Is heat removal capability adequate at this time (Y/N) )
PORM 372 22 3443
ERP PUZLIC SERVICE COMPANY OF COLORADO hat, 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 2 O
SECONDARY SYSTEM
- 11. Loops Operating I II !
l
Firewater
- 13. Status of Aux. Boilers Remarks Time Description 1
O PORM 372 22 3643
RE PUZLIC SERVICE COMPANY OF CELORADO h k st I FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page I of I q
%j EMER3ENCY C00RDINATOR'S CHECKLIST I. 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. .
- 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 P
1 FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-CR FORT ST. VRAIN NUOLEAR GENERATING STATION ,
Page 1 of 2 EMERGENCY COORDINATOR /CR DIRECTOR CHECKLIST, PART 2:
ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY
- 1. Sound Plant Emergency Alarm if ALERT or higher and announce nature of the emergency.
- 2. Seiect the PCC location based upon consideration of the dominant wind direction:
1 1) Training Center (Primary)
- 2) Engineering /QA Office Complex l (Alternate) l NOTE: If both onsite locations are l uninhabitable, - alternate O i l
offsite iocation are. in the order of preference, the l Johnstown County Shops, l Platteville Volunteer Fire l Department, and Longmont PSCo l Service Center.
- 3. Complete Notifications form (Attachment 4).
- 4. Make notifications.
PSC Operator Weld County Corraunications Center NRC Operations Cente-
=
PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION
[st2 Issue 2 Page 2 of 2 O
- 5. 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
- 6. Notify Security to provide clearance for protected area access, if required.
- 7. Receive initial personnel accountability reports.
- 8. Dispatch Fire Brigade and/or Search and Rescue teams as necessary.
O 9. Establish communications with TSC (dial 292) and notify of PCC location.
I PORM 372 22 3443
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION RE g,3 Issue 2 k
Page 1 of 3 (v
Work /Datasheet/ Checklist Control List NOTE: 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 C Checklist No.
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 ,
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO 3k FOriT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 3 O
V 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 Datasheet Numbers Copies Used Checklist Numbers' Copies 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 Sheet' for the affected procedure in the affected book.
PORM 372 22 3643 1
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. . - _ - - - - _ , _ . . _ _ . _ _ . _ _ - - _ . . . - . . _. e _- - _.--
R PUBLIC SERVICE COMPANY OF COLORADO g, FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 3 of 3 FORMS USE REPORTING SHEET (Continued)
COMMENTS !
Reported By:
Date:
Nuclear Documents Specialist
- Date Received 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 :opies.
O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE Issue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page I of 9 m ,
I i '
\_./
TITLE: OFFSITE DOSE CALCULATION METHODOLOGY l
ISSUANCE AUTHORIZED BY f% . u ,,, w ,. ] e L Y %d
~
E 've REV Ew PORc 5 8 0'AUG 2- 1984 /7E o Nb Sections Description Pace General ........................................................... 3 1.0 Criteria.....................................................3 2.0 Procedure.....................................................3 2.1 Monitored Release Calculations ......................... 4 2.1.1 Monitored Release - Manual....................... 4 2.1.2 Monitored Release - TI-59 Program ............... 4 n.
2.1.3 Monitored Release - Data Legger Program ......... 5 2.1.4 Monitored Release - IBM 370 Program ............. 6 2.2 Unmonitored Release Calculations ....................... 7 l 2.2.1 Unmonitored Release - Manual..................... 7 l 2.2.2 Unmonitored Release - TI-59 Program ............. 7 l 2.2.3 Unmonitored Release - Data Logger Program ....... 7 l 2.2.4 Unmoni.tored Release - IBM 370 Program ........... 7 3 . 0' Responsibilities.............................................7 4.0 References ................................................... 8 5.0 Referenced or Supporting Procedures........................... 9 Figure 1 Local Determination of Stack Concentration ............. 1 Figure 2 Site Sector Map......................................... 1 Table 1 Atmospheric Stability Categories ....................... 1 n
Table 2 Potentially Affected Sectors ........................... 1 (v)
FORM 372 22 3H2
PUZLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 2 of 9 d .
l Table 3 Dose Conversion Factors................................. 1 Attachment 1 Dispersion Factor 5............................... 1 Worksheet 1 Monitored Release Calculations (Manual) ......... 1 1
Worksheet 2 Monitored Release Calculations (TI-59)............I )
Worksbeet 3 Unmonitored Release Calculations (Manual) ....... 1 Worksheet 4 Unmonitored Release Calculations (TI-59)......... 1 Datasheet 1- Data Logger (or IBM) Monitored Release. . . . . . . . . . . 1 -
Datasheet 2 Data Legger (or IBM) Unmonitored Release. . . . . . . . .1 Datasheet 3 Status Board Update Sheet ....................... 1 Checklist 1 Data Logger Monitored Release ................... 1 Work /Datasheet/Checkl i st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Forms Use Reporting Sheet *............. ........................... 2 O -
ANYTIME A WORKSHEET. DATASHEET.ORCHECxLISTHASBEisWRITTEN' ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l 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.
~
o l
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PORM 372 22 3643 e _ _ _ _ . . . _ . _ . . . _ _ . . _ _ . . . _ _ . _ _ _____ _ _ ____
RERP-DOSE PUZLIC SERVICE COMPANY OF COLORADO Issu2 6 Page 3 of 9 FORT ST. VRAIN NUCLEAR GENERATING STATION General This procedure provides an overview of the available methodology for offsite dose calculations during an emergency at Fort St. Vrain.
The methodology available provides a large degree of flexibility in performing offsite dose calculations, and allows the user to select whatever method he feels the most proficient at using. For both the monitored and unmonitored cases, the options provided are essentially identical in their methodology employed.
This procedure is primarily intended for use by radiological assessment personnel at the Technical Support Center (TSC) and/or ,
~
l Forward Command Post (FCP) during the course of an emergency, and for l Control Room personnel for initial dose calculations.
1.0 Criteria l This procedure provides direction to CR, TSC and/or FCP personnel in the performance of offsite dose calculations under emergency conditions. This procedure does not govern calculations for routine release of radiological effluents as provided by station Technical Specifications. This procedu.e j 'may be implemented in the event of a radiological release to ti.e extent warran' ting activation of the FSV Radiological Emergency Response Plan (RERP).
O. 2.0 Procedure Emergency offsite dose calculations may be required for cases where the radiological effluents are being monitored by the exhaust ventilation monitors, or for cases where reactor building louvers have opened and primary coolant is escaping, unmonitored. The first four (4) parts of this procedure are related to calculational options for a monitored release. The last four (4) parts discuss calculational options for an unmonitored release.
For the case of unmonitored release, it is appropriate to
. utilize unmonitored release assumptions at the outset, and revert to monitored release calculations after the building louvers have closed.
All parts of this procedure are centered around the necessary worksheets and datasheets required for their use. Descriptive text is supplied to provide any general information required for adequate performance of that set of calculations. Worksheets -
are constructed in such a manner that they do not require a step-by-step reference to this procedure for use.
l l
As all of these calculations, whether computer assisted or not, are extremely time consuming, it is imperative that the -
individual utilize as much additional assistance from available personnel as they feel necessary. At the TSC, Computer Support
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P OR M 372 22 - 3843
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PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Issu2 6 Page 4 of 9 personnel have been adequately trained to provide assistance in both records keeping and data entry if required. Completion of the datasheets and checklists is optional, but should be performed as time permits.
2.1 Monitored Release Calculations Monitored release offsite dose calculations are performed utilizing the indications of plant ventilation exhaust monitors for noble gases and radiciodines. The primary monitors of interest are RT-7324, 1, and 2, and RT-73437, 1. The RT-7324 monitors are for noble gases, and RT-73437, 1 is for- radiciodines. Radiciodine monitors, RT-7325, I and 2 may be utilized if required, but could' provide overly conservative results in the presence of noble gases.
l
- In the event that the primary monitors are inoperative due l to power loss, etc., the emergency stack monitors RT-4802 l and 4803, powered by the ACM diesel, may be utilized per l HPP-13 to determine the activity concentration of Iodine l and Noble gas, respectively.
As a back up in the event that stack noble gas monitors
- f-- are offscale or inoperative, there is a manual method of -
\ determination of stack noble gas concentration. This method is described in detail in HPP-56. Figure 1 of this procedure provides the necessary conversion from a manual portable radiation detector reading to a stack noble gas concentration (uCi/cc). The criterion for determining the need for a manual stack concentration is whenever one, or both, of the stack noble gas monitors (RT-7324, 1, and 2) are offscale, or inoperative, during a radiological emergency. These readings should be obtained as frequenty as possible, so as to verify the noble gas release rates.
Offsite dose calculations should be performed at least-l every thirty minutes during a radiological emergency.
l
- These calculations should be utilized in determining the recommended protective actions (see RERP-PAG) and for keeping the Corporate Emergency Director (CED) and Technical Support Center Director appraised of radiological conditions.
l Dose conversion factors used in each of the methods l described are given in Table 3.
HM FORM 3M 3bG
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PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE l FORT ST. VRAIN NUCLEAR GENERATING STATION
- 5 of 9 v
2.1.1 Monitored Release - Manual This method is provided for situations where use of computer or calculator programs is not possible or to provide a manual verification of dose calculation results.
This calculation is easiest when carried out with the aid of a pocket calculator.
The procedure for this calculation is itemized on Worksheet 1 of this procedure.
. 2.1.2 Monitored Release - TI-59 Program The method is, quite simply, the monitored release
- manual method performed with the use of a TI-59 program recorded on magnetic cards.
The procedure for this calculation is itemized on Worksheet 2 of this procedure.
2.1.3 Monitored Release - Data Logger Program O
V For personnel locawd at the Technical Support Center or in the Control Room, this is the most desireable way of performing offsite dose calculations. This system allows a more precise ongoing tabulation of dose projection results for a series of release calcuations, as well as finger-tip access to key plant parameters required for these calculations.
For record keeping purposes, it is desireable to print all screens utilized in performance of this calculation. In the Control Room, this can be done l with the " PRINT CRT" key. In the TSC, a screen may be transferred to the Tektronix screen and then
. printed as follows. Fi rst, on the Tektronix keyboard press the " SCREEN RESET" button in the upper lefthand corner. Second, on the 2-on-1, press the " COPY CRT" key. This action begins transfer of the screen image to the Tektronix screen. After transfer of the screen is completed (about 20 seconds on average) the screen may oe copied to paper by pressing either the white " COPY"
, button on the Tektronix printer, or by pressing the I
" COPY" button in the upper right hand corner of the l Tektronix keyboard. (If the line printer is connected to the TSC terminal, screen copy is s performed by pressing the " PRINT CRT" button on the l
j- l 2-on-1 console.)
PORM 372- 22 3843 l
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l PUILIC SERVICE COMPANY OF COLOR ADO RERP-DOSE !
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 l Page 6 of 9 Checklist 1 is available in this procedure to assist in the proper sec;uence of actions for printing the required screens of this calculation.
Datasheet 1 is provided for use in gathering and summarizing the data utilized in performance of this computer assisted calculation (as well as for the IBM program).
This program is accessible by pressing the upper
" DEMAND FUNCTION OVERVIEW" button on the 2-on-1 to get the Demand Function menu (or by accessing
" DISPLAY" 941). On the menu, locate the cursor in the DF-41-0-0 box, and press "XMIT CURSOR". The instructions for performing the calculations are printed on each screen when brought up, in order.
It is advisable that an inexperienced user follow the printed instructions carefully and slowly.
During a long release where the release ending time is not precisely known or estimated, perform two calculations utilizing Program Option #2. First, make a 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> dose projection (substitute projected release duration where known) and then make a l thirty minute " puff" release projection using VQ Program ootien #2. The " puff" projection allows tabulation of doses received. The puff projections should be for discrete time intervals. Simply stated, this means that a " puff's" starting time should be the previous " puff's" ending time. These calculations may then be totaled (Step 8) utilizing ootion 3 and terunning DF-41-0-0.
2.I.4 Monitored Release - IBM 370 Program This program is set up to operate from any of the IBM computer terminals available throughout the company. It provides very detailed output and serves as an excellent data base for post-accident l , dose analysis. Its principal drawback is the job turnaround time on the company computer, and the availability of the ROSCOE programming utility.
Additionally, users must have available a ROSCOE sign-on.
The first step of this calculation is to gather data just as was done in 2.1.3 using datasheet 1.
i Data entry for this program is done by utilizing an l interactive ROSPROC developed specifically for this purpose. The user should log onto ROSCOE and then issue the following command:
O EXEC tP. wSE-ponu 373 22- 3643
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PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE 80 FORT ST. VRAIN NUCLEAR GENERATING STATION g 7
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v Issuing this command will invoke a data deck structuring program allowing instream data deck. i structuring and job submission for as many " puffs" and projections as desired. When the user is completed executing puff data, he should route his output to hardcopy by entering "END", while in output runout, and exiting the ROSPROC.
This method is setup so that the long terin l projection and puff accumulation calculations are done simultaneously. Entry of a projected duration l of release is done for each 30 minute update. This value is then added to the time elapsed from start of the update to current.
Values calculated in this manner (first set of output) represent projections from the start of the puff at the current release rate, under current meteorological conditions.
Calculations from this program will result in three pages of output for each set of data entered and a final summary output. The first page summarizes program inputs and the sigma y and sigma z calculations for dispersion. The second page O- summarizes dose rates and integrated doses for both l the projected release and for the 30 minute puff.
The third page summarizes dispersion factors, meteorology, release rates, and accumulated doses to that point of the release.
2.2 Unmonitored Release Calculations These calculation methods are provided for use in the extremely unlikely event that primary coolant leakage is so rapid and extreme that it causes the reactor building louvers to open. In'this event, design assumptions from the FSAR indicate that no more than 1/3 of the primary
.- coolant could escape unmonitored. Therefore, these calculations are performed once to estimate the projected dose commitment as a result of such a release. Once the louvers have reseated, all calculations will be able to be performed utilizing the stack monitors as described in Section 2.1.
2.2.1 Unmonitored Release - Manual Worksheet 3 itemizes the necessary steps for the performance of this calculation.
l FORM 372 22 3843
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION 5 e6 8 of 9 O
2.2.2 Unmonitored Release - TI-59 Program As was the case for the monitored release TI-59 program, this is a magnetic card recorded program ,
that mimics the manual calculation method. l Worksheet 4 itemizes the necessary steps for the performance of this calculation.
2.2.3 Unmonitored Release - Data Logger Program The data logger is the most convenient method for l performance of unmonitored release calculations.
Datasheet 2 is provided to record program inputs.
As was the case for monitored release calculations, be certain to print all screens of input and output snat were utilized in performing the calculation.
2.2.4 Unmonitored Release - IBM 370 Program (Program In Development) 2.3 Protective Action Recommendations Protective action recommendations are, in large part, p
V based .upon the ca-1culations contained herein.
Recommendations of offsite protective actions should be based upon the criteria set forth in RERP-PAG.
3.0 Responsiblities
~
l 3.1 Control Room Personnel l Perform initial radiological assessemnt as directed by the l Emergency Coordinator (Shift Supervisor). Utilize l Worksheets 1 or 3 for manual calculations, or Datasheets 1 l or 2 and Checklist 1 for data logger use. Report results I to Emergency Coordinator. Perform assessment as required l (or at least every 30 minutes) until the TSC is activated.
l ' 3.2 Radiological Assessment Coordinator l Obtain 30 minute updates of offsite dose calculations from Radiological Assessment personnel at the Technical Support Center. Use this to complete the status board update sheet, datasheet 3. Verify any calculations in question via manual or TI-59 calculations.
FCRM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE 15 sue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION ,
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V l 3.3 Technical Support Center Radiological Assessment l Perform calculations at an average rate of every 30 minutes during a radiological emergency, and transmit results to both the TSC Director and the Radiological Assessment Coordinator. Save all data sheets, checklists, worksheets and program outputs for transmission to Record Storage at the conclusion of the emergency.
l 3.4 Computer Support Personnel (TSC)
Assist the TSC Radiological Assessment individual on an as-needed basis, when available.
4.0 References -
4.1 NRC Regulatory Guide 1.145 4.2 Slade, Meteorology and Atomic Energy, 1968 5.0 Referenced or Succorting Procedures _
5.1 HPP-56, Manual Release Rate Determination r~' 5.2 RERP-PAG, Protective Action Guideline Recommendations (To
\ be developed).
5.3 RERP-ORG, FSV Emergency Organization and Responsibilities l 5.4 HPP-13, Continuous Air Monitors l 5.5 RERP-TSC, Technical Support Center Procedure l 5.6 RERP-FCP, Forward Command Post Procedure l 5.7 RERP-CR, Control Room Procedure l
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. PUBLIC SERVICE. COMPANY OF COLORADO h,E FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 1 of 1 (J3 TABLE 1 FORT ST. VRAIN ATMOSPHERIC STABILITY CATEGORIES
- l AT (*F) from Pasquill Stability ce** .
60m Tower Categories Classification (Degrees) s-1.7 A Extremely Unstable 222.5
>-1.7 to s -1.5 B Moderately Unstable <22.5 to 217.5
>-1.5 to s -1.3 C Slightly Unstable <17.5 to 212.5
>-1.3 to 5 -0.4 D Neutral <12.5 to 2 7.5
>-0.4 to s1.3 E Slightly Stable < 7.5 to 2 3.8
>+1.3 to s3.5 F Moderately Stable < 3.8 to 2 2.1
>+3.5 G Extremely stable <2.1
- per Proposed Revision 1 to Regulatory Guide 1.23, September 1980.
- Standard deviation of horizontal wind direction fluctuation (plume meander) over a period of 15 minutes to I hour.
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FORM 372 22 3643
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TABLE 2 POTENTIALLY AFFECTED SECTORS WITHIN 5 MILE EPZ (WIND FROM e DEGREES)
(SEE SITE FIGURE 1 FOR LOCATION OF SECTORS)
Stability Stability Category O*se<221' Category 22i'se<45' A D,E,N,0,P A D,E,N,0,P,EE B D,E,N,0 B D,E,N,0,P,EE C D,E,N,0 C D,E,N,0,P,EE D D,N,0 D D,E,N,0,P EE E 0,N,0 E D,E,0,P,EE F D,N,0 F D,E,0,P,EE G D,N,0 G D,E,0,EE Stability Stability Category 45'se<67?* Category 671's0<90' A D,E,F,N,0,P,Q,EE A A.D.E,F,0,P,Q,R,EE l B D,E,F,0,P,Q,EE B A,D,E,F,0,P,Q,EE C D,E,0,P EE C A,D,E,F,0,P,Q,EE D D,E,0,P,EE D A,D,E,F,P,Q Ox E D,E,0,P,EE E A,D,E,F,P,Q F D E,0,P,EE F A,D,E,F,P,Q G D E,0,P,EE G D,E,F,P,Q Stability Stability Category 90*<e<1121' Category 1121*re<135' A A,D,E,F,G,P,Q,R A A,0,E,F,G,H,P,Q,R B A,D,E,F,G,P,Q,R B A,D,E,F,G,H,P,Q,R C A,D,E,F,G,P,Q,R C A,D,E,F,G,P,Q,R D A,D,E,F,P,Q,R D A,D,F,G,Q,R E A,0,E,F,P,Q,R E A,D,F,G,Q,R F -
A,D,E,F,P,Q F A,F,G,0,R.
G A,0,E,F,P,Q G A,F,G,Q,R Stability Stability Category 135'se<1571 # Category 1571'ss<180' A A,B,0,F,G,H,Q,R A A,B,F,G,H,1,Q,R B . A F,G,H,Q,R 8 A,B,F,G,H,R C A,F,G,H,Q,R C A,B,F,G,H D A,F,G,H,Q,R D A,B,F,G,H E A,F,G,R E A,B,F,G,H F A,F,G,R F A,B,F,G,H G A,F,G,R G A F,G,H l
l O-PORM 372 22 3643
DOSE PUBLIC SERVICE COMPANY OF COLORADO FCRT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 2 of 2 (3
N Stability Stability Category 180'se<2021' Category 202i'se<225' A A,B,F,G,H,1,J A A,B,C,H,1,J,K B A,B,G,H,I B A,B,H,I,J,K C A,B,G,H,I C A,B ,H , I ,J , K D A,B,G,H,I D A,B,H,1,J E A,B,G,H,I E A,B,H,I,J F A,B,H F A,B,H,I,J G A,B,H G B,H,I,J Stability Stability Category 225'se<2471* Category 2471'*s0<270' A A,B,C,H,I,J,K,L A B,C,H,I,J,K,L,M B A,B ,C,H ,I ,J , K, L B B,C,1,J,K,L,M C A , B , C ,H ,I ,J , K C B,C,1,J,K,L D B,C,H,1,J,K D B,C,I,J,K,L E B,C,I,J,K E B,C,I,J,K,L F B,1,J,K F B,C,I,J,K,L G B,I,J,K G B,C,I,J,K,L l
Stability Stability Category 270'se<292i' Category 2921'50<315' l A B,C,0,I,J,K,L,M,N A B ,C ,D,J , K, L,M,N B B,C,D,1,J,K,L,M,N B C,D,J,K,L,M,N l (~-
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TABLE 3 DOSE CONVERSION FACTORS (DCF'S)
Radionuclide rem /hr 3
DCF(C1/m )*
Kr-83m 2.7E-1 Kr-85m 1.3E+2 Kr-85 1.7E+0 Kr-87 6.5E+2 Kr-88 1.7E+3 Kr-89 1.5E+3 Kr-90 1.0E+3 Xe-131m 9.9E+0 Xe-133m 2.7E+1 Xe-133 3.3E+1 Xe-135m 3.5E+2 Xe-135 2.0E+2 Xe-137 1.5E+2 Xe-138 6.8E+2 3 .
l Noble gas weighted average total body DCF 7.5E+2 l l (based on 879 Mw(t) design inventory) l l l I-131 1.2E+6 I-132 1.7E+4 I-133 2.3E+5 I-134 5.6E+3 I-135 5.7E+4 l Radioiodine weighted average thyroid DCF 5.3E+4 l l (based on 879 Mw(t) design inventory) l 1~ l l *DCF's for noble gases from "The EXREM III Computer Code for l Estimating External Radiation Doses to Populations from Environmental Releases," ORNL-TM-4332, with the exception of DCF's for Kr-89 and Kr-90, which are from " Final Environmental Statement, Light Water Breeder Reactor Program," Volume 3 of 5,
" Commercial Application of LWBR Technology," ERDA-1541.
DCF's for radiciodines from "INREM II: A Computer Implementation of Recent Models for Estimating the Dose s
Equivalent to Organs of Man from an Inhaled or Ingested Os Radionuclide," ORNL/NUREG/TM-84 PORM 372 22 3643
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' X/q VALUES (X10 soc /m' ) AT THE EFCLUSION AREA SOUNDARY (590s)
FOR AN AMEMoe9EIER LOCATED AT A HEIGHT OF 10 MEi[RS '
1 ACCORDING TO THE EQUAll0NS OF NRC REG Gul0E 1.145 WINOSPEED AT 10 METERS (MPH)
Stability
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j J C 23.250 11.630 7.751 4.650 3.22 2.584 1.938 1.550 1.163 0.775 0.465 i . .
l ; D 36.56 18.28 12.19 7.844 6.928 5.988 4.491 3.593 2.695 1.796 1.0T8
}i i d E 48.46 24.23 16.15 10.83 10.83 9.449 7.089 5.670 4.252 2.835 1.101 iM' l' F 88.42 44.21 29.47 20.35 18.54 14.42 10.81 8.650 6.488 4.325 2.595
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FOR AN ANEMOMETElt LOCATED AT A HEIGHT OF 10 METERS.
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O O O TABLE 2A 3
X/Q VALUES (X10 sec/m ) AT A DOWNWIND OISTANCE OF 2 MILES FOR AN AN[MOHET[R LOCATED AT A HEIGHT OF 10 METERS ACCOR0lNo TO TiiE [QUATIONS OF NRC RfC GUIDE 1.18s5
- WINOSI'[ED AT 10 MCIERS (MPil)
Stability 1 ,
Class 1.0 '2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 l
A 0.124 0.062 0.041 0.025 0.018 .
0.014 0.010 0.006 0.006 0.004 0.002 I
o 1.751 0.876 0.584 0.350 0.250 0.195 0.146 0.117 0.088 0.058 0.035
) c 12.97 6.8s83 4.322 2.593 1.852 1.48:1 1.081 0.865 0 .68s8 0.8s32 0.259
) i 1
0 38.13 19.07 12.71 7.859 6.104 5.019 3.972 3.177 2.383 1.589 0.953 E 64.89 32.se t 21.63 13.74 11. 8e6 9.821 7.961 6.369 8s.776 3.184 1.911 r 130.4 65.18 43.45 28.33 25.27, 22.53 17.91 14.33 . 1 0 . 78s 7.163 fe.298 G 250.1 125.0 83.35 56.60 56.14 51.72 38.79 31.03 23.28 15.52 9.310 J4 '
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- Page 4 of 14 m '
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! FIGURE 2.A.
,p ' DtSPERSION FACTOR (X/Q) vs. WINDSPEED FOR A DOWNWIND DISTANCE OF 2 Mt! ES, ACCDRDING TO THE EQUATIONS OF
' NRC REG. GUIDE 1.145. WIND 5PEEDS SHOWN ARE THE INDICATIONS 8 FOR AN ANEMOMETER !.OCATED AT - A HEIGHT OF 10 METERS.
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D Q O U i
1 TABLE 3A
-G 3 X/Q VAI.UES (X10 sec/m ) AT A 00WNWINO DISTANCE Or 8: MILES Toft AN ANEMOMETIR LOCATED AT A IIEICiti Or 10 METERS ACCORDING 10 litt EquAll0NS 00 NRC it(C Cul0E 1.18s5 I WIMOSPEED AT 10 METERS (Mrill Stability Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0
)
A 0.069 0. 038e 0.023 0.014 0.010 0.008 0.006 0.005 0.003 0.002 0.001
] 8 0.155 0.078 0.052 0.031 0.022 0.017 0.013 0.010 0.0F8 0.005 0.003
, C 3.963 1.982 1.321 0.793 0.566 0.480 0.330 0 . 2 68: 0,398 0.132 0.019 l
D 184. 8 7 7.434 4.956 '3.028 2.211 1.823 1. 8:11 1.132 0.889 0.566 0 . 38:0 4
I .' E 29.17 le.59 s 9.725 6.053 4.757 3.918 3.095 2.476 1.857 1.238 0 . 78:3 i
i r 65.46 32.73 21.82 13.85 11.840 9.626 7.585 6.068 8.551 4 3 . 0 38s 1.870 4
C 132.81 66.42 44.28 29.04 25.85 22.67 19.37 13.90 10.42 6.98s8 4.169 e
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, Issue 6
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DISPERSION FACTOR CC/Q) vs. WIND 5 PEED FOR A DOWWIND DISTANCE OF 4 MILES, ACCORDING TO THE EQUATIONS OF 5
NRC REG. GUIDE 1.145l WINDSPEEDS SHOWN ARE THE INDICATIONS -
FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS.
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O O O e
- TABLE 8sA ,
X/4 VALUES (X10~ sec/m') AT A DOWNWIND DISTANCE OF 5 MILES
- FOR AN AMEMOMET[R LOCATED AT A IIEIGili Or 10 MEi[RS 4
ACCORDING TO IHE [QUATIONS JF NRC RFG CUIDE 1.145 WINOSPEED AT 10 METERS (Mrill Stability l Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 !
a l
}
1
- A O.057 0.028 0.019 0.011 0.008 0.006 0.005 0.004 0.003 0.002 0.001 j
B 0.012 0.036 0.024 0.014 0.010 0.006 0.006 0.005 0.004 0.002 0.001 C 2.704 1.352 0.902 0.541 0.386 0.301 0.225 0.180 0.135 0.090 0.054 I
i 0 10.96 5.478 3.652 2.224 1.655 1.322 1.017 0.816 0.612 0. 8e08 0 . 28s5 9
E 22.43 11.21 7.476 4.630 3.586 2.92T 2.294 1.83T 1.377 0.918 0.551 ;
j F 52.07 26.03 17.36 10.93 8.819 7.347 5.759 4.608 3.456 2.304 1.3n2 l
i G 107.7 53.86 35.91 23.30 20.14 17.34 13.34 10.67 8.005 5.336 3.202 I
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RERP-DOSE
- ' Attachment 1 Issue 6 Page 8 of 14
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s PIGURE 4.A.
-- ^15PERSION FACTOR (X/Q) vs.WINDSPEED FOR A DOWNWIND
. DISTANCE OF 5 MILES, ACCORDING TO THE EQUATIONS OF
.NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS d
j FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS.
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O O Q :
TABLE SA
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X/Q VALUES (X10 sec/m') AT A DOVNWINO OISTANCE Or 6 MILES FOR AN ANEMOME1ER LOCAT[0 AT A HEICHI 0F 10 METERS ACCORDING TO IllE [ quail 0NS 0F NRC REC CulDE 1.145 l ,
f WINOSPLED AT 10 MEi[RS (MI'll) 1 l Stability
! Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 4
U T
- A 0.485 0.243 0.162 0.097 0.069 0.054 0.040 0.032 0.024 0.016 0.010 i
R 0.616 0.308 0.206 0.123 0.088 0.068 0.051 0.041 0.031 0.021 0.012 C 19.72 9.859 6.573 3.944 2.817 2.191 '1. 68:3 ' 315 0.986 0.657 0.394 1 0 85.61 42.31 28.54 17.35 12.84 10.21 7.830 6.284 4.713 3. 18s2 1.885 i
j E 179.6 89.81 59.87 36.93' 28.31 22.96 17.88 Ils . 3 3 10.75 7.166 #s.299 1
1
! F 431.9 215.9 144.0 90.18 71.66 59.15 46.17 36.93 27.70 18.8s7 11.08 l C 909.7 451s.9 303.2 195.3 165.2 140.8s 108.1 86.45 68a . 84 8:3.23 25.94 T M 3D M 2Mdm 40 M MM ecWT.
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Attachment I
( Issue 6 l
Page 10 of 14 i O 10-l
. s FIGURE ~3.A.
DISPERSION FACTOR fr/0) vs.WINDSPEED FOR A DOWNWIND DISTANCE OF 6 MILES ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS
-4 FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS 10 _,
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O O O
'i I
TA8LE 6A X/Q VALUES (X10~ sec/m') AT A DOWNWINO DISTANCE or 8 MILES
} TOR AN ANEMov4Elin 1.0CATED Al A ItEIGtli Of 10 ME1[RS
, ACCORDING TO 1HE EQUATIONS Or NetC REC CUIDE 1.145 L WINOSr[r0 AT 10 MET [RS (MPill j .
! Stability d
- Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 j .
1 l .}
i A 0.379 0.190 0.126 0.076 0.054 0 . 08:2 0.032 0.025 0.019 0.013 0.008
- D 0.8e88e 0.242 0.161 0.097 0.069 0.058e 0.08eo 0.032 0 . 0 281 0.016 0.010 1
l C 12.66 6.329 4.219 2.531 1.808 1.406 1.055 0 . 848: 0.633 0.422 0.253 O 57.94 28.97 19.31 11.71 8.599 6.808 5.195 4.169 3.126 2.084 1.251 l ' E 126.3 63.15 42.10 25.84 19. 58e 15.71 12.14 9.735 7.301 8s.867 2.920 4 !
- F 322.7 161.4 107.6 66.87 52.07 42.47 32.93 26.35 19.76 13.17- T.904
, i:
1 1 , G 698.4, 38s9 . 2 232.8 148.2 121.7 101.6 78.19 62.55 46.91 31.28 18.77
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RERP-DOSE Attachment 1 Issue 6
..... Page 12 of 14 10 _
s s
, i ;
i i i FIGURE 6 A. . .
_4 '
10 D!SPER510N FACTOR (X/Q) vs.WINDSPEED FOR A DOWNWIND DISTANCE OF $ Ml? 'C. ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS 8 s FOR AN ANEM tETER LOCATED AT A HEIGHT OF 10 METERS.
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1 TA8LE 7A X/Q VALUES (X10 sec/m') AI A DOWNWING lilSTANCE OF 10 mites
.i IOR AN ANEMOMETIR LOCAIED Al A 11E1C181 or 10 METERS l ACCORDING TO Tile EQUAil08tS OF NRC REC CulDE 1.18e5 WINDSPEED A1 ~10 METERS (MI'll) be '
Stability
.] Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 t -- -
i
'! A 0.313 0.156 0.104 0.063 0.045 0.035 0.026 0.021 0.016 0.010 0.006
.J
, '4 .
8 b. l:02 0.201 0.134 0.080 0.057 0.045 0.033 0.021 O.020\. 0.013 0.008
{
Uj C 8.833 4.416 2.9e s4 1.767 1.262 0.981 0.736 0.589 0.f82 8 0 .2 98: 0.177 LI ,
D 43.02 23.51 14.3f4 8.678 6.345 is008 3.810 3.057 ' 2.293 1.528 0.931 e
- E 99.81 49.90 33.27 20.35 15.26 12.20 9.384 7.52T 5 . 684 5 3.763 2.258
- s -
- ' r 256.9 128.5 85.64 52.96 40.71 32.95 25. 's's 281.35 15.26 10.18 6.105 n i G 568.7 284.3 189.6 - 119.8 96. f40 79.62 61.16 48.93 36.70' 28s.88 6 18s. 6 8
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- " RERP-DOSE Attachment 1 Issue 6 Page 14,of 14 ,
d.. tr3 -
s-FIGURS 7.A.
, ,g D15?ER510N FACTOR (X/Q) vs.WINDSPEED FOR A DOWNWIND DISTANCE OF 10 MILES, ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WIND 5PEEDS SHOWN ARE THE INDICATIONS s i FOR AN ANEMOMETER LOCATED - AT A MElGHT OF 10 METERS. .
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PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Workshsst 1 Issue 6 Page 1 of 10 (v3 WORKSHEET 1 ASSESSMENT OF RELEASE-MONITORED RELEASE This attachment is to be used only if the TI-59 calculator program is g 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 calculation.
- 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) uC1/cc/ cpm c) Maximum CPM, RIS-7324-2:
(RR-93539, blue pen) cpm I
d) Sensitivity, RIS-7324-2:
(I-14,203-P7) pCi/cc/ cpm e) Maximum CPM / Min, RIS-73437-1: cpm / min 1 NOTE: Maximum CPM / Min must be calculated as:
(Maximum CPM - Initial or Intermediate CPM)
( Eiapsed Time (min) )
l from strip chart.
l
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksh:et 1 Issue 6 Page 2 of 10
,O U
f) Sensitivity, RIS-73437-1: uCi/cc/ cpm / min g) Site Area Emergency Limit (as posted):
- 1) 6.6E-2 vCi/cc noble gas
- 2) 6.7E-5 uCi/cc2 '2I h) Ten Times Technical Specification Limits (as posted):
- 1) 2.5E-2 vC1/cc noble gas
- 2) 7.0E-8 vC1/ce282I
- 1) Exhaust Stack Flow (cfm):
(I-15, FI-7320) cfm j) Exhaust Stack Flow (cc/sec):
(Step 41 x 4.72E + 2) cc/sec l k) Average Wind Speed at 10 meters: mph O 1) Wind Direction at 10 meters: From Degrees NOTE: North = 0* increasing degrees - c.w.
m) Differential Temperature: "F (60m Tower) l n) ce = 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) or 4n).
Stability Category
- 6. Determine potential sectors affected within 5 mile EPZ using Table 2 and Site Sector Map (Figure 2).
Sectors O-POMM 372 22 3843
PUZLIC SERVICE COMPANY OF ' COLOR ADO RERP-DOSE l FORT ST. VRAIN NUCLEAR GENERATING STATION Worksh:et 1 l
Issue 6 Page 3 of 10 O
l l l l I Noble Gas Concentration i I I l
- 7. Calculate the exhaust stack noble gas concentration.
l a) RIS-7324-1 concentration = (step 4a) x (step 4b)
=( )x( )
= pCi/cc ,
b) RIS-7324-2 concentration = (step 4c) x (step 4d)
=( )x( )
= pC1/cc
! c) If either RIS-7324-1 or RIS-7324-2 is off-scale high, l record.the stack concentration as obtained by local,
! portable instrument (refer to HPP-56 or Figure 1 for Q 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 l obtained from RT-4803, located on level 11 of the Turbine l Building adjacent to the reactor plant exhaust stack l (refer to HPP-13 for instructions).
Local Indicated Concentration = pCi/cc d) Enter the highest of 7a), 7b), or 7c) pC1/cc I 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 -f Ci/pci)
=( )x( ) x (1 E -6)
= C1/sec POmM 373 22 3643 l
PUZLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 6 Page 4 of 10 Ov l l l l Classification of Event l l 1 I i
l 9. Determine the EAB dilution factor from Attach- '
l ment 1, Table 1A, using the Stability Category l (Step 5) and wind speed (Step 4k).
Dilution Factor = sec/m' General Emeroency Determination l 10. Determine whole body dose rate at the EAB.
l -
Dose Rate = (step 8) x (7.5 E+2 Rem / hour) x (step 9) l ( c1/m')
l =( ) x (7.5 E+2) x ( )
= Rem / hour n If the resulting dose rate at 'the EAB is 2 1 Rem / hour, the V 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 Emeroency Determination i 11. Criteria for Site Emergency: If Step 7d) is greater than or equal to 6.6 E-2 pCi/cc, 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 this
, attachment.
Radiolooical Alert Determination
~
l 12. Criteria for Radiological Alert: If Steo 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.
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PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION
- Worksh;et 1 Issue 6 l
Page 5 of 10
/7 V
I I l Curies of Noble Gas Released l l
l 1 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 l I l Accumulated Whole Body Gamma Dose at EAB l l 1 l 14. Calculate the dose received at the EAB.
l' - Dose = (step 10) x (step 3) ~~
~
=( )x( )
= Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
l l l Projections l l l l 15. If the release is continuing, consult with the Shift Supervisor and estimate the total numoer 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.
Preliminary estimate of release hours hours.
O -
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PUZLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE Workshr,t 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 6 of 10 o
O l l 16. Project the total whole body gamma dose at the EAB. I l Projected dose at EAB = (step 10) x (step 15)
=( )x( )
= Rem l l l 131 I Conc ~entration i I I l 17. Calculate the exhaust stack 1811 concentration.
I a) RIS-73437-1 concentration = (step 4e) x (step 4f)
=( )x( )
= uCi/cc l b) If RIS-73437-1 is off-scale high or if a readout is not 7' I available due to power loss, etc., record the stack L l ~
concentration as obtained from RT-4802, located on level .
I 11 of the Turbine Building adjacent to the reactor plant I exhaust stack (Refer to HPP-13 for instructions).
I Local Indicated Concentration = pCi/cc I I i 1311 and Total Radiciodine Release Rate i l l I 18.- Calculate the source term Q (1811 release rate).
l Q = (step 18) x (step 4j) x (1 E-6 C1/uti)
=( )x( ) x (1 E-6)
= C1/sec l
O PORM 372 22 3842
--,.-3 - _ _ - , - , , . _ _ _ , . - _ . - . . _ . . _ . - . _ _ _ _ _ y
~
PUZLIC SERVICE COMPANY OF COLOR ADO agap-coss FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 6 Page 7 of 10 !
p.
V l 19. Calculate Q7 for total radioiodine release.
l QT = (step 18) x (1.05 E + 2)*
=( ) x (1.05 E + 2)*
= Ci/sec
- Ratio of total radiciodines to 1821 in cesign inventory.
I i l Classification of Event l l l General Emergency Determination l 20. Determine the thyroid dose rate at the EAB.
l Dosa Rate = (step 19) x (5.3 E+4 Rem / hour) x (step 9) l ( C1/m')
_ l =( ) x (5.3 E+4) x ( )
~
= Rem / hour If the resulting dose rate at the EAB is 2 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 attacnment.
Site Area Emergency Determination l 21. Criteria for Site Area Emergency: If Step 17 is greater than or equal to 6.7 E-5 uC1/cc, 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 Step 17 is greater than or I equal to 7.0 E-8 vC1/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 23.
I PORM 372 22 3843 1
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksh:et 1 Issue 6 Page 8 of 10 (v
i l l Curies of Radiciodine Released l l l 1 l l 23. Calculate the curies of radiciodine released to present time.
l Curies Released = (step 19) x (step 3) x (3.6 E+3 sec/hr)
=( )x( ) x (3.6 E+3)
= curies l l l Accumulated Thyroid Dose at EAB l l l l 24. Calculate the dose received at the EAB.
l Dose = (step 20) x (step 3)
O =( )x( )
= Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
1 l l Projections l l l l 25. ~If the release is continuing, consult with the Shift Supervisor and estimate the total numoer of hours the release will continue l (i.e., from beginning 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.
O PORW 372 22 3843
PUZLIC SERVICE COMPANY OF COLORADO RERP-DOSE Font ST. VRAIN NUCLEAR GENERATING STATION W;rksheet 1 Issue 6 Page 9 of 10 1 26. Project the total thyroid dose at the EAB.
l Projected Dose at EAB = (step 20) x (step 25)
=( )x( )
= Rem l 27. Determine the recommended protective action for the general l population based on the results of steps 16 and 26. (Refar to l RERP-PAG.)
l 28. The whole body gamma dose rate at the EAB is (step 11): Rem / hour l 29. The classification of the event based on noble l gases is (step 10 g step 11 o_r step 12):
l 30. The noble gas release rate is (step 8): Ci/sec l 31. The accumulated whole body gamma dose at the EAB l 1s (step 14): Rem O l 32. The total number of curies of noble gas release l to the present time is (step 13): Curies 1 33. The projected whole body gamma dose at the EAB is l (step 16): Rem l Based on projected release duration of (step 15): Sours l 34. The thyroid dose rate at the EAB is (step 20): Rem / hour i
O POmM 373 23 3843
PU LIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksh::t 1 Issue 6 Page 10 of 10 f3 J
l 35. The classification of the event based on radio-
- 1 iodines is (step 20 of step 21 or step 22):
l 36. The radioiodine release rate is (step 19): Ci/sec l 37. The accumulated thyroid dose at the EAB is l (step 24): Rem l 38. The total number of curies of radiciodine l released to the present time is (step 23): Curies l 39. The orojected thyroid dose at the EAB 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) classificatiun is to be used l to determine recommended protective actions.
=.
l l
O -
PORM 372 22 3843
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE
. FORT ST. VRAIN NUCLEAR GENERATING STATION Worksh:Ot 2 Issue 6 Page 1 of 6 O
V l
WORKSHEET 2 ASSESSMENT OF RELEASE US:NG TI-59 CALCULATOR PROGRAM-MONITORED RELEASE This attachment is only to be used if the TI-59 calculator program is used. If the program is not used, use Worksheet 1.
This attachment is used to determine the following:
a) Estimated noble gas and radiciodine release and release rate; b) 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.
Q 1. Collect the following data:
a) Date/ Time of beginning of release:
b) Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation:
c) Hours between la) and Ib): hours (STO 11) d) Maximum CPM, RIS-7324-1: cpm (RR-93539, red pen) (STO03) e) Sensitivity RIS-7324-1: uti/cc/ cpm (I-14,403-P7) (STO 04) f) ' Maximum CPM, RIS-7324-2: cpm (RR-93539, blue pen) (STO 05) g) Sensitivity, RIS-7324-2: uC1/cc/ cpm (I-14,203-P7) (STO 06)
A V
l l
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PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 .
Issue 6 Page 2 of 6 (vD
- b) Maximum mR/hr, Cutie Pie-2520 Probe: mR/hr (STO 01)
- i) Maximum mR/hr, E-500-GM Probe mR/hr (STO 02) j) Maximum CPM / MIN, RIS-73437-1: cpm / min (STO 07)
NOTE: Maximum CPM / Min must be calculated as:
(Maximum CpH - Initial or Intermediate CPM)
(
Elapsed Time (min) )
from strip chart.
k) Sensitivity, RIS-73437-1: pCi/cc/ cpm / min (STO 08)
- 1) Site Emergency Limit (as posted): 1) 6.6E-2 uti/cc noble gas
^-
- 2) 6.7E-5 uC1/cc 181I m) Ten Times Technical Specification l Limits (as posted): 1) 2.5E-2 pCi/cc noble gas
- 2) 7.0E-8 pCi/cc 182I n) Exhaust Stack Flow (cfm):
(I-15,FI-7320) cfm (STO 09) o) Average Wind Speed at 10 meters: mph
- p) Wind Direction at 10 meters:
NOTE: North = 0* increasing degrees-c.w. From Degrees q) Differential Temperature 'F (60m Tower)
Steps lh) and li) used only if RIS-7324-1 cr RIS-7324-2 off-scale high.
O PORM 373 22 3643
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE
' FORT ST. VRAIN NUCLEAR GENERATING STATION Worksh::t 2 Issue 6 Page 3 of 6 (3
V l r) ce = From Data Logger, or square root of l (maximum fluctuation in wind direction I over period of 15 minutes to one hour).
l (OPTIONALCALCULATION) 1
- 2. Determine Stability Category using l Table 1 and Steps 1q) or 1r).
Stability Category
- 3. Determine potentially affected sectors l within 5 mile EPZ from Table 2 and using l Steps Ip) and 2. (See Site Sector Map, l Figure 2.) ,
Sectors 1 4.. Determine the EAB dilution factor from l
Attachment 1, Table 1A, using the l Stability Category (.itep 2) and wind speed (Step lo).
Dilution Factor sec/m' (STO 10)
O 5. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from l beginning to end). Use two hours if no better l estimate is available. If the release has terminated, enter value from step 1c).
Preliminary estimate of release hours hours. (STO 12)
- 6. Prepare the TI-59 for data entry, a) , Place TI-59 in printer / security cradle. .
b) Plug in printer / security cradle.
c) Turn on printer / security cradle and TI-59.
d) Depress " TRACE" button on printer, e) Obtain the magnetic card labeled "FSV Off-Site Dose Calculation (RERP) - Monitored Release."
1 O
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PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION W2rksheet 2 Issue 6 Page 4 of 6
()
v f) Read magnetic card into TI-59.
- 1) Depress l1l,l@l , l @ l , l M l keys.
- 2) Insert magnetic card into right side of TI-59.
Card should be right side up with the "1" in the upper left-hand corner.
- 3) "1" will be displayed if the card was read properly -continue with Step 7. If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card with the same title and repeat Step 6f).
- 7. Input the necessary data into the indicated TI-59 storage registers, a) Step Ic) = l@l 11 b) Step Id) = l@l 03 O c) st a 2-) - imi o4 d) Step If) = l@l 05 e) Step Ig) = l@l 06 f) Step 1h) = l@l 01
- )
~
g Step 11) = l@l 02 h) Step lj) = l@l 07 -
- 1) Step 1k) = l@l 08 j) Step in) = l@l 09 k) Step 4) =
l@l 10
- 1) Step 5) =
l@l 12 pomW 373 23 3H3
PUBl.IC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksh:et 2 Issue 6 Page 5 of ci i O l G l l
- 8. Run Dose Assessment Program a) Depress l@l key.
b) Wait until a number is displayed. A flashing number indicates improper execution of the program. Depress lCMl and [RSTl keys and repeat Steps 7 and 8.
l
SUMMARY
l
- 9. a) The whole body gamma dose rate at the EA3 is(RCL 19): Rem / hour b) The classification of the event based on noble gases is:
- 1) If Step 10.a) 2 1 Rem / hour, GENERAL EMERGENCY.
- 2) If RCL 17 2 6.6E-2 uCi/cc (Step 1.1)1),
SITE AREA EMERGENCY.
Ov
- 3) If RCL 17 2 2.5E-2 uC1/cc (Step 1.m)1) and s 6.6E-2 vCf/ce, RADIOLOGICAL ALERT.
c) The noble gas release rate is (RCL 18): C1/sec d) The accumulated whole body gamma dose at the EAB is (RCL 21): Rem e) The total number of curies of noble gas released to the present time is (RCL 20): C1 f) The p*ojected whole body gamma dose at tne EAS is (RCL 22): Rem g) The thyroid dose rate at the EAB is(RCL27): Rem / hour O
FORM 373 22. as43 O
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION W;rksheet 2 Issue 6 Page 6 of 6
- h) The classification of the event based on radiciocines is:
l 1) If Step 9g) 2 5 Rem / hour, GENERAL EMERGENCY.
l l 2) If RCL 23 2 6.7E-5 vC1/cc <..:<l
~
(5 :ep 1.'D2),- A SITE AREA EMERGENCY.
l 3) If RCL 23 2 7.0E-8 uti/cc l (Step 1.m)2) and i < 6.7E-5 uCi/ce, ,
RADIOLOGICAL ALERT.
- 1) The radiotodine release rate is(RCL26): Ci/sec j) The accumulated thyroid dose at the EAB is (RCL 29): Rem
(
k) The total number of curies of radiciodine released to the ~
- present time is (RCL 28):
{~ The arojected thyroid dose at Ci 1) the EAB is (RCL 30): Rem Based on projected release duration of (RCL 12): hours
- 10. Determine the recommended protective action for the general population based on RERP-PAG.
l *If this classification differs from the classification in Step 9b),
the higher (i.e., more severe) classification is to be used to determine recommended protective actions.
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PUBLIC SERVICE COMPANY CF COLOR AD3 RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 6 Page 1 of 10
/S L
WORKSHEET 3 ASSESSMENT OF RELEASE-UNMONITORED RELEASE This attachment is to be used only if the TI-59 calculator program is not used. If the TI-59 program is used, Worksheet 4 is to be used.
This attachment is used to determine the following due to an unmonitored release via the Reactor Building Louvers or the PCRV Relief Valves:
a) Estimated whole body and thyroid gamma dose and dose rate at the EAB; b) Classification of the release; c) Projected whole body and thyroid gamma dose at the EAB; and d) Recommended protective action for the general population.
- 1. Date/ Time of beginning of release _
n- 2. Date/ Time of ending of release. If release is' V still occurring, enter the Date/ Time of the calculation.
- 3. Hours between 1. and 2. hours
- 4. Collect the following data:
a) Maximum CPM, RIS-9301:
(RR-93256, Pt. 10) cpm b) Sensitivity RIS-9301: sci /cc/ cpm c) Primary coolant 1881 equivalent
,' circulating inventory: C1 d) Primary coolant 1881 equivalent plateout inventory: Ci e) Primary Coolant Volume: sec f) Site Emergency Limit (as posted): 1) 6.6E-2 uti/cc noble gas
- 2) 6.7E-5 9C1/cc1881 g) Ten times Technical Specification Limits (as posted): 1) 2.5E-2 uti/cc noble l O 9>
90RM 373
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- 3M3 l
1 PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE '
FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 l Issue 6 l Page 2 of 10
~
i (V)
- 2) 7.0E-8 uCi/cc 2'I h) Average Wind Speed at 10 meters: mph i) Wind Direction at 10 meters: From Degrees NOTE: North = 0* increasing degrees - c.w.
j) Differential Temperature *F (60m Tower) l k) ce = Data logger or square root of l (maximum fluctuation of wind direction over l a period of 15 minutes to one hour).
l (OPTIONALCALCULATION)
- 5. Determine Stability Category using Table 1, l Step 4j or 4k:
Stability Category
- 6. Determine potentially affected sectors O i l
~'**'" 5 = 5'z =>'"9 T d' 2 "o 5' and 5 (see Site Sector Map, Figure 2).
as ~ ~ ~ ~ - -
Sectors
- 7. Calculate the release noble gas concentration:
RIS-9301 concentration = (step 4a) x (step 4b)
=( )x( )
= SC1/cc
- 8. Calculate the source term, Q (noble gas release rate):
ng ,
a) Reactor Building Louvers Q
ng
= (step 7) x (5.8 E +7)* x (1 E -6 Ci/uct)
=( ) x (5.8 E +7)* x (1 E -6)
= C1/sec
" Release rate (cc/sec) from louvers (FSAR, Section 14.11.2.6).
O pomu 272 22 3643 t .
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE W;rksh:et 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6' Page 3 of 10 O
b) PCRV Safety Valves Q ng = (step 7) x (1.9 E +7)" x (1 E -6)
=( ) x (1.9 E +7)" x (1 E -6)
= r sec
" Release rate (cc/sec) from both PCRV safeties
(,FSAR, Section 6 .8).
l l l Classification of Event l l l
- 9. Determine weighted noble gas dose conversion factor from Table 3: 7.5E+2 Rem / hour C1/m 3
- 10. Determine the EAB atmospheric dilution factor l from Attachment 1, Table 1A, using Steps 5 O
~
'"d '":
Dilution Factor ' sec/m 8 General Emergency Determination
- 11. Determine the whole body dose rate at the EAB:
a) Reactor Building Louvers Dose Rate = (step 8a) x (step 9) x (step 10)
=( ') x ( )x( )
= Rem / hour l b) PCRV Safety Valves Dose Rate = (step Bb) (step 9) x (step 10)
=( )x( )x( )
= Rem / hour O
l PORM 373 22 3M3 l
PUBLIC SERVICE COMPANY OF COLSRADD RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION W;rkshest 3 Issue 6 l Page 4 of 10 l
(
(_/
- 12. If the resulting dose rate at the EAB is 2 1 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the
- Shift Supervisor of the General Eme gency Condition. Then go directly to Step 15.
Site Area Emergency Determination
- 13. If Step Ba. or 8b. is greater than or equal to 9.6E-1 Ci/sec, the classification of event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Area Emergency Condition. Then go directly to Step 15.
'adiological Ale-t Determination R
l 14. If Step 8a. or 8b. is greater than or equal to 3.7 E-1 C1/sec l (ten times the Technical Specification limit), the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 15.
g ; ,,_.- - _ _ . _
d l Curies of Noble Gas Released l l l
- 15. Calculate the curies of noble gas released to present time, a) Reactor Building Louvers l Curies Released = (step 8a) x (step 3) x (3.6 E+3 sec/hr)
=( )x( ) x (3.6 E+3) ,
= Curies b) PCRV Safety Valves Curies Released = (step 80) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= Curies t
O V
POMM 372 22 3443 l
PUBLIC SERVICE COMPANY OF COLCRADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 6 '
Page 5 of 10 tO v
I I l Accumulated Whole Body Gamma Dose at EAB l l l
- 16. Calculate the dose received at the EAB.
a) Reactor Building Louvers Dose = (step 11a) x (step 3)
=( )x( ) .
= Res b) PCRV Safety Valves Dose = (step lib) x (step 3)
=( )x( )
q = Rem V
NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
I I l Projections !
I I
- 17. 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). Use two hours if a more l reasonable estimate is not available. If the release has
, terminated, enter value from step 3.
Preliminary estimate of release hours hour (s).
- 18. Project the total whole body gamma dose at the EAB.
a) Reactor Building Louvers Projected Dose at EAB = (step lit) x (step 17)
=( )x( )
O
- a-POmM 373 23.J643
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PUBLIC SERVICE COMPANY OF COLOR AD9 RERP-DOSE FORT ST. VRAIN NUCLE AR GENERATING STATION Worksheet 3 Issue 6 i Page 6 of 10 ,
O -
i b) PCRV Safety Valves j Projected Dose at EAB = (step lib) x (step 17)
=( )x( )
= Rem
- 19. Calculate the release 1811 equivalent concentration (Reactor Building Louvers or PCRV Safety Valves).
- I Equivalent Concentration = .
(step 4c) + (step 4d) x (5.7 E-3) * (step 4e)
=( )+ ( ) x (5.7 E-3) *( )
= Ci/cc
- " Amount of plateout ***I equivalent released (FSAR, Section 14.11.2.7.1).
- 20. Calculate the source term, Q (881I equivalent release rate).
. a) . Reactor Building Louvers l Q = (step 19) x (5.8 E+7 cc/sec)
, =( ) x (5.8 E+7)
= C1/see b) PCRV Safety Valves l Q = (step 19) x (1.9 E+7 cc/sec)
=( ) x (1.9 E+7) -
= C1/sec l l l Classification of Event l l 1
- e3
- 2648
. *+.*=rw~-- .
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUOLEAR GENERATING STATION Worksheet 3 Issue 6 ,
Page 7 of 10 !
<3 N.s
- 22. Determine the thyroid dose rate at the EAB.
a) Reactor Building Louvers l
Dose Rate = (step 20a) x (step 21) x (step 10)
=( )x( )x( )
= Rem / hour b) PCRV Safety Valves -
Dose Rate = (step 20b) x (step 21) x (step 10)
=( )x( )x( )
=____ Rem / hour General Emergency Determination
- 23. If the resulting dose rate at the EAB is 2 5 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the P)
V
~
Shift Supervisor 'of the General Emergency Condition. Then go-directly to Step 26 of this. attachment.
Site Area Emercency Determination 24 If Step 20a or 20b. is greater than or equal to 9.8E-4 Ci/sec, the classification of the event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Area Emergency Condition. Then go directly to Step 26 of this attachmint.
Radiological Alert Determination .
l 25. .If Step 19 is greater than or eoual to 1.0 E-7 C1/sec (ten times ,
l the Technical Specification 11mit)6 the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 26.
PonW 3r3 23 3H3
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 6 Page 8 of 10 0" 1 1
1 I l Curies of 888I Equivalent Released l l l
- 26. Calculate the curies of 8881 equivalent released to present time.
a) Reactor Building Louvers l Curies Released = (step 20a') x (step 3) x (3.6 E+3 sec/hr)
=( )x( ) x (3.6 E+3)
= Curies b) PCRV Safety Valves Curies Released = (step 20b) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
O -
= curi -
l l Accumulated Thyroid Dose at EAB l ll
- 27. Calculate the dose received at the EAB.
a) Reactor Building Louvers Dose =
= (step 22a) x.(step 3)
= Rem b) .PCRV Safety Valves Dose = (step 22b) x (step 3)
=( )x( )
= Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
~,o. 3r3. .w4
PU LIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION W;rksh ut 3 Issue 6 l Page 9 of 10 (9
v l
I I l Projections l l l
- 28. 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). Use two hours if a more l reasonable estimate is not available. If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hour (s).
- 29. Project the total thyroid dose at the EAB.
a) Reactor Butiding Louvers Projected Dose at EAB = (step 22a) x (step 28)
=( )x( )
= Rem ,
b) PCRV Safety Valves Prejected Dose at EAB = (step 22b) x (step 28)
=( )x( )
= Rem
- 30. Determine the recommended protective action for the general population based on the results of Steps 18 and 29. Refer to RERP-PAG.
1 I l Summary l l l
- 31. The whole body gamma dose rate at the EAB is (Step 11a or lib): Rem /hr
- 32. The classification of the event based on noble gases is (Step 12 of Step 13 or Step 14):
- 33. The noble gas release rate is (Step Sa or 86): C1/see PORW 373 + 23 + 3M3
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUOLEAR GENERATING STATION Worksheet 3 Issue 6 Page 10 of 10 V
l
- 35. The total number of curies of noble gas released to the present time is (Step 15a or 15b): Curies
- 36. The orojected whole body gamma dose at the EAB is (Step 18a or 18b): Rem
- 37. Based on projected release duration of (Step 17):
hours
- 38. The thyroid dose rate at the EAB is (Step 22a or 22b): Rem / hour
- 39. *The classification of the event based on 1811 equivalent is (Step 23 of Step 24 or Step 25):
- 40. The 1811 equivalent release rate is (Step 20a or 20b): C1/sec
- 41. The accumulated thyroid dose at the EAB is (Step 27a or 27b): Rem
- 42. The total number of curies of 181I equivalent released to the present time is (Step 26a or 26b): Curies
- 43. The projected thyroid dose at the EAB is (Step 29a or 29b): Rem Based on projected release duration of (Step 28): hours -
l *If this classifi:ation differs from the classification in Step l 32, the higher (i.e., more severe) classification is to be used -
to determine recommended protective action.
O PoRM 373 22 3643
_ .__ _ __ Y~7 ' __h _ _ _ _ . . _ _ _ _
/
[ PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE
. FORT ST. VRAIN NUCLEAR GENERATING STATION Vorkshest 4
), Issue 6 Page 1 of 5 WORKSHEET 4 ASSESSniENT OF RELEASE USING TI-59 CALCULATOR PROGRAM-UNMONITORED RELEASE This attachment is only to be used if the TI-59 calculator program is used. If the program is ny used, use Worksheet 3.
This attachment is used to determine the following due to an unmonitored release via the Reactor Buf2 ding Louvers or the PCRV Relief Valves:
a) Estimated whole body and thyroid gcmma dose and dase rates at the EAB; b) Classification of the release; c) Projected whole body and thyroid gamma dose at the EAB; and d) Re:ommended protective action for the general population.
- 1. Collect the following data:
a) Date/ Time of beginning of release:
b) Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation:
c) Hours between la) and Ib): hours (STO 07) d) Maxkum CPM, RIS-9301: cpm (RR-33256, Pt.10) (STO 01) e) Sensitivity RIS-9301: vC1/cc/ cpm (STO 02) f) Primary Coolant 181I equivalent C1 circulating inventory: (posted) (STO 03) g) Primary Coolant 182 equivalent Ci plateout inventory: (posted) (STO 04) h) Primary Coolant Volume: (posted) cc (STO 05) i l A -
1 FORM 372 22 36A3 l
, PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 6 !
Page 2 of 6 l Q-v
- 1) Site Emergency Limit: (posted)1) 6.6E-2 pCi/cc noble gas
- 2) 6.7E-5 uCi/cc 2'1I j) Ten Times Technical Specification Limits (posted):
- 1) 2.5E-2 pC1/cc noble gas
- 2) 7.0E-8 pCi/cc 281I k) Average Wind Speed at 10 meters: mph
- 1) Wind Direction at 10 meters:
NOTE: North = 0* increasing degrees-c.w. From Degrees m) Differential Temperature 'F (60m Tower)
~
l n) ce = From Data Logger, or square root of l (maximum fluctuation in wind direction l over period of 15 minutes to one hour).
l (OPTIONAL CALCULATION)
- 2. Determine Stability Category using l Table 1 and Steps 1.m) and 1.n).
Stability Category
- 3. Determine potentially affected sectors l within 5 mile EPZ using Table 2 and Steps l 11) and 2 (see Figure 2, Site Sector Map).
Sectors
- 4. Determine the EAB dilution factor from Attachment I using the Stability l Category (Step 2) and wind speed (Step ik).
Dilution Factor sec/m' (STO 06)
O. .
PORM 372 22 3M3
~
l PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 6 Page 3 of 6
- 5. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from l beginning to end). Use two hours if a more l reasonable estimate is not available. If the release has terminated, enter value from step 1.c).
Preliminary estimate of release hours hours.(STO 08)
~
- 6. Prepare the TI-59 for data entry.
a) Place TI-59 ,in printer / security cradle. ,
b) Plug in printer / security cradle.
c) Turn on printer / security cradle and TI-59.
d) Depress " TRACE" button on printer, e) Obtain the magnetic card labeled "FSV Off-Site Dose Calculation (RERP) - Unmonitored Release."
f) Read magnetic card into TI-59.
~
- 1) Depress l11, lMl , lEl , lWITEl keys.
- 2) Insert magnetic card into right side of TI-59.
Card should be right side up with the "1" in the upper left-hand corner.
- 3) "1" will be displayed if the card was read properly - continue with Step 6f)4). If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card with the same title and repeat Step 6f).
- 4) Depress l2l ,l@l ,lQl , (WRiiEl keys.
- 5) Insert card into right side of TI-59.
Card should be upside down with the "2" in the lower left-hand corner.
- 6) "2" will be displayed if the card was read properly - continue with Step 7. If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card with the same title and repeat Step 6f).
PDAM 372- 22 3843
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 6 Page 4 of 6 (v~'\
- 7. Input the necessary data into the indicated TI-59 storage registers.
a) Step Ic) = l5T6l 07 b) Step Id) = l@l 01 c) Step le) = 15TDI 02 d) Step If) = l@l 03 e) Step ig) = l5TUl 04 f) Step 1h) = l@l 05 g) Step 4 =
l@l 06 O Step 5 h) =
l@l 08 -
- 8. Run Dose Assessment Program.
a) Depress lR3l key.
b) Wait until a number is displayed. A flashing number indicates improper execution of the program. Depress lCLRl and l E l keys and repeat Steps 7 and 8.
O-FORM 372 32 3843
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 6 Page 5 of 6 (g .)
l
SUMMARY
l
- 9. a) The release path is:
- 1) Reactor Building Louvers
- 2) PCRV Reliefs b) The whole body gamma dose at the EAB is (RCL 12 for louvers, RCL 13 for reliefs). rem / hour c) The classification of the event based on noble gases is:
- 1) If Step 10b) 2 1 Rem / hour, GENERAL EMERGENCY.
- 2) If Step 10c) 2 9.6E-1 C1/see SITE AREA EMERGENCY.
Q 3) If Step 10c) 2 3.7E-1 C1/sec and s 9.6E-1 C1/sec, RADIOLOGICAL ALERT.
- 4) If RCL 112 9.6E-1 C1/sec, SITE AREA EMERGENrY.
- 5) If RCL 11 > 3.7E-1 C1/sec and < 9.6E-1 Ct/sec, RADIOLOGICAL ALERT.
e) The accumulated whole body gamma dose at the EAB is (RCL 16 for louvers, '
RCL 17 for reliefs): Rem
- f) The total number of curies of noble '
! gas released to the present time l is (RCL 14 for louvers, RCL 15 for reliefs): Ci g) The projected whole body gamma dose at tne EAB is (RCL 18 for louvers, RCL 19 for reliefs): Rem l Based on a projected release duration l of (RCL 08): hours i
POMM 372 22 3643
RERP-DOSE PUZLIC SERVICE COMPANY CF COLOR ADO Workshist 4 Issue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 6 l
O h) The thyroid dose rate at the EAB is (RCL 24 for louvers, RCL 25 for reliefs): Rem / hour l i) The 1821 equivalent release rate is (RCL 22 for louvers, RCL 23 for reliefs): C1/sec
- j) The classification of the event based on 1811 equivalent is:
- 1) If Step 10h) 2 5 Rem / hour, GENERAL EMERGENCY. -
- 2) If Step 101) 2 9.8E-4C C1/sec SITE AREA EMERGENCY
- 3) If Step 101) 2 1.0E-7 Ci/sec and < 9.8E-4 Ci/sec RADIOLOGICAL ALERT.
k) The accumulated thyroid dose at the EAB is (RCL 28 for louvers, RCL 29 for Q reliefs): Rem
- 1) The total number of curies of 282r equivalent released to the present time is (RCL 26 for louvers, RCL 27 for reitefs): C1 m) The projected thyroid dose at the EAB is (RCL 30 for louvers, RCL 31 for reliefs): Rem
. Based on projected release duration of (RCL 08): hours
- 10. . Determine the recomended protective action for the general population. Refer to RERP-PAG.
l *If this classification differs from the classification in Step 9c),
the higher (i.e., more severe) classification is to be used to determine recommended protective actions.
PORM 372 3643
O O O o
24 f3 di 11 1
RADIOLOGICAL EMERG RESPONSE PLAN N 0944 h E D , C STEP 2: VERIFY AND/BR MANUALLY ENTER THE FOLLOWING STANDARD DATAe 3
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hm m
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. TT-93110-2 60 METER TOWER 48.5 METERS PRIMARY O I
NB INST # TOP RX BLDG 42.7 METERS IST ALT (FROM CHART ON I-13)
NOTE: SELECT THE WIND SPEED AND WIND DIRECTION INSTRUMENTS FRBM o .-. o :o
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BEGINNING OF RELEASE ...DATE ( ) TIME ( : ) EO
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zm ENDING OF RELEASE ......DATE ( / / ) TIME ( ) z CURRENT DATE AND TIME ..DATE ( / / ) TIME ( ) EO O MONITBRED RADIATION LEVELSe yg RIS-7324-1 (RR-93539 PT # 1) .......-( , ) E( ) MAXINUM CPM %
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. STEP 4: ENTER THE NETER0 LOGICAL DATA: y, ft)
WIND SPEED ELEVATION SELECTION I5 HIN AVE -$
ENTER SELECTED ELEVATION ( )nETERS AND AVERAGE (
10.0 NETERS PRINANY
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PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1 -
Issue 6 Page 1 of 2 O
v Checklist 1 - Data Logger Monitored Release l l 1. Collect data for calculation, using copies l of Datasheet 1 as required for instrument l sensitivities, meteorological data, and l radiation monitor readings.
l l 2. Access the dose assessment menu via demand l function 41 or screen 941.
l l 3. Before performing calculations, initialize l the summing screen by going to step 1 on l the menu, entering option 4, returning to l the menu and submitting DF-41-0-0.
1 l NOTE: Option 2 must be used when performing calculations for
(')
'v l
l record keeping or dose reporting purposes.
autcmatically resets to option 1 every time DF-41-0-0 is This l run, and must be set to cotton 2 for each calculation.
l 4. Following the screens on the menu, perform l a " duration of release" calculation. To l accomplish this, enter the release start l date and time, the current time, and the l projected or estimated end of release l time. Use two hours from current as a l default value whenever this value isn't l known.
l l 5.. After entering all data and returning to l the menu, submit DF-41-0-0.
l l 6. Print all screens Tsed for input and I results. Screens tha', should be printed I are: 944, 942, 948, 951, 945, and 947.
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PORM 372 22 3M3
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- - . - _ _ _ _ = _ _ - - - - _ _ . _ _ - _ -.. . . - .
. . .- ... . . . - - - . . . . . - . . . .-- = . . . - . . . .. . .
PUBLIC SERVICE COMPANY OF COLORADO ch;cklist 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 2 of 2 l 7. Perform a " puff" calculation. To do this, l change the release start time to the l current time, and resubmit DF-41-0-0. Be l sure that option = 2.
l l 8. Print screens used for input and results.
l Screens that should be printed are: 944 l and 942.
I I 9. Set option to 3, and resubmit 0F-41-0-0 to l total the results.
l l 10. Print screen 949, which displays total I results.
I O i 11. comai t-I paiicabi- s etioas datasheet 3, and transmit information to or - - - - - - - -
~ ~
l Radiological Assessment Coordinator at the l FCP.
I l 12. Discuss results of assessment with senior l Health Physics representative for use in l dispatching monitoring teams, etc.
l l 13. Transmit prints of result screens to TSC Director for use in completing fact sheet.
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PORM 372 - 22
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 6 Page 1 of 3 Work /Datasheet/ Checklist Control List Worksheet No. Title Number Copies 1 Monitored Release Calculations 5 (Manual) 2 Monitored Release Calculations 10 (TI-59) 3 Unmonitored Release Calculations 2 (Manual) 4 Unmonitored Release Calculations 2 (TI-59)
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Datasheet No.
1 Data Logger (or IBM) Monitored Release 20 2 Data Logger (or IBM) Unmonitored Release 2 3 Status Board Update Sheets 20 Checklist No.
1 Data Logger-Monitored Release 20 O
POmM 372
- 22 3843
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL -
Issue 6
,_ Page 2 of 3
.I ) ..
FORMS USE REPORTING SHEET l 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 Datasheet Numbers Copies Used Checklist Numbers Cootes 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 thi s " Forms Use Reporting Sheet" for the affected procedure in the affected book.
l POMM 3M 32 3DO
" ' ~ " " ~
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 6 Page 3 of 3
') -
v FORMS USE rep 0RTING SHEET (Continued)
COMMENTS Reported By:
Date:
l Nuclear Documents Specialist Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the h originating-individual / department upon completion of this form to notify users that the procedure ha r. been updated. and that all worksheets, checklists, and datasheets are present in the required l
number of copies.
l l
O PORM 372 22 3S43 .
..-..--~- ,
BOOK 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION
) service PUBLIC SERVICE COMPANY OF COLORADO RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATION ISSUE EFFECTIVE NO. SUBJECT NUMBER OATE l 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-FIELO Field Monitoring Procedure 6 08-06-84 RERP-HOME Home Packet for Off-Shift Notifications 12 08-06-84 l RERP-ORG FSV Emergency Organization and l Responsibilities 7 10-10-84 RERP-PAG Protective Action Guideline Recemmendations 3 08-06-84
'ERP-PCC
. Personnel Control Center Procedure 14 08-06-84 l RERP-SEOC State Emergency Operations Center j -
Procedure 9 10-10-84 RERP-SURVEY Inplant/Onsite Radiological Monitoring 4 08-06-84 l.RERP-THYROIO Thyroid Blocking Agent
.l Administration 4 10-10-84 9
9 FORM tBf 372 22 3843
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G
l RERP-ECP PUBLIC SERVICE COMPANY OF COLORADO Issue 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 5 [
1 l
c V N TITLE: EXECUTIVE COMMAND POST PROCEDURE ISSUANCE AUTHORIZED g g4 3
BY M 6b 4f dNbb EFFECTIVE PORC R EVIEW m 589 M b W DATE 10-10 84 TABLE OF CONTENTS Section Description Page 1.0 Criteria for Implementation................................... 2 2.0 Procedure..................................................... 2 3.0 Responsibilities ............................................. 3 4.0 References ................................................... 4 m 5.0 Re ferenced or Supporti ng Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . . 5 (J
Figure 1 Executive Command Post Organization..................... 1
-Figure 2 Emergency Organization ................................. 1 Attachment 1 Support Equipment / Material........................... 1 Checklist 1 ECP Director's Checklist............................. 1 Work / Data sheet /Checkli st Control U st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e R e p o rt i n g S h e e t* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 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, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
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FORM 372 + 22 3642 l l
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RERP-ECP Issue 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 5 0Public Service pusuC sERWCE COMPANY OF COLORADO r~
ESTABLISHING THE EXECUTIVE COMMAND POST 1.0 Criteria for Imolementation When the FSV Radiological Emergency Response Plan (RERP) requires augmentation of resources, the Executive Command Post Director shall activate the Executive Command Post (ECP).
2.0 Procedure 2.1 Staffing The ECP Director shall perform personnel accountability to assure that the initial manning functions of the ECP can be met.
If not during normal working hours, those personnel required to man the ECP are notified by telephone (see RERP-HOME or RERP PHONE LISTS). It is the responsiblity of the ECP Alternate Director, or the first individual contacted by the ECP Director,. to ensure that the notifications are made. Refer to the call list for the ECP for instructions, names, and telephone numbers.
2.2 Communications
- The ECP Director shall establish communications with the Forward Command Post (FCP).
2.3 Activation The Executive Command Post (ECP) shall be established and operational within ninety (90) minutes after an ALERT or higher level accident. -
2.3.1 The ECP will be located:
a) Primary - Room 620, Headquarters Building, b) Alternate - PSC Lookout Center in Golden.
~2.3.2 The ECP is manned by senior corporate personnel, facilities, equipment, and financial resources in an emergency situation. The ECP supports PSC
. personnel stationed at onsite and offsite emergency centers.
O conmsim.m.mo
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RERP-ECP Issue 9 FORT ST. VilAIN NUCLEAR CENERATIN3 STATION Page 3 of 5 Public 0SerVlCe PusuC SERVICE COMPANY OF COLORADO gO 3.0 Responsibilities 3.1 Executive Command Post Director - Checklist 1 3.1.1 The ECP Director will perform personnel accountability to assure that the ECP staffing requirements can be met.
3.1.2 Assumes overall responsbility for providing the Corporate Emergency Director (located at the Forward Command Post) with the counsel, expertise, and resources available within the PSC organization. -
3.1.3 Coordinates emergency assistance, provides reentry and recovery support, station and co-ordinates site modifications review by the Nuclear Facility Safety Committee as appropriate.
3.1.4 Supervises the ECP emergency operations Mangers, communications, and clerical personnel, and briefs ECP staff.
3.1.5 Dispatches headquarters management, administrative and technical support personnel as requested by the
() Corporate Emergency Director (CED).
3.1.6 Terminates the ECP when the emergency condition is
- te rmi nated.
3.2 Communications Support 3.2.1 Establish communications with the Forward Command Post (FCP) (see RERP PHONE LISTS for phone numbers, if required).
3.2.2 When instructed to do 50, inform the FCP that the ECP is manned and ready and of the location (Room
, 620 or Lookout Center).
3.2.3 Receive status of plant and emergency and assessment of condition and inform ECP Director, who will brief the ECP staff.
3.2.4 Request location of Personnel Control Center (PCC).
. 3.2.5 Maintain communications flow between ECP and FCP.
3.3 Clerical Support .
~
Clerical assistant (s) keep an ongoing record (log) of all actions taken.
O FOAMttl372 22 3843
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RERP-ECP
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Issue 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5 Public 0 Service pusuC SERVICE COMPANY OF COLORADO 3.4 Manager of Technical Support 3.4.1 Provide CEO and onsite emergency operations with technical advice in nuclear, mechanical, civil, and electrical engineering.
3.4.2 Provide engineering support, technical experts, and consultants as requested. (See RERP-SUPORG, should the need for non-PSC organization assistance be identified.)
- 3.5 Manager of Media Relations 3.5.1 Coordinates communications between the ECP and FCP.
3.5.2 Assists the ECP Director and PSC media relations personnel in preparation of press releases, announcements, and interviews.
3.6 Hanager of Resources ,
3.6.1 Coordinates provision of manpower and equipment from within PSC, and from consultants / contractors, to supports on-site emergency operations.
3.6.2 Provides requested technical and craft manpower; O
personnel or consultants for engineering / design and contruction reviews; temporary housing, office, transportation, and contruction equipment;
. purenasing, financial, legal and general office support; and, food deliveries and related logistics support to designated emergency operations. (See RERP-SUPORG, should the need for non-PSC organization assistance be identified.)
3.7 Manager of Security 3.7.1 Coordinates PSC security operations with public law enforcement agencies. -
3.7.2 Acquires additional security manpower, hardware, and equipment, as requested.
4.0 References -
4.1 FSV Radiological Emergency Response Plan l .
O
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. , . . , . . . . , . . ~ . . - . -
i_ _ . _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ _ _ .- . _ _ .
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RERP-ECP Issue 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 5 0Public Service rusuC SERVICE COMPANY OF COLORADO O
5.0 Referenced or Supportino Procedures 5.1 RERP-FCP, Forward Command Post Procedure ,
5.2 RERP-HOME, Home Packet for Off-shift Notifications 5.3 RERP-SURVEY, Inplant/Onsite Radiological Surveys 5.4 RERP-SUPORG, Use and Coordination of Non-PSC Support Organizations
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mu ec 9 au z, E EXECUTIVE COMMAND POST ORGANIZATION E5 i
j Fort SLVrain Nuclear Generating Station t DIRECTOR - O EXECUTIVE COMMANO POST $ 5 3 i' c
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M O d WP - PUBLIC AFFAIR 51 VP - ACCOUNTINC s MANAGER CLAIMS, SAFETY @ Q O Z MANAGERf MANAGER OF PUBLIC SECRETARYf NSING
& SECURITYtSECURITY l MUCLE RELATIONS VP FINANCE & TREASURY COORDINATOR m
- ENGINEERING SUPPORT
- MEDIA RELATIONS
- MANPOWER SUPPORT
- SECURITY COORDINATION d NATM
- LOGISTICS SUPPORT
- LAW ENFORCE 4NT LIA150N
- TECNMICAL EXPERTS
- CONSULTANTS
- FINANCIAL SUPPORT
- MANPOIIER, EQUIPMENT
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RERP-ECP Figure 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issua 9 9'
OService PUBUC SERVICE COMPANY OF COLORADO O
FIGURE 2 EMERGENCY ORGANIZATION g
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l ' FORM f B' 372 72 3843
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RERP-ECP Attach. 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9
- 9' 0 service PusuC SERVICE COMPANY OF COLORADO O
SUPPORT EQUIPMENT / MATERIALS
- 1. Communications equipment - telephones.
- 2. Fort St. Vrain Radiological Emergency Response Plan.
- 3. State Radiological Emergency Response Plan.
- 4. Local Government Emergency Plan.
- 5. Maps a) Fort St. Vrain area and environs.
b) Regional.
- 6. Fort St. Vrain Station layout drawings (see RERP-SURVEY).
- 7. Other support available.
! a) Reproduction Equipment.
b) Commerical television station monitoring equipment.
c) Radio-television recording equipment.
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, RERP-ECP Chicklist 1 Issue 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION U
0 Service rusuC sERVICIE COMPANY OF COLORADO 9'
1 ECP LIRECTOR'S CHECKLIST t
NOTE: All information is to be recorded by the Clerical Assistant Time
- 1. Personnel Accountability
- a. Hasager of Technical Support'- Nuclear Site l Engineering Maneger/Nucleer t.icensing Manager
- b. Manager of Media Relations - VP Public Affairs /
I Manager of Public Relations.
' \.
'. c Manager of Resources - VP Accounting /VP of Finance & Treasurer.
- d. Manager of Security - Manager of Claims, Safety l & Security / Security Coordinator.
? e. Clerical assistants. Secretary to VP Accounting.
- f. Commsnications Support Person.
- 2. Staffing requirements met.
- 3. Communications established with FCP.
- 4. FCP infomed that ECP is manned and ready and location.
- 5. Status of plant and emergency and assessment of condition received from FCP.
- , 6. , Location of PCC requested and received.
i
- 7. Staff briefing conducted.
' FORM (8)372 22 3843
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.. . . - . . . . . . ....a.... . . - . - .-. . . . . . . . .
RERP-ECP WS/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 Page 1 of 3 0 SerVICO PUBUC SERVICE COMPANY OF COLORADO O
Work /Datasheet/ Checklist Control List S
Worksheet No. Title Number Copies None N/A N/A Datasheet No.
None N/^ N/A Checklist No.
1 ECP Director's Checklist 2
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'FOAMi81372 22-3643
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RERP-ECP WS/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 0Public Service PUBUC SERVICE COMPANY OF COLORADO 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 OV Datasheet Numbers Copies Used Checklist Numbers ' Copies 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 Q Sheet" for the affected procedure in the affected book.
FORM (8)372 22-3643
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- . . . . . . . . ....w.. - ... ..-. . ..._a._... . . . .
RERP-ECP
~
WS/DS/CL Issue 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION
- 9' 0 Service rusuC sERWCE COMPANY OF COLORADO FORMS USE REPORTING SHEET (Continued) i COMMENTS Reported By:
Dete:
Nuclear Documents Specialist
- Date Received 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.
l l -
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1 O
kmutair72 22 3ec
. .._..,. .--..~...-~,...m -mm . y. . .,, . . .yp ~7, 7. , _,
RERP-ECP
- Checklist 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9
- 9' 0 Public Service PUBLIC SERVICE COMPANY OF COLORADO N
ECP DIRECTOR'S CHECKLIST NOTE: All information is to be recorded by the Clerical Assistant Time
- 1. Personnel Accountability ,
- a. Manager of Technical Support. - Nuclear Site l Engineering Manager / Nuclear Licensing Manager
- b. Manager of Media Relations - VP Public Affairs /
Manager of Public Relations.
- c. Manager of Resources - VP Accounting /VP of Finance & Treasurer.
- d. Manager of Security - Manager of Claims, Safety
& Security / Security Coordinator. .
O e. Clericai assistants - Secretary to ve Accounting.
- f. Communications Support Person.
- 2. Staffing requirements met.
- 3. Communications established with FCP.
- 4. FCP informed that ECP is manned and ready and location.
S '. Status of plant and emergency and assessment of condition received from FCP. .
- 6. . Location of PCC requested and received, i 7. Staff briefing conducted. -
\
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pongtg3yy2 22 3643
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, , ., ~,, . .-- ,---. - - - . , . - - . .,,-.,.-.,,y., .. --- -
RERP-ECP Checklist 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9
- 9 0 Service PUBLIC SERVICE COMPANY OF COLORADO O
ECP DIRECTOR'S CHECKLIST I
NOTE: All information is to be recorded by the Clerical Assistant Time
- 1. Personnel Accountability ,
- a. Manager of Technical Support - Nuclear Site l Engineering Manager / Nuclear Licensing Manager
- b. Manager of Media Relations - VP Public Affairs /
Manager of Public Relations.
- c. Manager of Resources - VP Accounting /VP of Finance & Treasurer.
- d. Manager of Security - Manager of Claims, Safety
& Security / Security Coordinator.
Q e. Clerical assistants - Secretary to VP Accounting.
- f. Communications Support Person.
- 2. Staffing requirements met.
- 3. Communications established with FCP.
- 4. FCP informed that ECP is manned and ready and location.
5 '. Status of plant and emergency and assessment of condition received from FCP.
- 6. . Location of PCC requested and received.
- 7. Staff briefing conducted.
l 1
0 1 FORM 18)372 22 3843
..._-.,....._.._s- . . _ _ _ . . . _ . _ _ . ,_, _ _ _ _ _ , __ _,. , . . _
--- . . . . .. . . . _ _. . . _ . . _ . _ = _ _ . _ . , _ _ . _ , . . _ . , _ . , . , _
RERP-ECP
!. WS/DS/CL 1
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9
- E' service PUBUC SERVICE COMPANY OF COLORADO O
t Work /Datasheet/ Checklist Control List Worksheet No. Title Number Copies l
- None N/A N/A s Datasheet No.
None N/A N/A Checklist No. .
1 ECP Director's Checklist 2 I
O FoAMitl372 22 3842 y_ . _ _ . _ _ . - . . .
...m _ , _ . - , _ _ _ _ _ _ _ , . - _ . _ . . - . . _ . _ _ _ _ _ _ _ _ _ _ _ _ . . . _ , _ _ _ _ _ _ . . _ . , . _ , _ . _ _ _ . . _ _ _ _ . ,
-. . . . . ~. -
RERP-ECP WS/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 Page 2 of 3 Service rustic suavice courAmy or cotonano
/~'s V
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 4
) Datasheet Numbers Copies Used l
l Checklist Numbers Copies 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 Sheet" for the affected procedure in the affected book.
'FORMiel372 22 3843 sa
, - - - , . , . . - - - - +-, , , ,, - - - + - - , - - - - + , , - - - , - - - - - - - - - - , - - - - - . ~ , - , - - _
RERP-ECP WS/DS/CL Issue 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION
- 9' SGIVice PUBUC SERVICE COMPANY OF COLORADO O .
FORMS USE REPORTING SHEET (Continued)
COMMENTS Reported By:
Date:
Nuclear Documents Specialist
- Date Received Date Replaced
- Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to Q notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.
9 O
pommes m.m.ws:
- _ = _. . _ . . . . . _ . . . _ . . _ . . _
A PUBLIC SERVICE COMPANY OF COLORADO RERP-EXP Issue 2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 1 of 4 l
l p
l TITLE: EMERGENCY EXPOSURE GUIDELINES ISSUANCE AUTHORIZED g,, tv L,,I 4 BY 4 N /- %c4 M PORC EFFECTIVE REVIEW PORc 5 8 0 AUG 2 - 1984 DATE b" ko" b h Section Description Pace General ........................................................... 2 1.0 Criteria For Implementation................................... 2 2.0 Procedure..................................................... 2 3.0 R e s pon s i b i l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 4.0 References ................................................... 3 5.0 Re ferenced or Supporti no Procedure s. . . . . . . . . . . . . . . . . . . . . . . . . . . 4 A
V Table 1 Exposure Criteria for Emergency Workers................. 1 Datasheet 1 Job Briefing Verification Sheet ................. 1 Work /Datasheet/ Checklist Control List ............................. 1 Forms Use Reporting Sheet *......................................... 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l 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.
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O PORM 372 22 3442 l
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Y~ RERP-EXP PUZLIC SERVICE COMPANY OF COLORADO Issue 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 4 g
General This procedure provides guidance and maximum exposure criteria for use in the event of a severe radiological emergency at Fort St. Vrain where it may be necessary for members of emergency teams to exceed established quarterly or annual radiation exposure limits. The guidance contained herein is given as dose equivalent limits, as it is recognized that certain critical statien/ lifesaving functions may be required to be carried out under extreme radiological conditions, and that, in the context of an accident situation, these actions may require emergency workers to receive doses in excess of occupational limits. These exposures may be justifiable if it may be determined that benefits to society are being achieved, and that every reasonable effort is being made to maintain emergency workers doses as low as reasonably achievable.
1.0 Criteria for Implementation This procedure shall be implemented only under the ensuing conditions:
1.1 The need to exceed established radiation exposure limits to save a life or minimize the consequences of an incident has been identified.
1.2 A radiological survey and/or installed radiation monitor h'~)s readings (airborne and area) have been utilized to provide a projected whole body dose required to complete the work.
2.0 Procedure Table 1 of this procedure summarizes the radiological dose equivalent limits for an emergency situtaion as defined in Section 1 of this procedure.
2.1 Personnel accepting emergency assignments where they may receive radiation dose equivalents in excess of occupational limits shall be volunteers of good health (preferably males over 45 years of age).
2.2 Emergency personnel volunteering for these missions shall be made broadly familiar with the potential risks associated with the projected radiation exposure.
2.3 Any such exposure under the provisions of this procedure are to be limited to once in a lifetime.
2.4 Personnel shall not enter any area where dose rates are unknown or unmeasurable.
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2.5 Personnel shall be provided high and low range pocket dosimeters suitable for measurement of anticipated exposure levels, in addition to permanently recording film badges and any extremity monitoring devices deemed appropriate by the Senior Health Physics Representative at the Technical Support Center or a delegated Health Physics Technician at the Personnel Control Center.
3.0 Resoonsibilities 3.1 Personnel Control Center (PCC) Director The PCC Director is responsible to authorize volunteers selected for high exposure assignments (in excess of occupational dose equivalent limits) to receive such doses and to ascertain that documentation of such authorization is performed on Datasheet 1, provided herein. He shall confer with the most Senior Health Physics Representative at the TSC, or his designee, prior to dispatching any such volunteer personnel from the PCC with regard to proper personnel monitoring devices and protective clothing / devices required for the assignment.
3.2 Senior Health Physics Representative (TSC)
The Senior Health Physics Representative at the TSC will J be responsible to assess monitoring data with regards to emergency team assignments and evaluate the projected assignment dose and any requirements for stay time, personnel monitoring, and protective clothing and equipment. In conjunction with these responsiblities, the senior Health Physics representative shall also consider the need for radioprotective drugs (see RERP-THYROID).
3.3 Technical Support Center Director The TSC Director has overall responsibility for the direction of onsite emergency activities, and, as such, must be resconsible for determining the need for elevated-risk assignments where occupational dose limits would be exceeded.
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A RERP-EXP 5 PUBLIC SERVICE COMPANY OF COLORADD Issue 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 g
'd 3.4 Personnel Accountability and Exposure Controller (PCC)
When requested by the PCC Director, assure proper documentation of projected dose, staytimes, and protective / dosimetric equipment requirements specified by the senior Health Physics representative at the TSC.
Perform job briefing and sign Datasheet 1.
4.0 References 4.1 Manual of Protective Action Guides and Protective Actions f or Nuclear Incidents, U.S.E.P. A. , June 1980.
4.2 10CFR20, Code of Federal Regulations.
4.3 NCRP 42, Radiological Factort, Affecting Decision-Making in a Nuclear Attack, National Council on Radiation Protection and Measurements, 1974.
5.0 Referenced or Supporting Procedures 5.1 RERP-ORG, FSV Emergency Organization and Responsiblities 5.2 RERP-THYROID, Thyroid Blocking Agent Administration 5.3 RERP-DOSE, Offsite Cose Calculation Methodology v RERP-PCC, Personnel Control Center Procedure 5.4
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- 1. Emergency dutles not related 5 Ree 25 Ree to protecting egulpeent, personnel, or the pulatic. "
- 2. Prevent extensive equipment 25 Ree (planned) 125 Ree damage, rurther escape ** effluents, 12 Ree (unplanned) or contrul fires.
- 3. Lifesaving Missions, e.g., search 75 Ree Unileited**
and rescue or injured people, prevent conditions that would injure nualpers or people.
- Respiratory protection will see provided as necessary.
- Although respirators and potasslue lodido blocks should be used where errective to control dose to coergency tese workers, thyrold dose may not be a tielting Factor for lifesaving elssion, m includes performing accident assessment, providing First ald, performing personnel decontaminetton, providing salpulence service, and providing medical treatment services.
A RERP-EXP 5 PUBLIC SERVICE COMPANY OF COLORADO Datasheet 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 2 ;
DATASHEET 1 JDB BRIEFING VERIFICATION SHEET
- Volunteers Names Date Time Destination Projected Dose O
- Complete one Job Briefing Sheet for each high exposure emergency team.
Comments
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FORMS USE rep 0RTING SHEET l 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 nave been utilized from this copy:
Werksheet Numbers Cecies Used Datasheet Numbers Copies Used g
V Checklist Numbers Copies 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 Sheet" for the affected procedure in the affected book.
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FORMS USE REPORTING SHEET (Continued)
COMMENTS Reported By:
Date:
l Nuclear Documents Specialist
- Date Received Date Replaced l* 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 V
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,j, FORT ST, VRAIN NUCLEAR GENERATING STATION Issue 2 l
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FORMS USE REPORTING SHEET l 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 Datasheet Numbers Copies Used O
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. When this form is received, it will be necessary to replace t
. the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book.
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PUBLIC SERVICE COMPANY OF COLORADO WS/DS/CL RERP-EXP lssue 2 FORT ST. VRAIN NUCLE AR GENERATING STATION
)' Page 3 of 3 O
FORMS USE REPORTING SHEET (Continued)
COMMENTS 1
Reported By:
i Date:
l Nuclear Documents Specialist Date Received Date Replaced
(
l* Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to A notify users that the procedure has been updated and that all V worksheets, checklists, and datasheets are present in the required number of copies.
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PUZLIC SERVICE COMPANY OF COLORADO Issue 11 RERP-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 8
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(\ TITLE: FORWARD COMMAND POST PROCEDURE l 1
ISSUANCE AUTHORIZED A w .a 74 BY WM 9%4M
" "C EF ECBVE agy gw PORc 5 8 0 AUG 2 - 1984 E TABLE OF CONTENTS Section Description Page 1.0 Cri te ri a for Imo1 ementati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Procedure.................................................... 3 3.0 Re s po n s i b i l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4.0 References .................................................. 7
. . _ _ 5.0_ Referenced or Succorting Procedures.......................... 7 O- F49 3e 1 'oc tioa ">P 2 Figure 2 Forward Command Post Fl oor P1 an. . . . . . . . . . . . . . . . . . . . . . . . 1 Figure 3 Forward Command Post Organization...................... 1 Figure 4 Emergency Organization ................................ 1 Figure 5 Site Sector Map........................................ 1 Figure 6 Aerial View Map of Plant .............................. 1 Attachment 1 Support Equipment / Materials .................... 1 l Datasheet 1 Forward Command Post Radiological Status Board.................................... 1 l l Datasheet 2 Plant Status Board.............................. 1 Checklist 1 Corporate Emergency Director's Checklist. . . . . . . . 1 )
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- - 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, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
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[v) ESTABLISHING THE FORWARD COMMAND POST I
1.0 Criteria for Implementation l When the FSV Radiological Emergency Response Plan (RERP)
! requires augmentation of resources, generally for an ALERT or higher emergency classification, the Corporate Emergency Director (CED) shall activate the Forward Command Post (FCP).
2.0 Procedure 1
l 2.1 The Forward Command Post (FCP) shall be established in the garage of the PSC Fort Lupton Service Center. (See Figure 1)
The FCP functions as the control and coordination center for on-scene state / local / federal emergency response forces, and communicates with the State EOC and with the Weld County EOC (Weld County Communication Center) for effective coordination of county forces. A senior representative of D0 DES is responsible for control and coordination of FCP emergency response activities.
2.2 Corporate Emergency Director (Checklist 1) 2.2.1 The CED will perform personnel accountability to assure that the FCP staffing requirements can be met. If not during normal working hours, those personnel required to man the FCP are notifed by telephone. It is the responsibility of the CED alternate to ensure that the notifications are l made. Refer to RERP PHONE LIST or RERP-HOME for l the FCP call list for instructions, names, and phone numbers.
2.2.2 Assumes overall command of PSC emergency operations .
and is the prime contact between-Fort St. Vrain and governmental authorities.
. 2.2.3 The CED shall establish communications and verify
( that primary and secondary communcation links to the Technical Support Center (TSC) are available.
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v 2.3 Station Technical Liason The Station Technical Liason shall provide technical interpretation, assistance, and guidance, as requested, throughout the course of events. He shall review the incoming plant data and advise the Corporate Emergency Director as to the trend of the accident. Additionally, he shall assist state / local / federal FCP personnel 11, areas of plant technical data.
2.4 Radiological Assessment Coordinator The Radiological Assessment Coordinator shall evaluate or perform the offsite dose consequence assessments (see RERP-DOSE), provide technical advice to the Corporate Emergency Director with regard to Protective Action I recommendations (see RERP-PAG), and shall assist the Senior Health Physics representative at the TSC with decisions regarding emergency exposure limits for emergency team members (see RERP-EXP), the need for administration of thyroid blocking agent (see RERP-THYROID), and receive / interpret field monitoring data (see t
RERP-FIELD). He shall also perform core damage evaluations as required (see RERP-CORE).
(] 3.0 Responsibilities 3.1 Corporate Emergency Director 3.1.1 The CED is responsible for direction and coordination of:
a) PSC onsite and offsite emergency functions.
b) Interface between PSC and local / state / federal emergency response activities.
c) Transmission of plant status updates and radiological release data to the ECP and PSC Personnel at the State EOC and media center persennel, and briefing the PSC FCP staff.
~ d) Notification of state and local agencies concerning recommended protective actions.
e) Provision of administrative, technical, and logistical support to station emergency operations via the ECP.
l f) Continuity of emergency organization resources.
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RERP-FCP PUBLIC SERVICE COMPANY OF COLORADO Issue 11
. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 8 q
J 3.1.2 The CED provides direction to, and coordination for, the TSC Director and the Nuclear Engineering Manager (assigned to the State EOC). He will coordinate additional headquarters support via the Executive Command Post (ECP).
l 3.1.3 Terminates the emergency or de-escalates the i emergency category according to the status of the l event. Deactivates the FCp when the emergency has l been brought to a recovery phase. May also l deactivate upon de-escalation to an Unsual Event l category.
3.1.4 Acts as Recovery Director per Section 9.0 of the RERP.
3.2 Communications Personnel 3.2.1 Establish communications with the TSC. (See Figure 2 for Emergency Kit and phone jack locations).
Primary l
Telephone (open line) __
p V Secondary PSC Radio Verify secondary system.
3.2.2 Inform the TSC that the FCP is manned and ready.
3.2.3 Receive status of plant and emergency and assessment of condition and inform CED.
3.2.4 Request location of Personnel Control Center (PCC).
3.2.5 Communication is to be established with the Executive Command Post (ECP) and the State Emergency Operations Center (EOC). Inform the CED when accomplished.
a) Appraise them of the situation as directed by I the CED.
b) Inform them of the location of the PCC, should it be necessary to dispatch assistance to the plant.
FORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO Issue 11 page 6 of 8 FORT ST. VRAIN NUCLEAR GENERATING STATION g
V 3.2.6 Maintain communications flow between the TSC, ECP, and State EOC.
3.3 The FCP staff keeps an ongoing record (log) of all actions taken. The Radiological Assessment Coordinator will assign one of the clerical staff responsibility for l updating the FCP status boards at approximately 30 minute i intervals.
l Data for radiological updates is to be obtained from, and reviewed by, the Radiological Assessment Coordinator prior to posting. Datasheet 1 is l provided as a working copy for radiological status board updates. These sheets shall be retained for record l keeping purposes. Datasheet 2 will be provided by l Technical Liaison personnel to update Plant Status Boards.
3.4 Station Technical Liaison a) Provide assistance and substantiated data on l emergency status and conditions. Provide staff l assistant copies of Datasheet 2 for use in updating Plant Status Board, l
b) Coordinate company emergency response actions with those of state / local / federal agencies.
3.5 Media Relations Provide assistance to the FCP Public Information Team (PICT) in the preparation of news and related media releases.
3.6 Radiological Assessment Coordinator.
3.6.1 In coordination with the TSC Radiological Assessment individual, perform and/or evaluate a preliminary assessment of the actual and/or potential radiological release. Utilize this l
information to complete Radiological Status Board Update Sheets (Datasheet 1). Verify any l
calculations in question via manual or TI-59 calculations.
3.6.2 Based on the above assessment, identify and recommend to the Corporate Emergency Director the classification of the emergency (ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY) and recommended protective actions to reduce exposures to the general population (see RERP-PAG).
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RERP-FCP PUBLIC SERVICE COMPANY OF COLORADO Issue 11 FORT ST. VRAIN NUCLEAR GENERATING STATION page 7 of 8 l
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3.6.3 Monitor radiation levels and meteorological data, and provide the Corporate Emergency Director with l estimates of the dose to the general population based on actual releases and meteorology.
3.6.4 Obtain a 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> weather prediction from Stapleton Airport National Weather Service (refer to Outside Assistance Phone Numbers) and provide the FCP Director with estimates of the projected dose to the general population based upon plant conditions and foreseeable contingencies.
3.6.5 Assign a member of the clerical staff responsibility for posting updates to the FCP status board located outside the PSC staff area.
l Supply and review all radiological data to be posted.
3.6.6 Provide guidance to the TSC Senior Health Physics representative on matters regarding administration of thyroid blocking agent to site personnel (see RERP-THYROID).
3.6.7 Perform core damage evaluations as required (see RERP-CORE).
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(_) 4.0 References 4.1 FSV Radiological Emergency Response Plan 4.2 State Radiological Emergency Response Plan 5.0 Referenced or Suecorting Procedures 5.1 RERP-ORG, FSV Emergency Organization and Responsibilities 5.2 RERP-DOSE, Offsite Dose Calculations 5.3 RERP-EXP, Emergency Exposure Guidelines 5.4 RERP-FIELD, Field Monitoring Procedure 5.5 RERP-HOME, Home Packets for Offshift Notifications 5.6 RERP-PAG, Protective Action Guideline Recommendations 5.7 RERP-THYROID, Thyroid Blocking Agent Administration 5.8 EP-CLASS, Event and Emergency Classification Overview
. 5.9 RERP-SURVEY, Inplant/Onsite Radiological Monitoring 5.10 Fort St. Vrain Final Safety Analysis Report 4
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V SUPPORT EQUIPMENT / MATERIAL
'1. Communication equipment - telephones and radios
- 2. Fort St. Vrain Radiological Emergency Response Plan (FSV RERP)
- 3. State FSV Radiological Emergency Responae Plan (State RERP)
- 4. Local government emergency plans - Weld County Plan
- 5. Evacuation time study
- 6. Maps (See RERP implementing procedures RERP-DOSE, RERP-SURVEY, and RERP-PCC.)
a) Fort St. Vrain area and environ b) Sectors
! c) Regional d) Health Physics Survey Maps of FSV Buildings w) 7. Public Information Plan
- 8. RERP Implementing Procedures
- 9. Office supplies a) Writing tablets b) Pens, pencils, and erasers c) Chalk .
d) Criculator e) Graph Paper l 10. P & Is
- 11. FSAR
- 12. E Drawings (Electrical) l 13. I and C Drawings (Instrumentation and Control)
. 14. Technical Specifications
] 15. Administrative Procedures Manual
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- 16. Emergency Procedures
- 17. Medical Emergency Plan
- 18. Calculator / Printer
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. Datashest 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 11 Page 1 of 1 G
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PUBLIC SERVICE COMPANY OF COLORADO k t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 11 Page 1 of 2 m
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CHECKLIST 1 l
CORPORATE EMERGENCY DIRECTOR'S CHECKLIST l NOTE: All information is to be recorded by the Clerical Assistant.
Time
- 1. Fort Lupton PSC office notified of intent to occupy building.
- 2. Personnel Accountability I
a) Station Technical Liaison b) Radiological Assessment Coordinator c) Clerical Assistants d) Media Relations
, e) Additional personnel from outside agencies.
l O 1. Coioraeo oePartmeat of seaith a) Radiological monitoring, technical, and health units, as required b) Public information representative
- 2. State Division of Disaster Emergency Services 1
- 3. Weld County Sheriff's Office
- 4. Colorado State Patrol
- 3. Staffing requirements met.
- 4. Communications established with TSC.
- 5. TSC informed that FCP is manned and activated.
k E
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I PUBLIC SERVICE COMPANY OF COLORADO .C ek t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 11 Page 2 of 2 13 U
Time j 1
- 6. Status of emergency and assessment of plant condition received from TSC.
- 7. Staff briefing conducted.
- 8. Outside agency briefing conducted.
- 9. Location of PCC requested and received.
- 10. Communications established by ECP.
- 11. ECP appraised of plant condition and informed of location of PCC.
- 12. Communication established by State EOC.
- 13. State EOC appraised of plant condition and informed of location of PCC.
- 14. Initial Radiological Assessment (Actual) obtained Release Rate Curies Released Dose Rate Dose Received Protective Action Guide
- 15. Preliminary Radiological Assessment (Projected) obtained Release Rate Curies Released
. Dose Rate Dose Received Protective Action Guide
- 16. Meterological forecast obtained (12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />).
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PUBLIC SERVICE COMPANY OF COLORADO [jfF FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 11 Page 1 of 3 O
WORK /DATASHEET/ CHECKLIST CONTROL LIST Worksheet No. Title Number Copies None N/A N/A Datasheet No.
l 1 Forward Command Post Radiological Status Board 25 l 2 Plant Status Board 25 Checklist No.
1 Corporate Emergency Director's Checklist 2 e
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FORM 372 22 3643
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R F PUZLIC SERVICE COMPANY OF COLORADO g, j FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 11 Page 2 of 3 l
' 1
,e FORMS USE rep 0RTING SHEET !
l 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:
Wnrksheet Numbers Copies Used O
~
Datasheet Numbers Ceo4es used Checklist Numbers Copies 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 j . , the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book, d
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A FORM 372 22 3643
N RERP-FCP
. PUZLIC SERVICE COMPANY OF COLORADO WS/DS/CL l FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 11 l Page 3 of 3 O
FORMS USE REPORTING SHEET (Continued)
COMMENTS Reported By:
Date:
Nuclear Documents Specialist Date Received Date Replaced
- Nuclear Documents Specialist will transmit this form to the
.. originating individual / department upon completion of this form to O
notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.
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' RERP-FIELD PUBLIC SERVICE COMPANY OF COLORADO Issue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 6 f
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TITLE: FIELD MONITORING PROCEDURE ISSUANCE AUTHORIZED 7"/7 y BY MMAM PORC EFFECTIVE REVIEW m 5 8 0 N 31 1984 DATE b b* k Section Description Page General ........................................................... 2 1.0 Crite ri a For Impl emen ta ti on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.0 Procedure..................................................... 2 3.0 Re s p o n s i b i l i ti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4.0 References ................................................... 6 5.0 Referenced or Supportino Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . . 6 Table 1 Instrument Check Source ......................... 1 Worksheet 1 In-field Sampling Data........................... 1 Datasheet 1 In-field Sampling Results ....................... 1 Datasheet 2 Field Monitoring Team Deployment................. 1 Checklist 1 Equipment Operability ........................... 1 Work / Data sheet /Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Forms Use Reporting Sheeta......................................... 2
- ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN i
ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l 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 TA3 BED SECTION FOLLOWING EACH PROCEDURE.
k 4-FORM 372 22 3M2
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PUZLIC SERVICE COMPANY CF CCLORAD3 RERP-FIELD Issue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION page 2 of 6 ,
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General Emergency offsite radiological monitoring, in the event of a radiological emergency at Fort St. Vrain, will be performed by FSV monitoring teams until field monitoring teams from the Colorado Department of Health (C0H) respond to the scene. The data collected by these field teams will be relayed directly to the Technical Support Center to aid in the assessment of offsite radiological consequences. The TSC will transmit field measurement data to the Forward Command Post for use by PSC and state radiological assessment personnel.
The PSC Field Monitoring Teams are deployed from the Personnel Control Center. The teams are in radio communication with the senior Health Physics representative at the TSC and report directly to him with all data. In addition, the field teams are directed by the senior Health Physics representative after initial deployment.
1.0 Criteria For Implementation The Field Monitoring Teams are assembled at the Personnel Control Center anytime that the full FSV emergency organization is activated. The initial deployment of these teams is at the direction of the TSC Director. ..
Il v
2.0 Procedure The Field Monitoring Teams shall be composed of a driver and an HP Technician. There is provision for the deployment of two
, field teams, one with survey responsibilities near site, primarily out to the site Exclusion Area Boundary (EAB), and the other from the EAB to the outer perimeter of the plume exposure Emergency Planning Zone (EPZ), approximately a five (5) mile radius.
2.1 The decision to deploy Field Monitoring Teams is the responsibility of the TSC Director. He shall make this decision, based upcn projected offsite doses, as advised by the TSC Radiological Assessment individual, and the consideration of the ability to effectively assess these dose rates in the field (lower level of detection, weather conditions, etc.) as advised by the senior Health Physics representative at the Technical Support Center.
2.2 Each field monitoring team leader shall check required survey instrumentation for operability per Checklist 1.
O PORM U2 a 22 3643
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PUZLIC SERVICE COMPANY OF COLORADO fEW FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 6 O
v 2.3 The monitoring teams shall assure that all required ir.struments, equipment, and supplies are present in the survey vehicle prior to departure. This equipment shall include:
- RM-14 or RM-15 l
- SAM-2 scaler
- 5 piece SAM-2 shield and detector
- Air sampler with Silver Zeolite cartridges and pre-filters
- Field Use Maps
- Wipes
- Pencil
- Field Radio
~~
- Copy of RERP-FIELD O.
- Spare 3atteries 2.4 The proper selection of dosimetry and protective equipment is the responsibility of the senior Health Physics representative at the TSC. He shall utilize calculated or estimated parameters to determine potential exposure and estimated stay times (see Datasheet 2). This information shall be relayed to the PCC director for use in the briefing of the field monitoring teams. ,
NOTE: Two separate copies of Datasheet 2 may need to be completed if projected conditions differ for the EAB and EPZ monitoring teams.
2.5 Field Monitoring teams act under the direction of the I senior Health Physics representative after their initial -
! deployment from the PCC. The Health Physics Technician assigned to each team shall ensure that good health physics practices are employed while in the field. This is to include:
l
- Keeping survey instruments (as appropriate to radiation levels) operating at all times to evaluate ambient radiation conditions and plume location; I
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PoItM 372 22 3643 l
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EW PUZLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 6 im
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- Wearing all protective clothing and equipment prescribed by the senior Health Physics representative at the TSC;
- Spending as little time as necessary in elevated radiation exposure areas; and,
- Travelling outside of predicted plume trajectory whenever possible, te minimize exposure and spread of contamination.
2.6 The senior Health Physics representative shall communicate the sampling location designations by utilizing easily recognizable landmarks, in particular, the intersections of county roadways (e.g., Weld County Roads 19 and 38, the confluence, meteorological monitoring towers, etc.).
2.7 The Field Monitoring Teams, in the interest of dose reduction and facilitating rapid data transmission, may transmit raw field monitoring data directly to the senior Health Physics representative at the TSC, where
- calculations may be performed. Worksheet 1 is provided l for both data collection and calculations.
2.8 The Field ' Monitoring teams shall collect the following s data at each sampling location:
Ambient Radiation Level (mrem /hr)
I-131 Air Concentration (vCi/cc)
- Gross Particulate Concentration (cpm /cc) 2.9 The senior Health Physics representative at the Technical Support Center shall accumulate data on Worksheet I and complete all required calculations. After calculations are completed, data should be recorded on Datasheet 1, a partial scale survey map of the plume exposure EPZ. This map should be utilized in concert with dose projection results to keep the TSC Director and FCP personnel abreast of current data and dose assessment results.
2.10 Operation of Eber11ne SAM-2 counters is outlined below.
- Take a one minute background count and record on Worksheet 1 (or transmit to TSC via radio communication).
- Collect Air Sample on Silver Zeolite Cartridge
. (HPP-12) and determine sample volume.
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PORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO -]Ew FORT ST. VRAIN NUCLEAR GENERATING STATION page 5 of 6 O
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. Load cartridge in detector shield and close shield door.
- Take a one minute count of air sample cartridge and record on worksheet 1 (or transmit to TSC via radio communication).
I-131 concentration (pCi/cc or Ci/m')
- CPM B
) x 1.0E-10 x H cc V Where:
CPM 3 = Gross counts ;;er minute of sample CPMB = Counts per minute of background 1.0E-10 = Unit Conversion Factor V = Sample Volume in ft 8 15 = Normal air sample volume 3
(3 ft / min x 5 min) 2.11 At the conclusion of FSV field monitoring activities, the e driver shall-return the vehicle, passengers,'and contents
's to the Personnel Control Center, inform the PCC Director of the team's arrival, and request a contamination survey of the vehicle, its passengers, and its contents.
Decontamination shall be handled in accordance with FSV Health Physics Procedures (HPP-10 and HPP-11) with area posting and control as required in accordance with HPP-9.
3.0 Responsibilities 3.1 Health Physics Technician (Field)
Perform surveys as directed by the senior Health Physics representative at the TSC. Ensure that good health physics practices are employed throughout the course of field monitoring efforts.
3.2 HealthPhysicsTechnician(PCC)
Perform contamination surveys as required on returning field monitoring personnel and equipment.
3.3 SeniorHealthPhysicsRepresentative(TSC) l Assume overall responsibility for t'he conduct of field l monitoring activities. Direct field teams to appropriate l
sampling locations utilizing TSC dose projections and current meteorological conditions as a basis.
. I PORM ,* f2 22 3843
4 PUBLIC SERVICE COMPANY OF COLORADO (PFELD FORT ST. VRAIN NUCLEAR GENERATING STATION page 6 of 6 m
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3.4 TSC Director Assume ultimate responsibility for all activites centered from site, including the initial dispatch of field l monitoring teams.
3.5 PCC Director Brief departing monitoring teams of recommended protective actions, dosimetry, and estimated stay times as determined by senior Health Physics representative at the TSC.
Ensure adequate contamination survey (and decontamination) of returning field monitoring personnel and equipment.
4.0 References 4.1 Instruction manuals for Eberline SAM-2 counting equipment.
5.0 Referenced or Supoorting Procedures 5.1 RERP-EXP, Emergency Exposure Guidelines.
5.2 RERP-DOSE, Offsite Dose Calculation Methodology.
5.3 RERP-ORG, FSV Emergency Organization and Responsibility, s
5.4 RERP-TSC, Technical Support Center Procedure.
5.5 RERP-PCC, Personnel Control Center Procedure.
5.6 HPP-9, Establishing and Posting Controlled Areas.
5.7 HPP-10, Area and Equipment Decontamination 5.8 HPP-11, Personnel Decontamination.
5.9 HPP-12, Portable Air Sample Collection and Analysis.
5.10 HPP-66, Operation of Portable Survey Instrumentation.
5.11 HPP-67, Calibration and Operation Procedure for the Eberline SAM-2 Stabilized Assay Meter.
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F PUBLIC SERVICE COMPANY OF COLORADD $~FELD FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 1 of 1
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TABLE 1 l INSTRUMENT CHECK SOURCE l OA/ENG PCC CHECK SOURCE l CS-137 SCN 103 l INSTRUMENT ACCEPTABLE RANGE l RM-14/15 with HP-210 2.100 - 6,300 cpm l PIC-6A 0.5 - 1.5 mrem /hr l R0-2 0.25 - 0.75 mrem /hr l R0-5A 0.15 - 0.45 mrem /hr l E-400 0.5 - 1.5 mR/hr l E-500 0.4 - 1.2 mR/hr l TRAINING PCC CHECK SOURCE l Ba-133 SCN 107 l INSTRUMENT ACCEPTABLE RANGE l RM-14/15 with HP-210 15,000 - 45,000 cpm l PIC-6A 5.5 - 16.5 mrem /hr l R0-2 4.5 - 13.5 mrem /hr l R0-5A 3.0 - 9.0 mrem /hr l E-400 7.5 - 22.5 mR/hr l E-500 6.5 - 19.5 mR/hr l H.P. ACCESS AREA CHECK SOURCE l Cs-137 SCN 80 Cs-137 SCN 75 l INSTRUPENT ACCEPTABLE RANGE l RM-14/15 with HP-210 19,000 - 57,000 cpm l PIC-6A 3.3 - 9.8 mrem /hr l R0-2 1.3 - 3.8 mrem /hr l R0-5A 1.1 - 3.3 mrem /hr l E-400 4.5 - 13.5 mR/hr l E-500 4.0 - 12.0 mR/hr l NOTE: Center active detector area directly over the source.
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FORM 372 22 3643
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WORKSHEET 1, IN-FIELD SAMPLING DATA
- 1) Date: / /
- 2) Time: :
- 3) Field Team: ( ) EAB ( ) EPZ (CheckOne)
- 4) Sample Number:
- 5) Sample Location (describe):
- 6) Ambient Radiation Level: mrem /hr
- 7) Air Sample Data:
a) Flow Rate ft /8 min b) Collection Time minutes c) Volume Collected O 7a) ft*/ min x 7b min = ft-d) Volume Correction Factor (VCF):
15.0 ft*
=
7c) ft'
- 8) Particulate Activity Concentration:
a) Particulate Filter Count Rate = cpm
.t) Background Count Rate = cpm l c) Net Count Rate 1
1 8a) cpm - 8b) cpm ~= cpm d) Gross Beta Activity l
[8c) cpm x 7d) ] = pCi/cc I 2.36E+11 1
4 FORM 373 22 3443
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PUBLIC SERVICE COMPANY OF COLORADO j I f3 Issue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 2 i
- 9) 131I Activity:
a) Cartridge Count Rate = cpm b) Background Count Rate = cpm c) Net Count Rate 9a) cpm - 9b) cpm = cpm d) 1311 Activity 9c) cpm x 1.0E-10 x 7d) = uti/cc O
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LD PUBLIC SERVICE COMPANY OF CELCRADD hg } FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 5 of 5 Ov Datasheet 1 - In-field Sampling Results Sample i Ambient I Gross l I-131 I Location Number i Radiation i Particulatel Air l(Use simple (See Work- I Levels l Activity i Concentra- I description) sheet No. 1)I (mR/br) I (cpm /cc) I tion l I I I (uci/cc) i I l i l 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 1 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...___ _ _ _ . 1 I l l l l l l l l l l l l l l l l l l l l l l I I l l 1 1 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 I I I I I I I I I I I I I I I I I I I l i I I I O
4 PORM 372 22. M42
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RE D PUBLIC SERVICE COMPANY OF COLSRAD9 , 2 FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 6 Page 1 of 3 g U Datasheet 2 Field Monitoring Team Deployment (To be completed by senior HP representative at the TSC)
- 1) Area to be surveyed
- 2) Route to be taken
- ' -~~- ~
~
- 3) Calculated or estir;ated parameters "
O a) General Radiation Level (mrem /hr) l b) Airborne Activity Level (yci/cc)
- 4) Projected Time to complete survey (hr)
- 5) - Projected Exposure l 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) G v 4 POM M 3 72 + 2J . 344J
. , . . . . . . . . ~ . . . - . . . . . . . . . . . . . . . . _ . - . . , n. .. . . . . . _ . . . . .
4 RE FIEW PUBLIC SERVICE COMPANY OF COLORADO , h, 2 FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 6 Page 2 of 3
- 7) Team Members:
- 8) Dosimetry requirements:
Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range
?) 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 1 PORM 373 + 22
- 2443 ,
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RERP-FIELD PUBLIC SERVICE COMPANY OF COLORADO Datasheet 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 3 of 3 O (V
- 10) Comments:
l a) Save used filters and cartridges for Radiochemistry l analysise l b) Leave the emergency vehicle running while in the field and l upon return to avoid battery discharge. l I I l O D 4 . PORM 372 22 3643 i
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LD PUBLIC SERVICE COMPANY OF COLORADO k t} j FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 1 of 2 l O d \ CHECKLIST 1 l l EQUIPMENT OPERABILITY (To be completed by field monitoring team leader.)
- 1. RM-14 or RM-15 Verify that RM-14 or RM-15 exhibits proper response for given instrument check source (see Table 1).
l 2. R0 SA/D or RO 7 with RO 7-LD probe Verify that PIC-6A or equivalent instrument exhibits proper response for given instrument check source (see Table 1).
- 3. SAM-2 i The SAM-2 is to be set up in the emergency vehicle, using 12V
( DC, and a routine performance check performed as follows:
- 1) Allow a two-minute instrument warmup and set switches to, O setti=9 Postee o# iastro eat cover-
- 2) Take a one-minute background count on the empty shield.
(CB) l 3) Carefully place SCN 107.00 (133 Ba check source) in the sample holder. Slide the shelf into tne assembly and close the door on the lead shield.
- 4) Take a one-minute count on the source. (CS) l
- 5) Obtain the net count rate of the source by subtracting CB from C5.
- 6) Compare the net count rate with control limits established durir,g calibration. These ' values are found on the instrument cover.
- 7) If instrument response is not within acceptable range, I contact senior Health Physics representative at the TSC for further action.
- 8) Leave instrument running after operability check.
o - PORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION
$-[E Issue 6 t
Page 2 of 2 O
- 4. Air sampler Verify that the air sampler is operable by setting it up in the emergency vehicle and running unit for approximately one minute at proper flows.
O l l O 4 FORM 372 22 3643
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4 F PUZLIC SERVICE COMPANY OF COLORADO f FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 ) Page 1 of 3 O Work /Datasheet/ Checklist Control List Worksheet No. Title Number Copies 1 In-Field Sampling Data 15 Datasheet No. 1 In-Field Sampling Results 3 2 Field Monitoring Team Deployment 3 Checklist No. O 2 ea#49=e#t over dilits a 1 l l PORM 372 22 3643
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l R D PUBLIC SERVICE COMPANY OF COLORADO g, l .. FORT ST VRAIN NUCLEAR GENERATING STATION Issue 6 Page 2 of 3 I l FORMS USE REPORTING SHEET l 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 h"nbers Copies Used Checklist Numbers Cootes 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 O Sheet" for the affected procedure in the affected book. t I PORM 372 22 - 3643
F D PUBLIC SERVICE COMPANY OF COLORADO f FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 3 of 3 O v FORMS USE REPORTING SHEET (Continued) l l COMMENTS Reported By: Date: l Nuclear Documents Specialist
- Date Received Date Replaced l" 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 O' worksheets, checklists, and datasheets are present in the required number of copies.
O l.$ PORM 372 22 3643 l . _... _ .=,...-r. ._ ~~~a.. _- -. -.- ---...- .. - .
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Issue 12 FORT ST. VRAIN NUCLEAR GENERATING STATION page 1 of 5
\
TITLE: HOME PACKET FOR OFF-SHIFT NOTIFICATIONS ISSUANCE A W . l. 9 4 AUTHORIZED BY WM Nc4Ur PORC EFFECTIVE REVIEW PbRc 5 8 0 AUG2- 1984 DATE b- b ~ b Sections Description Page 1.0 Criteria for Imolementation.................................. 3 2.0 Procedure.................................................... 3 3.0 Re s oo n s i b i l i ti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4.0 References .................................................. 5 5.0 Referenced or Suoporting Procedures.......................... 5 Figure 1 Notification Fanout.................................. 1 O. 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 Table............................ 1 Table 7 GENERAL EMEP.GENCY 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
- O Att chmeat 4 noti fic ti o# or emerse#cv eve =t . . . . . . . . . . . . . . . . . i FORM 372 22 3642
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PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Issue 12 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 5 O Attachment 5 ECP Director's Call L1st........................ 1 Attachment 6 FCP Di rector's (CEDs) Call Li st . . . . . . . . . . . . . . . . 1 Attachment 7 PCC Di rector's Cal l Li st. . . . . . . . . . . . . . . . . . . . . . . . 1 Attachment 8 State EOC Call List ............................ 1 Attachment 9 TSC Di rector's Call Li st. . . . . . . . . . . . . . . . . . . . . . . . 1 Attachment 10 Facility Directors / Alternates .................. 1 l l O l l O F OR M 372 22 - 3643
- _ . - -.__m . -__
H PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 5 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 I 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 2.1 ANI Notifications Notification to American Nuclear Insurers (ANI) is Q required under five (5) general categories listed below:
- Losses believed to be near, or above, the deductible (550,000);
- Incidents where fixed fire protection systems have operated under other than test conditions;
- Incidents where prompt assistance could help prevent further less 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 I to this procedure. Additional plant management contacts may be ' made utilizing Table 1 for reference. p O l ro m an.ss-sus i
RERP-HOME
'PUBLIC SERVICE COMPANY OF COLORADO Issue 12 FORT ST. VRAIN NUCLEAR GENERATING STATION page 4 of 5 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 5. When these events transpire, 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 C Notification to both offsite authorities and the NRC within fifteen (15) minutes 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 l EVENT are reported to the state utilizing the notification I format of Attachment 3. The plant management contact shall assist the completion of this form. If the event is () an ALERT, or higher, RERP event, Attachment 4 shall be completed. The Shift Supervisor may consult with plant management regarding incident classification. 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. 2.3.2 ALERT or Higher RERP Event For an ALERT cr higher RERP event, the notification , fanout shown in Figure 1 of this procedure shall l occur to assure prompt facility activation and I 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 Attachments 5-9, herein. The Facility Director primary and alternates are shown on Attachment 10. (3 G 1 FORM 372 22 3M3
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Issue 12 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 5 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 5.0 Referenced or Supporting Procedures 5.1 RERP-PHONE LISTS 5.2 RERP-CR, Control Room Procedure O
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l l F ORM 372 22 - 3643 1 I l . - l
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P PUBLIC SERVICE COMPANY OF COLORADO hck 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 1 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 Department. l Subsequent l Date/ l l l Contacts l Time i Remarks l l Plant Management l l l l(Contact 1) l l l l Supt. of Oper. l l l l218: 532-3489 I I l l Station Manager l l l l201: 442-3829 I I l l Administrative / l l l l Tech. Serv. Mgr. l l l l202: 663-2363 l l l l Manager, Nuclear l l l l Production l l l l200: 833-4092 l l l l Radiation Pro- l l l ltection Manager l l l l203: 663-1230 l l l O ivice eresideas. l Production i l i l i l l571-7305 l l l l797-4122 l l l l Media Relatior.s l l l l Bob Burns l l l 1571-8481 l l l 1759-9740 l l l l or l l l l Gary Reeves l l l l571-8479 l l l 1424-4958 l l l l or l l l lMarily Mora l l l l571-8462 l l l l694-2369 I I l l ARC l l l
!G.L. Plumlee, IIII l l l490; 776-9541; l l l l l Pager: 890-2225I I l
- Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. In these cases, utilize the exchange in parentheses.
FORM 372 22 3643 J
RE HOME PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 1 TABLE 1 PLANT MANAGEMENT CONTACTS
- Page Plant Home Phone Ext. Phone Supt. of Operations 890-0558 218 532-3489 Station Manager 890-0698 201 442-3829 Admin./ Tech.
Serv. Manager 890-0810 202 663-2363 Mgr. Nuclear Prod. 890-0699 200 833-4092 Rad. Protection Manager 890-1775 203 663-1230 Vice Pres., Prod. N/A 797-4122, 8-571-7305 659-1180
~O l l
- Listed in order of preferred contact sequence. i I
l l l l O-n FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO @-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION IS$ye J2 Page 1 of 4 b l TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT l 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.
sulted in the plant, including its principal safety barriers, being seriously degraded - or being in an unanalyzed condition tFat significantly compromises plant - safety. p 2. Any event or condition 2. Reactor scrams, loop shutdowns, Q that results in manual or automatic and automatic starting and 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. I l C) P OR M 372 22 3643
R "" PUBLIC SERVICE COMPANY OF COLORADO a FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 4 (D v TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiating Event
- 3. Any event or condition 3. a) During refueling operations, that alone could have a .01Ap 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 puli-to-lock. Setpoints not
of radioactive reset.
s material; or d) Loss of HEPA filtration. d) mitigate the con-sequences of an accident. l l O P OR M 3 M 22 3&Q
RE -H E PUBLIC SERVICE COMPANY OF COLORADO , e FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 4 TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Tyoical Indication Initiating Event
- 4. a) Any airborne radio- 4. As determined by analysis active release that and evaluation.
exceeds 2 times the applicable cor. centra-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 i 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. I l the transport of a radioactively contam-1 inated person to an ! offsite medical facility for treatment. i 1 PORM 372 D 3&C
l
. l l
RE HOME PUBLIC SERVICE COMPANY OF COLORADO , l FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 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) 011 or chemical spill which could reach the South Platte River or St. Vrain Creek and which is therefore reportable to the EPA. O O e i FORM 372 22 300
RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Table 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 3 0 l l TABLE 3 NON-EMERGENCY EVENTS: ONE-HOUR REPORT I Event Typical 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
- minimum, by a senior i s licensed operator.)
4 , O PORM 372 3643
RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Table 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 3 TABLE 3 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical Initiating Event f
- 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 w that is outside excess of design the design basis limits with failure
'of the plant; or to trip plant.
- 2. Winds experienced in excess of FSAR design levels.
c) Ir a condition c) As determined. not covered by the plant's operating and ' emergency , procedures. 1
- 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 l significantly hampers plant personnel from site personnel in the completing requisite performance of duties assignments. necessary for the safe operation of the plant. O R> FORM 372 22 M43
PUBLIC SERVICE COMPANY OF COLORADO RE H E FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 3 l TABLE 3 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical Initiatino 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 G gas releases, or in excess of 10 CFR 20 V radioactive releases. Appendix B, Table I. O FORM 372 22 - 3643 l
RE HOME PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 4 b, TABLE 4 j NOTIFICATION OF UNUSUAL EVENT Event Indication
- 1. Any unplanned radio- 1. Alarms on:
logical release to RT 7312 ! the Reactor Building CAM (s) l 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 i Specification limits. b) As determined by l 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. I l 1 FORM 372 22 - 3643
RE H E PUBLIC SERVICE COMPANY OF COLORADO , FORT ST VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 4 O v 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 (50P 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.
~7'_")% % 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
V PORM 372 22 3643 l
1 RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Table 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 4 A V 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. (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-LCO 4.5.1
- 2) Steam / Water Dump System - LCO 4.3.3
([]) FORM 372 22 3443
R PUBLIC SERVICE COMPANY OF COLORADO a FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 4
~'h (V
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 - LCO 4.2.6, LCO 4.10.1-
-- LCO 4.10.5 - - - - -
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, an_d RT 73437-1; or c) RT 73437-2 and-RT 4801; or d) RT 6212 ag RT 6213. l NOTE: Use ELCO 8.1.1 Technical Specification Limits as basis. O PORM 372 22 3643 l .
RE HOME PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 5 (3 V TABLE 5 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 (Smrem/hr) accompanied by 230 Kv OCB trips and-RAT undervoltage/ loss -~~
-~ ~ --
~
s , 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 l 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. l FORM 372 22 3643
- n. .
RERP-HOMC PUBLIC SERVICE COMPANY OF COLORADO Table 5 l FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 ! Page 2 of 5 7-~. d TABLE 5 ALERT Event Indication
- 5. Loss of offsite power and 5. 230 KV OCB trips and RAT vital onsite AC power undervoltage/ Toss of power alarm for up to 30 minutes. accompanied by 4 KV bus undervoltage 480V bus under-voltage, af 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 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
, These times are LOFC from 100% power. Times may be l l correspondingly longer for lower power levels (See LCO 4.2.18). i O I c om u an m42
R " PUBLIC SERVICE COMPANY OF COLORADO a e FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 5 (aD TABLE 5 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 pC1/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 l 27.0 x 10 pCi/cc I-131.
~
C f) RT 4802 indicating 2 7.0 x 10 pCi/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. As observed or reported.
compromise. FOR M 372 22 - 3643
m PUBLIC SERVICE COMPANY OF COLORADO RERp-HOME
. Table 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 5 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 1 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: p) n-. 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, eith control of shutdown systems established from local stations.
(Control room integrity breached). O F OR M 372 3643 l
HOME PUBLIC SERVICE COMPANY OF COLORADO (E FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 5 of 5 O a l TABLE 5 i ALERT Event Indication
- 16. All alarms 16. Control room observation.
(annunciators) lost I for more than 15 minutes and reactor is not E tdown; or, plant transient experienced while all alarms lost. (Parameterindication still functional.)
- 17. Other plant conditions 17. As deemed necessary by -
warranting precautionary Shift Supervisor. activation of the PCC, TSC, and FCP. O l l l F Om M 372 22 - 3643
~ ~ ~ ~
E H ME PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 4 I v 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. l 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 O
ovea- eecre sias Re ctor pressure.
- 4. Determination of inability 4. 230 KV OCB trips a_nd n RAT to restore onsite AC undervoltage/ loss of power power. alarm accompanied by 4Ky bus undervoltage, 480v bus undervoltage, and Diesel l
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 .0 lap at 220*F.
'6. Major damage to spent 6. a) Visual observation.
l fuel due to severe cask l damage resulting in release b) area radiation monitor of radioactivity to plant alarms. environs. O FORM 372 22 3643
^ ~ ~ " "
PUBLIC SERVICE COMPANY OF COLORADO y,E HlME FORT ST VRAIN NUCLEAR GENERATING STATION lssue 12 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) VaricJs alarms according to atfected 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 p's corresponding to concentration indications greater than 50 mrem / on:
hr or 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 pC1/cc 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 8 pCi/cc b) These dose rates are mixed noble gasses.
projected based on other plant parameters or are measured in the environs. l
- 9. Imminent loss of physical 9. Situation evident.
control of the plant due to security breach. (Response detailed in Station Security Plan.) O l l FORM 372 22 3643
RE HOME PU LIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 4 A V TABLE 6 SITE AREA EMERGENCY Event Indication
- 10. Severe natural phenomenon 10. I being experienced or '
projected (with plant not 1 in cold shutdown), such as; a) earthquake greater a) Seismic Recorder Operate i than Safe Shutdown alarm with indication of Earthquake ground motion greater than 0.10g horizontal or greater than 0.067g vertical, b) flood greater than b) As reported or observed. design levels O V c) winds in excess of c) average wind velocity 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 1
] (OBA #2) radiation alarms.
i ! FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO , "!" FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 4 ('% G TABLE 6 SITE ARi.A 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 O I FORM 372 + 22 3643
~
e
RE H E PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 1 rs TABLE 7 GENERAL EMERGENCY Event Indication l 1. a) Effluent monitors 1. Stack monitor RT-7324-1, 2 detect levals 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. I b) These dose rates are ( projected based on other plant para meters, or are measured r-' in the environs.- ___ (>g
- 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, i O - P oR M 372 - 22 200
R PUZLIC SERVICE COMPANY OF COLORADO hga nt 1 I FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 4 ; U ATTACHMENT I I IMPAIRED FIRE PROTECTION NOTICE l 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 Company of Colorado Unit No. One
- 2. Location: Fort St. Vrain, Platteville, Colorado I
Below Is the Information Which Will Be Requested Of The Caller O 3. Caller's Name: Phone:
- 4. Date and time of occurrence:
- 5. Details ar.d extent cf impairment:
l . 6'. Did impairment result from a loss? l[l*Yes l[l No If yes, details:
" Loss would be a fire, accidental system operation, windstorm damage, etc.
- 7. Restoration (of system) begun? l[ lyes l[l No Restoration work to be continuous? l[lYes l[l No
- 8. Impaired area or equipment operable? ~[1Yes l l[l No O Estimated restoration time:
FORM 372 22 3643
l PUZLIC SERVICE COMPANY OF COLORADO [~c g3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 4
/-
N._/ -
- 9. Precautions: l[jValvestaggedout l[lDiscontinuedwelding, cutting,andhotwork l[lDiscontinuedsmoking l[lNotifyControlRoom(Shift) Supervisor,or other applicable management.
l[l Notify Fire Department / Fire Brigade l[lIncreasedwatchmanserviceto hourly l[l Extra extinguishers /firehose in area Other:
- 10. Contacts made by Shift Supervisor:
a) Name of ANI contact: b) Time of ANI contact: O V Management
Contact:
a) Name of management contact: b) Time of management contact: 1
- 11. Additional contacts made/ received:
a) Per attached call sheet log. l l 112. 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 1 l e) Time of ANI contact: l l l
- 13. The Shift Supervisor shall send the completed copies of the completed forms directly to Technical Services.
FOR M 372 - 22 3443
PUBLIC SERVICE COMPANY OF COLORADO [g(c t3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 4
- 14. If Notification was a Fire /All-Risk 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. O O PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ya nt 1 FORT ST. VRAIN FJUCLEAR GENERATING STATION Issue 12 Page 4 of 4 v l 1 1 I I I I l CALL I TIME I DATE I CONTACT (NAME) I 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 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 l I i l i l l I I I I I I I I I I I i i l I I I I I I I i l I i I i l 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 n l I I I I I V 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 l 1 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 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 l l l l l l l [ l i I I I I l i 1 I I I I I I I I I I I I I I I I i 1 I I I l t . 1 PORM 372 22 3843
RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Attachment 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 q Page 1 of 4 V 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:
Loop Shutdown? Scram? Initiating signal (s): Was event result of an LCO Action Statement? Other pertinent information: l l l 5. Actions Taken: l l l l PORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO [c t2 FORT ST. VRA!N NUCLEAR GENERATING STATION Issue 12 Page 2 of 4 m (_)
- 6. Status:
Reactor power at time of report: Under control by on-site staff, no off-site assistance anticipated. Final report. Under control by on-site staff. Will keep NRC advised. Off-site assistanca may be required. Will advise. (See Item #7) Off-site assistance required. (See Item #7)
- 7. If off-site assistance is anticipited or required, describe assistance that has been or may be requested:
O
- 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 contact: b) Time of NRC contact: l FORM 372 22 3643 l l .
PUBLIC SERVICE COMPANY OF COLORADO c t2 FORT ST, VRAIN NUCLEAR GENERATING STATION lssue 12 Page 3 of 4 w] 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 reportable occurrence is required and prepare a facsimile copy if a 14 day report is indicated. b) Send a copy to the Superintendent, Operations. c) Send a copy to PORC. O O P ORM 372
- 22
- 3643
PUBLIC SERVICE COMPANY OF COLORADO fffa ft2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 4 (-) q.) l l 1 l l l l CALL I TIME I DATE I CONTACT (NAME) l COMMENTS / REMARKS l 1 I I l l l 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 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 l l 1 1 I I I I I I I l l l 1 I I I I I I I I I I I I I I I l l l l 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 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 l I I I i l I I I I I I I I I i l_ 1 1 I I I I I I l l l l l l 1 l l 1 I I I I I I I I I I I I I I I l l l l l l 1 I I I I I .I I I I I I I I O P ORM 372 + 22
- 3643
1 RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION $y p Page 1 of 3 v 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 Unusual Hazards (circle one) O xircraft Expiosion Tex 4c sateriai Other (Specify) Spent Fuel In-ident
- 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.) l Offsite assistance required. (See Item 7.) O P ORM 3 72 + 22 3643 l
PUBLIC SERVICE COMPANY OF COLORADO [g r]g 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12
. Page 2 of 3
'u)
- 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 r.otifications as follows: l Contact with State EOC (279-8855) and Governor's Office (866-2471)l l or Mansion (837 8350) l l 1 g 1. READ the following statement verbatim:
"THIS IS A NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION. THIS NOT FICATION 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).
e ( PORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO [,P nt 3 ' FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 3
- 3. RECORD the following information:
Name of State EOC contact Date/ Time Name of Governor's Office / Mansion Contact Date/ Time Call back verification from State EOC, Datc/ Time Call back verification from Governor's Office / Mansion Date/ 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 s- 1. READ the following st tement 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 o'f the information recorded in Step A (Page 1 of this Attachement).
- 3. RECORD the following information:
Name of NRC Contact Date/ Time O U FORM 372 2:2 3MJ
RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Attachment 4 FORT ST. VRA,1N NUCLEAR GENERATING STATION Issue 12 r; Page 1 of 5
\J l
l 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. l l l 1 l Required Information l l l
- 1. This is (Name) , Shift Supervisor at the Fort St.
Vrain Station.
- 2. At (Time) we experienced an (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident.
- 3. a) There is NO, repeat NO, radioactive release taking place, and no speciaT protective actions are recommended at this time.
1 (~') o OR l b) A small radioactive ralease I} taking place, but NO l protective actions are recommended at this time and l are not anticipated to be. OR l c) A radioactive release I}, repeat 11, taking place, and we recommend that people in areas l remain indoors with l windows and ocors closed. l OR l d) A radioactive release 11, repeat I!, taking place, and we recommend that evacuation of areas be considered. l
- 4. Personnel Control Center to be located l 5. Further information on incident conditions will be provided in followup messages.
O V PORM 372 22 360
i PUZLIC SERVICE COMPANY OF COLORADO [c g4 FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 12 Page 2 of 5 v I I l SUPPLEMENTAL INFORMATION l l l NOTE: This information is to be supplied to the NRC and the Colorado Department of Health 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: .
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; Thyroid rem 2 Miles: WB rem; Thyroid rem 5 Miles: WB _ rem; Thyroid rem
- 11. Estimated accumulated dose at EAB:
WB _ rem; Thyroid rem o . POMM 372 22 3643
RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Attachment 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 5 g-) C/
- 12. Areas expected to be impacted by release
- 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 O radiation levels. Whole Body 1 to 5 Take shelter and consider selective Thyroid 5 to 25 evacuation. Monitor radiation levels. Establish Controlled Area and limit access. Whole Body 5 and above Conduct mandatory evacuation. Monitor Thyroid 25 and above radiation levels and adjust area for mandatory evacuation based on these levels Control Access.
- 16. Prognosis for worsening of event -
- 17. - Date and time of report
- 18. Name of person providing report
- 19. Telephone number for call back I
O l l PORM 372 22 340 l
. . - , . . ~
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION hm Issue 12 t4 o . Page 4 of 5 V
- 20. Description of any requested off-site assistance B. The Emergency Coordinator will make notifications in sequence as follows:
I I l l PSC Company Operator 8-571-4591 l l or 8-571-0111 1 I I
- 1. INSTRUCT the Operator to initiate the " Fort St. Vrain Radiological Emergency Call List."
- 2. READ verbatim the information recorded in Part A (Page 1 of this attachment).
- 3. RECORD the following information:
Time PSC Operator Notified Time Operator Callback Received l I l Weld County (911 Using Greeley Line) l 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 l Time Weld County Callback Received O l [ PORM 372 22 3643 l , v i , . g- - ._. _ _ _
PUBLIC SERVICE COMPANY OF COLORADO 4 FORT ST. VRAIN NUCLEAR GENERATING 5TATION Issue 12 ( Page 5 of 5 I I 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 10CFR50.72, 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 l
] TIME of NRC Contact l
l l O P OR M 3 72
- 22 3443
RERP-HOME PUBLIC SERVICE COMPANY OF COLORAD'3 Attachment 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 2 V 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 following telephone calls:
- 1. If you are the response center / post Director:
- a. Call your response center / post Alternat:s 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 C) r co#t et a 8x in esc oner tor:
- a. Call the first person on the attached list and -
inform him to complete the call list. l l l l l POPM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO ha m nt 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 2 O ECP DIRECTOR'S CALL LIST First call all primaries, then call all alternates. PSC Extension Home Time Manager - Technical Support l Primary - M. E. Niehoff 785-1403 690-3879 Alternate - Mike Holmes 571-8409 988-4522 Manager - Media Relations Primary - R. T. Person, Jr. 571-7323 753-9292 Alt. - W. D. Fitzmaurice 571-7158 424-8053 Manager - Resources Primary - D. D. Hock 571-7211 394-3063 l Alternate - J. Bumpus 571-7821 388-7645 Manager - Security Primary - E. O'Neal 571-7709 757-0038 l Alternate - E. Lane 571-8533 321-4016 O - l POmW 372 22 3643 l l
PUBLIC SERVICE COMPANY CF COLORADO c t6 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 . p Page 1 of 2
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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 d inform him to complete the call list.
O V 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 PORM 372 22 s 3643
PUBLIC SERVICE COMPANY OF COLORADO f+ m nt 6 FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 12 Page 2 of 2 gd 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 - C. H. Fuller 785-1202 663-2363 Alternate - J. W. Gahm 785-1350 452-0507 g Radiological Assessment U Primary - T. Borst 785-1203 663-1230 (Pager) 890-1775 Clerical Assistance Primary - D. Merritt 785-1271 737-2339 Primary - D. Heath 785-1272 223-5121 Alternate - S. Katcher 785-1212 356-0351 Media Relations Primary - M. Mora 571-8462 694-2369 Alternate - S. Volsted 571-7242 755-5164 l i i O Pomu 272 22 3643 l
R PUBLIC SERVICE COMPANY O COLORADO [g,P y FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 3 Q 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 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. Contact persons to set up the facility by calling those individuals with asterisks (*) after their names and by notifying fcur (4) Health Physics O" Technicians listed. Inform all persons of the l 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 aj inform him to complete the call list as specified in 2.a. above. ,
l PORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO $, g7 ' FORT ST. VRAIN NUCLEAR GENER ATING STATION Issue 12 Page 2 of 3 v PCC DIRECT 0P'S CALL LIST Plant Extension Home Time Personnel Accountability and I & C Technicians G. Redmond* 251 9-339-3152 T. Bash 11ne 262 8-303-686-9763 P. Bearly 455 8-303-669-6636 M. Benedict 313 9-353-7209 M. Blossom
- 261 9-785-6302 R. Dickerson 273 8-303-287-6089 T. Dillen 262 9-356-3370 R.'Ervin 315 9-330-7178 D. Frye 276 9-587-4768 R. Hamblin 254 8-303-667-1703 C. Harding 311 9-785-2398 l E. Hays 319 8-303-778-7702 J. Hohn 260 9-785-6322 C,g/
m W. Holcomb 312 9-330-2068 R. Hooper 458 8-303-452-3614 D. Horihan 250 78-776-7976 S. Lehr* 451 8-303-422-1280 G. McAfee 260 8-303-857-6498 l R. Moler 456 78-772-9357 G. Murphy
- 254 9-785-2542 l M. Murphy 454 8-303-279-6762 G. Powers 252 8-303-426-1623 D. Reed
- 314 9-785-2159 l l R. Rivera 453 8-303-667-1906 T. Shafer* 457 9-587-4061 C. Stieff* 209 9-587-2500 J. Switzer 452 9-587-4134
. R. Teel 261 8-303-288-1959 R. Wyatt 262 8-303-493-3649 Maintenance. Repair, and Damage Control R. Webb* 229 78-776-8219 (Pager) 855-7257 R. Lamb" 336 78-772-0757
- 0. Nelson
- 246 9-587-4189 O
FORM 372 22 3M3
PUBLIC SERVICE COMPANY OF COLORADO [,P y FORT ST. VRAIN NUCLEAR GENERATING ST ATION Issue 12 fm Page 3 of 3 U Monitoring Teams - Health Physics (Notify four of the following initially.) J. Brown 245 9-339-3972 P. Glahn 245 8-303-450-5292 L. Hutchins 245 9-330-7187 l G. Madison 245 8-303-833-2278 K. Morse 245 9-353-6163 K. Nasveschuk 245 78-651-6254 1 E. J. O'Donoghue 245 8-303-452-3514 S. Sherrow 245 9-353-1338 l S. Sieg 245 8-303-663-3468 l G. Valentine 245 8-303-532-4861 Radiochemistry V. McGaffic (P)* 278 9-587-2752 D. Miller (A)* 279 8-303-663-3595 S. Poet (A) 279 78-652-2297 i M. Prochownik (A) 279 9-785-6010 l S. Rima (A) 279 78-772-4068 Operating Staff Support g _V As Required - See RERP Phone Lists. Maintenance (Electrical, Mechanical) As required .at the discretion of the PCC Director - Refer to RERP Phone Lists. Hazards Control Team Fire Brigade Members 1 l O - 1 FORM 372 22 3643
l RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Attachment 8 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 2 ( L' STATE EOC CALL LIST INSTRUCTIONS (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.
P 3.~ If you are the PSC alternate contact and are notified by d the PSC operator:
- a. Call the first person o- the attached list and-inform him to complete the call list.
O I F ORM 372 - 22 3643 l 1
PUBLIC SERVICE COMPANY OF COLORADO ff nt 8 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 2 STATE EOC CALL LIST (For Contacts by PSC) Extension Home Time Technical Assistance H. L. Br~ey (Primary) 571-8404 469-4238 l J. R. Reesy (Alt.) 571-8406 755-1720 Radiological Consultant Janet Johnson 491-5930 482-3029 Media Relations
---R A. Burns (Primary)- 571-8481 -- - - ---- 759-9740 G. Reeves (Alt.) 571-8479 424-4958 i
O F OR M 372 22 - 3643
RERP-HOME PUBLIC SERVICE COMANY OF COLORADO Attachment 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 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: l l
- 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 aj 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.
l l w 3. If -you are-the response center / post -Alternate Director ~and s are contacted by the PSC Operator:
- a. Call the first person on the attached list and-inform him to complete the call list.
O FORM 372 22 3643
PUJ.LIC SERVICE COMPANY OF COLORADO ht m nt 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 3 TSC DIRECTOR'S CALL LIST l l First call all primaries, then call all alternates. Plant l Reactor Physics Extension Home Time Primary - F. Novachek 270 457-8034 (Pager) 890-1941 Alternate - R. Heller 284 772-1093 Radiolooical Assessment l Primary - J. Sills 265 221-5059 l (Pager) 890-2223 Alternate - S. Johnson 267 663-1431 Plan; Condition Assessment Call two off-duty Shift Supervisors M. Deniston 219 776-3776 D. Evans 219 776-9672 J. Hak 219 - - - - -776-1904' -
- ~ - --
O i l o "ooe* J. Hunter 229 or 347 219 775-2843 330-1411 H. O'Hagan 219 776-8232 G. Reigel 219 330-4235 J. Vandyke 219 or 346 772-2476 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 l Health Physics / Health Physicist Primary - T. Schleiger 242 785-6314 l Alternate - B. Woodard 244 678-0818 l l* Also contacted as alternate to Control Room Director by PSC l operator. O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO [a nt 9 FORT ST. VRAIN NUCLEAR GENERATING STATION 155ue 12 l Page 3 of 3 l V l Administration / Logistics Primary - A. Kitzman 206 737-2578 Alternate - P. Collins 207 587-2172 Alternate - P. Bollig 204 339-3972 Alternate - D. Connelly 210 353-4575 Telephone Console Operators Primary - D. Edwards 217 669-1680 Alternate - D. Libal 213 651-1404 Computer Support
" Primary - D. Klaus 437 466-5046
" Alternate - D. Bilstein 333 532-2546 l " Alternate - D. Haloin 376 353-1993
- Computer Services Page Number: 855-3234 l
t l O PORM 372 22 3643 l .
i . O' O 1 O RERP-HOME Attachment 10 s issue 12 Page 1 or 1 i ATTACliMENT 10 Facility Directors / Alternates Extension Gity !!ssa Time l Technical SuDDort Center
, s. Prima ry: D. W. Wa rembourg 5-785-1200 F rede rick 5-303-833-8092 Alternate: L. M. McBride 5-785-120s Boulder 5-303-48s2-3829 E93 trol Room Director
- b. Prima ry: W. J. Franek 5-785-1218 Berthoud 5-303-532-3489 Alternate: D. P. Ilood 5-785-1347 Longmont 5-303-776-188:3 Personnel Control Qgnier
- c. Prima ry: J. Class 5-785-1253 Brighton 5-303-659-8:116 Alternate: 5. R. Wi l l ro rd 5-785-1327 Brighton 5-303-659-5258
[qIws N Command Post
- d. Prima ry: C. H. Fuller 5-785-1202 Loveland 5-303-663-2363 Alternate: J. W. Cahm 5-785-1350 Northglenn 5-303-452-0507 99Ipo_ Late (marge _ngy_pirgq1o_f.
(at Forward Comm_apd Poll)
- e. Prima ry: D. R. Lee 797 8:122, 571-7305 Brighton 9-659-1180 Alternate: J. K. Fuller 329-1104 Denve r 9-779-1109 f.Kteutive Command Post
- f. Prima ry: R. F. Wa l ke r 571-7333 Denver 9-23ts-9298 Al te rna te: B. O'Donnell 571-7381 Denver 9-388-0211
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- g. Prima ry: D. McNeiIls 571-7254 Denver 9-965-319T Alternate: H. L. Brey 571-88:08: Broomrield 9-8 69-4238
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RERP-ORG _ PUBLIC SERVICE COMPANY OF COLORADO Issue 7 g FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 12 O \ TITLE: FSV EMERGENCY ORGANIZATION AND RESPONSIBILITIES ISSUANCE ([y{g
$" "'" d3dn56fr TW6/kW RE'EW PORC 58 9 00T 3- 1984- /TE"' 10. to. 9 tt Section Description Page General...........................................................2 1.0 Criteria ..................................................... 2 2.0 Procedure..................................................... 2 3.0 Responsibilities ............................................ 11 4.0 References .................................................. 12 O G 5.0 Procedures Referenced:..................:.................... 12 Figure 1 Onsite-Offsite Emergency Organization................... 1 Figure 2 Emergency Organization Fort St. Vrain Nuclear Generating Station ..................................... 1 Figure 3 Executive Command Post Organization..................... 1 O
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- DORM 372 22 3642
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Issue 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 12 Public 0 Service PUBUC SERVICE COMPANY OF COLORADO bg Generql This procedure defines the authority and general responsibilities of key individuals within the FSV Emergency Organization. Positions and responsibilities of personnel located at the six emergency response facilities; Forward Command Post, Tecnnical Support Center, Control Room, Personnel Control Center, Executive Command Post, and State Emergency Operations Center; are discussed (see Figure 1). This procedure is general in nature and cannot specify the actions of personnel on a stsp-by-step basis. Personnel are trained in their areas of responsiblity and are expected to be able to utilize the multitude of implementing procedures and emergency equipment provided. This procedure is provided for reference purposes during a radiological emergency at Fort St. Vrain. 1.0 Criteria This procedure is automatically implemented whenever an event has occurred at Fort St. Vrain which is classified as an ALERT or higher emergency class, as determined by the on-duty Shift Supervisor (Emergency Coordinator). Staffing changes, if i . required by a particular situation, may be made. at the dit:retion of the responsible facility directors. 2.'s Procedure 2.1 Emergency Coordinator The Emergency Coordinator is the on-duty Shift Supervisor. The title of Emergency Coordinator is retained by the duty 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 2). The Emergency Coordinator is responsible for:
- Initial accident classification;
- Recommending protective actions;
- Initiating emergency actions to mitigate the accident;
*. Notifying offsite authorities;
- Diagnosing accident conditions; Estimating radiological exposures; and O
d
- Establishing communications with the TSC.
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. . _ _ . _ . _ . . . . . . . ._ m RERP-DRG l Issue 7 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 12 l 0 Service rusuc sanwes courAny or cotonApo Responsibility for the decision for offsite notification and protective action recommendation may not be delegated.
2.2 Forward Command Post (FCP) The FCP functions as the control and coordination center for on-scene state / local / federal emergency response forces, and communicates with the State EOC and the Weld County EOC (Weld County Communication Center) for f effective coordination of state and county forces. A ' senior representative of Division of Disaster Emergency Services (00 DES) is responsible for control and coordination wP S FCP emergency response activities. 2.2.1 Corporate emergency Director (CED) The CED assumes overall command of PSC emergency operations, and is the prime contact between FSV and gevarnmental authorities. The CED is responsible for direction and coordination of: i a PSC onsite and offsite emergency functions;
- Interface between PSC and state / local / federal emergency response activities; ;
- Transmission of plant status updates and radiological release data to the ECP, PSC personnel at the State EOC, and media center personnel;
- Notification of state and local agencies '
regarding recommended protective actions;
- Provision of administrative, technical, and logistics support to station emergency
, operations via the ECP; and
- Continuity of emergency organization j resources. -
The CED provides direction to the TSC Director and the Nuclear Engineering Manager at the State EOC. 1 He will coordinate additional headquarters support i O via the Executive Command Post, and is responsible to make the determination of when the emergency condition is terminated, and the recovery phase has begun. O 1 1
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Isse2 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 12 Public 0 Service PUBUC SERVICE COMPANY OF COLORADO O 2.2.2 Station Technical Liaison The Station Technical Liaison is responsible to provide assistance and substatiated data on emergency status and conditions as required. He also serves to coordinate company emergency response actions with those of state / local / federal aoencies. 2.2.3 Media Relations The Fic Media Relations personnel at the FCP provide assistance to the State Public Information Coordination Team (PICT) in the preparation of news and related media releases, and the control of rumors in accordance with the PSC RERP Public Information Plan. 2.2.4 Radiological Assessment Coordinator The Radiological Assessment Coordinator is responsible for coordinating the radiological assessment activities between PSC and those of l state / local / federal agencies. His particular responsibilities include:
- In coordination with the TSC Radiological Assessment individual, perform and/or evaluate a preliminary assessment of the actual and/or
. potential radiological release.
- Based upon the above assessment, identify affected offsite areas, and recommend an emergency classification and recommended offsite protective actions to the Corporate Emergercy Director. .
Obtain a 12 hour weather prediction from the National Weather Service. Continue to evaluate radiological assessment data as it arrives and continue to make recommendations of emergency classification and offsite protective actions to the Corporate Emergency Director.
- Confer with state / local federal agencies on an as-needed basis to discuss PSC radiological assessment activities relative to those of offsite authorities.
l FoRMiB)372 22 3M3
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RERP-ORG Issu) 7 Page 5 of 12 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service PUBUC SERVICE COMPANY OF COLORADO O 2.2.5 Clerical Staff The PSC clerical personnel assigned to the FCP maintain an ongoing record (log) of all actions taken by PSC at the Forward Command Post. In addition they assuine responsibility for the posting of the FCP status board information and assist in the timely transmission of data between the FCP and TSC, as well as between the FCP and the State Emergency Operations Center (SEOC) PSC staff and the Executive Command Post (ECP). 2.3 Technical Support Center Site emergency command activities are centered in the Technical Support Center, located immediately adjacent to the Reactor Building and within short walking distance of the Control Room. The TSC also serves as the pricary point for onsite-offsite communications. 2.3.1 TSC Director The TSC Director is in command of onsite emergency operations. The TSC Director is authorized to initiate emergency actions, including declaration
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of a particular emergency class and providing . U protective action recommendations to offsite authorities. The TSC Director's responsibilities are:
- Assumes overall responsibility for the coordination and direction of onsite emergency response centers;
- Transmits preliminary assessment information to the FCP; Directs the Personnel Control Center (PCC) actions;
- Confers, on an on going basis, with the Corporate Emergency Director after activation
( of the FCP; and
- Notifies the Corporate Emergency Director of the need for assistance or support.
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RERP-ORG Issue 7 Page 6 of 12 i Public FORT ST. VRAIN NUCLEAR GENERATING STATION SerVICO PusuC sERWCE COMPANY OF COLORADO O 2.3.2 Engineering and Technical Analysis Engineering and Technical Analysis personnel are responsible for direction of core physics analysis, electrical and mechanical engineering activities, liscensing related activities, procedures development, and system analysis as required. 2.3.3 Plant Condition Assessment Plant Condition Assessment personnel are responsible for the assessment of plant st stus, focusing on significant plant problems and trends, and for providing recommended corrective actions to the TSC Director. 2.3.4 Emergency Maintenance Emergency Maintenance personnel are responsible to recommend repair / damage control and corrective actions for plant mechanical and electrical systems. This individual estimates time and manpower requirements for emergency repairs, and develops emergency repair work procedures, as required. 2.3.5 Instrumentation and Control Support The Instrumentatiorr and Control (I&C) individual determines alternative I&C capabilities or configurations, and advises for the repair / installation / modification of I&C equipment. 2.3.6 Radiological Assessment The Radiological Assessment individual is responsible to assess offsite radiological doses and consequences, determine affected offsite areas, and confer with both the TSC Director and the Radiological Assessment Coordinator (FCP) regarding calculation results and recommended offsite protectivu actions. In addition, the Radiological .
- Assessment individual should confer with the Hea-1th
. Physics representative at the TSC regarding offsite dose projections in areas where field monitoring trams are to be deployed. The Radiological
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Assessment individual is responsible for verification of any calculation prior to transmission to the Radiological Assessment Coordinator at the FCP. O . Mutsian 22.ase
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RERP-ORG Issue 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 12 Public 0 Service rusuC sERWCE COMPANY OF COLORADO O 2.3.7 Health Physics The senior Health Physics representative at the TSC is responsible for the assessment of onsite radiological doses, direction of all Health Physics / Radiochemistry survey personnel or teams, ensuring that adequate personnel dosimetry measures are taken, and evaluation of doses of field and emergency team personnel (particularly with regard to a need for thyroid blocking).
-- 2.3.8 Administrative and Logistics Support The Administrative and Logistics Support individual provides technical documents, provides assistance with communications and analytical equipment, arranges required clerical support beyond the personnel directly assigned to the TSC, and makes any arrangements necessary for food / transportation / housing support as required.
2.3.9 Computer Support Computer support personnel . provide technical support in the areas of computer hardware and software modifications / development /or repair, as O' required. In addition, this individual is responsible to arrange for timely offsite advice or assistance as directed by the TSC Director.
- Computer support personnel 'also have received training in offsite Dose Calculation metnodology.
This training is provided for the purpose of assisting the TSC Radiological Assessment individual in gathering data and, where requested, l assist in data entry at the TSC plant computer l console. i
, 2.4 Control Room .
Emergency control and accident mitigation is provided by Control Room personnel. Intially, accident assessment and control is directed from the Control Room (see Section
- 2.1). -
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RERP-ORG Issue 7 Page 8 of 12 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service rusuC SERVICE COMPANY OF COLORADO O 2.4.1 Control Room Director The Control Room (CR) Director is responsible for control of plant operations, assessing plant operational aspects, and implementing any ) recommended corrective actions. In addition, the CR Director may request any additional operations l personnel necessary through the TSC Director. 2.4.2 Technical Advisor Tha Technical Advisor is responsible to provide
- technical analysis and advice as requested, and to
! prrvide recommendations of corrective actions necessary to restore the plant to a safe and stable condition.
2.4.3 Plant Control and Plant Operations Plant Control and Plant Operations responsibilities . are handled by personnel already on-shift and assigned those responsibilities. 2.5 Personnel Control Center The Personnel Control Center (PCC) serves as manpower O marshalling location to provide a pool of personnel available for emergency assignment. Personnel are assigned to perform functions consistent with their routine job classification. t 2.5.1 Personnel Control Center Director The PCC Director is responsible for continued personnel accountability, assembling personnel for
- repair /danage control or radiological survey teams, search and rescue teams, reserve operating staff, and establishing radiological control areas as directed. In particular, his responsiblities
. include the following:
- Continued personnel accountability;
- Assuring that all emergency workers at-risk I are evaluated by the Senior Health Physics l
representative at the TSC. with regard to a need for thyrcid blocking;
- Coordinates with Security personnel to control access to the owner controlled area; O
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RERP-ORG Issue 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 12 0PublicService rusuc sERWCE COMPANY OF COLORADO
- 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;
- Coordinates entry /re-entry - of required personnel with the Lead Security Officer;
- Relocates the PCC to an alternate onsite or offsite location, as required;
- With the concurrence of the TSC Director, authorizes volunteer emergency workers to receive doses in excess of 10 CFR 20 limits (see RERP-EXP); and,
- Receives reports of accidental or emergency exposure in excess of occupational limits, and informs the TSC Director of these occurrences; Q and,
- Refers any requests for outside assistance to the TSC Director.
2.5.2 Personnel Accountability Personnel Accountability personnel are responsible for maintaining continued personnel accountability l and exposure estimates, handling search and rescue assignments, performing first aid and personnel decontamination, and assisting in the medical transport of injury victims.
~
2.5.3 Maintenance, Repair, and Damage Control Perform mechanical and electrical repair / damage control, emergency maintenance, and temporary . modifications. 2.5.4 Hazards Control
~
Extinguish fires, purge hazardous gases, and combat natural emergencies. O romism2 22.see .
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_. _ _ . . _. _ - .__. .~. ._-..._-;_-.;...... . RERP-ORG Issue 7 Page 10 of 12 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 0SerVICO PusuC SERVICE COMPANY OF COLORADO \ 2.6 Executive Command Post l The Executive Command Post (ECP) is manned by senior corporate personnel with the authority to activate corporate personnel, facilities, equipment, and financial resources in an emergency situation (see Figure 3). The ECP supports PSC personnel stationed at onsite and offsite emergency res,ponse centers. 2.6.1 ECP Director The ECP Director will assume overall responsiblity - for providing the Corporate Emergency Director with the counsel, expertise, and resources available within the PSC organization. He coordinates emergency assistance, provides re-entry and recovery support, station and site modifications ' review by the Nuclear Facilities Safety Committee. 2.6.2 Manager of Technical Support I The Manager of Technical Support will provide the Corporate Emergency Director and onsite emergency operations with technical advice in nuclear, mechanical, civil, and electrical engineering. He C) ar v'd "S'"" "' '"aa r'- **c""'c **a'r*'- - and consultants, as requested. 2.6.3 Manager of Media Relations The Manager of Media Relations will coordinate communications between the ECP and other emergency facilities, and will assist the ECP Director and PSC media relations personnel in preparation of press releases, announcements, and interviews. 2.6.4 Manager of Resources
~
The Manager of Resources will coordinate provision of manpower and equipment from within PSC, and from consultants / contractors to support onsite emergency operations. He provides requested technical and craft support; personnel or consultants for engineering / design and construction reviews; temporary housing, office transportation, and construction equipment; purchasing, financial, legal, and general office support; and, food deliveries and related logistics support to designated emergency operations. O
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Issue 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 12 0Public Service PUBUC SERVICE COMPANY OF COLORADO O 2.6.5 Manager of Security l The Manager of Security will coordinate PSC security operations with public law enforcement agencies. He acquires additional security manpower hardware, and equipment, as requested. 2.7 State Emergency Operations Center The State Emergency Operations Center (State EOC) is the primary point through which the Governor, or his designee, exercises overall control and coordination of emergency response operations through the Colorado Division of Disaster Emergency Services. 2.7.1 Vice President of Governmental Affairs or the Manager of Nuclear Engineering This individual is responsible to coordinate PSC emergency response activities with those of state / local / federal agencies. 2.7.2 Media Relations Manager or News Director
- This individual is responsible for providing up-to-I n
U date site information to the Public Information Coordination Team (PICT) Chief (Governor's Office representative) and assisting the PICT in preparation of mutually acceptable news releases, fact sheets, background material media releases, and rumor control in accordance with the "PSC RERP Public Information Plan." 2.7.3 Radiation Specialist The Radiation Specialist is responsible for providing assistance and substantiated data regarding the site's emergency status and plant conditions to state / local / federal emergency response agencies assigned to the State EOC. 3.'O Responsibilities l l This procedure will be implemented whenever the Shi*t Supervisor
, declares an ALERT, or higher, emergency classification.
Individual responsibilities are specified in Section 2.0 of this procedure. t l I -- - . - - - . . y ,,,3 . . .n.,,
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RERP-ORG Issue 7 - FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 12 OPublic Service PUBUC SERVICE COMPANY OF COLORADO
$.0 References 4.1 Fort St. Vrain Nuclear Generating Station Radiological Emergency Response Plan 4.2 PSC RERP Public Information Plan 5.0 Procedures Referenced 5.1 RERP-CR, Control Room Procedure 5.2 RERP-ECP, Executive Command Post Procedure 5.3 RERP-FCP, Forward Command Post Procedure 5.4 RERP-PCC, Personnel Control Center Procedure 5.5 RERP-SEOC, State Emergency Operations Center Procedure 5.6 RERP-TSC, Technical Support Center Procedure 5.7 RERP-EXP, Emergency Exposure Guidelines 5.8 RERP-SUPORG, Use and Coordination of Non-PSC Support Organizations O
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- i EXECUTIVE COMMAND POST ORGANIZATION Fort St.Vrain Nuclear Generating Station f [
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- TECHNICAL EXPEkT5 COORDINATIM e LAW ENFORCEMENT LIAISON 2 e LOGISTICS SUPPORT
- CONSULTANTS ESS RE M AM S e MANPOWER, EQUIPMENT l
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TITLE: PROTECTIVE ACTION GUIDELINE RECOMMENDATIONS ISSUANCE d,, um L a7 47 AUTHORIZED BY 777 */Sf7JJ
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PORC EFFECTIVE REVIEW PORc 5 8 0 AUG 2 - 1984 DATE b- b> $ N 1 l Section Description Page l 1 1 General ........................................................... 2 1.0 Cri teri a for Impl ementati on. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.0 Procedure..................................................... 2 3.0 Responsibilities .................................. .......... 4 4.0 References ................................................... 5 5.0 Referenced or Supporting Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . . 5 m U 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 Distribution Summary......................... 1 Datasheet 1 ....................................................... 1 Work /Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e Rep o rti n g S hee t" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FOP. WARD IT TO THE NUCLEAR DOCUMENTS l 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. , O l + lA3 FORM 372 22 3642 l
PUZLIC SERVICE COMPANY OF COLORADO ue FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 5 O 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 mechanism for decision-making regarding protective action 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 Implementation 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 i determination of the most practical method of protecting the general public. This information shall be played to the TSC Director and the Corporate Emergency Director. Additionally, O this procedure may be used for reference information by the TSC U Director and the Corporate Emergency Director to assist in Jecision 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 I 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 protective 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. O
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A FORM 37J 22 3643
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 5 U,, 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 l 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 cetailed 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 summarizes the population distribution around the plant. The above stated values should be utilized in conjunction with a stated value for plume arrival delay, in or'er d to assess the effectiveness of an evacuation in dose avoidance. Simply stated, plume airivFdelay (T ) is the A sum of the time available before a projected release begins (TB ) and the time projected for plume travel (T )T 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. Sheltering as a protective action includes the following i actions: 1 (1) Seeking shelter indoors near the center of the
. lowest floor of the structure; . (2) Securing all intake / exhaust ventilation to *he .
structure during passage of the cloud;
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PORM 372 22 3643 i j
PUBLIC SERVICE COMPANY OF COLORADO $PPAG FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5 v (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. 3.0 Responsibilities 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 P.adiological 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 (Vl of the results of this appraisal and submit an assessment of recommended protective actions. 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 reouested, with respect to current plant conditions and the need for offsite protective actions. 3.5 Radiological Assessment (TSC) t Assist the TSC Director and Radiological Assessment Coordinator with this evaluation as requested. Confer with the Radiological Assessment Coordinator regarding persistance or prospect of conditions worsening.
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PUBLIC SERVICE COMPANY OF COLORADO f
. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 5 0 -
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. 5.0 Referenced or Supporting Procedures 5.1 RERP-DOSE, Offsite Dose Calculation Methodology. l 5.2 RERP-CR, Control Room Procedure l 5.3 RERP-ORG, FSV Emergency Organization and Responsibilities 5.4 RERP-FIELD, Field Monitoring Procedure {') - l l \ . l O V 1 PORM 372 22 - 3643
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( . - HERP-PAG l Table 1 issue 3 Page 1 or 1 TABLE 1 PROTECTIVE AC180N CUIDEl_IllL3 I?ccommended protectivo actions to reduce whole body ano 'hyroid dose from exposure to a gaseous plume , Projectert Dose (llem) _to thej opu_.la1Lon Recommended Actions tal go_mments Miole Body less than 1 N1 planned protective actions Previously recommended (b). State may issue an protective actions may Thyroid loss than 5 advisory to seek shelter and be reconsidered or await further instructions. terminated. HonI to r envi ronmenta 1 radiation levels. Miole Body 1 to 5 Seek shelter as a minimum. If constraints exist, V Consider evacuation. Evacuate special consideration lityroid 5 to 25 unless constraints make should be given for it imp rac t ica l . evacuation or children Monitor environmental and pregnant women, radiation levels. Control aCCOss. Whole body 5 and above conduct mandatory evacuation. Seeking shelter would be HonItor environmentaI an aIternative ir Thyroid 25 and above radiation levels svacuation were not and adjust area ror immediately possible. mandatory evacuat.lon based on these levels. Control access. 1 (a) These actions are recommended fo r planning purposes. Protective action decisions at the timo cr the incident must take existing conditions into consideration. (b) At the time of the incident, orricials may implement low-implet protective actions in keeping with the principle or maintaining radiation exposures as low as reasonably achievable. 1 i i
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I* RERP-PAG PUBLIC SERVICE COMPANY OF COLORADO WS/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION l$ sue 3 Page 2 of 3 FORMS USE REPORTING SHEET l 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 this copy: Worksheet Numbers Copies Used Datasheet Numbers Cooies Used Checklist Numbers Copies Used 1 . 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 necessar'y to replace . the noted number of forms, as well as this " Forms Use Reporting , . Sheet" for the affected procedure in the affected book. A l FORM 372 22 3643 o
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FORMS USE REPORTING SHEET (Continued) l COMMENTS I l 1 Reported By: Date: l Nuclear Documents Cpecialist
- Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this for, to-notify users that the procedure has been updated and that all
- worksheets, checklists, and datasheets are present in the required number of copies.
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.O FORMS USE REPORTING SHEET l 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 this copy: Worksheet Numbers Copies Used Datasheet Numbers Copies Used _ Checklist Numbers Copies Used The procecure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this . reporting form. Wh4n this form is received, it will be necessory to replace the noted number of forms, as well as this " Forms Use Reporting "
- Sheet" for the affected procedure in the affected book.
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., PUBLIC SERVICE COMPANY OF COLORADO g, j, I FORT ST. VRAIN NUCLEAR GENERATING STATION I$ sue 3 Page 3 of 3
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I FORMS USE REPORTING SHEET (Continued) l l t.0MMENTS Reported By: Date: l Nuclear Documents Specialist Date Received Date Replaced [* Nuclear Documents Specialist will transmit this form to the ! originating individual / department upon completion of this form to I C notify users that the procedure has been updated and that all - worksheets, checklists, and datasheets are present in the required number of copies. O O e O
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F OR M 372 22 - 3643
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- RERP-PCC PUBLIC SERVICE COMPANY OF COLORADO Issue 14 l
i FORT ST. VRAIN NUCLEAR GENERATING STATION page 1 of 14
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V ' TITLE: PERSONNEL CONTROL CENTER PROCEDURE ISSUANCE AUTHORIZED g g,g,I BY 'M1M 'M7,4J PORC - ' EFFECTIVE REVIEW EORc 5 8 0 AUG2 - 1984 DATE h- b- b TABLE OF CONTENTS Section Description Page 1.0 Criteria for Implementation.................................. 3 2.0 Procedure.................................................... 3 3.0 R e s p o n s i b i l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 4.0 References .................................................. 13 5.0 Referenced or Supoorti ng Procedure s. . . . . . . . . . . . . . . . . . . . . . . . . . 13 Figure 1 Traini ng Center Fl oor Pl an . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Figure 2 QA/ Engineering Complex Floor P1an...................... 1 Figure 3 Route to Johnstown County Shops........................ 1 Figure 4 Route to Platteville VFD .............................. 1 Figure 5 Route to Longmont Service Center ...................... 1 Figure 6 Sector Map ............................................ 1 l Figure 7 Site Map .............................................. 1 l Figure 8 Exclusion Area Map ..................................... I j l Figure 9 Emergency' Planning Zone (5-Mile) ...................... 1 l Figure 10 Emergency Organization ....................... ........ 1 Datasheet 1 Personnel Accountability and Exposure .............. 1 l l l Datasheet 2 Briefing Sheet for Field Monitoring Teams .......... 1 l Datasheet 3 Briefing Sheet for Inplant Monitoring Teams ........ 1 l Datasheet 4 Briefing Sheet for Emergency Teams.................. 1 O'%d ~
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0' P OR M 372 - 22 3642
s' RERP-PCC PUBLIC SERVICE COMPANY OF COLORADO Issue 14 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 14 1 Q O l Checklist 1 PCC Di rector 's Checkl i st. . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 , I Checklist 2 Recorder PCC Closecut Checkli st . . . . . . . . . . . . . . . . . . . . 1 Attachment 1 Recorder............................................ 1 Attachment 2 Communications...................................... 1 Attachn?nt 3 Decontamination .................................... 1 Attachment 4 Fort St. Vrain Security Department.................. 1 Attachment 5 Drivers ............................................ 1 Attachment 6 FirstAid..........................................1 Attachment 7 Instrument Accountability and Repair................ 1 Work /Datasheet/Chec kli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e Re p o rt i n g S h e e t* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2
- ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l- WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS O -l SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, O DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCED'JRE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
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$ ' P PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 14
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1.0 Criteria for Implementation 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 l Director at the direction of the Shift Supervisor (see RERP-CR). The Shift Supervisor prior to ordering PCC activation, shall l determine the PCC location. There are two designated onsite PCC locatior., and three designated offsite PCC locations. The preferreu 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. The decision of PCC location will be made based upon prevailing wind conditions and site accesibility to offsite respondants. 2.1 In the event that the PCC must be established offsite, the PCC Director is responsible for the transport of emergency equipment, including decontamination supplies, necessary to establish the offsite PCC. a) Emergency kits are stored at both the Training Center and the Engineering /QA Complex (see HPP-37). The kits include:
- 1) Emergency radiological monitoring equipment
- 2) First-aid and decontamination equipment
- 3) Protective clothing
- 4) Communications equipment
- 5) Portable lighting
- 6) Protective breathing apparatus
'h Fonu 372 22 3643 l
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a PUBLIC SERVICE COMPANY OF COLORADO (PyP FORT ST. VRAIN NUCLEAR GENERATING STATION page 4 of 14 l l l Ov 2.2 The PCC Director shall perform personnel accountability to assure that the initial manning requirements of the PCC can be met. If not during normal working hours, those personnel required to man the PCC are notified by telephone (see RERP-HOME). It is the responsibility of the PCC Alternate Director, or the first individual contacted by the Director, to ensure that the notifications are made. l 2.3 The PCC Director shall establish initial communications with the Technical Support Center (TSC) and verify ths.c primary and secondary communication links are available. l Communications personnel should be assigned to maintain l constant communication with the TSC. 2.4 Personnel reporting to the PCC
- Individuals assigned to the PCC must enter at the entrances designated on Figure 1 (Training Center) or Figure 2 (Engineering /QA Complex); remain in the FRISKING (or waiting) area until monitored for contamination.
- If contamination is .found, proceed to the O decontamination area as directed and initiate d decontambation procedures (see HPP-11).
- If contamination is not found, proceed to a clean area of the PCC as directed.
2.5 PCC Habitability Initiaily, and throughout the period that the PCC is activated, the PCC director is responsible for assurance of facility habitability. The PCC director shall request that Health Physics periodically monitor the arca (approximately every 15-20 minutes). Habitability is determined using an RM 14/15 set to alarm at 500 cpm, or if radiation levels are greater, by periodic air sampling. The HP Technician performing habitability checks shall inform the PCC Director of each survey's results, and ! assure that the Recorder enters results in PCC Log. 2.6 Personnel Accountability and Exposure Control After initial personnel accountability is completed at emergency stations (see G-5, Personnel Emergency . .e spon se) , each facility director assumes responsibility l for continued personnel accountability of the personnel
. assigned to him. This task is most challenging at the PCC, where repair / damage control teams, survey teams, b ,o. m . n .
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PUBLIC SERVICE COMPANY OF COLORADO (PPC FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 14 v PCC, where repair / damage control teams, survey teams, reserve operating staff, and search and rescue teams are assembled and dispatched into the plant. The PCC Director shall assign a member of the PCC staff proximate responsibility for maintaining records of personnel accountability and personnel exposure records for those individuals assigned to the PCC. This individual, the Personnel Accountability and Exposure Controller, reports directly to the PCC Director, who maintains ultimate responsibility for cortinued Personnel Acccuntability. Additionally, the PCC Director has the responsibility for authorization of selected volunteers to receive emergency exposures in excess of occupational limits (only with joint concurrence of TSC Director and the senior Health Physics representative at the TSC). These responsibilities are de r:ribed in detail in RERP-EXP, and include specific r ,uirements for record keeping and job briefings. Responsibility for record keeping of personnel accountability and exposure is assigned to the Personnel Accountability and Exposure Controller. He is provided Datasheet I to assist him in maintaining the required records. 2.7 personnel Assignments After activation of the PCC, the PCC Director shall assign one member of his staff responsibility for maintaining control over personnel assignments to teams or tasks. This individual is the Personnel Assignment Controller, and his responsibilities are summarized below. NOTE: The senior Health Physics representative at the Technical Support Center and the TSC Director shall be consulted prior to dispatching any personnel from the personnel Control Center. l l s.
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FORM 372 22 3643 m
k' RERP-PCC PUBLIC SERVICE COMPANY OF COLORADO Issue 14 FORT ST. VRAIN NUCLEAR GENERATING STATION page 6 of 14 () 2.7.1 Distribute equipment and appropriate Attachments or Datasheets of the PCC Procedure and record on the assignment board as personnel arrive and are available. a) Recorder Attachment 1 Checklist 2 b) Communication Attachment 2 c) Personnel Accountability and Exposure Controller Datasheet I d) Decontamination Attachment 3 e) Security Attachment 4 f) Drivers Attachment 5 g) First Aid Attachment 6 h) Instrument Repair and Accountability Attachment 7 i) Assign first supervisor to arrive at the PCC the duty of directing additional personnel to J their areas and retrieving them as necessary. j) Additional Personnel 2.7.2 Make every effort to ensure all arriving persons are assigned to each group in accordance with individual qualifications or, if not immediately assigned, assembled in an out-of-the-way place for further instructions. 2.7.3 Provide each group with additional manpower as reqd red. 2.7.4 With the assistance of the Personnel Accountability and Exposure Controller, contact or account for all personnel onsite and at the PCC. 2.7.5 Record all data for the master log. 2.7.6 List all available personnel on the control board i from the Emergency Kit so that, if additional assistance is needed, personnel can be called in. 2.7.7 Keep records of additional personnel assignments l - for master log. l O
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FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-PCC Issue 14 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 14 f) v 2.8 Radiological Monitoring Teams Radiological monitoring teams are dispatched from the PCC upon approval of the TSC Director, and under the overali direction of the senior Health Physics representative at the TSC. Protective clothing and equipment requirements along with maximum stay times, are determined by the senior Health Physics representative at the TSC and relayed to the PCC Director for use in the briefing of the l monitoring teams (see Datasheets 2 and 3). 2.8.1 Field Survey Teams Field Survey Teams to survey both the Exclusion . Area Boundary (EAB) and the plume exposure 1 Emergency Planning Zone (EPZ) are dispatched as required (see RERP-FIELD). Field Teams consist of a Health Phys.ics Technician and a Driver. Keys for the two site assigned Emergency Response vehicles and for tso site assigned vehicles generally located at the Engineering /QA complex are stored in the PCC Emergency Kits. 2.8.2 Inplant/Onsite Monitorir.g Teams p d Monitoring teams to survey the plant and protected areas consisting of at least a Health Physics Technician and an assistant shall be dispatched as required (see RERP-SURVEY). 2.9 Notification of Persons Living on Plant Property The PCC Director is responsible to assure prompt (within 30 minutes of activation) notification of individuals living on plant property. This may be done by telephone (see Attachment 2) or by personal contact. 2.10 Medical Transport Transport of injured or contaminated individuals is to be performed in accordance with the FSV Medical Emergency Plan. The TSC Director shall be notified of all such transport. h v-
' FORM 372 3643
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. PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION page 8 of 14 m k.) 4 l 2.11 Site Access Control / Security 2.11.1 PCC Guard Upon notification to activate the PCC, the Lead Security Officer.(LS0) shall dispatch one security guard to the PCC. Security responsibilities at the PCC are as follows:
- Assist in gate control of authorized eersonnel and vehicles at the PCC (if Engineering /QA Complex selected).
- Ensure that the outer perimeter gate is secured and that non-PCC personnel are not admitted to the PCC without prope-authorization.
= Assist with radio communications and access authorizations in cooperation with the LSO.
2.11.2 Site Response Guards After activation of the Personnel Control Center the PCC Director will coordinate access of
- h. personnel and vehicles into the protected area or vital areas with the LSO. Site response security personnel will:
- Check all site visitors cut through the Search and Identification Facility.
- Facilitate the exit of onsite personnel reporting to the PCC.
- Assist in personnel accountability (in particular the Central Alarm Station as specified in Procedure G-5).
= Assi st with personnel and' vehicle ingress / egress to and from protected and i vital areas. l CA
($' l Fomu 372 3643
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- -P PUBLIC SERVICE COMPANY OF COLORADO ,
. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 14 n
2.12 Locating or Relocating the Personnel Control Center Offsite In the event that the Personnel Control Center must be located or relocated offsite, one of the three locations listed below, in order of preference, will be used. An Emergency Kit and Instructions from a site facility will be utilized and must be transported to the alternate PCC. It is the PCC Director's responsibility to assure transport of Emergency Kit supplies. Privately owned vehicles will be used for transportation. 2.12.1 Johnstown County Shop The Jonnstown County Shop keys are located with the Emergency supplies in the PCC Emergency Kit. During business hours, the county should be notified of an anticipated use of the facility (See RERP PHONE LIST). During non-business ' hours, the County shall be notified by calling one of the individuals listed in RERP PHONE LIST, at home. The physical location of the Johnstown County Shop is shown on Figure 3. V 2.12.2 Platteville Volunteer Fire Department The Platteville Fire department should be notified of an anticipated use of the facility (See RERP PHONE LIST). Location of the facility is shown on Figure 4. 2.12.3 Longmont PSCo Service Center The Longmont Service Center should be notified of an anticipated.use of the facility (See RERP PHONE LIST). Keys (two) to the gate and side door of the Service Center are located with the emergency supplies. Access to the building shall be via the east side door. One key opens the yard gate and the other key opens the building door. Light switches are located on the east wall, just south of the overhead door, and on the north wall by the entrance. Physical loca. tion of the facility is shown on Figure 5. Cu 4 F ORM 372 3643
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k~ RERP-PCC PUBLIC SERVICE COMPANY OF COLORADO Issum 14 FORT ST. VRAIN NUCLEAR GENERATING STATION page 10 of 14 O v 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 Decontamination; and, HPP-21; Surface Radioactive 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. PCC Director will coordinate access to the plant site with the Weld County Sheriff's Department if PCC is to be established onsite. The PCC Director is also responsible for accountability of personnel leaving the plant after re-entry or being relieved. __ U 2.14.1 Re-entry Guidelines For support plant operations personnel, and corporate resources personnel the PCC Director shall: a) 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, b) Have the Personnel Accountability and Exposure Controller record accountability and exposure information. c) Have the LSO inform security of the personnel arriving and prepare to clear them through - security. l
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l0 F OR M 372 3643
l k' RERP-PCC PUBLIC SERVICE COMPANY OF COLORADO Issue 14
. : FORT ST. VRAIN NUCLEAR GENERATING STATION page 11 of 14
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l 2.14.2 Emergency Teams (see RERP-TEAMS) 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. 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 l Physics representative at the TSC. (See l Datasheet 4). The PCC Director must clear all Emergency 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 communication
- . equipment and have the Personnel Os 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 erter the area, establish communication with tt.e TSC, perform the duties in the most safe end efficient manner possible, and inform the TSC of completion of duties and intent to leave the area. f) Once their operati,ons have been completed, the team personnel will follow self-monitoring and personnel decontamination proced.ures 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. h) The PCC Director will inform the TSC of the return of the emergency team. S FORM 3% - 23 3643 a -
t PUBLIC SERVICE COMPANY OF COLORADO [PP y FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 14 ( l I) v 2.14.0 Personnel Leaving the Plant After Re-Entry or Being Relieved I a) Report to the PCC for accountability. b) The PCC Director informs the TSC. 3.0 Resoonsibilities 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 The PCC Director is 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. In particular, his responsiblities include the following:
= Continued personnel accountability; O -
Assurins that aii emerseacx werkers at-risk are evaluated by the Senior Health Physics representative at the TSC with regard to a need for thyroid blocking;
- Coordinates with Security personnel to control l access to the owner controlled area (Shift l Supervisor, in the capacity of Emergency l 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 i nj u. red I personnel; Coordinates access for personnel arriving from outside the plant with Weld County Sheriff's l Department;
- Coordinates entry /re-entry of required personnel with the Lead Security Officer;
- Relocates the PCC to an alternate onsite or
- offsite location, as required; + l s
FORM 372 22 3643
t. P PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 of 14
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- 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.
3.2 Senior Health Physics Representative (TSC) The senior Health Physics representative at the TSC is l responsible for the direction of radiological monitoring I teams dispatched from the PCC. He is also responsible for assessment of protective clothing, dosimetry, and equipment requirements and maximum stay times for the teams. 3.3 Personnel Accountability and Exposure Control Personnel Accountability personnel are responsible for O =>4at 4a4#9 exposure comt4a#ed estimates, aersomaei handling accouat b4'4*v search and
#d rescue assignments, performing first aid and personnel decontamination, and assisting.in the medical transport of injury victims.
The initial personnel accountability assessment prior to activation of the PCC shall be handled in accordance with Administrative Procedure G-5 and Security Instruction 6.10. 3.4 Maintenance, Repair, and Damage Control Perform mechanical and electrical repair / damage control, emergency maintenance, and temporary modifications. , 3.5 Hazards Control Extinguish fires, purge hazardous gases, and combat natural emergencies. 3.6 Other Personnel Detailed responsibilities of personnel assigned functions of Recorder, Communications, Decontamination, Security, Drivers, First Aid, and Instrument Repair / Accountability may be found in the Attachments to this procedure. + FORM 372 22 3643
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'7 PUBLIC SERVICE COMPANY OF COLORADO [P-P ue FORT ST. VRAIN NUCLEAR GENERATING STATION page 14 of 14 c_
4.0 References 4.1 FSV Radiological Emergency Response Plan 4.2 State Radiological Emergency Response Plan 4.3 PPC-83-1336 5.0 Referenced or Supporting Procedures 5.1 RERP-ORG, FSV Emergency Organization and Responsibilities 5.2 RERP-FIELD, Field Monitoring Procedure 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 l 5.7 RERP-CR, Control Room Procedure m 5.8 RERP-HOME, Home 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 5.15 HPP-12, Portable Air Sample Collection and Analysis t 5.16 HPP-21, Surface Radioactive Contamination Surveys l
5.17 HPP-37, RERP Inventory List ; 5.18 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 1 l t p 5.20 G-5, Personnel Emergency Response !
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A RE PUBLIC SERVICE COMPANY OF COLORADO , } FORT ST. VRAIN NUCLEAR GENERATING STATION IS$ye 14 Page 1 of 3 p bi PERSONNEL ACCOUNTABILITY AND EXp0SURE CONTROLLER
- 1. Assume the duty of maintaining accountability and recording personnel exposure for evacuated personnel and for emergency team personnel leaving the PCC on assignments.
- 2. Issue film badge and dosimeter (s) (at least a high range dosimeter is required for all team members). Record initiai 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 Expcsure Controller upon their return / arrival to the PCC.
- 4. Logged Exposure is Final Dosimeter Reading minus Initial Dosimeter Reading. _
.n (J 5. Current Exposure is Previous Exposure plus Legged Exposure.
- 6. Each time an individual is sent out on a team assignment, there should be a separate entry on the Personr.t1 Accountability and Exposure Record Forn. 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 parsennel on-site and at the Personnel Control Center.
- 9. Maintain accountability and recording of personnel contamination.
4 FORM 372 22 3643
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. PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION h
Issue 14 t2 Page 1 of 3
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N._m] l Datasheet 2 l Briefino Sheet for Field Monitorino Teams l (To be completed by senior HP representative at the TSC) l l l 1) Area to be surveyed i I l 2) Route to be taken I i 1 (] l 3) Calculated or estimated parameters l a) General Radiation Level (mrem /hr) l b) Airborne Activity Level (1:ci/cc) i l 4) Projected Time to complete survey (hr) l 5) Projected Exposure l 3)a) x 4) x 1.25 = (mrem) l 6) Maximum Stay Time (based upon 10CFR20 limits or, with th.e TSC l Director's Concurrence, the guidelines of RERP-EXP, Emmcgency l Exposure Guidelines) l (br)
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4' FORM 372 22 3643
a PUBLIC SERVICE COMPANY OF COLORADO t2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 ; Page 2 of 3 I O V l 7) Team Members: 1 I l 8) Dosimetry requirements: l Pocket Dosimeter - High Range (required) l Other required dosimetry (circle): l Film Badge l Pocket Dosimeter - Low Range O i l 9) Protective Equipment requirements l (Circle required equipment): l Full Anti-C's l Shoe Covers and Gloves . l . No Protective Clothing Required f l Full-Face Respirat'or 1 l l l Scott Air Pack l Thyroid Blocking Agent (see RERP-THYROID) l No Respiratory Protection Required PORM 372 22 3643
n' PUBLIC SERVICE COMPANY OF COLORADO t2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issu3 14 Page 3 of 3 O l 10) Comments: I a) Save used filters and cartridges for Radiochemi stry l analysis. l b) Leave the emergency vehicle running while in the field and l upon return to avoid battery discharge. + O FORM 372 22 3643
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. . , PUBLIC SERVICE COMPANY OF COLORADO Da t3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 3 'U) l Datasheet 3 l Briefing Sheet for Inolant/Onsite Monitoring Teams l (To be completed by senior HP representative at the TSC)
I 1) Area to be surveyed u I I l 2) Known parameters - l a) General Radiation Level (mrem /hr) l Det'ector RIS-(q> l b) Airborne Activity Level (vci/cc) l Detector 2 l c) Surface Contamination Levels
- DPM/100cm l 3) Projected Time to complete survey (br) l 4) , Projected Exposure l 2)a) x 3) x 1.25 = (mrem) l 5) Maximum Stay Time (based upon 10CFR20 limits or, with the TSC l l Director's Concurrence, the guidelines of RERP-EXP, Emergency l l Exposure Guidelines) l (hr) i* This parameter may be unknown prior to team deployment.
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i k l PU LIC SERVICE COMPANY OF COLORADO Da t3 l 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 2 of 3 l l l 6) Team Members: 1 I I l 7) Briefing of HP Techt ician Team Leader By: l (PCC Director). l 8) Dosimetry requirements: l Pocket Dosimeter - High Range (required) l Other dosimetry requirements (circle): l Film Badge
- l Pocket Dosimeter - Low Range i
l l TLD Finger Ring l Othor: l 9) Protective Equipment requirements l (Circle required equipment):
-l Full Anti-C's l Shoe Covers and Gloves l No Protective Clothing Required l Full-Face Respirator l Scott Air Pack l Thyroid Blocking Agent (see RERP-THYROID) l 'No Respiratory Protection Required O +
FCRM 372 - 22 3643
a PUBLIC SERVICE COMPANY OF COLORADO Da t3 FORT ST, VRAIN NUCLEAR GENERATING STATION Issue 14 Page 3 of 3 l 10) Comments: I a) Save used filters and cartridges for Radiochemistry I analysis. l O
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, PUBLIC GERVICE COMPANY OF COLORADO Da t4 Issue 14 f FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 3 O %.)
l Ditasheet 4 l Briefino Sh' set for Emeroency Teams 1 i l 1) Area (s) to be entered ; I l l 2) Known parameters: l a) General Radiation Level (mrem /hr) l Detector RIS-l b) Airborne Activity Level (uci/hr) l Detector l c) Surface Contamination Levels
- DPM/100cm2 l 3) Projected Time to complete task (hr)
{} l 4) Projected Exposure l 2)a) x 3) x 1.25 = (mrem) l 5) Maximum Stay Time l* Based upon 10CFR20 limits (3 rem / quarter whole body with I completed NRC Form 4, 3 E-09pci/cc unidentified airborne l contamination) or, with the TSC Director's Concurrence (NOTE: l Prior to activation of emergency organization, the Shift l Superviser may authorize exposures in excess of 10CFR20 limits), l the guidelines of RERP-EXP, Emergency Exposure Guidelines l (br) l* This parameter may be unknown prior to team deployment. f l l i O
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i& FoPM 372 22 3643
i^ RE PUBLIC SERVICE COMPANY OF COLORADO , g FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 2 of 3 1 l l 6) Team Members: I I l 7) Briefing of Team By: l 8) Dosimetry requirements: l Pocket Dosimeter - High Range (required) l Other required dosimetry (circle): l Film Badge l Pocket Dosimeter - Low Range s O l TLD Finger Ring 1 l 9) Protective Equipment requirements
] (Circle required equipment):
l Full Anti-C's l Shoe Covers and Gloves l No Protective Clothing Required l Full-Face Respirator j . l Scott Air Pack O i Thyroid Biock4ns Asent csee RERe-THvRDID) 4 ( EL F OR M 372 - 22 3643
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. PUBLIC SERVICE COMPANY OF COLORADO Da et 4
- FORT ST. VRAIN NUCLEAR GErlERATING STATION Issue 14 Page 3 of 3 O
l No Respiratory Protection Required l 10) Comments: O E i O O ._. .__ FORM 372 3643 l l
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PUBLIC SERVICE COMPANY OF COLORADO ck t1
. FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 5 PCC DIRECTOR'S CHECKLIST TIME NOTE: All information is to be logged by the Recorder.
- 1. Notification received to initiate Personnel Control Center (PCC) at the following location: .
- 2. Notify alternate director of emergency conditions and location of PCC. During off-duty hours, advise alternate to complete call list, location of PCC and wind direction.
- 3. Notify Health Physics to proceed to PCC to verify habitability (normal working hours).
O' 4. corr eviv hours) sexe or rea#est se >=rvex or habitability.
- 5. Habitability confirmed at PCC.
- 6. (Normal working hours) make announement by using telephone. Dial 6-0-4 and announce "PCC Emergency Team, report to Personnel Control Center located at . All other personnel remain at your emergency station." (Verify announcement was communicated by checking with Tech. Support Center personnel.)
l O JL __ _. _ FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO Ch k t1 T '
, FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 2 of 5 O'
<j P_CC DIRECTOR'S CHECKLIST TIME
- 7. Assign duties to arriving PCC response team members.
Note: Do not dispatch personnel from the PCC except under the direction of the TSC Director, and only after the senior Health Physics representative at the Tech. Support Center has been consulted. Name Time a) Health Physics (Habitability) b) Personnel Assignment Controller Note: Advise assignment controller to assign duties to other PCC emergency team members.
- 8. Controlled area established. All doors
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locked except the one being utilized for , controlled entry into the PCC.
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- 9. Manning requirements adequately met.
- 10. Verify area set up to receive contaminated i personnel.
l l
- 11. Notify Tech. Support Center of PCC status.
- 12. Status of plant and emergency as well as l assessment of condition received from Tech.
l Support Center.
- 13. Transport of injured / contaminated person (s) to St. Luke's Hospital required?
PORM 372 22 3643
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n" PUBLIC SERVICE COMPANY OF COLORADO k t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 7 Page 3 of 5
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PCC DIRECTOR'S CHECKLIST TIME a) If so, indicata transported individuals. b) TSC Director notified of need to transport injured / contaminated personnel offsite for treatment.
- 14. Wind direction and affected sectors identified, and need for protective -
clothing / equipment established by TSC.
- 15. Deployment of radiological monitoring teams requested by TSC.
l 16. Field Monitoring Teams l a) Briefing Sheets completed (Datasheet 2). l 1) EAB l 2) EPZ l b) Briefing of teims conducted. l 1) EAB l 2) EPZ l c) Teams dispatched. l 1) EAB l 2) EPZ O PORM 372 + 22 - 3b43
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1 PUZLIC SERVICE COMPANY OF COLORADO k t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 ,9
~
Page 4 of 5 O V pCC 0! RECTOR'S CHECKLIST TIME l 17. Inplant/Onsite Monitoring Teams I a) Briefing sheet completed (Datasheet 3). l l b) Briefing of team (s) conducted. - l l c) Team (s) dispatched. I l 18. Emergency Teams l a) Briefing sheet completed (Datasheet 4). I l b) Briefing of team (s) conducted. I l c) Team (s) dispatched. l l 19. Personnel dispatched to establish road blocks to the North and South of tLie plant along County Road 19 . IF NOT ALREADY DONE BY COUNTY / STATE LAW ENFORCEMENT AGENCIES. l 20. STANDARD MESSAGE FORM Completed persons living within property boundary notified AND/OR Driver (s) dispatched. l
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n PUBLIC SERVICE COMPANY OF COLORADO C L t1 FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 14 Page 5 of 5 O Gi PCC DIRECTOR'S CHECKLIST TIME l 21. Notification to Visitor's Center confirmed. l (May be performed by Emergency Coordinator.) l 22. Fort Lupton Fire Department notified to receive Visitor's Center occupants (See RERP l PHONE LIST). l 23. Personnel accountability verification completed - TSC notified. I 24. Need for immediate evaluation of film badge (s) indicated by Personnel Accountability and Exposure Contrc11er? O l 25. Additional Health Physics samples and surveys required? l 26. Additional PCC samples and surveys being performed as required (every 15-20 minutes while airborne release persists). l 27. Prepared to use PCC as a stsging area for relief and support personnel. l 28 Colorado State University Personnel arrived at PCC and TSC Director informed. O FORM 372 22 - 3643
R - CC ! .., PUBLIC SERVICE COMPANY OF COLORADO C 2 l FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14-
~
~2 l Page 1 of 1 l
im O CHECKLIST 2 Recorder PCC Closecut Checklist
- 1. Collect PCC Director's Checklist.
- 2. Collect Personnel Accountability and Exposure Controller Datasheets (Datasheet #1)
- 3. Collect any Emergency Exposure Job Briefing Datasheets utilized (RERP-EXP, '
Datasheet#1)
- 4. Attach Recorder Logs of PCC events and activities
- 5. Forward all Documents to the l FSV Nuclear Documents Supervisor for disposition.
l O l l l l O FORM 372 22 3643
x.. t .- PUBLIC SERVICE COMPANY OF COLORADO h[a nt 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 1 O
\.y RECORDER
- 1. 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.
- 2. Keep records of distribution of all contents of Emergency Kit.
- 3. Log records kept by all other PCC personnel into master log.
- 4. Assure that all data sheets and work sheets are collected and given to PCC Director when PCC operations are terminated (Checklist 2).
O O PORM 372 22 3643
a PUBLIC SERVICE COMPANY OF COLORADO nt 2 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 5 (3 V COMMUNICATIONS
- 1. EstabP sh communications with the Technical Support Center (TSC) and virify 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 s Telephone Secondary PSC Radio
- 2. When instructed to do so, inform the TSC that the PCC is manned and ready and prepared to receive personnel.
- 3. Receive status of plant and emergency and assessment of condition and inform PCC Director who will brief the PCC personnel.
- 4. With the PCC Director, fill out the STANDARD MESSAGE Form (Page 3).
- 5. ' 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.
l 6. Confirm Visitor's Center notification of emergency. Confirm l that Ft. Lupton Fire Station has been notified to receive l Visitor Center evacuees. Record time verified or notified. U 4 a FORM 372 22 3643
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.. PUBLIC SERVICE COMPANY OF COLORADO h nt 2
~
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 2 of 5 (3 V
- 7. Notify St. Luke's Hosptial in accordance with Medical Emergency Plan to prepare to receive injured and contaminated person (s) if required.
- 8. Notify a medical facility to prepare to receive injured person (s) if required.
- 9. If ne essary to relocate PCC, call facility as directed by PCC Director. Record the time of notification (See RERP PHONE LIST for telephone numbers).
- 10. Maintain communications flow between FCC and the TSC.
- 11. Keep records of all pertinent information for master log.
O i* PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ((nt 2 FORT ST. VRAIN NUCLEAR GENERATING STATION issue 14
-* Page 3 of 5 l %s)
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 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
~
FIRE DEPARTMENT), b\ G l 4 PORM 372 22 3643
I~ PUBLIC SERVICE COMPANY OF COLORADO [,P , nt 2 FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 14 Page 4 of 5 O 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 1 5. Vacant No Phone
- 6. Scott Houston 785-2358
- 7. Keith Russell 785-2589 l 8. Dave LaChance 785-6303 0
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I~ s. PUZLIC SERVICE COMPANY OF COLORADO h(([fnt2
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i' R PUBLIC SERVICE COMPANY OF COLORADO hga nt 3
. FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 2 q
DECONTAMINATION
- 1. Surv2y 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:
C If a person is injured and requires evacuation to a 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 recuired. , l l l l
* < 10 DPM/100 cm' alpha and < 100 DPM/100 cm2 beta gamma activity removable contamination outside radiological controlled areas.
1 l O l+ A - PoMM 372 22 3643 l
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RERP-PCC PUZLIC SERVICE COMPANY OF COLORADO Attachment 3 ,
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FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 1
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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.
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- I Pomu 372 22 3643 I 1
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i' PUZLIC SERVICE COMPANY OF COLORADO h*[c nt 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 1 (~') L.) FORT ST. VRAIN SECURITY DEPARTMENT PERSONNEL CONTROL CENTER RESPONSE GUARD
- 1. One guard reports to the Personnel Control Center.
- 2. Assist in gate control of authorized personnel and vehicles at the Personnel Control Center (Engineering /QA Complex) for equipment called to assist, if necessary.
- 3. Keep records of all PCC security actions taken for master log.
- 4. Ensure that the outer perimeter gate is secured and that non-PSC personnel are not admitted to the PCC without proper authorization.
- 5. Assist with radio communications and access authorizations with the LSO.
SITE RESPONSE GUARDS l 3 1. Check all site visitors ~out through Search & Identification l ! (d 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.
l 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).
{ l l O - PoRM 372 22 3643
k^ RERP-PCC PUBLIC SERVICE COMPANY OF COLORADO Attachment 5 FORT ST. VRAfN NUCLEAR GENERATING STATION Issue 14
; Page 1 of 1 i l
O' v DRIVERS l
- 1. Drive vehicles and assist teams. (Health Physics, Roadblock) 1
- 2. Obtain personnel dosimetry, instructions, maps, and communications equipment.
O I O A PORM 272 22 3643
PUBLIC SERVICE COMPANY OF COLORADO fft nt 6 FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 2 O \ L) l 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.
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- Utilize Fort St. Vrain Medical Emergency Plan as reference.
O PORM 372 22 3643
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;- . FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 1 O
INSTRUMENT ACCOUNTABILITY AND REPAIR
- 1. Repair instruments.
- 2. Keep records of who has been issued instruments.
- 3. Assist Health Physics with surveys.
- 4. Keep records of all actions taken, l
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FORM 372 22 3643
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. PUBLIC SERVICE COMPANY OF COLORADO t, L FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 14 Page 1 of 3 3
(V WORK /DATASHEET/ CHECKLIST CONTROL LIST Worksheet No. Title Number Copies j None N/A N/A l Datasheet No. 1 Personnel Accountability and Exposure 10 l 2 Briefing Sheet for Field Monitoring Teams 3 l 3 Briefing Sheet for Implant Monitoring Teams 2 l 4 Briefing Sheet for Emergency Teams 2
~ , . _ . _ _ ~ Checklist No.
1 PCC Director's Checklist 2 2 Recorder PCC Closecut Checklist 2 Attachment No. 2 Communications 2
.6 First Aid 2 l
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F OR M 372 22 3643
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RERP-PCC
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- , '> PUZLIC SERVICE COMPANY OF COLORADO WS/DS/CL
. FORT ST. VRAIN NUCLEAR GENERATINLi STATION Issue 14 Page 2 of 3 C,o FORMS USE REPORTING SHEET l 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:
l Worksheet Numbers Copies Used l l l l 1 (f Datasheet Numbers Cocies Used a Checklist Numbers Copies 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 Sheet" for the affected procedure in the affected book.
F Om u 37J . 22 3843
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, PUBLIC SERVICE COMPANY OF COLORADO g,5
, F09T ST. VRAIN NUCLEAR GENERATING STATION Issue 14 i Page 3 of 3 FORMS uSE REPORTING SHEET (Continued)
COMMENTS Reported By: Date: l Nuclear Documents Specialist
- Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the
. originating individual / department upon completion of this form to p/, , notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.
4 6 FomM 372 3643
- . . . - - . . = . . . - . . . .. . . . . .
PUZLIC SERVICE COMPANY OF COLORADO RERP-SEOC FORT ST. VRAIN NUCLEAR GENERATING STATION I of 5 O V N TITLE: STATE EMERGENCY OPERATIONS CENTER PROCEDURE ISSUANCE AUTHORIZED 4/25 % BY $ d REV EW DATE IO-lO- N TABLE OF CONTENTS Section Description Page 1.0 Criteria for Implementation................................... 2 2.0 Procedure..................................................... 2 3.0 Responsibilities ............................................. 4 4.0 References ................................................... 5 O s.o aererences or senaeriina areceeere . . . . . . . . . . . s Figure 1 State Emergency Operations Center Organization.......... 1 Figure 2 Emergency Organization ................................. 1 Checklist 1 Chec kl i st For State E0C. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Attachment 1 Support Equipment / Material........................... 1 Work / Data sheet /Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 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, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN Tile PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
~
l O Fomed 372 22 3442
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__- -- _ ..= . .a_ .._ s ._.. . , . . . . RERP-SEOC Issue 9 Page 2 of 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 0 SerVlCG PusuC SERVICE COMPANY OF COLORADO ( l ESTABLISHING THE STATE EMERGENCY OPERATIONS CENTER 1.0 Criteria For Implementation When the FSV Radiological Emergency Response Plan (RERP) requires augmentation of resources, generally for an ALERT or higher emergency classification, the State Emergency Operations Center (State EOC) shall be activated. 2.0 Procedure 2.1 Staffing The Assistant VP, Governmental Affairs (VP), or his alternate, the ~ Manager of Nuclear Engineering shall perform personnel accountability to assure that the Public Service Company manning functions at the State EOC can be met. If not during normal working hours, those personnel required to man the State EOC are notified by telephone (see RERP-HOME). It is the responsibility of the VP's Alternate, or the first person contacted by the VP, to ensure that the notifications are made. Refer to the State EOC call list for instructions, names, and phone numbers. The VP, or his alternate, shall establish communications and verify that primary and secondary communication links to the Forward Command Post (FCP) are O available. 2.2 Location The State Emergency Operations Center (State EOC)is located in D0 DES headquarters at Camp George West in Golden, Colorado. Provision is made for a facility to accomodate the needs of the media. 2.3 Function and Staffing . The State EOC is the primary point through which the Governor, or his authorized designee, exercises overall control and coordination of emergency response operations through the Colorado Division of Disaster Emergency Services (D0 DES). Staffing of the State EOC consists of authorized representatives of: a) Office of the Governor b) Division of Disaster Emergency Services c) Colorado Department of Health O
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u..___.-.. _ . _ . . . . .__._.._..__........___m__....__.. ..z.__,m..___ .._ ._ .~ RERP-SEOC Issue 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5 0 Service pusuC SERVICE COMPANY OF COLORADO OV
- 1) Provide up-to-date site information to the Public Information Coordination Team (PICT)
Chief (Governor's Office representative) and assist the PICT in the preparation of mutually acceptable news releases, fact sheets, and background material media releases, j) Briefs PSC Staff Personnel at the State EOC. k) Terminates manning by PSC personnel at the State EOC when the emergency condition is terminated. 2.4.2 Manager of Nuclear Er.gineering or Alternate (NuclearDesignManager) Provide assistance and substantiated data regarding site emergency status and conditions to local / state / federal emergency response agencies assigned to the State EOC. Receive status of plant and emergency and assessment of condition and inform VP or Alternate. 2.4.3 Radiation Specialist
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^>=$st '" aravidi"a ==6st #t$ t d e t r s rdias site emergency status and conditions.
3.0 Responsibilities 3.1 Vice President of Governmental Affairs or the Manager of
, Nuclear Engineering This individual is responsible to coordinate PSC emergency response activities with those of state / local / federal -
agencies. 3.2 Manager of Nuclear Engineering or Nuclear Design Manager This indivudual is responsibe for providing technical assistance as required, providing substantiated data regarding site emergency status and conditions, and i informing the VP or alternate of plant and emerge.ncy status. The Nuclear Design Manager assists the Manager of Nuclear Engineering as required. l . O . DOAMtB)372 22 3043 _ . . . . . . - . . . . . --m.-..,...--.
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Issue 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 5 n 0 Public Service rusuc senvoca cosaramy or cotonAno V l 3.3 Media Relations Manager This individual (Manager, Corporate Communications or Media Relations Director) is responsible for providing 1 up-to-date site information to the Public Information Coordination Team (PICT) Chief (Governor's Office ! representative) and assisting the PICT in preparation of mutually acceptable news releases, fact sheets, background material media releases, and rumor control in accordance with the "PSC RERP Public Information Plan." 3.4 Radiation Specialist The Radiation Specialist is responsible for providing assistance and substantiated data regarding the site's emergency status and plant conditions to state / local / federal emergency response agencies assigned to the State ECC. 4.0 References - 4.1 FSV Radiological Emergency Response Plan 4.2 State of Colorado FSV Radiological Emergency Response Plan
~ -
O~ 5.0 aerereecea or Seanortieo procederes 5.1 RERP-TSC, Technical Support Center Procedure
. 5.2 RERP-FCP, Forward Command Post Procedure 5.3 RERP-HOME, Home Packet for Off-Shift Notifications O .
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. RERP-SEOC Checklist 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 Page I of 1 o 0 Service pusuc sanvice couramy or cotonano Gl ASSISTANT VP, GOVERNMENTAL AFFAIRS (OR ALTERNATE) CHECKLIST FOR STATE EOC NOTE: All information is to be recorded by the Clerical Assistant Time
- 1. Personnel Accountability
- a. Technical Assistance
- b. Media Relations Manager
- c. Radiation Specialist
- d. Clerical Assistant
- e. Communications Support Person
- 2. Staffing requirements met
- 3. Communications established with FCP
- 4. FCP informed that State EOC is manned and ready
- 5. Status of plant emergency and assessment of conditions received from FCP 1
- 6. Staff briefing conducted
- 7. Location of PCC requested and receiv'd'e 1
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_.._._m . . . . . ._ _ ; _ . ; a .a _ . . . . . - _: . .. RERP-SEOC Attach. 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 9' 0Public Service pusuc ssRwee couramy or colorado SUPPORT EQUIPMENT / MATERIALS l
- 1. Communications equipment - telephones '
- 2. Fort St. Vrain Emergency Plan
- 3. State Emergency Plan
- 4. Local government emergency plans
- 5. Corporate Emergency Plan
- 6. Maps a) Fort St. Vrain b) Sectors c) Regional
- 7. Fcrt St. Vrain Station layout drawings
- 8. Office Supplies a) writing tablets b) pens, pencils, erasers I
l l O roamesm. :.aea
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RERP-SEOC WS/DS/CL PubliC FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 O 0 Service pusuc saRWCa COMPANY OF COLORADO '9' U v Work /Datasheet/ Checklist Control List Worksheet No. Title Number Copies None N/A N/A J Datasheet No. None N/A N/A 1 Checklist No. 1 Checklist for State EOC 2 J l lo roawie m.m.mo
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WS/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 0 Public Service rusuc service COMPANY OF COLORADO I' C 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 l Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this l , page, unless otherwise noted below in the comments to this reporting . , form. When this form is received, it will be necessary to replace I i n the noted number of forms, as well as this " Forms Use Reporting U Sheet" for the affected procedure in the affected book. roaw esime ne
. . . . . . , - , . - .. -.. .. . .. . . .: u .< ._ -. . .,...-u- - - - - .~..~:L-- -
RERP-SEOC WS/DS/CL Issue 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION E' OService PusuC SERVICE COMPANY OF COLORADO FORMS USE rep 0RTING SHEET (Continued) COMMENTS Reported By: Date: Nuclear Documents Specialist Date Received Date Replaced
- Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to O notify users that the procedure has been updated and that all worksheets, ch2cklists, and datasheets are present in the required number of copies.
O e I . I i O
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RERP-SEOC
" Checklist 1 Issue 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 1 l Service rusuc sanvies couramy or cotonaoo l
ASSISTANT VP, GOVERNMENTAL AFFAIRS (OR ALTERNATE) CHECKLIST FOR STATE EOC NOTE: All information is to be recorded by the Clerical Assistant
. Time
- 1. Personnel Accountability
- a. Technical Assistance
- b. Media Relations Manager i
- c. Radiation Specialist
- d. Clerical Assistant i e. Communications Support Person i O 2. Staffias reautremeats met i 3. ' Communications established with FCP i
! 4. FCP informed that State EOC is manned and ready
- 5. Status of plant emergency and assessment of 2
conditions received from FCP
- 6. Staff briefing conducted
; 7. Location of PCC requested and received l'
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RERP-SEOC Checklist 1 Issue 9 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 1
- 0 Service rusuc senvece couramy or cotonaoo s .
ASSISTANT VP, GOVERNMENTAL AFFAIRS (OR ALTERNATE) CHECKLIST FOR STATE EOC NOTE: All information is to be recorded by the Clerical l Assistant
. Time
- 1. Personnel Accountability
- a. Technical Assistance
- b. Media Relations Manager
- c. Radiation Specialist
- d. Clerical Assistant
- e. Communications Support Person
- 2. Staffing requirements met i 3. Communications established with FCP
. ~4 . FCP informed that State EOC is manned and ready
- 5. Status of plant emergency and assessment of i conditions received from FCP
- 6. Staff briefing conducted .
- 7. Location of PCC requested and received i
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RERP-SEOC WS/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 . Page 1 of 3 OPublic Service eunuc sunvece couramy or cotonano O Work /Datasheet/ Checklist Control List Worksheet No. Title Number Copies None N/A N/A Datasheet No. None N/A N/A Checklist No. 1 Checklist for State EOC 2 1 O . i k eoaum m.m.sme
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RERP-SE0C WS/DS/CL Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 9 Page 2 of 3 0 Service rusue senvics company or cotonaoo 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 l Checklist Numbers copies Used I l The procedure affected by this sheet is shown in the hesJer 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 n the noted number of forms, as well as this " Forms Use Reporting i U Sheet" for the affected procedure in the affected book. 6 fo#Wlet M . B .3eet j
RERP-SEOC WS/DS/CL Issue 9 Public FORT ST. VRAIN NUCLEAR CENERATIN3 STATION Page 3 of 3 Service rusuc sanvoca comramy or cotonano O FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: Nuclear Documents Specialist Date Received , 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 O worksheets, checklists, and datasheets are present in the required number of copies.
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- RERP-SURVEY PUBLIC SERVICE COMPANY OF COLORAD'3 Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 8 TITLE: INPLANT/0NSITE RADIOLOGICAL MONITORING ISSUANCE ,
AUTHORIZED 7 -24, BY d 7 m d _ _ _. PORC EFFECTIVE REVIEW Emc 5 8 0 JUI311984 DATE b '48' k Section Description Page 1.0 Criteria for Imo1ementation................................... 3 2.0 Procedure..................................................... 3 3.0 Responsibilities ............................................. 5 4.0 References ................................................... 6 5.0 Referenced or Supporting procedures........................... 6 Datasheet 1 Inplant/Onsite Monitoring Team Deployment ....... 1 O V Datasheet 2 Basement Floor Survey Map (E1. 4740'6") . . . . . . . . .1 Datasheet 3 Floor E1. 4756'0" Survey Map..................... 1 Datasheet 4 Floor E1. 4771'0" Survey Map..................... 1 Datasheet 5 Floor E1. 4781'0" Survey Map..................... 1 Datasheet 6 Grade Floor Reactor Butiding E1. 47 91 ' Surv ey Ma p . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Datasheet 7 Cafeteria E1. 4829'0" Survey Map................. 1 Datasheet 8 Floor E1. 4816'0" Survey Map..................... 1 Datasheet 9 Floor E1. 4829'0" Survey Map..................... 1 Datasheet 10 Control Room / Health Physics Access Survey Ma p ( E L . 482 9 ' 0" ) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Datasheet 11 Floor E1. 4839'0" Survey Map..................... 1 Datasheet 12 Floor E1, 4849'0" Survey Map..................... 1 Datasheet 13 Floor E1. 4864'0" Survey Map..................... 1 po Datasheet 14 Refueling Floor E1. 4881'8" Survey Map........... 1 PoRM 373 33 3443 m, _ _ _ _ _ _ _ - - ... . ... - - .___ _ _, _ _ _ _ _ _ . . . . . . _
RERP-SURVEY PUBLIC SERVICE COMPANY OF CO'.ORADD Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 8 ( U Datasheet 15 Elevation 4960'0" Survey Map..................... 1 Datasheet 16 Grade Floor Turbine Building E1. 4791'0" Survey Map........................... 1 Datasheet 17 Mezzanine Floor Turbine Building l E1. 4811'0" Survey Map........................... 1 l Datasheet 18 Operating Floor Turbine Building j E1. 4829'0" Survey Map........................... 1 Datasheet 19 Turbine Building, Elevations 4846'6", 4864'0", 4885'0" Survey Map ..................... 1 Datasheet 20 Turbine Building Elevations 4921'6", 4904'0" Survey Map....................................... 1 Datasheet 21 Reactor Building, Elevations 4916'8", 4906'8" Survey Map....................................... 1 Datasheet 22 Reactor Building, Helium Storage E1. 4791'0" Survey Map........................... 1 Datasheet 23 Plant Site Survey Map ........................... 1 - - - - Work / Data sheet /Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Forms Use Reporting Sheet * ....................................... 2
- ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l 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.
O LJ l l l \ postu 373 33 3443
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SURVEY PUBLIC SERVICE COMPANY OF COLORADD FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 8 q J 1.0 Criteria for Imolementation This procedure provides guidelines for the activities of inplant radiological monitoring teams dispatched after the activation of the FSV Emergency Organization, as specified in RERP implementing procedure RERP-ORG. 2.0 Procedure The purpose of this procedure is to provide generalized instructions for inplant or onsite radiological monitoring teams dispatched from the Personnel Control Center (PCC) (or, from the Health Physics Access Area) during the course of a radiological emergency at Fort St. Vrain. This procedure supplements the routine Health Physics Procedures (HPPs), and requires a working knowledge of their general content. 2.1 Monitoring Teams Monitoring teams will be dispatched from the Personnel Control Center upon approval of the Technical Support Center (TSC) Director, and under the overall direction of the senior Health Physics representative at the TSC. The team (s) shall be comprised of, as aminimum,two(2) 7m ~ ~ ~~ - individuals. Under most circumstances, this would be a () Health Physics Technician, who leads the team, and an assistant. Two team member:, are required to assure safety of the team members. 2.2 Equipment Utilize the existing inplant instrumentation to the maximum extent possible to assess the anticipated general radiation levels and airborne contamination hazards in the area (s) to be surveyed. Utilize this data with an appropriate level of conservatism to determine the protective equipment needed, as well as to establish stay time requirements (see section 2.3). The data shall also be used by the team members to determine the equipment which shall be used for the survey. , Anticipated equipment requirements are summarized below:
- Ion chamber instrument with adequate range, as determined above PIC-6A, 1 mR/hr - 1000 R/hr R02, 0.2 mR/hr - 200 mR/hr R05, 0.1 mR/hr - 1000 R/hr R07, 10 R/hr - 10' R/hr -
- Portable Air Sampler with sample cartridges. .
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- 4. .
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- Bags for transporting samples to RC Lab or HP Office for analysis.
- Wipes and envelopes.
- Protective Equipment (as determined by senior Health Physics representative at the TSC).
- Personnel Dosimetry (as determined by senior Health Physics representative at the TSC).
- Flashlights, if required.
- Portable Radio, where practical.
- Appropriate radiation survey forms for the area to be surveyed (see HPP-1).
- Pencil or Pen.
- Stop watch, or equivalent, for timing sample collection times.
- Liquid sample containers, where called for.
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- Other instrumentation as may be required per Health Physics Procedures.
2.2.1 Equipment shall be checked or calibrated as required, as described in Health Physics Procedures. 2.3 Protective Equipment / Dosimetry The proper selection of dosimetry and protective equipment . is the re ponsibility of the senior Health Physics I . representative at the TSC (Datasheet 1), however, each j member of an emergancy response team should be equipped t with at least a high range dosimeter. He shall utilize I the available indications from inplant instrumentation to assess the potential exposure and environmental hazards. External exposure guidelines shall be utilized in accordance with RERP-EXP, " Emergency Exposure Guidelines." Inhalation protection shall be provided in accordance with the guidelines specified in RERP-THYROID, " Thyroid Blocking Agent Administration." O
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'J The senior Health Physics representative at the TSC shall also provide stay time requirements for the emergency team members, of the range of minutes to hours (provide a 25%
margin of conservatism) and inform the PCC Director of the maximum radiation level anticipated and projected team exposure for use in the briefing of the survey team. 2.4 Area Approach The Health Physics Technician leading a team shall approach any area to be surveyed with an appropriate radiation detection instrument operating. If radiation levels are significantly in excess of the expected radiation levels (+25%, or more), the Technician shall withdraw the team from the area and contact the senior Health Physics representative at the TSC for further instructions and/or stay time calculation. 2.5 Exposure Control . All inplant/onsite monitoring teams deployed shall be provided pocket dosimeters of an adequate range for the l anticipated exposure. (High Range dosimetry is required, l as a minimum.) The Health Physics Technician shall assure that team members check the dosimeter reading at an - O appropriate interval for the anticipated exposure rates, and report any radiation exposures in radiation excess of projected team exposures to the senior Health Physics representative in the TSC. 2.6 Data Collection Data to be collected shall be specified by the senior Health Physics representative at the TSC. Generally, this shall consist of: a General Area Radiation Levels in area where emergency maintenance is required; General Airborne Concentration Levels in areas where emergency maintenance is required;
- Surface Contamination Levels;
- Contact exposure rate with critical equipment; and
- Collection of any liquid effluent samples for radioisotopic analysis.
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I Data survey maps are provided on Datasheets 2-23. Additional copies, beyond that stored with the procedure, are available at the Health Physics Access Area on level 7 O or 18. t=rdia a=41e4 9 ! 4 PORM 372 22 3443
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- FORT ST. VRAIN NUCLEAR GENERATING STATION page 6 of 8 l (q) 3.0 Responsibilities 3.1 Senior Health Physics Representative (TSC)
The senior Health Physics representative at the TSC maintains overall responsibility for the direction and control of any dispatched monitoring teams. Data shall be collected under his guidance, and transmitted to the TSC, via voice links, for his analysis. The senior Health Physics representative is responsible for evalucting the ext 'ing exposure rate / airborne concentration data prior to team deployment, and to determine maximum stay times for the job. He is also responsible for transmitting pertinant radiological information to the Radiological Assessmei.t Coordinator at the Forward Command Post. 3.2 Team Leader (Health Physics Technician) The HP Technician acting as team leader shall assure that all data is collected in the safest manner feasible for the situation, and shall assure that team members are made aware of radiological hazards and follow good Health Physics practices. The Team Leader shall also be responsible to assure that team radiation exposures are in accordance with the projected team exposure and as low as reasonably achievable (ALARA), and that stay times are O'V adhered to. 3.3 Personnel Control Center Director The PCC Director must assure the control and coordination of the dispatch of all emergency teams, including monitoring teams, through the senior Health Physics representative at the TSC. (See RERP-PCC.) He is responsible for briefing the team members prior to departure from the PCC, using information supplied by the senior Health Physics representative at the TSC.
. 3.4 TSC Director The TSC Director has ultimate responsibility over site activities, and shall have the authority to determine when monitoring teams shall be dispatched, and when 10CFR20 radiation exposure limits may be exceeded (see RERP-EXP).
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r SURVEY PUZLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION page 7 of 8 (% O 3.5 Radiological Assessment Coordinator (FCP) The Radiological Assessment Coordinator is responsible for the final determination as to the need for administration of Thyroid Blocking Agent (see RERP-THYROID). The Radiological Assessment Coordinator shall also confer with the senior Health Physics representative at the TSC, with regard to the importance or need for collecting various data points, personnel exposures, plant conditions, ALARA considerations, recovery plans, and other radiological matters as appropriate. A.0 References 4.1 FSV Radiological Emergency Response Plan 4.2 Title 10 Code of Federal Regulations, Part 20 5.0 Referenced or Supportino Procedures 5.1 RERP-TSC, Technical Support Center Procedure 5.2 RERP-PCC, Personnel Control Center Procedure
-p- 5.3 RERP-EXP, Emergency Exposure Guidelines O 5.4 RERP-THYROID, Thyroid Blocking Agent Administration 5.5 RERP-ORG, FSV Emergency Organization and Responsibilities 5.6 HPP-1, Intervals of Surveys and Use of Survey Maps 5.7 HPP-8, Radiation Surveys 5.8 HPP-9, Establishing and Posting Controlled Areas 5.9 HPP-12, Portable Air Sample Collection and Analysis 5.10 HPP-16, Selection and Use of Respiratory Protection Equipment 5.11 HPP-20, Operation and Calibration of Radiation Detection Instruments 5.12 HPP-21, Surface Radioactive Contamination Surveys 5.13 HPP-27, Personnel Dosimetry 5.34 HPP-45, Air Activity Analysis Using the RM 14/15 with HP
_ 210 Probe 5.15 HPP-53, RT 7325-1 and RT 73437 Filter and Cartridge pd Removal (Emergency Accident Conditions) l l.. . _ _ _ .. FORM 372 22 3643 ,
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SURVEY PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 8 O - 5.16 HPP-56, Reactor Building Exhaust Stack Discharge Activity Calculation 5.17 HPP-57, Radiation and Airborne Radioactivity Monitoring During Abnormal Releases in the Plant 5.18 HPP-66, Operation of Portable Survey Instrumentation 5.19 HPP-67, Calibration and Operation Procedure for the Eberline SAM-2 Stabilized Assay Meter e 9
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. Page 1 of 3 O,-
DatasbeeG Inplant/Onsite Monitoring Team Deployment (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- 'ht l b) Airborne Activity Level (pci/cc) Detector c) Surface Contamination Levels
- DPM/100cm2
- 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)
(hr) This parameter may be unknown prior to team deployment. L. FORM 372 22 3843 .. _. .....---n..--- - - - _ -- wrem--.--~.~.--.,. ., ~.-. . m. m m - a r
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- 6) Team Members:
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- 7) Briefing of HP Technician Team Leader By:
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- 8) Dosimetry requirements:
Pocket Dosimeter - High Range (required) Other dosimetry requirements (circle): Film Badge _ _ _ _ _ _ _ _ _. _ Pocket Dosimeter - Low Range { - 'TLD-fingerRi ng --- 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 I O. i 4 .- FOR M 372 22 - 3643 l 1 y.,__ _ _ . - ,.,-- - - - . ._-...e -,
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- 10) Comments:
l a) Save used filters and cartridges for Radiochemistry I analysis. O o O 4 ._ f ORM 372 22 3643
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