ML20101D453
| ML20101D453 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 12/04/1984 |
| From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| P-84513, NUDOCS 8412240064 | |
| Download: ML20101D453 (1) | |
Text
=c PLIblie $?rVICO (Ontpliny N Cd@lfSdG 16805 WCR 19 1/2, Platteville, Colorado 80651 i
December 4, 1984 Fort St. Vrain Unit No. 1 P-84513 4
Regional Administrator Region IV f .
fp U.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 1000 f_ M l j $3(] ,
Arlington, TX 76011 g
Attention: Mr. Eric H. Johnson . J Docket No.: 50-267
Subject:
Radiological Emergency
_ Response Plan (RERP)
Dear Mr. Johnson:
i We are transmitting herein revisions to Fort St. Vrain's Station RERP Implementing Procedures.
One copy of the RERP-CR, Issue 3 procedure is being transmitted for filing in Book 1 of the Station RERP Implementing Procedures under the tab marked RERP-CR. Attachments, data sheet, checklists, and control list should immediately follow the procedure.
If difficulties or questions arise in filing this procedure, please contact Ms Sharilyn Johnson at (303) 785-2224, extension 275.
Sincerely, 8412240064 841204 PDR ADOCK 05000267 ./ J . W. Gahm F PDR Manager, Nuclear Production JWG/dal flooG Rcrua) ole m L.
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BOOK 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 0,$9FVICO PusuC SERVM:E COMPANY OF COLORADO O -
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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 3 11-28-84 RERP-DOSE Offsite Dose Calculations Methodology 6 08-06-84 l
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TITLE: CONTROL ROOM PROCEDURE 3
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_T_ABLE 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 . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.0 References .................................................. 15 n 5.0 Referenced or Supporting Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . 16 V e Figure 1 Response Center Manning Requirements .................. 1 Figure 2 Visitor's Center Evacuation Routes .......... ........ 1
, Table 1 Non-Emergency Events: Four-Hour Reports .............. 1 Table 2 Non-Emergency Events: One-Hour Reports................ 1 Table 3 NOTIFICATION OF UNUSUAL EVENT.......................... 1 Table 4 ALERT..................................................1 Table 5 SITE AREA EMERGENCY.................................... 1 Table 6 GENERAL EMERGENCY...................................... 1 i
Table 7 Initiating Event Cross-Reference ...................... 1 Table 8 Emergency Condition Cross-Reference..............:..... 1 Table 9 Protective Action Guides .............................. 1 Attachment 1 Phone Numbers for Notification.................. 1 Attachment 2 Non-Emergency Event Notification................ 1 i'~' !
Attachment 3 Notification of Unusual Event .................. 1 PORM 372 22 3642 -
RERP-CR Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 17 0 Service PusuC senviCE COMPANY OF COLORADO l
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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 Director Checklist.............................. 1 Checklist 2 Emergency Coordinator /CR Director Checklist:
Part 2 - ALERT or Higher Event.................. 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 THE PROCEDURE -
ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLCVING EACH PROCEDURE.
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Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 17 l Service PUBUC SERWCE COMPANY OF COLORADO I
tm O 1.0 Criteria for Implementation This procedure is te 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 f] 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
, 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 the event occurs during non-working hours. It is the responsiblity of the individual response center Alternate Directors (or the first i individual contacted by the Director) to ensure l that these notifications are made (see RERP-HOME).
Refer to RERP-PHONE LISTS for instructions and personnel names and telephone numbers.
O FORM (31372 22-3M3
4 RERP-CR
, Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 17 SerVICO Pusuc SERVICE COMPANY OF COLORADO O
V 2.2 On-Shift Control Room Personnel - Procedure 2.2.1 Implement Emergency Procedure actions required to limit the consequences of the event and return the plant to a safe and stable condition.
2.2.2 If a radiological release is involved, make a preliminary assessment of the release utilizing implementing procedure RERP-DOSE to perform offsite dose calculations. Worksheets, Datasheets, and Checklists for dose calculations are contained in RERP-DOSE, as summarized below:
Worksheet 1 Monitored Release - Manual; Worksheet 2 Monitored Release - TI-59; Worksheet 3 Unmonitored Release - Manual; Worksheet 4 Unmonitored Release - TI-59; Datasheet 1 Monitored Datalogger; Datasheet 2 Unmonitored Datalogger; and Checklist 1 Monitored Datalogger.
It is the Shift Supervisor's responsbility to ensure that the offsite consequence assessments are performed as required. Radiological Assessment will become the responsibility of the. Technical Q 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 the Shift Supervisor (Emergency Coordinator).
2.3.2 Datasheet 1, " Preliminary Assessment of Plant Conditions," is provided to assist in making initial assessment of plant status.
2.3.3 Provide technical support to Control Room staff, as required.
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- Issue 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 17 Public 039tVICe PusuC SERVICE COMPANY OF COLORADO f')8 u-2.4 Shift Supervisor (Emergency Coordinator) -
Initial Responses to all Events 2.4.1 Assume the position of the Emergency Coordinator until relieved by the Control Room Director (Primary: Superintendent of Operations; Alternate: Shift Supervisor, Training), or the TSC Director.
2.4.2 As 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 respenses. Checklist 2, a continuation of Checklist 1, is provided for use in the event of an ALERT or h'gher incident.
2.4.4 If a radiological release or potential radiolog. cal 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.)
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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 Eveat, 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 actions.
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RERP-CR
- Issue 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 17 l 0Public SerVICO PUBUC SERVICE COMPANY OF COLORADO O
2.4.7.1 Non-Emergency Events l
This group of operating events comprises a series of occurrences for which, in the wake of Three Mile Island 2, there was a need to receive notification and data early-on in the situation's course of events. The reporting requirements for this group of events have been revised to include only reports of those events which are related to the operations of the NRC and which affect the safety of the operating power plant. The category has been changed from "Significant Events" to "Non-Emergency Events" and split into two categories -- those events
.which should be reported as soon as 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 1 summarizes those events and representative oceurrences which would require a four-hour report and Table 2 summarizes those that would require a one-hour O report.
Refer to section 2.5, Non-Emergency Event Procedure, for act'ons required for this event classificati n.
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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RERP-CR
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0Public SerVICO PUBUC SERVICE COMPANY OF COLORADO V
2.4.7.2 NOTIFICATION OF UNUSUAL EVENT This classification is the least severe
- Emergency Class and applies to situations where unusual events are in process (or have occurred) which indicate a potential for degradation of the level of safety of the plant.
The plant is placed in a position of readiness for a possible cessation of routine activities and/or an augmentation of on-shift resources, however, the FSV Emergency Organization is not activated for the UNUSUAL EVENT.
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 O classification are presented in section 2.6, NOTIFICATION OF UNUSUAL EVENT.
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I RERP-CR 4 Issue 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 17 Public 0SerVICO Pusuc SERVICE COMPANY OF COLORADO O 2.4.7.3 ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY Declaration of an ALERT or higher Emergency Class will require implementation of the RERP and activation of emergency response centers.
Notification of State and Federal authorities should be initiated within 15 minutes after d'claration of the emergency.
If the event is an escalation of a previous emergency classification, followup notification to the NRC should be made immediately if an open line has not already been established.
Actions to take for these events are described in section 2.7, the procedure for ALERT or higher events. If the event is an escalation from a lower category,
. proceed directly to step 2.7.3.
Tables 4, 5, and 6 outline initiating
(]) events and Emergency Action Levels for the three classes of incidents:
- Table 4 - ALERT;
- Table 5 - SITE AREA EMERGENCY; and, Table 6 - GENERAL EMERGENCY.
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RERP-CR
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Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 17 0SerVlCe PusuC SERVICE COMPANY OF COLORADO U
2.5 Non-Emergency Event Procedure 2.5.1 In the event of an occurrence believed to be defined by Table 1 or 2, the Shift Supervisor or his authorized delegate may contact one member of plant management listed in order of preference in Actachment 1, although the responsibility of initial event classification is that of the Shift Supervisor, and may not be delegated.
2.5.2 The Shift Supervisor shall inform the management contact of the event classification, or may request management advice regarding the classification.
2.5.3 The Shift Supervisor and the management contact shall jointly fill out the "Non-Emergency Event Notification" Form (Attachment 2) to ensure that both have the same information.
2.5.4 The management contact shall then contact other management personnel listed, as appropriate.
2.5.5 The Shift Supervisor shall notify the NRC Operations center of the event as soon as possible, O and in all cases, within one hour or four hours as 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 degradation of plant conditions; I
- results of evaluations or assessments of plant l conditions; I
- effectiveness of response or protective measures taken; ar,
- information related to plant behavior that is not understood.
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FORM @ 372 22 3M3
RERp-CR
- Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 17 Service PUBUC SERVICE COMPANY OF COLORADO O
V 2.5.8 No further action is required unless there is an escalation to an RERP emergency classification as show6 in Tables 3-6 of this procedure.
In case of an escalation, refer to the appropriate section:
- Section 2.6 - UNUSUAL cVENT;
- Section 2.7 - ALERT or higher event.
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. Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 17 0 Service PUBUC SERVICE COMPANY OF COLORADO O
V 2.6 NOTIFICATION OF UNUSUAL EVENT 2.6.1 In the event of an occurrence believed to be defined by Table 3, the Shift Supervisor shall assume the position of Emergency Coordinator until relieved by the Superintendent of Operations (alternate: ShiftSupervisor, Training). !
2.6.2 Notify the on-duty Technical Advisor. (Refer to Attachment 1, Phone Numbers for Notification.)
2.6.3 Contact one member of plant management listed in order of preference in Attachment 1, Phone Numbers for Notification.
NOTE: In the event that no management person
- listed can be contacted, it is the Shift Supervisor's responsibility to classify the event and make notifications as required.
2.6.4 Inform the management contact of the classification of the event, or if desired, request management advice regarding the classification.
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.
, Alternate backup methods of contacting the NRC are l given in Attachment 1, Phone Numbers for Notification.
The on-duty Technical Advisor should be kept abreast of the event status.
2.6.7 Maintain an open, continuous communication line with the NRC upon request. Report any degradation of plant conditions, results of evaluations, or response actions and results.
FORM (81372 22 3843
RERP-CR Issue 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 17
& Public
%)7 Service PUBUC SERVICE COMPANY OF COLORADO O
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 ff an escalation occurs.
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FORMit}372 22 3ss3
RERP-CR Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 of 17 o
0 Service PUBUC SERVICE COMPANY OF COLORADO O
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 t
t" 4-6 of this procedure, the Shift Supervisor shall assume the position of Emergency Coordinator, until relieved by the Control Room Director (Primary:
Superintendent of Operations; Alternate: Shift Supervisor, Training), or the TSC Director.
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.
NOTE: In the event that no management person can be contacted, it is the Shift Supervisor's responsibility to classify the event and make notifications as required.
O 2.7.4 Inform the management contact of the classification of the event, or if desired, request management advice regarding the classification.
2.7.5 Checklist 2 is provided as guidance to verify completion of required responsibilitie:.
2.7.6 Sound the Plant Emergency Alarm, if not already 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, complete the " Notification of Emergency Event" Form (Attachment 4).
FORMt51372 22 3ges
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RERP-CR Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 17 f, 0 $9fVICO PusuC SERVICE COMPANY OF COLORADO U
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 are listed in Attachment 1, Phone Numbers for Notification, and are to be used in the event that the NRC oot line" cannot be used.
Read the information on the " Notification of 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 p at the VC to depart to the Fort Lupton Fire Station
() and, depending on the wind direction, specify the departure route (see Figure 2).
Wind from North Route #3 Wind from South Route #1 Wind from East Route #1 Wind from West Route #2 )
2.7.11 Notify Security of the impending arrival of emergency personnel and provide a fequate clearance for Protected Area access, where required. (If access is required to activate TSC, refer to RERP-Phone Lists or RERP-HOME, Attachment 9, for TSC Director's call list for personnel requiring access.)
2.7.12 Establish communications 'with the TSC after l facility activation using extension 293. (See Attachment 1, Phone Numbers for Notification, for alternate numbers if required.)
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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Foftteita372 22 3843
RERP-CR Issue 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 17 l Public
$9tVICO PUBUC SERVICE COMPANY OF COLORADO q
V 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 operations. 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 supplemental 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
's TSC Director. This recommendation shall be based upon the CR Director's determination that:
Radiation levels are stable or decreasing with time;
- Releases of radioactive materials to the environment have ceased, or are controlled within Technical Specification Limits; Fires, flooding, or similar hazards,no longer pose a threat to plant environment or personnel; and
- Measures have been successfully instituted to repair or compensate for malfunctioning plant equipment.
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- Issue 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 16 of 17 g 0PublicSerVICO PUBLIC SERVICE COMPANY OF COLORADO 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 Organization (see Figure 1). The Emergency Coordinator is responsible for:
- Initial accident classification;
- Recommending protective actions;
- Initiating emergency actions to mitigate the accident; Wotifying offsite authorities (NOTE: Notifications are required to be initiated within 15 minutes after declaration of an emergency);
Diagnosing accident conditions; I Estimating radiological exposures; and Establishing communications with the TSC should the FSV Emergency Organization be activated.
Responsibility for the decision for offsite notification l 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 plant 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.
3.3 Technical Advisor The Technical Advisor is responsible to provide technical analysis and advice as requested, and to provid recommendations of corrective actions necessary to restore i the plant to a safe and stable condition.
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of 17 Plant Room Personnel handled bycontrol and 4.0 responsibilities personn e l a lreadplant soperation Re ferences 4.1 y on shift andresponsibilitie s FSV assigned are Radiologica l those 4.2 5.0 State RadiologiEmergency Respon --
ca l se Plan Referenced 5.1 u or S ortin Emergency F espons e Plan RERP-TSC, Techni Procedures 5.2 EP cal 5.3 CLASS, Event and ESupport rocedur Center F e
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RERP-CR Figure 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issus 3 "8' 'l Service rusuc sanwes couramy or cotonano O
FIGURE 1 RESPONSE CENTER MANNING REQUIREMENTS
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1 RERP-CR Figure 2 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Service rusuC SERVICE COMPANY OF COLORADO 9 O
l FIGURE 2 VISITOR'S CENTER EVACUATION ROUTES Colorado Hww. 60 Johnstown ,
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2 .
9
)g Fort Lupton Municipal 31ds.
j s.
, , (618 4th St.)
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m RERP-CR Table 1 Public FORT ST. V.1AIN NUCLEAR GENERATING STATION Issue 3 S'
0 Service PUBUC SERVICE COMPANY OF COLORADO C)
TABLE 1 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiating Event
- 1. Any event, found while 1. Determination as result of the reactor is shut- surveillance testing of Plant down, that, had it Protective Systems (PPS) that been found while the failure of PPS modules would reactor was in oper- have prevented a required ation, would have re- reactor scram from occurring.
suited in the plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that significantly l
l compromises plant safety.
O 2. Aav eveat or condition that results in
- 2. Reactor scrams. ioon shutdowns.
and automatic starting and
, manual or automatic loading of diesel generators l actuation of an only.
l Engineered Safety l Feature, including EXCEPTIONS:
( the Reactor Protection System. a) Manual scram initiated at 2% during a normal shutdown.
b) Only one of three channels tripped manually or auto-'
matica11y, but no final protective action takes place, nor is required.
l i
' 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.
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RERP-CR Table 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 0Public SGIVlCG Pusuc SERVICE COMPANY OF COLORADO (vD
~
TABLE 1 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 Buildtag sump pumps taken out of pull-to-c) control the release lock. Setpoints not reset.
O or redio et've material; or d) Loss of HEPA filtration.
d) mitigate the con-sequences of an accident.
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FonM(el372 22 3M3
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1 RERP-CR l Table 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 OSerVICO PuaLIC SERVICE COMPANY OF COLORADO
- 98
'd TABLE 1 NON-EMERGENCY EVENTS: FOUR-HOUR rep 0RT Event Typical Indication Initiating Event
- 4. a) Any airborne radio- 4. As determined by analysis active release that and evaluation.
exceeds 2 times the applicrble 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 O poiat of eatry iate 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 treatment.
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RERP-CR
. Table 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 0 Service rusuC SERVICE COMPANY OF COLORADO S U r-(T >
^
l TABLE 1 1 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiating Event
- 6. Any event or situation, 6. a) Onsite fatality for which related to the health a news release will be made.
and safety of the public or onsite personnel, or b) Inadvertent release of protection of the environ- radioactive material not ment, for which a news in excess of 10CFR20 limits release is planned or for an unrestricted area, notification to other but requiring report to government agencies has the State.
been or will be made, c) Oil or chemical spill which could reach the South Platte River or St. Vrain Creek and which is therefore reportable to the EPA.
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RERP-CR Table 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issus 3 O $9tVICO PusuC SERVICE COMPANY OF COLORADO O
TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR REPORT 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 licensed O operator.)
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FORM (t)372 22 3843 l
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. .q RERP-CR Table 2 -
Public FORT ST. VRAIN NUCLEAR GENERATING ST/. TION Issue 3 Service PUBUC SERVICE COMPANY OF COLORADO #E' U O -
TABLE 2 s.
NON-EMERGENCY EVENTS: ONE-HOUR rep 0RT
?T Event ~ ,
Typical Initiating Event 1
- 2. Any event or condition i I
during operation that I results in the condi-tion of the plant, including its principle safety nar<;ers being seriously r.2yaded; or j results in th: plant I being:
a) In an unanalyzed 2. a) As determined.
1 I
condition that significantly.
compromises plant safety;.
b) In a candition b) 1. Reactor pressure i that is outside excess of design O the design basis of the plant; or limits with failur to trip.-lani.,
11
, 2. Winds ev .,ced in excess of FSAR design levels.
c) In a condition c) As determined.
not covered by the plant's l operating and emergency l procedures.
l 1
- 3. Any natural phenomenon 3. a) Toxic ga> raiease in i m.e-or other external -
diate cicinity of plant.
condition that poses an ar.tual threat to the b) Extremely high winds or safety of the plant or severe storm preventing fignificantly hampers plant personnel from site personnel in the completing requisite performance of duti o assignments, necessary for the s Afe operation of the plant. ,
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RERP-CR Table 2
'Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 9'
[(SerVICO Pusuc SERVICE COMPANY OF COLORADO O
TABLE 2
\
NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical Initiating Event
- 4. Any event that res'ults 4. a) Loss cf significant in a major loss of portion of Control Room emergency assessment indication.
capability, off site 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 fcca chlorine cylinders, perfor;ance of duties necessary for the safe c) Accidental gaseous ri.dio-operation.of the plant, logical release resulting including fires, toxic in onsite concentrations 9ts releases, or in excess of 10 CFR 20
- O radioactive releases. Appendix B, Table I.
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FORMts)372 32 3043
RERP-CR
. Table 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 0Public $9IVlCe PusuC SERVICE COMPANY OF COLORADO 9"
(^':
v 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 affluent in discharge offsite.
excess of Technical Specification limits. b) As determined by station personnel.
O 3. Indication of minor 3. a) 25% increase in fuel damage detected circulating activity in primary coolan+. 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 l of radiologial '
or toxic materials.
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FOAM (B)372 22-3843 ,
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RERP-CR l Table 3 )
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 2 of 4 Service rusuc suavice comeAmy or cotonaoo O
V TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 5. Abnormal coolant temp- 5. Violations of eratures or core region LCO 4.1.7 or LCO 4.1.9 temperature rises for region outlet to the extent mismatch, or region requiring shutdown in AT, respectively, accordance with to the extent that Technical Speci- shutdown per Station fications. Technical Spect-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) c)
r'aeds 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
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ponutot372 22 3ps3
RERP-CR Table 3
~
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 !
9 Service PUBUC SERVICE COMPANY OF COLORADO O
TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 7. c) Onsite or near site plant related accidents that could result in the release of toxic material or spills of flammable materials.
- 8. Any serious radio- 8. As occurring.
logical exposure of plant personnel or the itansportation to offsite facilities of contaminated personnel .
who may have been injured.
O ( rod bir cea#at 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 1
- 2) SteamNater Dump System - LCO 4.3.3
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RERP-CR l Table 3 l A Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issum 3 9*
J
%FService pusuC SERVICE COMPANY OF COLORADO O
TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication 10.(Cont). 3) PCRV penetration flow restriction devices - LC0 4.2.7 and LCO 4.2.9
- 4) PCRV penetration secondary closures -
- 5) PCRV Safety Valves -
- 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. Datai.oggerAlarm/ Alarm on radiological effluent Summary indication of non-monitors not functional. operational alarm or indication on:
a) RT 7324-1, 2 and RT 4803; or b) RT 73437-1, ?, RT 4802, and RT 7325-1; or c) RT 73437-2 and RT 4801; or d) RT 6212 and RT 6213.
NOTE: Use ELCO 8.1.1 Technical Specification Limits as basis.
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RERP-CR Table 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 9
$9fVICO PusuC SERVICE COMPANY OF COLORADO O
TABLE 4 ALERT Event Indication
- 1. Rapid, severe fuel 1. Coolant Inventory of particle coating a) >2.4{ril(Mev) Beta-Gamma failure. lb b) circulating I-131 activity equivalent >24Ci c) plate out I-131 >1x10* C1 d) SR 5.2.6 or SR 5.2.11 results.
- 2. Rapid, gross failure of 2. Loop 1 Hot Reheat Header (HRH) one steam generator reheat activity high (5 mrem /hr);
section with loss of or, Loop 2 HRH activity offsite power. high (5 mrem /hr) accompanied by 230 Kv OCB trips and RAT undervoltage/ loss O of power aiarm.
- 3. Primary coolant pressure 3. PAL 9335 decay (to a value greater PAL 9347 than 100 pst less than PAL 9359 normal pressure, aM 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 cf 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.
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RERP-CR Table 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 9
Service pusuC sERWCE COMPANY OF COLORADO l3, u
TABLE 4 ALERT Event Indication
- 5. Loss of offsite power ag 5. 230 KV OCB trips and RAT vital onsite AC power undervoltage/ loss of power alarm for up to 30 minutes, accompanied by 4 KV bus undervoltage, 480V bus under-voltage, and Diesel Trouble alarms.
- 6. Loss of all vital 6. DC bus 1 < 10 volts and DC power for up to DC bus 2 < 10 volts 30 minutes. -
- 7. Loss of primary coolant 7. All He flow indicators read forced circulation for zero.
between 2 and 5 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 subcritical condition by scram of the control b) Neutron rods. count rate not decreasing.
- 10. Serious fire which could 10. a) Any of various alarms on lead to substantial Fire Control Alarm Panel degradation of plant safety systems. b) Fire Pump 1A auto start .
c) Verbal reports These times are LOFC from 100% power. Times may be correspondingly longer for lower power levels. (See LCO 4.2.18 for time available to initiate depressurization as a function of reactor power level.)
l FORM (81372 22 3M3
RERP-CR
. Table 4 Public ' ORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 0 Service rusuC sERWCE COMPANY OF COLORADO 9' O
TABLE 4 ALERT Event Indication
- 11. Radiological effluents 11. a) RT 7324-1 indicating exceed 10 times technical 22.5 x 10 2 pCi/cc specifications instan-tenous limits. b) RT 7324-2 indicat.ng 22.5 x 10 2 pCi/cc c) RT 7325-1 indicating 27.0 x 10 ' pCi/cc d) RT 7325-2 indicating
~
27.0 x 10 ' pCi/cc e) RT 73437-1 indicating
~
27.0 x 10 ' pCi/cc I-131.
O <> at 48oz '"dic t'#9
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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. a) As observed or reported.
compromise.
13.' Severe natural phenom-
- 13. a) Seismic recorder operate enon being experienced (2.05 g) or projected, such as:
a) earthquake exceeding b) As Reported Operating Basis Earthquake levels; c) As Reported b) flood near design level; or, c) tornado striking facility.
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- RERP-CR Table 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Service rusuC SERVICE COMPANY OF COLORADO S Il v
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-periencedoranticipated.)
- 15. Evacuation of control 15. As deemed necessary by O room anticipated or required, with control of Shift Supervisor shutdown systems estabitshed from local stations.
(Control room integrity breacht.d.) .
- 16. All alarms 16. Control room observation.
(annunciators) lost for more than 15 minutes and reactor is not shutdown; or, plant transient experienced while all alarms lost.
'(Parameter indication still functional.)
- 17. Other plant conditions 17. As deemed necessary by warranting precautionary Shift Supervisor.
activation of the PCC, TSC, and FCP.
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RERP-CR Table 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION ' Issue 3 Service PUBUC SERVICE COMPANY OF COLORADO 9"
(")
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.
See LC0 4.2.18)
- 2. Non-isolable primary 2. Loop 1 or 2 HRH activity l coolant leakage through a alarm-high with Shift steam generator reheat Supervisor determination section. that leakage is non-isolable.
- 3. PCRV relief valve remains 3. RT 93252-12 alarm and rapidly open. decreasing Reactor pressure.
O 4. Determination of inability 4. 230 KV OCB trips ad RAT to restore onsite AC undervoltage/ loss of power power. alarm accompanied by 4Kv bus undervoltage, 480v bus undervoltage, and Diesel Trouble alarms. Standby Diesel Fail to Start.
- 5. Loss of functions needed 5. Inability to insert l for plant hot shutdown. sufficient control rods accompanied by failure of emergency reserve shutdown system - resulting in inability to maintain .014p at 220 F.
- 6. Major damage to spent 6. a) Visual observation.
fuel due to severe cask damage resulting in release b) Area radiation monitor of radioactivity to plant alarms.
environs.
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FOftM(8)372 22 3843
, RERP-CR Table 5 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 9
$9fVICS Pusuc SERVICE COMPANY OF COLORADO TABLE 5 SITE AREA EMERGENCY Event Indication !
- 7. Fire adversely affecting 7. a) Fire pump 1A start; safety systems, b) Fire Control Alarm Panel c) Various alarms according to affected safety system.
d) Shift Supervisor determines fire beyond capability of station staff.
- 8. a) Effluent monitors 8. Stack monitor alarm with detect levels corresponding stack corresponding to concentration indications f greater than 50 mrem / on:
' hr,or greater than 500 mrem /hr a) RT 73437-1, RT 4802, whole body for two c.nd RT 7325-1, 2
~
minutes at the 26.7 x 10 5 pCi/cc site boundary under I-131; or, adverse meteorology (or levels 5 times b) RT 7324-1, 2, the above for thyroid and RT 4803
~
dose rate). >6.6 x 10 8 pC1/cc b) These dose rates are mixed noble gasses.
projected based on other plant parameters or are
.neasured in the environs.
- 9. Imminent loss of physical 9. Situation evident.
control of the plant due to security breach.
(Response detailed in Station Security Plan.)
C)
FORM 181372 22 3043
' RERP-CR Table 5
~
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 i Service rusuc SERVICE COMPANY OF COLORADO 9" (3
V 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 levels greater than 90 mph O' or 10-second gusts exceeding 99 mph Q 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 shatdown 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 g (DBA #2) radiation alarms.
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- RERP-CR Table 5
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Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Service PUBUC SERVICE COMPANY OF COLORADO 9' n
G TABLE 5 SITE AREA EMERGENCY Event Indication
- 13. Evacuation of control 13. Remote :hutdown 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/E0Cs, monitoring teams, and precautionary public notification.
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FORM 181372 22 3043
RERP-CR Table 6 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 1 Service rusuc senvece comeAny or cotosiano O
G' TABLE 6 GENERAL EMERGENCY Event Indication
- 1. a) Effluent monitors 1. Stack monitor RT-7324-1, 2 detect levels alarm, or corresponding to corresponding dose 1 rem /hr whole rates determined'with body (or 5 rem /hr E-500 or cutia pie l 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.
' O 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.
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- RERP-CA Table 7 Issue 3
- Page 1 of 2 1
TABLE 7 INITIATiteG EVENT CROSS-REFERDjQL 4
l le0TIFICATION OF SITE AREA GENERAL
> ' UIIUSUAL EVENT ALERT EMERGEf1CY EMERGE 10CY radioactivity 1. unplanned release to 1. high radiation effluent monitors effluent monitors
. cvent reactor building or levels indicate 50 mres/hr indicate 1 res/hr its vents (1000 x normal) WB for 1/2 hour WB ( 5 res/hr
- 2. seny liquid release 2. effluents 10 x ( 250 mrom thyroid) or thyroid at exclusion I Tech. Spec. limits Tech. Spec, limits 500 mrom/hr WB for 2 a rea bounde ry l min. (2.5 rem thyroid) under actual at site boundary under meteoro;ogy or artverse meteorology or slallar dose rates ssellar dose rate projected)
! projected fuel 1. Indication or minor rapid and severe major duel damage damage damage in shipping cask
- 2. accidents within Colorado allowing release to involving fuel / waste plant en* Irons shipments Fire 10 minutes, possible serious, possible arrects safety systems sarety system degradation; substantIai sarety possible release of r/a / system degradation toxic matarlets natural phenomena severe, occurring or severe, component severe, component strains projected; risks strains near design levels (plant
< normal levels design levels not in cold shutdown) unusual hazards on/near site; impacts facility impacted / vi ta l a rea impacted /
explosions / accidents; explosion damage severe damage to shutdown could errect plant / release arrecting plant / entry equipment / vital area
. toxic / flammable material into facility / entry of toxic /
environs of toxic / flammable flammable gas gas security on going security security breach causing security breach compromise imminent loss of plant causing loss physical control of plant physical control l-e 4
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.i I RERP-CR I- Table 7 issue 3
'f
- Page 2 of 2 l
i i .
t t TABLE 7 j INITIATING EVENT CROSS-REFERENCE NOTiflCATION Of SITE AREA GENERAL i UMUSUAL EVENT ALERT EMERGENCY EMERGENCY i . a la rms effluent monitor problems all alarms lost for 15 t (ELCO 8.1.1) minutes and reactor not shutdown or transient experienced while alarms out l ,
- 1. loss or offsite inability to restore i! -
electrical power coupled with onsite AC
! - loss of vital AC power up to 30 minutes
- 2. loss of vital DC up to 30 minutes S/C gross failure or RH non-isolatable leak
! section coupled with through RH section
{
orrsite power loss plant 1. loss or engineered 1. prir a coolant 1. loss or primary coolant sarety feature p r ev. decay ci rcula t ion 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />
- 2. abnormal coolant / core couple,. with (more time for lower temps. requiring shut- stack s ta res power levels) down because of Tech. 2. loss or forced 2. loss or functions Specs. prima ry coolant needed for hot circulation 2 to 5 shutdown hours 3. PCRV rel ler va lve .
t
- 3. cont ro l rod inser- doesn't resca t tion problems 4. DBA #2 l 4. seconda ry coolant- 5. CR evacuation, inability
- residual heat rwmoval to control within 15 min.
system problems
- 5. evacuation of CR/ .
I shutdown from I-49 I
ciscellaneous serious radiological any other event any other event any other plant exposure to personnet/ warranting manning warranting manning of condition that transportation or con- or response centers response centers and allows possible i taminated person to precautiona ry public release or la rge
, off site racilities notirscation amounts of r/a I
. - _ _ - . . __ _ - . . _ = . _ . -
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- 4 RERP-CR
- d. t Table 8 i Issue 3
. . Page 1 of 1 h
TA8LE 8 EMERGE 90CY CONDITIOai CROSS-REFERENCE
! NOTIFICAT'10N SITE AREA CENERAL 091 USUAL EVENT ALERT EMERGEPCY EMERGENCY
., events are in have potential for have potential for involve actual or involve actual or a progress or have degradation of plant substatia l degra- likely railure(s) incinent occurred that level of safety dation of plant of plant protective substantial core level of safety equipment deg rada tion exists
' radioactive none requi-ing off small f ractions EPA PAGs except may exceed EPA PACS releases site monituring of EPA PACS near site boundary notification State /loca l/redera l Sta te/loca l/rede ra l Sta te/ loca l/rede ra l Sta te/loca l/redera l 4
emergency response not manned manned manned manned centers
!! rad ia t ion not oispatched , could be dispatched dispatched dispatched monitoring teams
,, protective at,tions none none considered initiated
. onsIto evacustIon no no could occur could occur status updates ' none ir applicable p rovided p rovided j
'I to offsite cutho ri t ies State monitoring not dispatched not dispatched dispatched dispatched teams L -
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O O . .O RERP-CR Table 9 issue 3
' Page 1 of 1 TABLE 9 PROTECTIVE ACT1088 CUIDES Recommended protective actions to reduce whole body and thyroid dose from exposure to a gaseous plume Gene ra l Publiq Projected Dose (Rem) to the P7eulation R t- .- d Actions fel Comeents Whole Body less than 1 flo planned protective actions Previously recommended (b). State may issue an protective actions may Thyroid less than 5 advisory to seek shelter and be reconsidered or await further instructions. to 1mina ted.
Monitor environmental radiation levels.
Whole Body 1 to 5 Seek shelter as a minimum. If constraints exist, Consider evacuation. Evacuate special consideration Thyroid 5 to 25 unless constraints make should be given for it lep ract ica l . evacuation of children Monitor envi ronmental and pregnant women.
radiation levels. Control SCCess.
Whole body 5 and above Conduct mandatory evacuation. Seeking shelter would be honitor environmental an a l te rna tive i f" Thyroid 25 and above radiation levels evacuation were not and ad,Just area for immediately possible.
mandatory evacuation based on these levels. Control access.
(a) .These actions a re recommended limits for planning purposes. Protective action decisions at"Protec the timet of the incident must take existing conditions into consideration (refer to RERP implementing procedure RERP-PAC, ive Action Guideline Recommendations").
(b) At the- time of the incident, officials may implement low-impact protective actions in keeping with the principle of maintaining radiation exposures as low as reasonably achievable.
RERP-CR
- Attach. 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 E'
0 Service rusuC SERVICE COMPANY OF COLORADO O
PHONE NUMBERS FOR NOTIFICATIONS Plant Management Contacts Page Plant home Phone Ext. Phone W. J. Franek, Supt. of Operations 890-0558 218 9-532-3489 D. P. Hood, Alternate N/A 347 78-776-1843 l C. H. Fuller, Station Manager 890-0810 202 8-303-663-2363 l F. J. Novachek, Tech./ Admin.
l Services Manager 890-1941 201 8-303-457-8034 l J. W. Gahm, Manager l Nuclear Production 890-6359 200 8-303-452-0507 l F. J. Borst, Support l Services Manager 890-1775 203 8-303-663-1230 l 0. R. Lee, Vice Pres., Prod. N/A 571-7105, 8-571-7305 8-303-659-1180 Resident NRC Inspector Page Plant Home Office Phone Ext. Phone G. L. Plumlee 785-2282 890-2225 490 776-9541 O Techn4cai adviser, Page Plant, Home Phone Ext. Phone J. Sills 890-2223 265 221-5059 l J. Eggebroten 890-2220 270 651-1523 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 l (301)492-8893 (301)492-7000 Health Physics Network *22(Touch-Tone) i 22 (Rotary Dici)
Technical Support Center l Preferred extension: 293 O ^1* ra t t a>4aas: 292 or 294 i
( FORM 181372 22 343
REP.P-CR Attach. 2 FORT ST. VRAIN NUCLEAFi GENERATING STATION Issue 3 A
- 9. Public Service PUBUC SERVICE COMPANY OF COLORADO 9' 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 cf 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:
4
- 3. This notification appears to be required pursuant to 10CFR 50.72, paragraph ((b)(1), "One-Hour Report"; or (b)(2)
"Four-Hour Report")(circle one).
- 4. Description of Event:
Reactor power prior to event:
O U Loop Shutdown? Scram?
Initiating signal (s):
Was event result of an LCO Action Statement?
Other pertinent information:
- 5. Actions Taken:
O -
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . - _ - _ - _ _ __-------J
RERP-CR
, Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 OService PUBUC SERVICE COMPANY OF COLORADO 9'
/'~S G
- 6. Status:
Reactor power at time of report:
Under control by onsite staff, no offsite assistance ar.ticipated. Final report.
Under control by onsite staff. Will keep NRC advised.
Offsite assistance may be required. Will advise.
(SeeItem#7)
Offsite assistance required. (See Item #7)
- 7. If offsite assistance is anticipated or required, describe assistarice that has been or may be requested: '
O
- 8. Does the event inv..lve 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:
I l a) Name of NRC contact:
O' b) Time of NRC contact:
~~
ronu m m.m.see
RERP-CR i
- Attach. 2 )
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3
- 9' U OPublicService rusuC SERVICE COMPANY OF COLORADO
(~'h V
Management Contact a) Name of management contact:
b) Time of management contact: .
- 11. Contacts made by management:
a) Per attached call sheet log.
- 12. The Shift Supervisor and Management Contact shall send their copies of the completed forms directly to Technical Services who will:
a) Determine if a Licensee Event Report is required and prepare a facsimile copy if a 30 day report is indicated.
b) Send a copy to the Superintendent, Operations.
c) Send a copy to PORC.
O i
i 1
l t
i l
con uisi m n .aso
RERP-CR l
. Attach. 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 n
OService rusuc SERVICE COMPANY OF COLORADO 9
yi i l l I I l I CALL I TIME I DATE I CONTACT (NAME) l COMMENTS / REMARKS I I I I I I I I I I I I I 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 I I I I I I I I I I I I I I I I I l i l I I i l 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 l l I I I I I I I I I I
~O l l l l l l l l l l l l l l l l l l l l l l l l 1 I I I l i I I l l 1 1 I I I I I I I I l 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 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 l l l 1 1 I I I I I I I I I l l 1 l l I I I I I I l l
. I I I I I l l l l l l l l l I I I I I O
l mum m.n me I- -
RERP-CR Attach. 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 ;
O$9fVICO PusuC SERVICE COMPANY OF COLORADO "9' I 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 Wint s Unusual Hazards (circle one)
Aircraft Explosion Toxic Material Other(Specify)
Spent Fual Incident
- 4. Description of Event
- 5. Actions Taken
, 6. Status:
Under control by onsite staff, no offsite assistance anticipated.
Under control by onsite staff. Will keep State and NRC advised.
Offsite assistance may be required. Will advise.
(See Item 7.)
Offsite assistance required. (See Item 7.)
O .
es<en FORMitl372 2lt.3883
E
]
1 Public RERP-CR a
OSerVICOFORT ST. VRAIN NUCLEAR GENERATING Attach. 3 TATION Issue 3 S
Pusuc sanvics COMPANY DO OF #9' COLORA 7
If offsite assistance is anticipated or n assistance that has been or may be requi required, describe
~ red: _
8.
At the present w release or the potential for offsite r ltime, s te the event does no B. The affect the general health and safety e eases of th that would e public.
Emergency Coordinator will make notifi cations as follows:
L1Contactw1WstateE0C(279-8855) l and Gov or Mansion (837-8350)ernor's Tiffice (866-2471)T I.
8 READ the following statement verbatim _g l
"THIS FORT ST. VRAIN NOTIFICATION DOES NUCLEARIS NOTGENERATING STATION.
HE A NOTIFICA EMERGENCY RE THIS REQUIRES RESPONSE CENTERS. THIS QUIRE ACTIVATION OF VERIFY BY CALLINGVERIFICATION OF RECEIPT BY NOTIFICATION
- 2. 571-7436 or 785-2223 " THE STATE.
READ all the information this ATTACHMENT). recorded in Step A (Page 1 of t
C)'
\ .
L
RERP-CR Attach. 3 Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION
- S' Service PusuC SERVICE COMPANY OF COLORADO (D
v
- 3. RECORD the following information:
Name of State E0C contact Date/ Time Name of Governor's Office / Mansion Contact Date/ Time Call back verification frcm State EOC, Date/ Time Call back verification from Governor's Office / Mansion Date/ Time l I l Contact with NRC Operations Center (Hot Line or 202-951-0550) l l l (Alternate means of notification are given in Attacliment 1.)
- 1. READ the following statement verbatim:
O "THIS IS NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION AT PLATTEVILLE, COLORADO. THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO 10CFR50.72, PARAGRAPH (a)(3). THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE ORGANIZATIONS."
- 2. READ the NRC Operations Center all of the information recorded in Step A (Page 1 of this Attachement).
- 3. RECORD the following information:
Name of NRC Contact Date/ Time i
i () .
! Fonutom2 22. sees
RERP-CR
. Attach. 4 Issue 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION
V NOTIFICATION OF EMERGENCY EVENT A. The Emergency Coordinator will complete Pages 1 and 2 of this attachment with the assistance of the first management contact.
I l l Required Information l I i
- 1. This is (Name) , Shift Supervisor at the Fort St.
Vrain Station.
- 2. At (Time) we experienced an (ALERT, SITE AREA EMERGENCY, GENERAL EMFRGCNCY) Class incident.
- 3. a) There is NO, repeat NO, radioactive release taking place, and no speciaT protective actions arz recommended at this time.
0,R b) A small release I_S taking place, but at this time NO protective actions are recomniended and are not anticipated to be.
0R c) A radioactiu release IS, repeat LS, taking place,
. and we recommend that people in areas
~ remain indoors with windows and doors closed.
0R
, d) A radioactive release IS, repeat IS, 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 locatec O
T ~;m.m.m.
.' Public FORT ST. VRAIN NUCLEAR GENERATING STATION
\ '
RERP-CR Attach. 4 Issue 3 Page 2 of 5 OService rusuc senvice courAmy or cotonApo 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 Gi.s Ci/sec; Iodine C1/sec
- 6. Estimated curies released:
Noble Gas C1; Iodine Ci
- 7. Wind Velocity MPH, from degrees.
to degrees, Air Temp 'F
- 8. Stability Category . Form of Precip.
- 9. Oose rate at EAB: WB _ rem /hr; Thyroid rem /hr 2 Miles: WB rem /hr; Thyroid rem /hr 5 Miles: WB rem /hr; Thyroid rem /hr
- 10. Projected dose at EAB: WB rem; Thyraid rem 2 Miles: WB rem; TFyroid rem 5 Miles: WB rem; Thyroid rem
- 11. Estimated accumulated dose at EAB:
roa m es m . m . sea 1
49 58* 9/ O
'> IMAGE EVALUATION / d#
\ p \f gtI/ TEST TARGET (MT-3) ///jp%
4 #"/ff'4,//'4 h/ IIII/Qs /
+ <-
lll I.0 ';m Bu ti ? LE
.i ! != lklM Z l.8 1.25 1.4 1.6 4 150mm >
4 6" ->
[%*%///// /+?b
+4y)b: /////
+yf4<g,e off :
RERP-CR Attach. 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 3 of 5 0Public Service rusuc sanwen company or cotonano
- 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)
Drojected 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 radiation levels.
.. O 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
() .
row nes sn.m.see
. _ - - - . . . . . . - . . . - - . - - . . . - -. - . . . . - - - ~ . . . - .. .. -
'~
RERP-CR Attach. 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3
- 9' 0 Service PUBUC SERVICE COMPANY OF COLORADC l3 U
- 20. Description of any requested off-site assistance B. The Emergency Coordinator will make notifications in sequence as follows:
1 I l PSC Company Operator 8-571-4591 l l or 8-571-0111 l l l
- 1. INSTRUCT the Operator to initiate the "Fo-t St. Vrain
.O Redieiosicai Emersencv Ceii tist.-
- 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 .
I I l Weld County (911 Using Greeley Line) l l l l 1. READ verbatim the information recorded in Part A (Page 1 l
of this attachment).
i 2. RECORD the following information:
l Time Weld County Notified Time Weld County Callback Received 1 '
FORM (El372 22 3M3 n------ -
- RERP-CR Attach. 4 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 5 of 5 Service rusuc senvice comeAmy or cotonApo 0 .
I I l NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l l l (Alternate means of notification are given in ~
Attachment 1).
- 1. READ Items 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
~O .
O 0
FORMI51372 22 3M3 I
- RERP-CR Datash::et 1 Public rORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 E'
Service PUBUC SERVICE COMPANY OF COLORADO k
PRELIMINARY ASSESSMENT OF PLANT CON 7ITIONS TECHNICAL ADVISOR
- 1. Brief description of event
- 2. Date/ Time of event
- 3. Date/ Time of assessment
- 4. If the data logger is operating, obtain the Demand Function Printout (or print the specified displays):
NOTE: All screens and demand functions are access *ble from Display 900.
DF 69-0-0 0F 76-0-0 O oF 77-1-0 Post Trip Review Helium Inventory PRIMARY SYSTEM
- 5. Current Reactor Power
- 6. ' Rod Runback Occur (Y/N)
If yes, record positions 2A 4F
- 7. If shutdown, are all rods fully inserted (Y/N)
- 8. Circulators Operating A B C D MODE:
Steam /Feedwater/Cond./ Firewater
- 9. Purification Train A B To: Storage, PCRV, or Ventilation l 10. Is heat removal capability ade.quate at this time (Y/N) f O
FORM (Si372 22 3043
=~ r - - - - - ---,e- ,,- , _e--e,, ,_ _ _ ..
- RERP-CR Datasheet 1 Issum 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION 9'
Service rusuC SERVICE COMPANY OF COLORADO m
b SECONDARY SYSTEM
- 11. Loops Operating I II
Firewater
- 13. Status of Aux. Boilers Remarks Time Description O
O
~ ~ ~ ~'
- RERP-CR l Checklist 1 l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 OSerVICe PUBUC SERVICE COMPANY OF COLORADO 9
(3
(./
EMERGENCY C00RDINATOR'S CHECKLIST
- 1. Initiate Emergency Procedure actions.
- 2. Technical Advisor notified. (Not necessary for NON-EMERGENCY events.)
- 3. Assign preliminary assessment of radiological release taking place.
- 4. Initiate protective actions for station personnel.
- 5. Classify event, using preliminary radiological assessment, if applicable.
- 6. Contact management and confirm classification.
- 7. If event is classified as an ALERT or more severe emergency, turn to Checklist 2 for ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.
- 8. Complete Notifications Form.
NON-EMERGENCY EVENT NOTIFICATION - Attachment 2 <
O 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 I
o -
I FomM(51372 22 3843
- RERP-CR Checklist 2 Issue 3 Public . FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 2 Service rusuc senvece comeAmy or cotonano m
U 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. Select the PCC location based upon consideration of the dominant wind direction:
- 1) Training Center (Primary)
- 2) Engineering /QA Office Complex (Alternate)
NOTE: If both onsite locations are uninhabitable, alternate O offsite locations are, in the order of preference, the Johnstown County Shops, Platteville Volunteer Fire Department, and Longmont PSCo Service Center.
- 3. Complete Notifications form (Attachment 4).
- 4. Make notifications. -
PSC Operator Weld County Communications Center i
NRC Operations Center 1-lO ponugg)3rJ.22 3043
~ . - . . . - . . .
- RERP-CR Ch:cklist 2 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 9'
Service pusuC SERVICE COMPANY OF COLORADO
,m.
V. 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 l (dial 293) and notify of PCC location.
O i
FoAMitl372 22 3043
- RERP-CR WS/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 S'
OPublic Service rustic ssRviCE COMPANY OF COLORADO
%.J 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 O C8ectiist Ne.
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.
l 2 Non-Emergency Event Notification 2 l
l 3 Notification of Unusual Event 2 4 Notification of Emergency Event 2 O
FoRMiel372 22 3043
~~^ ~
r
- RERP-CR l
- WS/DS/CL l Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 O'
0 Service rusuC senviCa COMPANY OF COLORADO 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 O Datasheet Numbe_rs 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
- O .
the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book.
FORMtel372 22 204
(_
RERP-CR s WS/DS/CL FORT ST. VRAIN NUCLEAR GENEI1ATING STATION Issue 3 Page 3 of 3 0Public Service rusuc senvics couramy or cotonano O
~Q)
FORMS USE REFCATING 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 s notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.
i
- v i - --- _ _ . . _ _ _
- t. .,_. ._ .-- .. . _ - . . _.