ML20072V529
| ML20072V529 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 04/12/1991 |
| From: | Fuller C PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| P-91124, PROC-910412, NUDOCS 9104220248 | |
| Download: ML20072V529 (192) | |
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April 12, 1991 Fort St. Vrain Unit No. 1 P-91124 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Stop P1-37 Washington, D.C.
20555 DOCKET NO:
50-267 SUBJ2CT: DEFUELING EMERGENCY RESPONSE PLAN - PLANT PROCEDURE DISTRIBUTION Gr.n tl emen :
We are transmitting herein the following:
Issue 1 of DERP Plant Section 1 Issue 1 of DERP Plant Section 2 Issue 1 of DERP Plant Section 3 Issue 1 of DERP Plant Section 4 Issue 1 of DERP Plant. Section 5 Issue 1 of DERP Plant Section 6 l
Issue 1 of DERP Plant Section 7 l-Issue 1 of DERP Plant Section 8 Issue 1 of DERP Plant Section 9 Issue 1 of-DERP Plant Section 10 Issue 1 of DERP Plant Section 11 Issue 1 of DERP Plant Section 12 Issue 1 of DERP Plant Section 13 Two copies of these procedures have also been transmitted to Region IV, Emergency Response Coordinator, in accordance with 10CFR50.54(q)
(Reference P-91125).
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P-91124 Page 2 April 12,1991 In accor'ance with 10CFR50.54(q), we have determined that the changes d
in these issues do not decrease the effectiveness of the Fort St.
Vrain Emergency Plans and the plans, as changed, continue to meet-the intent of 10CFR50.47(b) and 10CFR50 Appendix E.
If difficulties or questions arise in ffling these procedures, please contact Mr. M. H. Holmes at (303) 480-6960.
Sincerely,
.al w Charles H. Fuller Manager, Nuclear Production Fort St. Vrain Nuclear Generating Station CHF/bj Attachments cc:
J. B. Baird Senior Resident Inspector Fort St. Vrain Renee Millison Senior Emergency Planning Specialist Fort St. Vrain i
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$9tVIC9' PUBUC SERVICE COMPANY OF COLORADO DEFUEdiiG EMERGEN^i RESPCNSE PuW - PUNT ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE l
Table of Contents 1'
03-29-91 1
Introduction 1
03-29-91 J
l DERP Section 1 Defueling Emergency Response Plan:
l Section 1 Definitions 1
03-29-91 1 DERP Section 2 Defueling Emergency Response Plan:
I Section 2 Scope and Applicability, 1
03-29-91 l DERP Section 3 Defueling Emergency Response Plan:
1 Section 3 Summary of the FSV DERP 1
03-29-91 l DERP Section 4 Defueling Emergency Response Plan:
I Section 4 Emergency Classifications 1
03-29-91 l DERP Section 5 Defueling Emergency Response Plan:
I Section 5 Emergency Organization 1
03-29-91 1 OERP Section 6 Defueling Emergency Response Plan, i
Section 6 Emergency Measures 1
03-29-91 l DERP Section 7 Defueling Emergency Response Plan:
l Section 7 Emergency Facilities I
and Equipm'ent 1
03-29-91 4
1 DERP Section 8 Defueling Emergency Response Plan:
I Section 8 Maintaining Emergency l
Preparedness 1
03-29-91 l DERP Section 9 Defueling Emergency Response Plan:
I Section 9 Recovery 1
03-29-91 l DERP Section 10 Defueling Emergency Response Plan, l
Section 10 Letters of Agreement
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l and Supporting Plans 1
03-29-91 l DERP Section 11 Defueling Emergency Response Plan, 1
Section 11 Maps 1
03-29-91 l DERP Section 12 Defueling Emergency Response Plan, l
Section 12 Procedures That i
Implement or Supplement the Plan 1
03-29-91 l DERP Section 13 Defueling Emergency Response Plan, l
Section 13 Listings of Emergency Kits 1
03-29-91 FORM (D1372 22 3643
l-Issue 1 39' OSerVlCOS Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO TITLE:
DEFUELING EMERGENCY RESPONSE PLAN: INTRODUCTION EST "S'
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DERP Introduction Issue 1 O Service
INTRODUCTION The Fort St.
Vrain (FSV) Nuclear Generating Station is owned and operated by the Public Service Company of Colorado (PSC).
It is a High Temperature Gas-Cooled Reactor (HTGR) rated at 330 Mw (net).
FSV began commercial operation on July 1,1979 and ended operations on August 29, 1989.
FSV is located near Platteville, Colorado, approximately 40 miles north of Denver.
The Defueling Emergency Response Plan (DERP) has been reviewed and approved by the Nuclear Regulatory Commission (NRC),
and continues to be reviewed, and tested, by the NRC.
PSC's Quality Assurance Division audits the DERP in accordance with NRC Regulations (i.e.10CFR50.54(t)), and provides recommendations for improving the program.
The FSV DERP:
(1) provides a -mechanism to classify emergencies according to the severity of the situation; (2) describes the organization that will be established to manage the emergency; (3) defines the relationships between PSC and-the various federal / state / local response organizations; (4) outlines courses-of-action and corresponding protective measures to mitigate the onsite and offsite consequences of an accident; and (5) assures a safe-shutdown mode for eventual decommissioning.
Detailed procedures have been developed to implement the plan (DERP Implementing Procedures, Emergency Operating Procedures, and Abnormal O
Operating Procedures).
These procedures provide the foundation for the FSV Emergency Preparedness Program, s
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DEFUELING EMERGENCY RESPONSE PLAN: TABLE OF CONTENTS RESPONSIBLE AUTHORIZED h
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TABLE OF CONTENTS INTRODUCTION 1.0 DEFINITIONS 2.0 SCOPE AND APPLICABILITY 3.0
SUMMARY
OF DEFUELING EMERGENCY RESPONSE PLAN 4.0 EMERGENCY CLASSIFICATIONS 4.1 Classification 4.1.1 NOTIFICATION OF UNUSUAL EVENT 4.1.2 ALERT 4.2 Non-Emergency Events 4.2.1 One-Hour Report 4.2.2 Four-Hour Report 4.3 Spectrum of Possible Accidents and Initiating Events
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5.0 EMERGENCY ORGANIZATION 5.1 Normal Station Organization 5.2 Onsite Emergency Organization 4
5.2.1 Direction and Coordination 5.2.2 Plant Staff Emergency Assigr.ments 5.2.3 PSC Media Center 5.2.4 PSC Headquarters Support 5.3 Offsite Emergency Support 5.3.1 Local Services Suppcrt 5.3.2 Contract Support 5.3.3 Federal Assistance 5.4 Coordination with Participating Government Agencies 6.0 EMERGENCY MEASURES 6.1 Activation of Emergency Response Organization 6.2 Assessment Actions g-~g 6.3 Corrective Actions V
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DEFUELING EMERGENCY RESPONSE PLAN: SECTION 1 DEFINITIONS FONSIBLE UTHORIZED PORC EFFECTIVE REVIEW PORC 9 21 FEB 131991 DATE 3-2A - @
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DERP Section 1 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 4 0Public SerVlCO*
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t 1.0 DEFINITIONS The following are selected terms commonly used in this Defueling Emergency Response Plan (DERP).
1.1 ASSESSMENT
ACTIONS Actions taken during, or after, an accident to obtain and i
process information necessary to implement specific emergency measures.
1.2 ACCOUNTABILITY Process of identifying missing, onsite personnel.
1.3 ALERT i
Events which are in process or have occurred, that involve a potential for substantial degradation of the level of safety of the plant. Any releases of radioactive material are expected to be small fractions of the EPA Protective Action Guide limits.
1.4 COLORADO DEPARTMENT OF HEALTH (COH)
The state agency with primary resp'onsibility for carrying 4
out radiological emergency assessment actions and for providing Protective Action Recommendations to the Governor or his designee.
1.5 COLORADO DIVISION OF DISASTER EMERGENCY SERVICES-(WODES) l The state agency assigned primary operational responsibility for command and control of offsite response actions in the event of a radiological emergency at FSV.
1.6 CONTROL ROOM (CR)
The CR operates under the direction of a Shift Supervisor.
It is the-primary point at which plant conditions are monitored and controlled and corrective actions taken to a.
mitigate an abnormal occurrence.. It is the location where initial assessment and classification of. an incident is initiated.
1.7 CORRECTIVE ACTIONS Measures to reduce the severity of (or terminate) an emergency situation at or near the source of the problem, to prevent an uncontrolled release of radioactive material, or to reduce the magnitude of the release.
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O SerVICO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 4 -
PUBUC SERVICE COMPANY OF COLORADO 0
. 1 1.8 EMERGENCY ACTION LEVELS (EAL's) 1 l
Para.ieters or symptoms used to designate a particular l
clus of emergency. These parameters are indicators' of t;ie severity of an emergency, or potential severity, and are guides in determining appropriate emergency response measures.
EALs can also be referred to as " initiating events" for those events severe enough to cause an event classification.
1.9 EMERGENCY COORDINATOR This PSC individual has the responsibility and authority to initiate emergency actions immediately and unilaterally.
The on-shift Shift Supervisor initially assumes the role of Emergency Coordinator until such time as the emergency organization is activated and he is relieved by the Control Room Director or the Technical Support Center Director.
The Technical Support Center Director ultimately assumes the duties of the onsite Emergency Coordinator and is responsible for classification and notification.
1.10 EMERGENCY PLANNING ZONE (EPZ)
An area around FSV for which provisions are established for responding to postulated emergencies.
The EPZ for FSV is a 100 meter square from the Reactor Building Stack.
1.11 EMERGENCY RESPONSE ORGANIZATION Personnel who are assigned a specific emergency position as defined in this plan and who are trained to perform i
specific emergency response functions.
1.12 NOTIFICATION OF UNUSUAL EVENT Situations where unusual events are in process, or have occurred, which indicate a potential for degradation of the level of safety of the plant. -Time is available to i
take precautionary and constructive steps to prevent a i
more serious event and/or to mitigate any consequences that may occur.
No releases of radioactive material requiring offsite response or monitoring are expected at this level.
1.13 PLUME
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A distribution of radioactive material carried by
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prevailing winds.
FORM (0)372 22 3643
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PUBUC SERVICE COMPANY OF COLORADO 1.14 PROTECTIVE ACTION GUIDES (PAG's)
The projected radiological dose (or' dose commitment values) to individuals in the general population that would warrant Protective Action Recommendations (PAR's) following a release of radioactive material.
Protective actions are warranted if the dose reduction achieved is not. offset by the risks associated with taking the l
protective action.
The PAG's used in this response plan i
are those recommended by the Environmental Protection Agency (EPA),
1.15 PROTECTIVE ACTION RECOMMENDATIONS (PAR's)
Recommendations made to appropriate state / local officials (i.e.,
shelter) to prevent or minimize radiological exposure after an actual or projected release of radioactive material.
1.16 STALE RERP The State of Colorado FSV Radiological Emergency Response Plan, which documents specific responsibilities and procedures for state / local emergency response agencies responsible for offsite emergency operations and O
protection of tne affected population.
1.17 TECHNICAL SUPPORT CENTER (TSC)
The TSC is located adjacent to the Reactor Building in the Technical Support Building. This building is within. easy walking distance to the CR.
.The TSC monitors station conditions, provides information and analysis regarding reactor system problems, serves as the collection and analysis point for sampling and monitoring data, provides long and short-term guidance on corrective actions to the CR, serves as a staging area.and support base for emergency personnel, and serves as the manpower marshalling point for personnel awaiting assignment to emergency repair teams, damage control teams, radiological monitoring teams, search and rescue teams, or. similar activities.
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2.0 SCOPE AND APPLICABILITY l
PSC r2 cognizes that there is a potential for an accident to occur at FSV. This DERP is a result of the planning process that was conducted to define and classify the various types of emergencies that may occur. After establishing the types of credible events, the planning team continued its activities and (1) defined specific corrective actions that could be taken and (2) identified specific organizational structures that should be established to ensure that these corrective actions are executed properly and effectively.
Based upon the above, tne plan describes--
1)
The PSC emergency organization that would be established to respond to an accident at FSV.
2)
The notification process that would be used to alert the various organizations of the accident.
3)
The communication links that would be established and the various emergency response facilities that would be manned in the event of an accident.
The DERP Implementing Procedures, which effectively implement O
the plan, categorize the specific type of er.:ergency according to i
severity, designate responsibilities, and fully define actions to be taken by pre-assigned personnel to reduce the consequences of an accident.
In addition to the state and local support that may,be made available to FSV, the federal government may also provide assistance.
For example, the NRC and FEM would, in all likelihood, provide a variety of resources in the event of an accident at FSV.
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DERP Section 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION l
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DEFUEL'ING EMERGENCY RESPONSE PLAN: SECTION 3
SUMMARY
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DERP Section 3 Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 3
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v 3.0
SUMMARY
OF THE FSV DEFUELING EMERGENCY RESPONSE PLAN (DERP)
The FSV DERP delineates the organization for emergencies, classifies emergencies according to severity, defines and assigns responsibilities and authorities, and outlines measures to mitigate the consequences of an accident and minimize the effects on the health and safety of tha public and station personnel.
Radiological emergency planning for FSV has been coordinated at the state / local government levels. The State of Colorado, PSC and local government agencies are all signatory parties to the State RERP.
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The FSV emergency response organization is responsible for onsite emergency operations and for providing accurate plant 4
status information to offsite authorities.
Sections 4.0 thru 8.0 of the FSV DERP provide specific detail on the emergency preparedness program.
The contents of these sections are summarized below:
3 Section 4.0 - Emergency Classifications Describes emergency classifications, initiating events, emergency action levels (EAL's),
and corresponding PSC actions in response to each emergency classification.
EAL's and corresponding actions noted are based upon design characteristics specific to a defueling HTGR and upon applicable NRC guidance for nuclear power stat' ions.
Section 5.0 - Emergency Organization Describes the PSC emergency response organization, together with details on the function and responsibilities assigned to each segment of the organization.
Proviston is made for two onsite emergency control centers:
the Technical Support Center (TSC) and the Control Room (CR).
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This section also indicates specific assignments of personnel to emergency billets and notes local and contract support service arrangements.
Section 6.0 - Emergency Measures Describes the activation of the emergency organization, activities associated with assessing the emergency condition (s) and corresponding protective action / recommendations, and measures to aid injured and/or contaminated personnel.
l FoAMto)372 22 3643
DERP Section 3 Pubils FORT ST. VRAIN NUCLEAR GENERATING STATIOlJ e
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1 Section 7.0 - Emergency Facilities and Equipment Describes onsite facilities and equipment avail.able to assess emergency conditions, to support emergency operations, to protect and treat injured / contaminated personnel, and to control incident-related damage.
This section also outlines communication links with field / plant monitoring teams.
See:1cn 8.0 - Maintaining Emergency Preparedness Summarizes the station emergency training program, describes emergency drills and exercises, details methods to review and update the DERP, and describes procedures to maintain an adequate inventory of emergency equipment and supplies.
Section 9.0 - Recovery
- Defines, in general
- terms, a
recovery plan and organization.
Section 10.0 - Letters of Agreement and Supporting Plans
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Includes copies of Letters of Agreement with various local 5
agencies and contract support organizations.
Section 11.0 - Maps includes a
map of the
- EPZ, geographical area identification designations, and environmental dosimetry locations.
Section 12.0 - Procedures That Implement or Supplement the P.!a n A listing of procedures which implement or supplement the plan.
Section 13.0 - Listings of Emergency Kits A listing of emergency kits, protective equipment, and supplies stored and maintained for emergency purposes.
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rusuC SERVICE COMPANY OF COLORADO TITLE:
DEFUELING EMERGENCY RESPONSE PLAN: SECTION 4 EMERGENCY CLASSIFICATIONS PONSIBLE UTHORIZED nSSw PGC 9 21 FEB 131991 D7TE Ea4
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- PusuC ssRVICE COMPANY OF COLORADO O
4. 0, EMERGENCY CLASSIFICATIONS Emergencies are classified into two categories..
The classification system results in responses and procedures that are both timely and appropriate for each emergency condition.
When determining the classification of a particular situation, the highest classification (ALERT) should be consulted first, working down through the lowest, until the appropriate level of classification is determined.
l 4.1 CLASSIFICATION The following are the descriptions of the two classifications used in the system.
Each classification description ircludes appropriate levels of station emergency response actions.
The classifications given match those used in the State RERP except that the state also assigns a color code to each of the events.
For completeness, these color codes are identified in parenthesis after the classification title.
4.1.1 NOTIFICATION OF UNUSUAL EVENT (" CONDITION BLUE")
This classification applies to situations where O
unusual events are in process, or have occurred, which indicate a potential for degradation of the level of safety of the plant.
No releases of radioactive material requiring offsite response or monitoring tre expectec unless further degradation of safety systems occur.
In these situations, time is available to take precautionary and constructiva steps to prevent a more serious event and/or to mitigate any consequences that ny occur.
-This event status places the plant in a readiness position for a possible cessation of routine activities and/or an augmentation of on-shift resources.
State officials are promptly notified-of an unusual event.
Attachments B1 through B14 outline initiating events and response actions for the NOTIFICATION OF AN UNUSUAL EVENT class of incident.
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DERP Section 4 Issue 1 0 Service' Pubila FORT ST. VRAIN NUCLEAR CENERATING STATION Page 3 of 76 PUBUC SERVICE COMPANY OF COLORADO O
4.1.2 ALERT (" CONDITION GREEN")
1 This classification comprises events which are in l
process, or have occurred, which involve an actual or potential, substantial degradation of the level i
cf safety of the plant.
Any releases of j
radioactive materials are expected to represent j
small fractions of the EPA Protective Action Guide limits.
1 The purpose of the ALERT category is to assure that emergency personnel are readily available and to provide offsite authorities with comprehensive status information, Operator modification of plant I
operating status is a probable corrective action if
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such modification has not already been accomplished by automatic protective systems.
Declaration of an ALERT will trigger prompt initial and follow-up notification to offsite authorities.
6 If applicable, updated meteorological inform tion, verification of releases by surveys, and projected radiological effects on offsite areas will be provided to local and state authorities, The ALERT
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status is maintained until the event is declared to be terminated.
Attachments B1 through B14 outline initiating events and response actions for the ALERT class of i
incident.
4.2 NON-EMERGENCY EVENTS Non-Emergency Events are classified in two categories.
Items / Situations constituting Non-Emergency Events are specified in 10 CFR 50.72.
The following are descriptions of the two categories. The State-RERP does not assign.
colors to Non-Emergency Events.
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DERP Section 4 Issue 1 0 Service
- Pub ll3 FORT ST. VRAIN NUCLEAR CENERATING STATION Page 4 of 76 Pusuc sanwes courAmy or cotonAno 4.2.1 ONE-HOUR REPORT If not reported as a declaration of an Emergency Class, the licensee shall notify the NRC as soon as practical and in all cases within one hour of an occurrence involving any deviation from Technical Specifications, any event that poses an actual threat to the safety of the plant or significantly hampers site personnel in the performance of duties, or any event that results in a major loss of emergency assessment capability or communications capability.
Attachments B1 through B14 outline initiating events for one-hour reports,
.i 4.2.2 FOUR-HOUR REPORT If not reported as a declaration of an Emergency Class or as a one-hour report, the licensee shall notify the NRC as soon as practical and in all cases, within four hours of any event found while the reactor is shut down, that had it been found while the reactor was in operation, would have i
resulted in the plant being seriously degraded or being in an unanalyzed condition, any event that j
results in the automatic actuation of an Engineered Safety Feature, any airborne radioactive release that exceeds two times applicable concentrations, any liquid effluent release that exceeds two times applicable concentrations, any eveni, ' req'uiring i
transportation of a radioactively contaminated
- person, or any event for which a news release is 4
planned or notifications to o t he r -- government agencies have been or will be made.
l 4.3 SPECTRUM OF p0SSIBLE ACCIDENTS A,ND INITIATING EVENTS
~
The accidents which might occur at FSV have been analyzed in Section 14 of the FSV Updated FSAR and the Defueling SAR for their severity of consequence and probability of occurrence.
These accidents reflect the design
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characteristics of an HTGR and are addressed in Attachments 81 through B14'. from the viewpoint of initiating
- events, alarm actuation and/or associated readings, and consequent incident classification.
PoftMIDl372 22 3M3
DERP Section 4 Attachment A 0 Service
- Pubilg FORT ST. VRAIN NUCLEAR CENERATING STATION Issue 1 rusuc sanvecs comeAmy or cotonAno Page 5 of 76
'O ALERT CLASS DESCRIPTION:
Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any radiological releases are expected to be limited to small fractions of the EPA Protective Action Guideline (PAG) exposure levels.
PURPOSE:
(1) assure that emergency personnel are readily available to respond if situation becomes more serious or to perform confirmatory radiation monitoring if required, and (2) provide offsite authorities current status information.
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MIDl372 22 243
DERP Section 4 Attachment A OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- Pusue sanvoca courAmy or cotonAno Page 6 of 76 O
NOTIFICATION OF UNUSUAL EVENT (NOVE)
CLASS DESCRIPTION:
Unusual events are in process or have occurred which indicate a potential degradation of tb? level of safety of the plant.
No releases of radioactive i.iaterial requiring offsite response or monitoring are expected unless further degradation of safety systems occurs.
PURPOSE:
(1) assure that the first step in any response later found to s
be necessary has been carried out, (2) bring the operating staff to a state of readiness, and (3) provide systematic handling of unusual event information and decision-making.
t PoMM(01372 22 3083 '
DERP Section 4 Attachment A 0 Service
- Pubila FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC saRVDCE COMPANY OF COL.ORADO Page 7 of 76 0
NON-EMERGENCY EVENT:
GNE-HOUR REPORT CLASS DESCRIPTION:
If not -reported as a declaration of an Emergency Class, the licensee shall notify the NRC as soon as practical and in all cases within one hour of the occurrence of any of the items / situations identified within this procedure as 1 Hour Reports.
PURPOSE:
(1)
To ensure compliance with 10CFR Part 50,72(b)(1) "One-hour reports",
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FORMIDl372 22 3M3
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DERP Section 4 Attachment A OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 SerVICO' PusuC SERVICE COMPANY OF COLORADO Page 8 of 76 O
NON-EMERGENCY EVENT:
FOUR-HOUR REPORT CLASS DESCRIPTION:
If not reported as a declaration of an Emergency Class or as a One-Hour Report, the licensee shall notify the NRC as soon as practical and in all cases within four hours of the occurrence of any of the items / situations identified within this procedure as 4 Hour Reports.
PURPOSE:
(1)
To ensure compliance with 10CFR Part 50.72(b)(2)
"Four-hour reports".
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FORMtol372 22 3M3
DERP Section 4 Attachment B1 0 Service
- Publia FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC SERVICE COMPANY OF COLORADO Page 9 of 76 O
REACTIVITY ALERT Emeroency Action Level Typical Indication /
Initiating Event L1.1 Hazards being experienced As observed by or reported or projected, such as:
to station personnel, a) aircraft crash affecting vital structures; b) severe damage to fire protection cooldown equipment.
c) entry of toxic / flammable gas into vital areas.
Bl.2 Evacuation of control Inability to monitor shutdown room accompanied by count rate.
f inability to locally
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control shutdown systems within I hour.
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DERP Section 4 Attachment B1 0 Service
- Publia FORT ST. VRAIN NUCLEAR CENERATING STATION Issue 1 Pusue sanvoca COMPANY OF COLORADO Page 10 of 76 O
Page 2 of 5 EETIVITY NOTIFICATION OF UNUSUAL EVENJ Emergency Action Level Typical Indication /
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Initiatino Event _ _ _
Bl.3 Evacuation of Control Room As deemed necessary by anticipated or required Shift Supervisor.
with control of shutdown systems established from local stations.
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U PORM(D)372 213M3
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DERP Section 4 Attachment B1 OPubilg FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- Pusuc sanvece comeAmy or cotonAoo Page 11 of 76 O
Page 3 of 5 REACTIVITY ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event Bl.4 Any deviation from Any deviation from a Tech-Technical Specifica-nical Specification, when tions authorized the action is immediately pursuant to needed to protect the public 10 CFR 50.54(x).
health and safety, and no action consistent with Technical Specifications wnich can provide adequate or equivalent protection is immediately apparent.
(The action should be epproved, as a minimum, by a senior licensed operator.)
B1.5 Any event or condition that results in the Q
condition of the plant, V
including its principle safety barriers being seriously degraded; or results in the plant being:
a) In an unanalyzed a) As determined.
condition that significantly compromises plant safety; b) In a condition b) Winds experienced in that is outside excess of FSAR design the design basis levels.
of the plant; or, c) In a condition c) As determined, not covered by the plant's operating and i
emergency operating procedures, n
FORM (ol372 22 3843
DERP Section 4 1 OService*
Pubil?,
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC ssRVlCE COMPANY OF COLORADO Page 12 of 76 O
Page 4 of 5 REACTIVITY ONE HOUR NON-EMERGENCY EVENT (sj Emergency Action Level
'ypical Indication /
lnitiating Event i
Bl.6 Any event that compromises a) Fire posing undue safety of the plant, or personnel hazard, significantly hampers site personnel in the b) Accidental gaseous performance of duties radiological release necessary for the safe resulting in onsite conduct of plant activities, concentrations in excess including fires, toxic of 10 CFR 20, Appendix B, gas releases, or Table I, Column 1.
i radioactive releases.
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DERP Section 4 Attachment B1 0 service
- Pubilg FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc SERV CE COMPANY OF COLORADO Page 13 of 76 Page 5 of 5 REACTIVITY FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event Bl.7 Any unanticipated event Reactor scrams and automatic or condition, i.e., not starting and loading of diesel part of a preplanned generators only, sequence, that results in manual or automatic actuation of an EXCEPTIONS.
Engineered Safety Feature, including the a)
Only one of three channels Plant Protective System.
tripped manually or auto-matica11y, but no final protective action takes place, nor is required, b)
Actuation of the afore-mentioned systems which result from, and are a s
part of, the planned sequence during surveil-lance testing.
Bl.8 Any event or condition that alone could have prevented the fulfill-ment of the safety function of structures or systems that are needed to:
a) Maintain the reactor a) During defueling operations, in a safe shutdown a.0 lap shutdown margin condition, is not maintained due to incorrect rod removal sequence.
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1 FOftM(D)372 22 3643
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DERP Section 4 Attachment B2 O Service
- Pubilg FORT ST. VRAIN NUCLEAR CENERATING STATION Issue 1 PusuC ssRVICE COEPANY OF COLORADO Page 14 of 76 O
Page 1 of 5
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PRIMARY SYSTEM ALERT EAL Emergency Action level Typical Indication /
Initiating Event B2.1 Calculated bulk core CMG-4.
temperature reaches 760 'F without PCRV linse cooling.
B2.2 Non-isolable primary Shift Supervisor coolant leakage through a determination that laakage steam generator REHEAT is non-isolable, or EES section.
82.3 Fire affecting or a) Fire pump 1A start; potentially affecting equipment, components, b) Fire Control Alarm or instrumentation Panel; required to maintain a safe shutdown condition.
c) Various alarms according to affected safety x
system.
d) Shift Supervisor determines fire beyond capability of station staff.,
B2.4 High radiation levels or CAM (s) alarm high airborne contamination RIS 6212 which indicates severe RIS 6213 degradation in control of RIS 93252-12 radioactive materials.
Area Monitors (Increase by factor of 1,000 over normal.)
Alarms with corresponding meter readings on area or process monitors.
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FORM (D13T2 22 3M3
DERP Section 4 Attachment B2 0 Service
- Pubila FORT ST. VRAIN NUCLEAR GENERATING S1 ATION lssue 1 Pusuc sanvr. courAny or cotonAno Page 15 of 76 O
Page 2 of 5 PRIMARY SYSTEM ALERT EAL Emeroency Action Level Typical Indication /
Initiating Event B2.5 Radiological effluents a) RIS 7324-1 indicating exceed 10 times technical 22.5 x 10 8 pCi/cc specifications instantan-eous limits, b) RIS 7324-2 indicating
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22.5 x 10 8 pC1/cc c) RIS 7325-1 Indicating
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27.0 x 10 ' pCi/cc d) RIS 7325-2 indicating 27.0 x 10 pCi/cc e) RIS 73437-1 indicating
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27.0 x 30 ' pC1/cc I-131.
f) RIS 4802 indicating 2 7.0 x 10 pC1/cc I-131.
g) RIS 4803 indicating,
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a 2.5 x 10 8 uCi/cc B2.6 Evacuation of control Inability to monitor shutdown room accompanied by count rate, inability to locally control shutdown systems within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
i FORM (D)372 22 3043
DERP Section 4 Attachment B2 0Pubilg FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1
$9fVICO' Pusuc sERWCE COMPANY OF COLORADO Page 16 of 76 PRDIARY SYSTEM NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level Typical Indication /
Initiating Event B2.7 Any radiological Alarms on:
release resulting in RIS 7324-1 offsite effluent in RIS 7324-2 excess of Technical RIS 7325-1 Specification limits.
RIS 7325-2 RIS 4801 RIS 4802 RIS 4803 RIS 73437-1, 2 B2.8 Indication of minor a) 25% increase in j
fuel damage detected circulating activity in primary coolant.
from previous conditions, B2.9 Evacuation of Control As deemed necessary by O
Room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations.
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DERP Section 4 Attachment B2 0SerVlCe*
Pubils FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc saRVICE COMPANY OF COLORADO Page 17 of 76 O
Page 4 of 5 PRIMARY SYSTEM ONE HOUR NON-EMERGENCY EVENT (s)
EAL Emergency Action Level Typical Indication /
Initiating Event B2.10 Any event or condition that results in the condition of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:
a) In an unanalyzed a) As determined.
condition that significantly compromises plant safety; b) In a condition b) Winds experienced in that is outside excess of FSAR design O
the design basis
- levels, of the plant; or, c) In a condition c) As determined, not covered by the plant's operating and emergency operating procedures.
B2.11 Any event that compromises a) Fire posing undue safety of the plant, or personnel hazard, significantly hampers site personnel in the b) Accidental gaseous performance of duties radiological release necessary for the safe resulting in onsite conduct of plant activities, concentrations in excess including fires, toxic of 10 CFR-20, Appendix B, gas releases, or Table I, Column 1.
radioactive releases.
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DERP Section 4 Attachment B2 OPublic FORT ST VRAIN NUCLEAR CENERATING STATION Issue 1 Service
- Pusue senvece comeAny or cotonAoo Page 18 of 76 0
Page 5 of 5 PRIMARY SYSTEM FOUR HOUR NON-EMERGENCY EVENT (s)
E_AL Emergency Action Level Typical Indication /
Initiating Event B2.12 Any unanticipated event Reactor scrams and automatic or condition, i.e., not starting and loading cf diesel part of a preplanned generators only, sequence, that results in manual or automatic actuation of an EXCEPTIONS:
Engineered Safety Feature, including the e)
Only one of three channels Plant Protective System, tripped manually or auto-matically, but no final protective action takes place, nor is required, b)
Actuation of the afore-mentioned systems which rer?llt from, and are a Os part of, the planned sequence during surveil-lance testing B2.13 Any event or condition that alone could have prevented the fulfill-ment of the safety function of structures or systems that are needed to:
a) Remove residual heat a) Incorrect valve lineup which results in isolation of all reactor decay heat
- removal, b) Mitigate the conse-quences of an accident.
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PomM(Dl372 22 3043
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DERP Section 4 3 0 Service
- Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc sanvece comeAmy or cotonAm Page 19 of 76 O
Page 1 of 5 SECONDARY SYSTEM ALERT Emergency Action Level Typical Indication /
Initiating Event B3.1 Calculated bulk core CMG-4.
temperature reaches 760 'F without PCRV liner cooling.
B3.2 Non-isolable primary Shift Supervisor coolant leakage through a determination that leakage steam generator REHEAT or is non-isolable.
EES section.
B3.3 Fire affecting or a) Fire pump 1A start; potentially affecting equipment, components, b) Fire Control Alarm or instrumentation Panel; required to maintain a safe shutdown condition, c) Various alarms according to affected safety system.
d) Shift Supervisor determines fire beyond capability of station staff.,,
B3.4 Evacuation of control Inability to monitor shutdown room accompanied by count rate.
inability to locally control shutdown systems within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
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DERP Section 4 Attachment B3 0Publia FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 1 Service
- PusuC ssRVICE COMPANY OF COLORADO Page 20 of 76 O
SECONDARY SYSTEM NOTIFICATION OF UNUSUAL EVENT Emergency Act,1on level Typical Indication /
Initiating Event B3.6 Evacuation of control As deemed necessary by room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations.
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PoRM(D)372 22 3ec
DERP Section 4 3 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC saRWCE COMPANY OF COLORADO Page 21 of 76 O
Page 3 of 5 SECONDARY SYSTEM ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event 83.7 Any event or condition that results in the condition of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:
a) In an unanalyzed a) As determined.
condition that significantly compromises plant safety; b) In a condition b) Winds experienced in that is outside excess of FSAR design O
the design basis
- levels, of the plant; or, c) In a condition c) As determined, not covered by the plant's operating and emergency operating procedures, 4
FORM (D)372 22 3SO s
DERP Section 4 Attachment B3 OPubila FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- Pusuc sanvmu courAmy or cotonApo Page 22 of 76 O
Page 4 of 5 SECONDARY SYSTEM FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiatino Event B3.8 Any unanticipated event Reactor scrams and automatic or condition, i.e., not starting and loading of diesel part of a preplanned generators only.
sequence, that results in manual or automatic actuation of an EXCEPTIONS:
Engineered Safety Feature, including the a)
Only one of three channels Plant Protective System, tripped manually or auto-matically, but no final protective action takes place, nor is required.
4 b)
Actuation of the afore-mentioned systems which result from, and are a O
part of, the planned sequence during surveil-lance testing B3.9 Any event or condition that alone could have prevented the fulfill-ment of the safety function of structures or systems that are needed to:
a) Remove residual heat a) Incorrect valve lineup which results in isolation of all reactor decay heat removal.
b) Mitigate the conse-quences of an accident.
.o PoRM(D)F12 22 300
DERP Section 4 Attachment B3 O Service
- Pubilg FORT ST. VRAIN NUCLEAR GENERATING STATION Issus 1 Pusuc sanvice courAmy or cotonApo Page 23 of 76 O
Page 5 of 5 SECONDAxY SYSTEM FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B3.10 Any unplanned radiological As determined by analysis release which does not and evaluation, constitute classification of a NOUE will require notification to the Colorado Departmer,t of Health as a
" State Advisory". This in turn requires a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Non-Emergency event per 10CFR50.72(b)(2)(vi),
NOTE:
Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR20.403.
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FORM'D)372 22 300 l
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DERP Section 4 Attachment B4 0 SerVIC9' Public FORT ST. VRAIN NdCLEAR GENERATING STATION Issue 1 Pusuc sanwcs COMPANY OF COLORADO Page 24 of 76 O
Page 1 of 6 PCRV INTEGRITY ALERT Emergency Action Level Typical Indication /
Initiating Event B4.1 Non-isolable primary Shift Supervisor coolant leakage through a determination that leakage steam generator REHEAT is non-isolable.
or EES section.
B4.2 Fire affecting or a) Fire pump 1A start; potentially af'ecting equipment, components, b) Fire Control Alarm or instrumentation Panel; required to maintain a safe shutdown condition, c) Various alarms according to affected safety system.
d) Shift Supervisor determines fire beyond capability of station staff.
B4.3 High radiation levels or CAM (s) alarm high airborne contamination-RIS 6212 which indicates severe RIS 6213 degradation in control of RIS 93252-12 radioactive materials.
Area Monitors (Increase by factor of 1,000 over normal.)
Alarms with corresponding meter readings on area or process monitors.
FORM (D)372 22 3H3
DERP Section 4 Attachment B4 O Service
- Pub!!c FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusue saRVICs COMPANY OF COLORADO Page 25 of 76 O
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PCRV INTEGRITY ALERT Emergency Action Level Typical Indication /
Initiating Event B4,4 Radiological effluents a) RIS 7324-1 indicating d
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1 exceed 10 times technical 22.5 x 10 8 uti/cc i
specifications instantan-eous limits, b) RIS 7324-2 indicating
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22.5 x 10 8 uti/cc c) RIS 7325-1 indicating
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27.0 x 10 ' vC1/cc j
d) RIS 7325-2 indicating
~
27.0 x 10 ' pCi/cc e) RIS 73437-1 indicating
~
27.0 x 10 ' uCi/cc I-131.
f) RIS 4802 indicating
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l 2 7.0 x 10 ' pCi/cc I-131.
g) RIS 4803. indicating 3
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2 2.5 x 10 8 uCi/cc I
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.g FORM (D)372 22 3843
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DERP Section 4 Attachment B4 OService*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 l
Pusuc senveces comeAmy or cotonApo Page 26 of 76 O
Page 3 of 6
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PCRV INTEGRITY NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating Event NONE IDENTIFIED l
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o FORM (Dl372 22 3043
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DERP Section 4 Attachment B4 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc senvece courAmy or cotonAno Page 27 of 76 O
Page 4 of 6 PCRV INTEGRITY ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B4.5 Any event or condition that results in the condition of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:
a) In an unanalyzed a) As determined.
condition that significantly compromises plant safety; b) In a condition b) Winds experienced in that is outside excess of FSAR design the design basis levels.
A of the plant; or c) In a condition c) As determined, not covered by the plant's operating and emergency operating procedures.
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%.J FORM (D)372 22 3043
DERP Section 4 Attachment B4 0SerVICO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION lssur,1 PusuC s&RVICE COMPANY OF COLORADO Page 28 of 76 O
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Page 5 of 6 PCRV INTEGRITY FOUR HOUR WON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B4.6 Any unanticipated event Reactor scrams and automatic or condition, i.e., not starting and loading of diesel part of a preplarined gener: tors only, sequence, that resul'..s in manual or auto;aatic actuation of n EXCEPTIONS:
Engineered.ist:
Feature, d ici rif rn the a)
Only one of three channels Plant Pre',.tive :/ stem.
tripped manually or auto-matically,-but no final protective action takes place, nor is required, b)
Actuation of the afore-mentioned systems which result from, and are a
'N part of, the planned sequence during surveil-lance testing i
FOMM(0)372 22 3643 6
DERP Section 4 Attachinent B4 0 $9rVlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 1 Pusuc senvece COMPANY OF COLORADO Page 29 of 76 O
V Page 6 of 6 PCRV INTEGRITY FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B4.7 a)
Any unplanned radio-As determined by analysis logical release which does not constitute classification of a NOUE will require notification to the Colorado Department of Health as a " State Advisory".
This in turn requires a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Non-Emergency event per 10CFR50.72(b)(2)(vi).
b)
Any airborne radioactive release that exceeds 2 times the applicable concentrations of the Os limits specified in Appendix B, Table II of 10CFR20 in unrestricted areas when averaged over a time neriod of one hour.
c)
Any liquid effluent release that exceeds 2 times the limiting combined MPC (see Note 1 of Appendix B of 10CFR20) at the roint of entry.into
- he 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 10CFR10.403.
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FORM (Dl372 22 3843
DERP Section 4 Attachment B5 0SerVlC9' Public FORT ST, VRAIN NUCLEAR GENERATING STATION Issue 1 PUBUC SERVICE COMPANY OF COLORAM Page 30 of 76 O
Page 1 of 8 RADIOACTIVITY CONTROL ALERT Emergency Action Level Typical Indication /
Initiating Event B5.1 Non-isolable primary Shift Supervisor coolant leakage through a determination that leakage steam generator REHEAT or is non-isolable.
EES section.
B5.2 Damage to spent fuel a) Visual observation.
resulting in release of radioactivity to plant b)' Area radiation monitor environs.
alarms.
B5.3 High radiation levels or CAM (s) alarm high airborne contamination RIS 6212 which 1.idicates severe RIS 6213 degradation in control of RIS 93252-12 radioactive materials.
Area Monitors (Increase by factor r3 of 1,000 over normal.)
Alarms with correspending meter U
readings on area or process monitors.
FORM (D)772 22 3843
DERP Section 4 Attachment B5 0$9TVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PUBUC SERVICE COMPANY OF COLORADO Page 31 of 76 Page 2 of 8 RADIOACTIVITY CONTROL ALERT Emergency Action Level Typical Indication /
Jnitiating Event B5.4 Radiological effluents a) RIS 7324-1 indicating exceed 10 times Technical 22.5 x 10 2 pC1/cc Specifications instantan-eous limits, b) RIS 7324-2 indicating 22.5 x 10 2 pCi/cc c) RIS 7325-1 indicating 27.0 x 10 pCi/cc d) RIS 7325-2 indicating 27.0 x 10"' pCi/cc e) RIS 73437-1 indicating 27.0 x 10 pCi/cc I-131.
,3 f) RIS 4802 indicating 2 7.0 x 10 pCi/cc I-131, g) RIS 4803 indicating 2 2.5 x 10 2 pC1/cc O
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1 FORM (D)772 22.%43
DERP Section 4 Attachment B5 OService*
Publia FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc sanwca courAmy or cotonApo Page 32 of 76 Page 3 of 8 RADI0 ACTIVITY CONTROL NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating Event B5.5 Any radiological
- 1. Alarms 01:
release resulting in RIS 7324-1 offsite effluent in RIS 7324-2 excess of Technical RIS 7325-1 Specification limits.
RIS 7325-2 RIS 4801 RIS 4802 RIS 4803 RIS 73437-1, 2 B5.6 Any liquid waste a) RIS 6212 or 6213 alarm release resulting in with inatiility to prevent offsite effluent in discharge offsite.
I excess of Technical Specification limits, b) As determined by station personr,el.
O(_,/
B5.7 Indication of minor a) 25% increase in fuel damage detected circulating activity in primary coolant.
from previous conditions.
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FORM (Dl772 22 3843
DERP Section 4 Attachment B5 OSerVICe*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC SERVICE COMPANY OF COLORADO Page 33 of 76 o
Page 4 of 8 RADIOACTIVITY CONTROL NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating Event B5.8 Serious fire at the a) Any of various alarms plant lasting more on Fire Control Alarm than 30 minutes Panel; which could result in the release of b) Fire Pump 1A auto radiological or start; toxic materials.
c) Verbal reports.
B5.9 Any serious radiological As occurring.
exposure of plant personnel or the transportation to offsite facilities of contaminated personnel who may have been injured.
(Probably cannot be deter-mined within two hours -
x call to be made in a timely manner.)
B5.10 Accidents that may a) Abnormal radiation levels involve plant spent reported from cask.,
fuel shipments or plant radioactive b) Cask breached, waste shipments, c) As occurring or reported by shipper.
FORM (D)37J 22 3H3
DERP Section 4 Attachment B5 O Service
- Public FORT ST, VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc SERVICE COMPANY OF COLORADO Page 34 of 76 Page 5 of 8 RADIOACTIVITY CONTROL NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating Event B5.11 Indication or alarms Data Logger Alarm / Alarm on radiclogical effluent Summary indication of non-monitors not functional, operational alarm or indication on:
a) RIS 7324-1, -2 /ND
~~
RIS 4803; or b) RIS 7325-1, 2, RIS 4802, A_ND RIS 73437-1; or c) RIS 73437-2 AND RIS 4801; or a
1 NOTE:
Use ELC0 8.1.1 Technical Specification Limits
,d as basis.
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l FORM (D)372 22 3H3
DERP Section 4 Attachment B5 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc senvece comeAny or cotonAno Page 35 of 76 AV RADIOACTIVITY CONTROL Page 6 of 8 ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B5.12 Any event that compromises a) Fire posing undue safety of the plant, or personnel hazard.
significantly hampers site personnel in the b) Accidental gaseous performance of duties radiological release necessary for the safe resulting in onsite conduct of plant activities, concentrations in excess including fires, toxic of 10 CFR 20, Appendix B, gas releases, or Table I, Column 1.
radioactive releases.
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N' FOftM(Ol372 22 3ec
l DERP Section 4 Attachment B5 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1
$9fVIC9' PUBUC SERVICE COMPANY OF COLORADO Page 36 of 76 RADIOACTIVITY CONTROL
~
Page 7 of 8 FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B5.13 Any event or condition that alone could have prevented the fulfill-ment of the safety function of structures or systems that are needed to:
a) Control the release of a) Liquid waste monitor setpoints radioactive material; or, raised for liquid waste release completed.
Reactor building sump release started. Setpoints not reset.
b) Mitigate the conse-quences of an accident.
A B5.14 Any event requiring the As occurring.
V transport of a radio-actively contaminated person to an offsite medical facility for treatment.
B5.15 Any event or situation, a) On-site 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.
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FORM (Dl372 22 3M3
DERP Section 4 Attachment B5 0 SerVlCG*
Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC SERVICE COMPANY OF COLORADO Page 37 of 76 RADI0 ACTIVITY CONTROL FOUR HOUR NON-EMERGENCY EVENT (s)
Emergent / Action level Typical Indication /
Initiating Event B5.16 a) Any unplanned radio-As determined by analysis logical release which and evaluation does not constitute classification of a NOVE 3
will require notification to the Colorado Department
)
of Health as a " State Advisory".
This in turn requires a 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> Non-Emergency event per 10CFR50.72(b)(2)(vi).
b) Any airborne radioactive release that exceeds 2 times the applicable concentrations of the limits specified in O
Appendix B, Table II of 10CFR20 in unrestricted areas when averaged over a time period of one hour, c) Any liquid effluent release that exceeds 2 times the limiting combined MPC (see Note 1 of Appendix B of 10CFR20) at the point of entry into the receiving water (i.e.,
unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.
NOTE:
Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR20.403, o
FORM (D)372 22 3M3
DERP Section 4 Attachment B6 0 service
- Pubile FORT ST, VRAIN NUCLEAR GENERATING STATION Issue 1 PUSUC SERVICE COMPANY OF COLORADO Page 38 of 76 Page 1 of 5 p
ALERT EAL Emergency Action level Typical Indication /
Initiating Event B6.1 Calculated bulk core CMG-4 temperature reaches 760 'F without PCRV liner cooling.
B6.2 Damage to spent fuel a) Visual observation.
resulting in relesse of radioactivity to plant b) Area radiation monitor
- environs, alarms.
86.3 Actual or attempted loss, As reported and/or confirmed theft, diversion, or by shipper, LSO, Control Room or sabotage of shipments of any member of the Security force.
irradiated spent fuel that have the potential to degrade public health and safety G
i FORM (D)772 22 3643 eaY
DERP Section 4 Attachment B6 O $9fVICO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc ssRVICE COMPANY OF COLORADO Page 39 of 76
,q-1 U
Page 2 of 5 FUEL 1
NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level Typical Indication /
Initiating Event B6.4 Indication of minor a) 25% increase in fuel damage detected circulating activity in primary coolant.
from previous conditions.
B6.5 Accidents involving a) Abnormal radiation levels plant spent fuel reported from cask, shipments or plant radioactive b) Cask breached.
waste shipments.
c) As occurring or reported by shipper.
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bO)
FORM (D)372 22 384 -
DERP Section 4 Attachment B6 0SerVIC9' PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PUBUC SERVICE COMPANY OF COLORAM Page 40 of 76 Page 3 of 5 ONE HOUR NON-EMERGENCY EVENT (s)
EAL Emergency Action Level Typical Indication /
Initiating Event B6.6 Any deviation from 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-tions which can provide adequate or equivalent protection is immediately apparent.
(The action should be approved, as a minimum, by a senior licensed operator.)
B6.7 Fire involving As occurring or reported shipping cask, breach by shipper.
\\m not determined.
s 1
4 FOM(ol372 22 3643
DERP Section 4 Attachment B6 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 SerVICG' PUBUC SERVICE COMPANY OF COLORADO Page 41 of 76
(%
Page 4 of 5 ONE HOUR NON-EMERGENCY EVENT (s)
EAL Emergency Action Level Typical Indication /
Initiating Event B6.8 Any event or condition that results in the condition of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:
a) In an unanalyzed a) As determined.
condition that significantly compromises plant safety; b) In a condition b) Winds experienced in that is outside excess of FSAR design Os the design basis
- levels, of the plant; or, c) In a condition c) As determined, not covered by the plant's operating and emergency operating procedures.
O FORM (Ol372 22 3H3
DERP Section 4 l
Attachment B6 l
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- Pusuc sanvice comeAny or cotonApo Page 42 of 76 O
Page 5 of 5 FUEL FOUR HOUR NON-EMERGENCY EVENT (s)
EAL Emergency Action Level Typical Indication /
Initiating Event B6.9 Spent fuel shipping As occurring or reported vehicle delayed WITH by shipper, media coverage.
B6.10 Public protest of spent As occurring or reported fuel shipment WITH media by shipper, coverage.
B6.11 Cask out of position, As occurring or reported breach not determined.
by shipper.
j FORM (olW2 22 3643
DERP Section 4 Attachment B7 0Public FORT ST VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- PUBUC SERVICE COMPANY OF COLORADO Page 43 of 76 O
MOISTURE INGRESS ALERT EAL Emergency Action level Typical Indication /
Initiating Event B7.1 High radiation levels or CAM (s) alarm high airborne contamination RIS 6212 which indicates severe RIS 6213 degradation in control of RIS 932S2-12 radioactive materials.
Area Monitors (Increase by factor of 1,000 over normal.)
Alarms with corresponding meter readings on area or process monitors.
I O
.g 6
FORM (Ol372 22 3843
1 l
DERP Section 4 Attachment B7 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1
$9fVlCe*
Pusuc senvecs COMPANY OF COLORADO Page 44 of 76 O
MOISTURE INGRESS NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level Typical Indication /
_ Initiating Event NONE IDENTIFIED 8
O O
FORM (D)372 22 3M3
DERP Section 4 Attachment B7 O $9fVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC saRVICs COMPANY OF COLORADO Page 45 of 76 O
V MOISTURE INGRESS ONE HOUR NON-EMERGENCY EVENT (s)
EAL Emergency Action Level Typical Indication /
Initiating Event B7.2 Any deviation from 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-tions which can provide adequate or equivalent protection is immediately apparent.
(The action should be approved, as a minimum, by a senior licensed operator.)
O e
i O
U FORM lD1372 22 3643
DERP Section 4 Attachment B7 OService*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc sanvice comeAny or cotonAno Page 46 of 76 O
MOISTURE INGRESS FOUR HOUR NON-EMERGENCY EVENT (s)
EAL Emergency Action Level Typical Indication /
Initiating Event B7,3 Any unanticipated event Reactor scrams and automatic or condition, i.e., not starting and loading of diesel part of a preplanned generators only, sequence, that results in manual or automatic actuation of an EXCEPTIONS:
Engineered Safety Feature, including the a)
Only one of three channels Plant Protective System, tripped manually or auto-matically, but no final protective action takes place, nor is required, b)
Actuation of the afore-mentioned systems which result from, and are a O'
part of, the planned sequence during surveil-lance testing 1
l l
.I l
FORM (D)712 22.;M43
DERP Section 4 8 OService*
Public FORT ST, VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC SERVICE COMPANY OF COLORADO Page 47 of 76 O
PLANT PROTECTIVE SYSTEM ALERT Emergency Action Level Typical Indication /
Initiating Event B8,1 Evacuation of control Inability to.nonitor shutdown room accompanied by count rate.
inability to locally control shutdown systems within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
O
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l l
l O
FORM (D)372 22 3H3
DERP Section 4 Attachment B8 0 Pubilg FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 service
- PusuC SERVICE COMPANY OF COLORADO Page 48 of 76 O
PLANT PROTECTIVE SYSTEM NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating Event B3.2 Evacuation of Control As deemed necessary by Room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations.
T j
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FORM (Ol372 22 3043 j_'
DERP Section 4 8-0 SerVICO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PUBUC SERVICE COMPANY OF COLORADO Page 49 of 76 O
Page 3 of 4-PLANT PROTECTIVE SYSTEM ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B8.3 Any deviation from 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-tions which can provide adequate or equivalent protection is immediately apparent.
(The action should be approved, as a minimum, by a senior licensed operator.)
88.4 Any event that results a) Loss of significant O,
in a major loss of portion of Control Room emergency assessment indication.
capability, offsite response capability, b) Loss of Emergency or communications Notification System, capability.
c) Loss of all offsite communication systems.
3(c) 1 I
L ron m oi m.22 3.o l
\\
l
DERP Section 4 Attachment B8 0 service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc senvics COMPANY OF COLORADO Page 50 of 76 PLANT PROTECTIVE SYSTEM FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B8.5 Any event, found while Determination as result of the reactor is shutdown, surveillance testing of Plant that, had it been found Protective Systems (PPS) that while the reactor was failure of PPS modules would in operation, would have prevented a required have resulted in the reactor scram from occurring.
plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that signifi-cantly compromises plant safety.
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FORM (o)372 3 3643
DERP Section 4 Attachment B9 0$9fVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc sanvtes COMPANY OF COLORADO Page 51 of 76 a
Page 1 of 4 FIRE ALERT Emergency Action Level Typical Indication /
Initiating Event B9.1 Fire affecting or a) Fire pump 1A start; potentially affecting equipment, components, b) Fire Control Alarm or instrumentation Panel; required to maintain a safe shutdown condition.
c) Various alarms according to affected safety system.
d) Shift Supervisor determines fire beyond capability of station staff.
89.2 Evacuation of Control Inability to monitor shutdown Room accompanied by count rate.
inability to locally p
control shutdown systems V
within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
s
(~.
(
FORMtol372 22 3643
DERP Section 4 9 OService*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PUBUC SERVM:E COMPANY OF COLORADO Page 52 of 76 Page 2 of 4 FIRE NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating Event 89.3 Fire within the a) Any of various alarms plant lasting more on Fire Control Alarm than 30 minutes.
Panel; b) Fire Pump 1A auto start; c) Verbal reports.
89.4 Evacuation of Control As deemed necessary by Room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations.
(::)
FORM (D)372 E 3843
DERP Section 4 9 0 service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PUBUC SERVICE COMPANY OF COLORADO Page 53 of 76 O
Page 3 of 4 ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level
. Typical Indication /
Initiating Event 89.5 Any event that results a) Loss of significant in a major loss of portion of Control Room emergency assessment indication.
capability, offsite response capability, b) Loss of Emergency or communications Notification System.
capability.
c) Loss of all offsite communication systems.
89.6 Any event that compromises a) Fire posing undue safety of the plant, or personnel hazard, significantly hampers site personnel in the b) Accidental gaseous performance of duties radiological release necessary for the safe resulting in onsite
]
conduct of plant activities, concentrations in excess
/
including fires, toxic of 10 CFR 20, Appendix B, gas releases, or Table I, Column 1.-
radioactive releases.
89.7 Fire involving shipping As occurring or repor3ed.
cask, breach not by shipper, determined.
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FOHMIDl372 22 36C
DERP Section 4
' Attachment 89 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 SGTVICO*
PUBUC SERVH:E COMPANY OF COLORADO Page 54 of.76 Page 4 of 4 FIRE FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event NONE IDENTIFIED
.c O
FORM (01372 22 3sc
DERP Section 4 Attachment B10 G$9fVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 l
PUBUC SERWCE COMPANY OF CO'. ORAM Page 55 of 76 i
O ELECTRIC p0WER ALERT Em gency Action Level Typical Indication /
Initiating Event B10.1 Fire affecting or a) Fire pump 1A start.
potentially affecting equipment, components, b) Fire Control Alarm or instrumentation Panel.
required to maintain a safe shutdown condition.
c) Various alarms according to affected safety
- system, d) Shift Supervisor determines fire beyond capability of station staff.
B10.2 Loss of offsite power AND 230 KV OCB trips AND RAT vital onsite AC power undervoltage/ loss of power for up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, alarm accompanied by 4 KV bus O
undervoltage, 480V bus under-voltage, AJ Diesel Trouble al a rnis.
B10.3 Loss of all vital I-06F (2-5) alarm and DC power for up to DC bus 1 and DC bus 2 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, showing no voltage.' #
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FORM (01372 22 3H3
l DERP Section 4 Attachment BIO 0SerVICG*
Pubilg FORT ST. VRAIN NUCLEAR CENERATING STATION
!ssue 1 Pusuc sanvu:a COMPANY OF COLM Page 56 of 76 O
Page 2 of 4 ELECTRIC p0WER NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating Event B10.4 Loss of offsite power OR 230 KV OCB trips AND RAT onsite AC power undervoltage/lossTf power ct.pability.
alarm accompanied by 4 KV bus undervoltage. OR both Diesel Generators AND the ACM Diesel inoperabTe'.
B10,5 Indication or alarms Data Logger Alarm / Alarm on radiological effluent Summary indication of non-monitors not functional, operational alarm or indication on:
a) RIS 7324-1, -2 AND
~-
RIS 4803; or b) RIS 7325-1, 2, RIS 4802, AND RIS 73437-1; or c) RIS 73437-2 AND RIS 4801; or d) RIS 6212 AM RIS,6313 NOTE: Use ELCO 8.1.1 Technical Specification Limits as basis, t
FORM ID) M2. D.3M3
DERP Section 4 Attachment B10 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- PusuC SERVICE COMPANY OF COLORADO Page 57 of 76 0
Page 3 of 4 ELECTRIC POWER ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B10.6 Any event or condition that results in the condition of the plant,
)
including its principle safety barriers being 1
seriously degraded; or l
results in the plant being:
i a) In an unanalyzed a) As determined, condition that significantly compromises plant safety; B10.7 Any event that results a) Loss of significant in a major loss of portion of Control Room O
emergency assessment indication.
capability, offsite response capability, b) Loss of Emergency or communications Notification System, capability, c) Loss of all offsi,te, communication systems.
I l
FORM (Dl372 22 3N3
~
DERP Section 4 Attachment B10 OPublia FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1
$9fVICO' PusuC saRVN:s COMPANY OF COLORADO Page 58 of 76 O
ELECTRIC POWER FOURHOURNON-EMERGENCYEVENT(sj Emergency Action Level Typical Indication /
Init.ating Event B10.8 Any unanticipated event Reactor scrams and automatic or condition, i.e., not starting and loading of diesel part of a preplanned generators only, sequence, that results in manual or automatic actuation of an EXCEPTIONS:
Engineered Safety Feature, including the a)
Only one of three channels Plant Protective System.
tripped manually or auto-matically, but no final protective action takes place, nor is required, b)
Actuation of the afore-mentioned systems which result from, and are a O
part of, the planned sequence during surveil-lance testing.
.4
?
O PORMtD)372 22 3M3
DERP Section 4 Attachment Bil 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc saRVICE COMPANY OF COLORADO Page 59 of 76 OV Page 1 of 4 NATURAL PHENOMENON ALERT Emergency Action Level Typical Indication /
Initiating Event B11.1 Severe natural phenom-enon being experienced or projected, such as:
a) earthquake exceeding a) Seismic recorder operate Operating Basis (2.05 g)
Earthquake levels; (probably cannot be determined within two hours - call to be made in a timely manner.)
b) flood near design b) As Reported level; or, c) tornado striking facility.
c) As Reported I
e FORM (D)712 22 3843
DERP Section 4 Attachment Bil 0 Service
- Pubila FORT ST. VRAIN NUCLEAR GENERATING STATION
!ssue 1 Pusuc sanvece comeAny or cote P89e 60 of 76 O
Page 2 of 4 NATURAL PHENOMENON NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating _ Event B11.2 Natural phenomenon that may be experienced or threatened that represent risks beyond normal levels:
a) earthquake a) Seismic Recorder operates J
b) floods b)-d) As visually observed by, or reported to, i
c) tornados station personnel, i
d) extremely high winds j
i O
j FORM (D)lrf2 22 3843
DERP Section 4 Attachment B11 0 $9tVIC9' Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 1 l
1 Pusuc senvecs COMPANY OF COLORADO Page 61 of 76 O
Page 3 of 4 RATURAL PHENOMENON ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B11.3 Any event or condition that results in the condition of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:
a) In a condition a) Winds experienced in that is outside excess of FSAR design the design basis levels.
of the plant; or, B11.4 Any natural phenomenon Extremely high winds or or other external severe storm preventing condition that compromises plant personnel from O
the safety of the plant completing requisite or significantly hampers assignments.
site personnel in the performance of duties necessary for the safe conduct of plant activities.
. e B11.5 Any event that compromises a) Fire posing undue safety of the plant, or personnel hazard, significantly hampers site personnel in the b) Accidental gaseous performance of duties radiological release.
necessary for the safe resulting in onsite.
conduct of plant activities concentrations'in excess including--fires, toxic of 10 CFR 20, Appendix B,
~
gas releases, or Table I, Column 1.
radioactive releases.
O conmoim.m.see..
/
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.2
DERP Section 4 11 0Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- Pusue sanwes courAmy or cotonAno Page 62 of 76 l
Page 4 of 4 NATURAL PHENOMENON FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event NONE IDENTIFIED t
O
.g Iv FMM(D)372 22 3043
DERP Section 4 Attachment B12 Publia FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 SerVICO' PusuC ssRVICE COMPANY OF COLORADO Page 63 of 76 O
Page 1 of 6 SECURITY ALERT Emergency Action Level Typical Indication /
Initiating Event B12.1 Complete or imminent loss As reported and/or confirmed of physical control of by the LSO or by any member
- facility, of the Security Force.
B12.2 Actual acts of sabotage As reported and/or confirmed that results in or have by the LSO or tt.e imminent potential by any member of the to release radioactive Security Force, material.
B12.3 Explicit confirmed threats As reported and/or confirmed that an act of sabotage or by the LSO theft will be attempted or by any member of the within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />.
Security Force.
B12.4 Any act which has the As reported and/or confirmed O
apparent intent of by the LSO l
destroying or disrupting or by any member of the operation.
Security Force.
B12.5 Actual or attempted loss, As reported and/or confirmed theft, diversion, or by shipper, LSO, Control, Room, or sabotage of shipments of any member of the Security force.
irradiated spent fuel that actually have the potential to degrade public health and safety (10 CFR 73.71).
B12.6 Actual acts of sabotage As repcrted and/or confirmed that have the potential by the LSO for affecting the safe or by any member of the or routine operation of Security Force.
a facility.
("%
d PORM{01772 22 3M3
DERP Section 4 Attachment B12 0Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION issue 1 Service
- Pusuc sanwen comeAwy or cotonAno Page 64 of 76 O
Page 2 of 6 SECURITY ALERT Emergency Action Level Typical Indication /
Initiating Event B12.7 Mass demonstration or As reported and/or confirmed civil disturbances at or by the LSO near a facility that hold or by any member of the the confirmed or suspected Security Force.
potential for affecting the routine or safe operations of the facility.
B12.8 Major loss of the physical As reported and/or confirmed security system that by the LSO provides the opportunity or by any member of the for undetected access from Security Force, outside the facility to vital areas that is not or cannot be compensated.
O B12.9 Unavailability of the As reported and/or confirmed minimum number of security by the LSO personnel for periods or by any member of the exceeding 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, Security Force.
B12.10 Unexplained explosion As reported and/or confirmed or fire within the by the LSO protected or vital or by any member of the areas that could effect Security Force.
plant safety.
B12.11 Loss of Central and As reported and/or confirmed-Secondary Alarm Stations by the LSO resulting from a known or by any member of the-or suspected malevolent Security Force.
act.
B12.12 A kidnapping with a As reported and/or confirmed demand for SNM as by the LSO ransom.
or by any member of the Security Force.
O V
^
FORM (D)372 22 3M3 s
DERP Section 4 Attachment B12 0 Service
- Pubil9 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc senvms cowAny or cotonAno Page 65 of 76 O
Page 3 of 6 SECURITY NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiatina Event B12.13 Actual, potential, or As reported and/or confirmed unconfirmed acts of by the LSO sabotage that do not or by any member of the have the potential, or Security Force.
have not adversely offected the routine or operations of the fae'lity, 812.14 Attemptea or actual As reported and/or confirmed theft of Special Nuclear by the LSO Material (SNM).
or by any member of the l
Security Force.
B12.15 Attempted or actual As reported and/or confirmed intrusions of unauth-by the LSO r
orized persons, weapons, or by any member of the explosives or other Security Force.
devices into the protected area due to a failure of equipment or procedures when no malevolent intent is confirmed or suspected.
B12.16 Unsubstantiated or As reported and/or confirmed potential threats, such by the.LSO as bomb threats or or by any member of the extortion.
Security Force.
212.17 Less of a major portion As reported and/or confirmed-
~
of a physical security by the LSO system that is nr by any member of the compensated.
Security Force.
B12.18 Confirmed tampering with As reported and/or confirmed security equipment that by the LSO results in a minor degrad-or by any member of the ation of the system.
Security Force.
O V
Ponu toim.m.see
DERP Section 4 12 OPublia FORT ST. VRAIN NUCLEAR GENERATING STATION issue 1 Service
- Pusuc senwes comeAmy or cotonAm Page 66 of 76 O
Page 4 of 6 SECURITY NOTIFICATION OF UNUSUAL' EVENT Emergency Action Level Typical Indication /
Initiating Event 812.19 Theft or loss of documents As reported and/or confirmed containing classified by the LSO information, or by any member of the Security Force.
B12.20 Sickouts or labor As reported and/or confirmed problems affecting the by the LSO readiness of the or by any member of the security forces.
Security Force.
B12.21 Unauthorized or As reported and/or confirmed inadvertent discharge of by the LSO a firearm, or by any member of the Security Force.
B12.22 Loss of both central and As reported and/or confirmed O
secondary alarm station by the LSO when cause is known and is or by any member of the not considered sabotage.
Security Force.
B12.23 Known fraudulent records As reported and/or confirmed and accounts of SNM.
by the LSO or by any member of 'tKe Security Force.
B12.24 Any security / safeguards As reported and/or confirmed event which the Lead by the LSO Security Officer deems or by any member of the necessary to take NOUE Security Force.-
precautions.
O
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PORM(Dl372 22 3M3
OERP Section 4 12 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- PUBUC SERWCE COMPANY OF COLORADO Page 67 of 76 O
SECURITY ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action level Typical Indication /
Initiating Event B12.25 As Reported By a Lead Security Officer (LS0) or the Security Supervisor O
o l
FORM (o)772 22 3M3
DERP Section 4 Attachment B12 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- Pusuc sanyms couramy or cotonAno Page 68 of 76 O
SECURITY FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B12.26 As Reported By a Lead Security Officer (LS0) or the Security Supervisor O
e r
O PoRM(D)372 22 3843 m.
_m._
__m
._..__._:_m.___.-
~ -
DERP Section 4 Attachment B13 i
OSerVlCe*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc sanvsca COMPANY OF COLORADO Page 69 of 76 Ov Page 1 of 4 OTHER HAZARDS ALERT
)
Emergency Action Level Typical Indication /
Initiating Event B13.1 Damage to spent fuel a) Visual observation.
resulting in release of radioactivity to plant b) Area radiation monitor environs.
alarms.
B13.2 Severe natural phenom-a) Seismic recorder operate enon being experienced (2.05 g) or projected, such as:
b) As Reported a) earthquake exceeding Operating Basis c) As Reported Earthquake levels; b) flood near design level; or, c) tornado striking facility.
i B13.3 Other hazards being 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.
B13.4 Other plant conditions As deemed necessary by warranting precautionary Shift Supervisor.
activation of the TSC.
O v
. FORM (D)372 22 3M3
DERP Section 4 Attachment B13 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- PusuC sanWCa COMPANY OF COLORADO Page 70 of 76 O
OTHER HAZARDS NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
Initiating Event B13.5 Unusual Hazards 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 O
detrimental effect on the plant; or, c)
Onsite or near site plant related accidents that could result in the uncontained release of toxic material or spills of flammable materials, B13.6 Accidents involving a) Abnormal radiation levels plant spent fuel reported from the cask, shipments or radioactive waste shipments, b) Cask breached, c) As occurring or reported by shipper, O
FoMM(Dl372 22 3M3
DERP Section 4 13 0Pubila FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1
$9fVIC9' Pusuc saRVICs COMPANY OF COLORAM Page 71 of 76 O
Page 3 of 4 OTHER HAZARDS ONE HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event 813.7 Any natural phenomenon Extremely high winds or or other external severe storm preventilig condition that poses an plant personnel from actual threat to the completing requisite safety of the plant or assignments, significantly hampers site personnel in the performance of duties necessary for the safe conduct of plant activities.
B13.8 Any event that results a) Loss of significant in a major loss of portion of Control Room emergency assessment indication.
capability, offsite response capability, b) Loss of Emergency or communications Notification System.
s capability.
c) Loss of all offsite communication systems.
B13.9 Any event that compromises a) Fire posing undue safety of the plant, or personnel hazard; '
significantly hampers site personnel in the b) Accidental gaseous performance of duties radiological release necessary for the safe resulting in onsite conduct of plant activities concentrations in excess including fires, toxic of.10 CFR 20, Appendix B, gas releases, or Table I, Column 1.
radioactive releases.
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O FoAMiol372 22 3M3
DERP Section 4 Attachment B13 0 Service
- Pubils FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc senvics COMPANY OF COLORADO Page 72 of 76 O
Page 4 of 4 OTHER HAZARDS FOUR HOUR NON-EMERGENCY EVENT (s)
Emergency Action Level Typical Indication /
Initiating Event B13.10 Any event or situation, a) On-site 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.
t) Oil or chemical spill which is reportable to the EPA.
B13.11 Any event requiring the As occurring.
O transport of a radio-actively contaminated person to an offsite
. edical facility for treatment.
9
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DERP Section 4 Attachment B14 OService*
Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc sanvoca comeAmy or cotonApo Page 73 of 76 O
PERSONNEL INJURY ALERT EAL Emergency Action level Typical Indication /
~
Initiating Event i
NONE IDENTIFIED O
e e
9 0
PORMID)372 22 3M3
DERP Section 4 Attachment B14 O$9FVlCO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC SERVICE COMPANY OF COLORADO Page 74 of 76 O
Page 2 of 4 PERSONNEL INJURY NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level Typical Indication /
Initiating Event B14.1 Any serious radiological As occurring.
exposure of plant personnel or the transportation to offsite facilities of contaminated personnel who may have been injured.
(Probably cannot be deter-mined within two hours -
call to be made in a timely manner.)
O 4
O FORM (D)372 22 3M3 i
../
~..
DERP Section 4 Attachment B14 0Publia FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- PusuC sERWCE COMPANY OF COLORADO Page 75 of 76 l
O PERSONNEL INJURY ONE HOUR NON-EMERGENCY EVENT (s)
EAL Emergency Action Level Typical Indication /
Initiating Event NONE IDENTIFIED O
t b) l l
FORM (D) 372 + 22 3043 i-
DERP Section 4 Attachment B14 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 1
$9fVICO' Pusuc saRVICE COMPANY OF COLORADO Page 76 of 76 O
Page 4 of 4 PERSONNEL INJURf FOUR HOUR NON-EMERGENCY EVENT (s)
EAL Emergency Action Level Typical Indication /
s Initiating Erent 814.2 Any event or situation, a) On-site 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.
D B14.3 Any event requiring the As occurring.
transport of a radio-actively contaminated person to an offsite medical facility for treatment.
4
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.PORMID)372 22.N43
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U t nr St:C t10fl D
!ssue 1 age 1 of 13
@ Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc sunvece courAmy os cotonAno TITLE:
DEFUELING EMERGENCY RESPONSE PLAN: SECTION 5 EMERGENCY ORGANIZATION PONSIBLE UTHORIZED REOSw PORC 9 21 FEB 131991 57TE S M 41 DCCF NUMBER (S)
Qh 122.9 O
FT, ST. VRAIN NON-CONTROLLED CDP
- VERIFY ISSUE ST ATUS WITH SITE OOCUMENT
'/
CONTROL CENTER PRIOR TO USE FORM (D)372 22 3642
DERP Section 5 Issue 1 Page 2 of 13 O Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO 5.0 EMERGENCY ORGANIZATION 5.1 NORMAL STATION ORGANIZATION The Normal Shift Organization is depicted in
-.1.
Additional information is provided in the station Technical Specifications.
Duties and responsibilities of operating personnel are set forth in station administrative procedures.
5.2 ONSITE EMERGENCY RESPONSE ORGANIZATION The onsite Emergency Response Organization (ERO) for the two emergency' classifications is depicted in Attachments 5.2 and 5.3.
In the event of an emergency, the on-duty Shift Supervisor has the responsibility to initiate immediate actions to limit the consequences of the emergency and to return the plant to a safe and stable condition.
He is also assigned the responsibility of Emergency Coordinator and retains this authority until relieved by the Control Room Director or Technical Support Center Director.
(If during an event the Shift Supervisor is unable to perform as Emergency Coordinator, the most senior Reactor Operator assumes that role.)
In this interim capacity as Emergency Coordinator, he is responsible for:
- 1) classification and declaration of the emergency event; 2) initial notification of appropriate governmental agencies; 3) initiation of protective actions for station personnel; 4) initiation of any required corrective actions to mitigate the consequences m f the event; 5) diagnosing the accident condition and estimating radiological exposures based on radioactive material releases and prevailing meteorological conditions;
- and,
- 6) making protective action recommendations (PARS) to appropriate offsite authorities.
He may confer with FSV and PSC management.for advice or concurrence with initial accident classification.
~
However, contacting management should not delay-in making an event classification and declaration, nor should it delay the required offsite notifications.
The notification time requirements start-upon
-event declaration, regardless of whether manage 7,ent contact is desired or accomplished.
O v
FORMtDl372 22 3M3
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DERP Section 5 Issue 1
- 9' 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc sanvice courAmy or cotonApo O
The Emergency Coordinator is responsible for initially classifying the incident, providing PARS, initiating corresponding emergency
- actions, notifying offsite authorities of the
- incident, and establishing communications with the TSC.
The_ responribility of ensuring that event classification, offsite notifications, and protective action recommendations are completed MAY M be delegated.
The FSV ERO operates from two onsite emergency centers, the Control Room (CR) and the Technical Support Center (TSC),
and will be manned and operational within 90 minutes after classification of an ALERT level incident..3 shows emergency personnel assignments by function.
For clarity, normal job titles are also indicated.
Qualification requirements (per the normal titles) are giv u in corporate job descriptions.
5.2.1 Direction and Coordination Initial direction and coordination of onsite emergency operations will be the responsibility of the Shift Supervisor, as shown in Attachment 5.2 O
and discussed previously. This responsibility will remain with the Shift Supervisor until such time as the ERO is activated (Attachment 5.3).
During an ALERT, overall command of PSC emergency operations wiil be exercised by the TSC D Wector.
He will provide direction to, and. coordination for, the emergency response organization.
A description of the duties and responsibilities of the key members of the FSV emergency response organization is provided below:
NOTE: Only primary positions are indice.ted. A complete listing of qualified personnel for the various positions may be obtained from the FSV Emergency Phone Book maintained by the Emergency Planning Coordinator.
a.
The TSC Director - (Vice President, Nuclear Operations) is in command of PSC emergency operations.
Duties and responsibilities include direction and coordination of:
1.
Emergency response functions.
- Foam (D)372 22 3M3 i
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DERP Section 5 Issue 1
- 9' 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COtORADO O
2.
Transmitting plant status updates and radiological release data to appropriate offsite agencies.
3.
Ensuring adequate administrative, technical, and logistic support is available.
4.
Ensuring.
continuity of emergency organization resources.
NOTE The decisions associated with items 5 and 6 can not be delegated.
5.
Notifying the state and local agencies of any PARS.
6.
Declaring a
particular class of emergency, terminating the emergency or de-escalating the event classification.
7.
The TSC staff, which is responsible for collecting and analyzing the technical information necessary for assessment of plant operational aspects.
8.
Providing technical counsel in support of the CR.
9.
Assessment of radiological release consequences.
- 10. Continued personnel accountability.
3.
Assembling personnel for repair / damage
- control, radiological monitoring,-
and search and rescue teams.
- 12. Assembling personnel.
for-
' reserve
_ operating staff.
13.
Ensuring PSC. property residents have been contacted.
14.
Establishing radiological control' areas as directed.
b.
The 'CR Director
- (Operations Manager), is responsible for control of plant operations, assessing plant operational aspects, and O
implementing recommended corrective actions.
FORM (Ol372 22 3043 m.
DERP Section 5 Issue 1 age 5 of 13 0$9fVlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc SERVICE COMPANY OF COLORADO O
5.2.2 Plant Staff Emeroency Assionments As previously discussed there are two principal onsite groups, the CR and the TSC, which compYise the station emergency response organization. Both groups operate under the supervision of a director located at the emergency center.
Each center director is responsible for center communications and for assigning an individual to keep a record of important events, decisions, and actions that occurred in response to the emergency situation.
A description of the duties of the staff groups located 1n the CR and TSC are provided below:
a.
CONTROL ROOM (CR) 1.
Plant Control The Shift Supervisor is responsible for overall plant control and directs plant operations to terminate the incident, regain plant
- control, and minimize accident consequences.
OV 2.
plant Operations The Reactor Operators have been trained to assist the Shift Supervisor in implementing plant corrective actions.
The normal onsite shift operations staff will be augmented by other operations personnel as dictated by the particular emergency situation.
3.
Communications The CR communicator maintains continued communications with the NRC via the Emergency Notification System (ENS) or a back-up of commercial telephone lines. A competent, plant-knowledgeable individual will be assigned to the communicator position.
If available, a licensed operator is utilized.
O l
l FORMID)372 22 3M3
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DERP Section 5 Issue 1 Pub;!c FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 13 0 Service
- PusuC SERVICE COMPANY OF COLORADO O
4.
Technical Assistance The Technical Advi[or (TA) provides technical analysis / advice and recomnfends corrective actions necessary to bring the 1
plant to a safe and stable condition.
The TA may also perform dose assessment evaluations in support of the plant operations staff.
5.
Health Physics The onshift HP technician will provide HP, radiological assessment, and hazards control support to the Control Room.
Once the TSC is activated he will be supported by additional HP personnel, and will coordinate activities with the TSC HP Coordinator.
b.
Engineering & Technical Analysis Team Personnel in this group perform core O
physics analyses, provide electrical.and mechanical engineering, procedures development, determind alternative I&C capabilities or configurations and repair / install / modify instrument and control equipment, system analysis support, collect technical data for status board updates,. and maintain communications with the NRC.
.The Engineering and Technical Analysi s Coordinator (ETAC) is responsible for the activities of this group.
He is also responsible for-informing the LSO of any emergency situations that may impact the FSV security force.
2.
Health physics This group performs assessment of onsite radiological doses, directs radiation surveys and
- minimal, onsite decontamination actions as required, and ensures that the habitability of the TSC area is being monitored.
FORM (D)T12 22 3843 i
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Otxe section o Issue 1 age 7 of 13 0 Service
- PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION
' PUBUC SERVICE COMPANY OF COLORADO 3.
Dose Assessment This group performs radiological assessment activities and confirms that offsite dose cun,6;uences are limited to a small fraction of the EPA guidelines.
4.
Auministrative & Logistics Support This group will provide needed technical documents, communications and analytical equipment, clerical assistance, and other support for the ERO.
5.
Computer Services Technical support in the areas of' computer hardware and software development / modification will be provided.
6.
TSC Core This group is responsible for maintaining personnel accountability, including O
personnel contamination surveys / exposure
- records, and formation / dispatch of corrective action
- teams, search and rescue teams, and monitoring teams, 5.2.3 PSC Media Center In the event of an ALERT declaration, a PSC Media Center may be established at the FSV Visitor-Center located on PSC owner controlled land to the west of FSV. Media Relations personnel responding to this center will prepare and provide news and related media releases and control ru nors in accordance with the FSV Public Information Manual.
5.2.4 PSC Headquarters Support Public Service company of Colorad" maintains the capability to provide coroorate saport in the event of an emergency at fert St. Vrain.
Headquarters Support includes :>nior corporate personnel with the authority e activate PSC personnel, facilitits, and equiprants as well as financial resources which may be needed in an emergency situation.
13 Q
i t
FORM (D)372 22 443 '
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_ ~ _.. _,. - _ _ _ _ _ _ _ _ _ _ - -,
DERP Section 5 Issue 1 age 8 of 13 0 $9fVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc SERVICE COMPANY OF COLORADO 5.3 0FFSITE EMERGENCY SUPPORT 5.3.1 Local Services Support In emergency situations, assistance from outside companies and services may be required. Assistance available from outside companies includes ambulance l
service to transport injured and/or cor.taminated personnel, medical treatment, and hospital facilities for station personnel who require such assistance.
In addition, a specific agreement has been developed with the Platteville Volunteer Fire Department for onsite fire protection assistance.
Letters of agreement for these services are contained in Section 9..4 lists these agencies by the type of service.
5 3.2 Contract Support Specialized assistance from contractors may also be requested in an emergency situation.
Contract support may include construction, dosimetry and laboratory analysis, and decontamination and rad-waste disposal assistance.
Provisions have O.,
been made for selected contract support firms -to provide this assistance, on request.
5.3.3 Feceral Assistance In addition to coordination-with state /1ocal govermental entities, technical assistance. from certain federal agencies in the area of communications, radiological monitoring and laboratory analysis, transportation, and weather forecasts may be requested. The State of Colorado wili officially request federal assistance. PSC will, therefore, channel contacts with federal agencies (except NRC) through the state.
The fc11owing agencies will be notified / requested to provide assistance, as necessary:
a.
The Nuclear Regulatory Commission, Office of Inspection and Enforcement, Region IV, via the NRC Incide.c Response Center in Bethesda, MD.
b.
The Departrent of Energy (DOE) - Radiological Assistance 'eams (RAT), Idaho Falls, Idaho and Rocky F%ts, Colorado; Aerial Monitoring System (AMS),Las Vegas, Nevada.
00E will
(
acM vate the Interagency Radiological Assistance Plan (IRAP) as necessary.
FORM 101372 22.ud3
DERP Section 5 Issue 1
- 9' 0 Service
Federal Emergency Management Agency (FEMA),
Region VIII, Denver, Colorado.
d.
Upon request by the State of Colorado,'the i
Federal Radiological Emergency: Response Plan (FRERP) will be activated, with response from numerous federal agencies with
_ emergency resources.
5.4 COORDINATION WITH PARTICIPATING GOVERNMENT AGENCIES The State of Colorado, through the Division of Disaster Emergency Services (000ES), has responsibility -for control of offsite actions.
The concept of -operations for discharging this responsibility, together with a
discussion of action responsibilities assigned to various state / local governmental agencies is contained in the-State RERP.
For a complete discussion of authority,-
assigned responsibilities, capabilities, and activation and communicatior arrangements, refer to the State RERP.
Based on the remaining, credible defueling accidents, offsite dose corsequences will be negligible and PSC does not anticipate emergency classifications above an ALERT.
With no offsite consequences, PSC does not expect / rely l
upon activation of the State RERP te support a Fort St.
,~
Vrain emergency.
4
?
l.
O FORM (ol772 22-3643
DERP Section 5.1 0 SerVlCO' Public FORT ST VPAIN NUCLEAR GENERATING STATION 10 of 13 PUBUC BERVICE COMPANY OF COLORADO O
NORMAL SHIFT ORGANIZATION Fort St. Vrain Nuclear Generating Station 4
l SHIFT SUPERVISOR l l TECHNICAL ADVISORI
.......I (SRO)
[**j l
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_l (1) l I
(1)* I II I
I I
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LEAD SECURITY l
l HP TECHNICIAN ll l
OFFICER I
I (1)
Il I
(1) l l
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l l REACTOR OPERATOR l l SECURITY GUARDS l l_l (RO) lul l
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l lEQUIPMENT OPERATORS l l_I (2) l II I
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i l l AUXILIARY TENDERS l l_I (2)**l I
I NOTES.
SR0 SENIOR REACTOR OPERATOR.
R0 REACTOR OPERATOR.
HP HEALTH PHYSICS TECHNICIAN TECHNICAL ADVISOR IS ON CALL 24 HOURS PER DAY AND WILL REPORT TO THE CONTROL ROOM WITHIN 1 HOUR.
DURING COLD SHUTDOWN ONLY ONE R0 IS REQUIRED TO BE ON DUTY. AN INDIVIDUAL WITH AN SR0 LICENSE OTHER THAN THE ON-DUTY SHIFT SUPERVISOR IS NOT REQUIRED, NOR IS AN AUXILIARY TENDER.
LINE OF AUTHORITY COMMUNICATION 9
FORM (0)?72 22 3643
.=.-
DERP Section 5
'.2 3
O Service
- Public FORT ST VRAIN NUCLEAR GENERATING STATION e
M 13 PUBUC SERVICE COMPANY OF COLORADO EMERGENCY ORGANIZATION (NOTIFICATION OF UNUSUAL EVENT)
Fort St. Vrain Nuclear Generating Station l
SHIFT SUPERVISOR
- l l TECHNICAL ADVISOR l l
(SRO) l"l l
l 1,2,3 l
l 8 l I
I l
1 l
l l
l
~
l HP TECHNICIAN l l
REACTOR OPERATOR l l
LEAD SECURITY l l
I"l (SRO) 1"l OFFICER l
4 l
4,6 l l
l l
6,7 l 1
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1 NOTES:
EMERGENCY COORDINATOR ON CALL 24 HOURS A DAY, ONE HOUR MAXIMUM RESPONSE TIME 1
PLANT OPERATIONS AND CONTROL 2
0FFSITE NOTIFICATION
~
j 3
PLANT CONDITION ASSESSMENT l
4 HEALTH PHYSICS & DEFUELING ASSESSMENT 5
REPAIR AND DAMAGE CONTROL 6
HAZARDS CONTROL 7
PERSONNEL ACCOUNTABILITY 8
TECHNICAL ASSISTANCE LINE OF AUTHORITY COMMUNICATION "a***"
FORMt01372 22 3643
DERP Section 5-.3 OPublic FORT. ST. VRAIN NUCLEAR GENERATING STATION -
g 33 Service
- Pusuc saRvice comeAmy or cotonAno O
iuatoaa m mos El8ERGENCY RESPONBE ORGANIIATION PORT ST.VRAIN NUCLEAR GE95 RATING STATION TiensumoR w, NuotaAR opeRAroNo
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.g TechniestSupporttoOperemons secuswrycooRoosArom NOTE: Onlyprimarypoetsonoareindlested. A seoupwryPuRoommL esmplete Noting of queNfled pereennel for the O
VerlOUS peshione mey 130 otilainell (fom the PSV Emergency Phone Book.
I 4
1 OCSITRob ROOM TeoHNtoAL SWpoRT CWffW FORM (D)372 22 3tM3
=
DERP Section 5.4 ssue O $9fVICO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO OV LOCAL AGENCY AND CONTRACT SUPPORT SERVICES Fort St. Vrain Nuclear Generating Station Local Agency Support Service Volunteer Fire Department Onsite Fire Protection Platteville, Colorado Assistance / Ambulance Service' Volunteer Fire Departments Mutual Aid Fire Protection Milliken, Johnstown, Gilcrest, Assistance' Colorado St. Luke's Hospital Medical Treatment /Decon-Denver, Colorado tamination Assistance Contract Support Support Service Colorado State University Environmental Monitoring O,
Fort Collins, Colorado Assistance.
Controls For Environmental Chemical-Radiochemical Pollution, Inc.
Laboratory. Analysis Santa Fe, New Mexico
.g EBASCO Services, Inc.
Engineering, Construction, Golden, Colorado
' Procurement Assistance General Atomic Corporation NSSS, Reactor Physics, and San Diego, California Systems Modification-Assistance-Dr. Hilding G. Olson-Nuclear Engineering
~
San Angelo, Texas Consultant R. S. Landauer, Jr. & Co.
Environmental Monitoring, Glenwood, Illinois Dosimetry Processing Stone & Webster Engineering Corp.
Engineering / Construction /
Denver, Colorado System Modification Assistance Western Radiation Consultants, Inc.
Radiation Protection Fort Collins, Colorado i
i FORM (0)772 22 3643
~
DERP Section 6 O ServlCO' Public FORT ST VRAIN NUCLEAR GENERATING STATION gf g PUBUC SERVICE COMPANY OF COLORADO TITLE:
DEFUELING EMERGENCY RESPONSE PLAN, SECTION 6 EMERGENCY MEASURES PONSIBLE UTHORIZED
/
PORC EFFECTIVE REVIEW MNC 9 21 FEB 131991 DATE 3 - 2.9 9l DCCF NUMBER (S) hO-l 7M O
r FT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTBOL CENTER PP'OR TO USE FORM (D)772 22 3642
DERP Section 6 FORT ST VRAIN NUCLEAR GENERATING STATION e1 0Public Service
- PusuC SERVICE COMPANY OF COLORADO O
6.0 EMERGENCY MEASURES Station emergency measures will be initiated upon, and recording to, incident classification.
This section icentifies segments of the station emergency response organization that will be activated by class of emergency, details methods and procedures for assessment actions, specifies actions to correct or minimize the emergency situation, describes protective actions to prevent or minimize radiological exposure, and sets forth measures to assist persons injured or exposed to radiation and radioactive material.
6.1 ACTIVATION OF EMERGENCY RESPONSE ORGANIZATION The two classes of emergency defined in Section 4 require a varying degree and scope of emergency responses.
The emergency organization activated in each emergency classification is shown in Section 5.
The Shift Supervisor will immediately initiate action to limit the
=
consequences of the event and to return the plant to a safe and stable condition.
The emergency organization for a NOTIFICATION OF. UNUSUAL EVENT consists of. normal shift personnel.
No augmentation is required.
For ALERT level accidents, onsite emergency response facilities will be manned and activated, The plant radiological emergency
(
alarm is sounded for ALEkT level accident classifications.
The plant fire alarm will be sounded to indicate all emergency conditions involving a fire, regardless of event classification.
The location and extent of the event is announced over the station Gai-tronics system, or public address system.
If the emergency occurs during a back shift period, the Shift Supervisor in the role of Emergency Coordinator, establishes the plant emergency response organization per Section 5.2.
e a
s FORM (D)372 22 3643
DERP Section 6 Issue 1 0 Service
NOTE: Activation of the FSV.
Emergency
Response
Organization is not required in a NOVE.
Classification of an incident as a NOTIFICATION OF UNUSUAL EVENT (NOVE) or higher event requires notification consisting of the following telephone contacts, as indicated in Attachment 6.1.
The state and local emergency response organization is notified by two telephone calls:
the first to Weld County Communications
- Center, and then directly to the Colorado Department of Health.
Notification is authenticated by either a
call-back or the fact that the microwave link was used.
The Nuclear Regulatory Commission's Operations Center is notified via the Emergency Notification System or commercial telephone service.
The NRC Resident Inspector in contacted as well as the on-duty Technical Advisor (TA) and a plant management contact (optional).
If the event is classified as an ALERT,-a telephone call is made to initiate the Emergency Pager System (primary) or to plant management to initiate the Notification Fanout Call Lists in the event that the Emergency Pager
-System is inoperable.
Personnel / equipment augmentation -may vary according to O-specific circumstances.
The functions of the Emergency Response Facilities (ERFs) include:
Control Room Assessment of Plant Operating Conditions Implementing Corrective Actions Fire Fighting Direction Personnel Accountability (Initial)
FORM (D)372 22 3643
DERP Section 6 Issue 1 0 SGTVICe*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 21 Pusuc SERVICE COMPANY OF COLORADO O
Technical Support Center Command Plant Systems Assessment Reactor Engineering Recommendation of Corrective Actions Dose Projections Health Physics Assessment Notification / Communications Protective Action Recommendations Offsite Communications Personnel Accountability (Continued)
Emergency Response Emergency Repair / Damage Control Radiological Surveys Radiation Protection (Personnel Monitoring / Dosimetry /
~
Decontamination / Access / Reentry Control)
Search and Rescue /First Aid Fire Brigade backup
6.2 ASSESSMENT
ACTIONS The assessment of plant conditions, radiation levels, and offsite consequences is initially coordinated by the Shift Supervisor (Emergency Coordinator).
-As the Emergency Response Organization is activated,
.the assessment functions are conducted by personnel working in the Control Room and TSC.
Coordination of these efforts is
,done by the Cirectors in each center. Overall management is provided by the Technical Support Center Director in the TSC.
The different types of assessment actions are described in Attachment 6.2, Assessment will continue throughout the emergency period.
Continued. assessment may result in reclassification of the incident and consequent alteration in emergency response actions.
O FORM (of T/2 22 360
DERP Section 6 Issue 1 0 $9fVICO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5'of 21 PUBUC SERVICE COMPANY OF COLORADO O
Incidents involving potential or actual release of radioactive materials to the environment require special methods of assessment to ensure that responses are appropriate for protection of the population-at-risk and station personnel.
Post-accident sampling is described in appropriate Health Physics and Radiochemistry procedures.
FSV also has an extensive system for monitoring radioactive materials released to the environment (e.g.,
gaseous, process liquid, and reactor building ventilation exhaust). The station is equipped with process and system monitors capable of initiating appropriate alarms and/or actuating control equipment for containment of radioactive materials if pre-established limits are reached.
These systems will monitor activity releases during-accident conditions.
In any accident where release: are not monitorable, emergency procedures provide
" theoretical" worst-case relecse rates corresponding to the Design Base Accidents outlined in Section-14 of the FSV Updated FSAR and the Defueling SAR.
The site has a permanent meteorological installation which indicates and records wind speed and direction and temperature differentials on a continuous basis in the-Control Roem.
Additional readout capability is provided
\\
in the TSC via plant computer links.
In the-event that meteorological information in the Control Room and TSC is unavailable, arrangements and procedures have been developed to secure necessary meteorological information from the 10 meter National Oceanic and., Atmospheric Administration (NOAA) tower located on PSC property to the north of the plant.
The methodology and technique used to predict offsite concentrations of radioactive noble gases and iodine are contained in DERP-DOSE.
Air concentration levels are-verified by a field monitoring team consisting of an HP Technician / Training Instructor and an assistant deployed -in a vehicle with portable emergency radiological instrumentation-- including an air tampler with silver zeolite cartridges, radiation survey meters, and portable radios on PSC frequencies.
These teams are deployed from the TSC, and have the capability to sample radiciodine concentrations as low as 1 X 10E-7 pC1/cc under field conditions.
Information so developed will assist offsite emergency response authorities to reach appropriate decisions on modification of emergency protective actions initiated as a result of previous estimates of exposure levels (see DERP
_h (d
implementing procedure-DERP-FIELD, Field Monitoring Procedure).
FORM (D)372 22 3643
k DERP Section 6 Issue 1 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 2*
Service
- PUBUC SERVICE COMPANY OF COLORADO I
Unmonitored releases are descrihed in detail in DERP
-implementing procedure OERP-DOSE, Offsite Dese Calculation Methodology.
6.6.1 Due to Fort St. Vrain's core design and design base accident analyses, PSC field monitoring teams do not sample and analyze _all radionuclides identified in Table 3 of NUREG 06S4/ FEMA-REP-1, Rev. 1.
PSC field monitoring teams primarily conduct air and ground surf ace radiation sampling.
Environmental monitoring, as contracted with Colorado State University, prov' des more in-depth radiological monitoring concerning ground / water deposition and food chain impact.
6.3 CORRECTIVE ACTIONS Station procedures contain steps for preventive and/or corrective actions to avoid or mitigate serious consequences of an incident.
Control and display of information is centralized in the Control Room.
The information provided by this instrumentation forms the basis for declaration of emergency' classes.
Corrective actions will also involve _ response by the following organizations:
Fire Fighting The Fire Brigade will respond -to station fire calls.
If outside assistance is required, a call is made to the Weld County Emergency Communications Center who then dispatches appropriate fire departments, normally the Platteville Volunteer Fire Department (VFD).
Upon arrival, the fire department will be escorted to the fire scene by security personnel.
Damage Control, Repair, and Decontamination For minor emergencies, station _ personnel will handle cleanup, repair, and damage control.
For more major site emergencies, the support of company personnel, or specialized outside contractors, may be required to assist in damage control, cleanup,-
and repair operations.
O FoftM(Dl372 22 3643
DERP Section 6 Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 21 SerVlCe*
PUBUC SERVICE COMPANY OF COLORADO 6.4 PROTECTIVE ACTIONS Actions to protect station personnel,
- visitors, and residents on FSV company property are the responsibility of the Shift Supervisor (as Emergency Coordinator) until he is relieved.
Measures for the protection of the general public are detailed in the State RERP.
6.4.1 Protective Cover and Personnel Accountability a.
Onsite Protective actions for personnel on FSV company property will be taken whenever a radiological emergency has occurred, or may occur, which results in concentrations of airborne activity, or radiation ' levels, in excess of. normal limits for.a specified area or areas, that cannot be readily controlled.
In addition, protective actions will be taken for' these personnel in other emergency situations such as
- fires, floods, and tornadoer where personnel safety is N
threatened.
Notification of_-these personnel will be by actuation of plant alarm systems, s
telephone calls, and Gai-tronics announcements as applicable.
Property residents are notified via telephone.
If no one answers, a PSC repres6ntitive is sent to verify / notify applicable residences.
Notification will be accomplished as soon as assessment actions permit a determination of the emergency class and corresponding actions.
Station personnel will_ be notified of appropriate actions to be taken at their respective personne's accountability stations or by appropriate supervisory personnel.
FoMM(D)772 22 3643
DERP'Section 6 Issue 1 0Public FORT ST VRAIN NUCLEAR GENERATING STATION Page 8 of 21 SerVlCe*
PUBLIC SERVICE COMPANY OF COLORADO O
1.
Personnel Accountability FSV performs a " positive" accouatability, meaning that only personnel present in the protected area are accounted for.
This method is accomplished utilizing the security computer system which provides a listir.g of all badges presently within the protected area at any given time.
Site visitors inside the protected area will be escorted by their escort personnel to the Security Building where they will be monitored for contamination and normally depart the site, or be told to report to a specific loca* ion.
Their escorts will then report to their predesignated personnel accountability stations.
Visitor Center personnel will be notified and-advised of appropriate protective actions, as needed.
Personnel response for accountability x_,
will not differ, regardless of time of day.
The majority of personnel will exit via the security building, where they will be monitored for contamination, and report to the Visitor's Center to await forther instruction.
Alf
'pe rsonnel.
within the protected area will report to their assigned accountability stations
' indicated on.their badges.
Security personnel will conduct the accountability process.
The protected area accountability stations are contacted by a Security Officer with a list of personnel who should be present at the station.
If a person is missing from the accountability station, this will be noted by the Security Officer.
s
's FORM (D)372 22 3643
DERP Section 6 4
Issue 1 0SerVlCe*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 9 of 21
- PusuC SERVICE COMPANY OF COLORADO O
The Security Officer will also record and report any personnel with the Visitor Center as their designated accouhtability station which are shown as still being within the protected area.
The number and/or names of missing individuals will be reported to the Shift Supervisor by Security.
This initial accountability process will be completed within-30 minutes of the activation of the alarm.
The TSC Director has responsibility for maintaining personnel accountability after the initial accountability process has been completed.
Refer to Administrative Procedure G-5, Personnel Emergency Response, for specific details of the personnel accountability process.
2.
Security and Access Control Support personnel reporting-to the station during an emergency-report to the O
badge cube.
Any necessary instructions relative to entering the plant will be posted at the badge cube entrance.
1 3.
Rescue Operations The search and rescue' function is handled by trained Fire Brigade, Health Physics, or auxiliary plant personnel.
When station personnel are unaccounted for in the initial or subsequent. emergency accountability,.the Shift Supervisor
- assigns, or requests from the TSC, a search and rescue team. to locate and, if.
necessary,- rescue personnel.
The teams:
-will utilize OERP implementing procedure DERP-TEAMS, Emergency Team Formation and Direction, and will observe the' emergency exposure limits outlined in.4.
O FORM (01372 22 3643 '
DERP Section 6 Issue 1 O$9fVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION-Page 10 of 21 PusuC SERVICE COMPANY OF COLORADO O
b.
Offsite The Emergency Coordinator will recommtnd appropriate initial prciective actions to offsite authorities, to include sheltering, based upon consideration of relative benefits of the alternatives.
The action which affords the greatest ; mount of dose avoidance for accidents (where projected or measured offsite doses are expected to exceed Protective Action Guides - Attachment 6.3) will generally be preferred.
Evacuation of members of the public is not necessary. With FSV permentally shutdown and in the defueling mode of operation, engineering analysis has been performed to document that no accident potential exists that will result in offsite releases greater than 1 Rem at the EPZ boundary.
The TSC Director will reco? mend any additional appropriate protective actions once. he has assumed control of the emergency -resporse organization.
Protective actions for offsite areas are initiated by state / local emergency response organizations as detailed in the State RERP.
The State of Colorado has adopted the EPA Protective Action Guides for, initiating actions to protect the general public.
Plans
.for activating state / local emergency. response agencies and performing various protective actions and services are specified in the State RERP.
6.4.2 Use of Onsite' Protective Equipment and' Supplies l
A variety of protective equipment is available onsite to
-minimize radiological exposures, contamination problems, and fire fighting hazards.
The types.of equipment, their criteria for-
- issuance, location, 'and means of distribution are noted in Attachment 6.5.
i
~
FORM (o)372 22 3643
DERP Section 6 Issue 1 0 service
6.4.3 Contamination Control Measures Measures will be taken to prevent, or Ininimize, direct or subsequent ingestion of radioactive materials deposited within the exclusion area. As necessary, af fected areas will be identified and isolated.
Details-of contamination control measures for onsite areas are contained in station procedures.
The following is an outline of those procedural controls:
1.
Radioactive Contamination of Personnel I
Controls have been established to ensure that levels of removable contamination outside radiologically controlled areas will be maintained at less than allowable limits.
Emergency decontamination limits are established in DERP implementing procedure DERP-DECON, Emergency Decontaminatien Practices.
The environment of personnel working within radiological control areas are
. h i
supervised by Health Physics (HP) v personnel.
Radiation Work Permits-(RWPs) 4 may be required for personnel in.such areas.
Specific instructions, i
precautions, and limitations are listed on RWPs.
. Protective clothing is required for individuals entering contaminated areas.
Individuals leav.ing radiological control areas are monitored for contamination d
upon de'parture, i
Quarterly integrated accumulations of l
radionuclides in the body vill not exceed 5
accumulation levels which would result
.from exposure-to the maximum permissible 2
concentrations- (MPC) of radionuclides in-air or drinking water for occupational exposure as indicated in 10CFR20.103.
Food 'for emergency personnel will be provided from offsite sources.
1 p
!V FoRMID)372 22 3643
-.~...-
DERP Section 6
- 0. Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pag 12 of 21 Puntic senvice company or cotonAno
!D V
Exposure to airborne concentrations
+
higher than the MPC will be prevented or avoided.
If axposures are nbcessary, wearing appiopriate, properly f.i tted respiratory protective equipment will be required, as determined by HP.
Periodic air samples will be taken in selected operational and work areas to ensure that MPC levels are not exceeded.
2.
Radioactive Contamination of Equioment Tools and equipment used in radiological control areas will be-checked for contamination before they are taken outside the control area.
If any equipment is found to be contaminated.and decontamination is not practical, the item will remain controlled.
Emergency decontamination limits are established in DERP implementing procedure DERP-DECON, Emergency Decontamination Practices.
Equipment and tools will be m
ty unconditionally released for use outside the area only if removable contamination and radiation levels are less than the allowable limits.
Removal of material from. radiological control areas with radiation and contamination levels in excess of specified limits. must be approved for release by
.HP personnel.
Any contaminated material approved for release will be packaged, sealed, and labeled with a
properly executed radioactive material tag and handled in accordance with approved procedures.
O U
FoflM(D)J72 22 3643
DERP Section 6 0 PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION Pa 13 of 21 Service
- PUBUC SERVICE COMPANY OF COLORADO 6.5 AID TO AFFECTED PERSONNEL 6.5.1 Emergency Personnel Exposure Criteria Exposure records are maintained for station personnel at the
- TSC, as required.
This information will be utilized in determining emergency team assignments.
Criteria used for limiting doses to emergency workers are based on recommendations of the EPA and are shown in.4.
Emergency workers will carry self-reading dosimeters in addition to film badges.
Emergency dosimetry services will be provided j
through the services of an outside contractor.
Emergency dosimetry service response is provided on a 24-hour basis.
Every effort will be made to minimize emergency worker doses through the use of protective equipment and supplies.
The TSC Director is responsible for emergency team assignments and may authorize emergency workers to receive doses in excess of 10CFR20 limits.
This' authorization to exceed occupational exposure limits shall be performed in accordance with DERP O
implementing procedure OERP-EXP, Emergency Exposure Guidelines,
.and shall be given only after consultation with the senior HP Representative at the TSC.
The TSC Director will be notified of. accidental or emergency exposure in excess of occupational limits.
Those individuals'will not be assigned to further emergency team operations.
Decisions to accept doses in excess of occupational limits in life saving situations will' be on a volunteer basis.
In no case will doses be permitted to exceed 75 Rem Whole Body.
The TSC Director is also responsible _for assuring the distribution of film badges and self-reading. dosimetric devices to emergency personnel and assuring the ongoing accountability of each worker's dose.
O I
FORM (ol372 22*3643
DERP-Section 6 OSerVlCe*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION 14 of 21 PUBUC SERVICE COMPANY OF COLORADO OV 6.5.2 Decontamination and First Aid Provisions have been made to assist personnel who are injured, or who may have received high radiation doses.
There are station personnel who are trained in first aid and decontamination procedures.
In addition, onsite decontamination areas are equipped with decontamination supplies and other specialized equipment.
Personnel found to be contaminated (any detectable activity above background) will undergo decontamination in accordance with the appropriate HP Procedures.
Where contamination of large or open wounds is involved, personnel will be immediately transported to designated offsite medical facilities where they will receive prompt medical attention in accordance with.the FSV Medical Emergency Pian, MEP-FSV.
4 Each emergency team will include members trained in first aid.
First aid kits are available at station locations in accordance with PSC policy specified in the General Instructions.
6.5.3 Medical Transportation Injured / contaminated personnel who require medical attention will be transported to St.
Luke's Hospital by helicopter, or Weld County Ambulance Service. A personal vehicle may be utilized if-appropriate. Ambulance crews are pro'vi'ded' training to handle contamination cases.
PSC health physics trained personnel will accompany contaminated patients to the
- hospital,
'if.
possible.
Communications between FSV and emergency medical vehicles will be channeled through the Weld County Communications Center.
6.5.4 Medical Treatment Arrangements for : treating contaminated patients have been made with St. Luke's Hospital in Denver.
In situations where there isn't time to transport a patient to St.
Luke's, North Colorado Medical Center,- Greeley, may be utilized.
In these cases, FSV Health Physics personnel will respond to assist in contamination control at the hospital.
O FORM (Dl372 22 3643
DERP Section 6 Issue 1 0 Service
Hospital staff at St. Luke'.s are trained to treat contaminated
- patients, Following decontamination, personnel suspected
'to have ingested radionuclides will undergo whole body counting at PSC or CDH facilities.
Communications between FSV and fixed medical facilities are via commercial telephone and are handled in accordance with the MEP-FSV.
6.6 COMMITMENTS The step (s) and section(s) listed below may not be deleted without issuance of comparable controls.
The procedure
- itself, if initiated as a result of commitment corrective action, may not be deleted without issuance of comparable controls.
6.6.1 The statements concerning field monitoring sampling and applicable isotopes from NUREG 0654/ FEMA-REP-1, Rev. 1, Table 3, is a result of QDR 87-083.
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-f
DERP Section 6 O $9TVICe*
Public FORT ST VRAIN NUCLEAR GENERATING STATION u
Pusuc sanvece COMPANY OF COLORADO Page 16 of 21 NOTIFICATION CALL SEQUENCE REQUIRED IN THE EVENT OF A NOUE OR ALERT l
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O DERP Section 6
- .3 Issue 1 Page 19 of 21 Recommended protective actions to avoid / reduce whole body and thyroid dose f rom exposure to a gaseous plume Projected Avoidable Dose (Rem) 10 Emergency Team Workers Recommended Actions (a)
Comments Whole body 25 Control exposure of emergency teams members to these levels except for lifesaving missions, Thy ro id 125
( Appropriate controls for
{i\\
emergency workers, include Al though respi rators and time limitations, resp i ra to rs, stable iodine should be and stable lodine.)
used where effective to control dose to emergency Whole Bodf 75 Control exposure of emergency team workers, thyroid team members performing dose may not be a limiting lifesaving missions to this factor for lifesaving level. -(Control of time missions.
of exposure will be most erfective.)
(a) These actions a re recommended limits for planning purposes and any exposures in excess of occupational (10CFR20) limits must be handled in accordance with DERP Implementing procedure OERP-EXP, " Emergency Exposure Guidel ines."
Protective action decisions at the time of the incident must take existing conditions into consideration.
e a
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(
V DIRP Section 6.4 Issue 1 Page 20 of 21 Exposure Criteria for Emergency Workers *
. Situation Whole Body T hy ro l d *
- 1.
Emergency duties not related 5 Rem 25 Rem to protecting equipment, personnel, or the public.***
2.
Prevent extensive equipment 25 Rem (planned) 125 Rem damage, further escape of effluents, 12 Rem (unplanned) or cont rol fires.
- 3. Lifesaving missions, e.g.,
sea rch 75 Rem Unlimited ****
and rescue of injured people, preveet conditions thz would injeee numbers of people.
- Admini stered in accordance with DERP Implementing procs t'
%RP. MP, " Emergency Exposure Guidel ines".
- Respiratory protection will be provided as necessa ry.
- Includes performing accident assessment, prov ' ~.ng fi rst a
,7rf c.ing personnel decon ta m i na t ion, providing ambulance service, and providing med.;at t rea tme ". < vices.
- Although respirators should be used where effective to contro, dasa to emergency team workers, thyroid dose may not be a limiting factor for a lifesaving mission.
i i
4
3 i
l DERP Sectioa 6
'.5 Issue 1
- (
Page 21 of 21 B
i
+
Use of Protective Iquipment and Supplies t
l Criteria for i
1 uts i pmen t issuance l_oca t ion Means of Distribution i
+
- 1) Full Faco Canister As needed by Emergency a) Selected Emergency a) Issued at TSC Respi rator.
Teams ' in areas of high Monitoring Mits i
airborne radioactivity b) Respiratory issue b) Picked up a t nea rest
'l Lockers-Turbine Deck.
station as directed by Health Physics Pe rsonne 8.
I
- 2) Self Contained a) Inha lation haza rd during a) Control Room a) Used as needed by Breathing Apparatus fire fighting b) Various Areas in ope ra to rs, b) Ai rborne radioactivi ty in Station
.b) Issued as needed by
. excess ol' administratively Health Physics
' set' levels Personnel.
c) Toxic. gas haza rd
- 3) Protective Clothing As needed in a rea s of a) Various Areas of a) Issued as needed by
( Cove ra l i s, Hood s, -
known contamination the station.
Health Physics Boots; Cloves). '
b) Emergency Kits.
Personnel.
b) Issued at TSC tt) Ai r-fed Respi rator Airborne radioactivity.
a ) Cont ro l Room a) Used.as required by in excess of administratively b) Respiratory issue ope ra to rs.
set" levels.
Lockers-Turbine Deck.
b) issued-by Health s
Physics Personnel.
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Issue 1 9'
2I 0SerVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO TITLE:
DEFUELING EMERGENCY RESPONSE PLAN: SECTION 7 EMERGENCY FACILITIES AND EQUIPMENT PONSIBLE 3" """ g)$L lge PCEO 9 21 FEB 131991
[F TlVE m
TE DCCF NUMBER (S) h-/ 2.3 l
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PT. ST. VRAIN NON CONTROLLED COPY VERIFY 188UE STATUS WITH SITE DOCUMENT O
CONTROL CENTER PRIOR TO Ued FORMt01372 22 3642 m
DERP Section 7 Issue 1 0 Service
- Public FORT ST VRAIN NUCLEAR GENERATING STATION PusWC SERWCE COMPANY OF COLORADO 7.0 EMERGENCY FACILITIES AND E0VIPMENT This section describes:
emergency response facilities; onsite and offsite communication systems links; assessment facilities andegyipment; protective {acilitiesandequipment;firstaid and medical facilities; and damage control equipment and supplies.
7.1 EMERGENCY RESPONSE FACILITIES 7.1.1 Technical Support Center (TSC)
FSV emergency command activities are centered in the TSC located immediately adjacent to the Reactor Building and within short walking distance from the j
Control Room (CR). The TSC will be manned within 90 minutes of a declaration of an ALERT classification.
The TSC is equipped with telephones, NRC Emergency Notification System (ENS) and Health Physics Network (HPN) telephones, telecopier, and radios for communications with the CR.
The,TSC is equipped with a CDC-1700 terminal for-O visualization of plant parameters and dose calculations. Additionally, essential drawings,.
specifications, and procedures are maintained in the TSC.
Radiation monitoring equipment, protective clothing, communications equipment, protective breathing apparatus, and first-ai<l equipment are located in an Emergency Kit which is sealed and inventoried on a regular basis by HP.
The habitability requirements-for the TSC are similar to those. imposed upon the CR.
In the event the TSC becomes uninhabitable, senior management personnel would relocate to the CR. The remainder of the TSC staff would relocated to another convenient location, as directed.
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Ponutom2 22 see l
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DERP 5ection 7 Issue 1 4
0 SGTVlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO 7.1.2 Control Room (CR)
Energency assessment eno contr61 is initially directed from the CR by the Shift. Supervisor prior to activation,,of the TSC. The CR, lou:ted adjacent to the Reactor Building, is designed to be habitable during Design Basis Accidents. The #R contains full plant instrumentation, technical drawings, radio, telephone, and intercom systems.
Emergency radiological monitoring equipment, protecti w breathing apparatus, and protective clothing are located nearby.
7.1.3 Media Briefinos If necessary, briefings with the media can take place at the FSV Visitor Center, located to the west of the 'lant 7.2 COMMUNICATIONS SYSTEMS j
Communications between onsite and offsite consist of commercial telephones and dedicated microwave links.
From the TSC, messages are relayed to designated agencies via Weld County, 000ES, and Colorado National Guard radio O
communication systems. Two-way radios will be used to maintain communications between the TSC and inplant teams.
Primary telephone and radio cennication links between the TSC and the CR shown in Attactment 7.1.
State and County Communications facilities Gre-manned on.a 24-hour basis. These are the principle entities involved in the notification fanout pror.ess.
7.3 ASSESSMENT
FACILITIES AND EQUIPMENT Emergency measures described in Section 6 depend upon the availability of the monitoring instruments and laboratory facilities necessary for proper assessment of the emergency situation. This section describes the equipment used in the assessing situation.
7.3.1 Onsite Systems and Equipment a.
Geophysical data collection / analysis equipment is grouped into two categories:
meteorological and seismic.
FOMM(D)372 22 3M3
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DERP Section 7 Issue 1 0PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION Service
- Pusuc ssRWCa COMPANY OF COLORADO 1.
Meteorological Monitors Information is obtained from installed instrumentation on the primary 60 meter metporological tower with readout in the CR. The following information is available: wind direction, windspeed, standard deviation of wind direction (sigmatheta), precipitation, dewpoint,
~
tettperature, and temperature differential with height.
Backup meteorological data is readily accessible on a round-the-clock basis from the 10 meter National Oceanic and Atmospheric Administration (NOAA) meteorological tower located north of the plant in the same general area as the primary 60 meter meteorological tower.
2.
Seismic Instruments Information is obtained from passive and active instruments giving absolute peak acceleration in three orthogonal m
directions. The system determines h
whether operating basis or safe shutdown maximum accelerations are exceeded in any-of three directions.
B b.
Area and process radiation monitoring systems are divided into seven basic groups as<-
described below:
1.
Area Monitors There are 21 area monitors, 17 in the reactor building and 4 in the turbine building.
Each area monitor uses a Geiger-Mueller tube as a detector and has a self-contained check source. -The area monitors share two common annunciators,-
one which may De cleared before the problem is resolved (readout in Control Room), and another in conjunction with local annunciators which may not be cleared until the problem is resolved.
In addition, there is an area monitor located in the TSC with remote readout and local alarm.
O FOMM(Ol372 22 3M3
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DERP Section 7 Issue 1 89' 0 Service
Equipment Monitors These monitors determine radiation levels J
in specific effluent streams.
Redundant monjtorsareprovidedseparatepower sources.
3.
Liquid Monitors i
These devices are specifically designed to monitor liquid effluents. They utilize gamma scintillation detectors consisting of an Nal(T1) crystal optically coupled to a photomultiplier tube.
4.
Gas Monitors These monitors consist of a plastic beta scintillator which is coupled to a 1
photomultiplier tube to monitor effluents in the gaseous phase.
5.
Particulate and Iodine Monitors These monitors continuously draw a portion of the airborne effluent through a filter assembly. Any buildup of radioactivity on the filter is measured with a gamma scintillation detector. The filter is backed by an activated charcoal cartridge for adsorption of iodine and may be removed to te counted and isotopically analyzed on a multichannel
- analyzer, 6.
Emergency Stack Monitor (PING)
This device is a single unit containing particulate, iodine, and noble gas monitors to measure Reactor Building ventilation exhaust effluent during a i
loss of power to the normal operating stack monitors.
7.
Reactor Building Ventilation Exhaust Stack Monitors This system monitors exhaust air from the reactor building for particulates, noble gas, and Iodine-131 contaminants.
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u w section /
Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Service
- PUBUC SERVICE COMPANY OF COLORADO c.
System Monitors detect and/or control problems within plant syst6ms.
These.may be pressure detectors, heat detectors, flow elements, heat rise detectors, or similar devices designed to monitor plant parameters. Many of these c
detectors are capable of initiating control actions to prevent or mitigate damage or release of radioactive material, d.
Fire Protection Systems have been designated to meet the criteria of 10CFRSO Appendix R.
Specific information regarding Fire Detection / Suppression at FSV is contained in the FSV Fire Protection Program Plan, e.
Radiation Analysis is cecoinplished using radiochemical laboratory equipment, radiation monitoring stations, and fixed air sampling stations to provide the capability for detailed, isotopic analysis.
f.
portable Survey Instruments provide flexibility and backup capability for radiation measurements in areas not served by installed monitors or where installed monitors O
t may be inoperative.
Specific equipment and their locations for FSV onsite radiological assessment is summarized in Attachment 7.2.
.a 7.3.2 Offsite Systems and Equipment Support The environmental radiological monitoring program for the FSV environs is provided by Colorado State University (CSU).
It consists of a comprehensive sampling system to monitor radioactivity in the ecosystems and atmosphere near the station. The contractual agreement with CSU also includes provisions for environmental monitoring in the event of an emergency.
CSU can respond within four (4) hears, and has facilities for radiochemistry and camma spectrometry analyses.
Wer.cher observations and forecasting may also be cbtained through the National Weather Service (NWS) radio or from the Stapleton Airport National Weather Service Station. Offsite facilities are summarized in Attachment 7.3.
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l FORM (Dl372 22 3843
DERP Section 7 Issue 1 0 $9fVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO 7.4 PROTECTIVE FACILITIES AND EQUIPMENT CR shielding and ventilation are designed to allow personnel habitability at all times.
The TSC is locatdd to the east of the Reactor Building in close proximity to the CR and is provided shielding and HVAC similar to the CR.
Portable radiation monitoring instrumentation, protective breathing apparatus, protective clothing, and portable lighting are available near the CR.
i 7.5 FIRST AID AND MEDICAL FACILITIES Necessary treatment-sJpplies are Contained in a Irauma Kit located in the Fire Brigade bunker on level 7 of the turbine building.
In the event of an emergency, another first-aid area is provided in the HP access area.
First-aid treatment of injured individuals will be 3
administered by trained personnel. Advanced medical care, if required, will be obtained by transporting the individual (s) to St. Luke's Hospital and/or North Colorado Medical Center.
7.6 OAMAGE CONTROL EQUIPMENT AND SUPPLIES Fire hose stations, extinguishers, and hydrants are Oi strategically located throughout the station for use in the event of fire. Self-contained breathing apparatus (SCBA) equipment is located strategically throughout the
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station to be used as necessary for fire fighting, entry into airborne radioactivity areas, or entry into toxic gas areas. Selected equipment spare parts are stored in the warehouse for equipment repair.
7.7 DEDICATED EMERGENCY RESPONSE VEHICLES A four-wheel drive vehicle has been procured for use during an incident in which EPZ monitoring capabilities are required.
The vehicle is capable, at all time, of responding to the site within 60 minutes, regardless of weather or road conditions and is under the direct control of Emergency Planning personnel.
7.8 COMMITMENTS None O
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Uthf bt Ction /.1 Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 21 SerVICO' PusuC SERVICE COMPANY OF COLORADO Gi l
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Primary Link Commercial Telephone Lines or Dedicated Microwave Lines Secondary link
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PSC Radio System
@@@@@: ga@@@@@@@ Backup Link Commercial Telephone Lines NOTEj, The TSC and CR also have the plant Gai-Tronics system available for their use.
o PORM(Dl372 22+3843
DERP Section 7.2 t
Issue 1 0 Service
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Description and Functional
- System Location Applicability 1.
Geophysical Monitors Meteorological Wind Speed Indicators Measures wind speed @
-~
located on 60m tower 58m above ground north of the plant.
level and 10m above ground level.
Wind Speed Indicator Measures wind direction located on 60m tower
@ 58m and 10m above north of the plant-Same ground level Instrument as previous
- listing, Delta Temperature Sensors Measures temperature located on 60m tower differential between north'of the plant.
10m and 58m elevation.
O Rain Gauge on 60m Measure precipitation tower.
Ten Meter Tower Windspeed, Wind direction, Provide bxkup Temperature, Solar Radiation, meteorological para-etc. located North of meters (Operated by plant.
NOAA)-available via data logger, modem dial-up or via remote readouts at tower.
Strong Motion 1 Detector Below PCRV Record ground Accelographs 1 Detector on Top accelerations in of PCRV three mutually or 1 Detector at N.W. Corner orthogonal directions of Visitor Center with respect to time.
Ground motion acti-vates the SMA's and trips an annunciator in the CR.
FORM (D)772 22 3M3 i
UtKP bection /.2 Issue 1 OService*
Public FORT ST. VRAIN NUCLEAR GENERATING STATIONPage 10 of 21 PUBUC SERVICE COMPANY OF COLORADO O
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Description and Functional
- System location Applicability Seismoscopes 1 detector below PCRV Smoked glass supported 1 detector on top of PCRV on a pendulum. As relative motion occurs, a stylus scribes a record on the glass.
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O FORM (o)372 22 3043 I
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utne section /.2 Issue 1 0SerylCO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 21 PUBLIC SERVICE COMPANY OF COLORADO O
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
For monitor setpoints refer to the FSV Master Setpoint List.
Channel and' Radiation Transmitter Description and Control Number Location Action 2.
Radiation Monitors Liquid Monitors
~
RT6212 &
Radioactive liquid 10 ' uCi/mi (also, if RT6213 effluent monitors.
cooling tower blowdown Reactor b dg.-
drops to < 1100 gpm),
Elev. 4771' closes HV-6212 &
HV-62249, trips transfer pump P-6202 & 6202S, and trips reactor building sump pumps
~7 to prevent 1 X 10 pCi/ml MPC value at site perimeter from being exceeded. (ELCO 8.1.2)
RT46211 Gas waste No control action RT46212 compressor cooling water monitor.
Reactor b1dg. -
Elev 4740' O
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FORM tD)372 22 3643
...2 0$9fylC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION 12 of 21 PUBLIC SERVICE COMPANY OF COLORADO m
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
For monitor setpoints refer to the FSV Master Setpoint List.
Channel and' Radiation Transmitter Description and Control Number Location Action Gas Monitors (Plastic Beta Scintillators)
RT7324-1 Reactor building Close block valve RT7324-2 ventilation exhaust FV-6351, divert ex-monitors. The haust from filters to monit, ors are gas waste vacuum tank, located on the shutdown turbine building Turbine Deck and service building Elev. 4829' ventilation and begin recirculation of control room ventilators. Also, closes reactor supp.
inlet dampers.
(ELCO 8.8.1)
RT6314-2 Gas Waste Exhaust High alarm diverts the Monitor. Operated flow to the gas waste in series with the vacuum tank, iodine and particu-(ELCO 8.8.1) late monitors.
Located on Elev. 4781' on the east wall outside the gas waste cubicles.
Particulate and Iodine Monitors (Nal gamma scintillation detectors)
RT6314-1 Monitor the gas Has the same control waste effluent action as RT6314-2.
stream up stream (ELC0 8.8.1) of the gas monitor RT6314-2.
Located inside the gas waste blower cubicle on Elev. 47818 o
l FORM (D1372 22 3643
DERP Section 7.2 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION 13 of 21 Serv lCO' PUBLIC SERVICE COMPANY OF COLORADO OG ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
For monitor setpoints refer to the FSV Master Setpoint List.
Channel and' Radiation Transmitter Description and Control Number Location Action RT73437-1 Reactor Plant ELCO 8.8.1 -Close valve Ventilation Exhaust FV6351, divert flow to lodine-131 gas waste vacuum tank.
Monitor Loc:
Shutdown turbine building Sampler / Detector:
ventilation and place E1.,4916 the control room vent-Turbine Side ilation on recirculation.
Readout E1. 4829 Control Room This iodine monitor consists of two single channel analyzers, one window being set for the photopeak energy of interest (i.e. L 21), and one being set for an adjacent energy region.
The adjacent region window Os provides a background subtraction capability, thus allowing the monitor to discriminate 1881 from noble gas radioisotopes. A 2 inch by 2 inch NaI(T1) crystal is utilized as the detector for this monitor.
RT73437-2 Reactor Plant Same automatic action Ventilation as RT73437-1.
Exhaust Beta Particulate Monitor Loc:
Samples / Detector:
E1. 4916 Turbine Side Readout
~
El. 4829 Control Room This particulate monitor consists of an alpha detector and a plastic beta scintillation detector viewing a fixed filter for particulate radioactivity. The alpha channel provides a live measurement of radon concentration which is subtracted from the beta measurement.
FORM (Ol372 22 3843
DERP Section 7.2 OSerVlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pa 1 of 21 PusuC ssRVICE COMPANY OF COLORADO O
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES a
NOTE:
For monitor setpoints refer to the FSV Master Setpoint* List.
Channel and
~
Radiation Transmitter Description and Number location Emergency Stack Monitors (" PING" - Particulates, Iodine, Neble Gases)
Provided to Monitor Reactor Building Ventilation exhaust effluent during loss of power to the normal operating stack monitor.
RT 4801 Reactor Plant Ventilation Exhaust Beta Particulate Monitor Loc:
E1, 4885, turbine side RT 4802 Reactor Plant Ventilation Exhaust Iodine Monitor Loc:
E1, 4885, turbine side RT 4803 Reactor Plant Ventilation Exhaust Noble Gas Monitor t
Loc: El. 4881, turbine side Reactor Building Ventilation Exhaust Stack Monitor RT 7325-1 Reactor Plant Ventilation
.o Exhaust Iodine and Particulate Monitor Loc:
Samples / Detector:
El. 4921 Turbine Side Readout El. 4829 Control Room RT 7325-2 Reactor Plant Ventilation Exhaust G-M Detector Loc:
Sampler / Detector:
El. 4921 Turbine Side Readout El. 4829 Control Room I
FOM (Dl372 22 3M3
i DERP Section 7.2
'fof21 OService*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pa I
Pusuc sanvics company or coton4oo O
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
For monitor setpoints refer to the FSV Master Setpoint' List.
Channel and' Radiation Transmitter Description and Number Location TSC Ventilation Monitor RIT 7937 TSC Ventilation Inlet and TSC Ambient Atmosphere Particulate, Iodine, Noble Gas Loc:
Sampler / Detector:
El. 4791 TSC Building Readout El. 4791 TSC Building O
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DERP Section /.2 Issue 1 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 16 of 21 Pusuc sanvece comeAmy or cotonApo O
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
For monitor setpoints refer to the FSV Master Setpoint List.,
q Channel and Radiation Transmitter Number Location Elevation Reactor Building Area Radiation Monitors RT93250-1 Refueling Machine 4881 Control Room RT93252-1 Northeast Refueling Floor 4881 RT93250-2 East Walkway Outside HSF 4854 RT93252-2 South Stairwell 4864 RT93250-3 Hot Service Facility 4856 Platform O
a'eazs1-2 set s vic 8,
sect 4 n 48e8 RT93250-4 Outside HSF Door 4839 RT93252-4 Instrument Room-Analytical 4829 Instrument Board R193251-5 Gas Waste Filters 4781 RT93251-6 Truck Bay 4791 RT93252-6 Near South Stairwell 4791 RT93251-7 Core Support Filter 4781 RT93252-7 East Walkway-4781 RT93250-8 North East Walkway 4771 RT93251-8 Decontamination Laundry 4771 RT93251-9 Buffer Helium Dryer Loop I 4740 RT93250-14 Refueling Floor /
4881 East Wall i
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I FORM (D)712 22 3043
DERP Section 7.2 OSerVlCG*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pag 1 of 21 PUBUC SERVICE COMPANY OF COLORADO O
ONS:TE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
For monitor setpoint9 refer to the FSV Master Setpoint List.
Channel and Radiation Transmitter Control Number Location Elevation Action Turbine Duilding Area Radiation Monitors RT93250-13 Near Concensate Demin-4791 eralizers RT93251-1 Reacto'r Plant Exhaust 4864 Filter Room RT9 251-4 General Office Area 4816 RT93250-5 Control Room 4829 Technical Support Center Area Radiation Monitor RIA-7951 Technical Support Center
'4811 3.
System Monitors Process Monitors affecting the Assessment of Radiological Accidents are shown in Attachments Cl-C14 of DERP Section 4.
4.
Fire Detection Smoke Detectors Detect products of combustion Rate of Heat Rise Detects quick rise of Detector temperature Fixed Heat Detector Detects a set temperature FOftM(o)372 22 3M3 -
Uthr beCLlon /.2 Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION age 18 of 21 P
Service
- rusuc sunvice comeAmy or cotonApo O
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument.
Description and Functional System Location Applicability 5.
Facilities Whole Body Counter Detect, identify, and quantify internal deposition of radio-activity Radiochemistry Equipped for radiological Laboratory analysis Radiation TLD Measure radiation dose Monitoring Stations rates (operated by Outside Security Fence, contract with Colorado inside owner controlled StateUniversity) area.
4 Fixed Air Sampling Sample particulates and Stations-Just Outside radiciodines(operated Security Fence by contract with Colorado State University)
Emergency Lab Ge-Li Detector Multi-Channel, Analyzer 6.
Portable Survey Instruments Airborne Particulate Detect-airborne Monitors contamination Beta-Gamma Air Detect airborne Monitor radioactivity Alpha Survey Meters Detect surface contamination Neutron Detectors Determine neutron flux rate Ion Chambers-Determine gamma dose rate Beta-Gamma Geiger-Surface and area l
Mueller Survey Meters:
radiation and contamination levels-O l
- FORM (D)372 22 3M3.
OtiRP Section /.2 Issue 1 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 19 of 21 Pusuc senvece comeAmy or cotonAno O
ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrumeqt Description and Functional System Location Applicability SAM-II Portable Multi-Verification of airborne Channel Analyzers I-131 levels in the field Scintillation Determine gamma dose Counters rate Pancake Geiger-Determine surface Mueller Monitors contamination levels Proportional Counter Determine alpha-beta-gamma contamination Hi and to Vol Air Samplers Detect airborne iodine and particulate contamination 4
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FORMlol372 22 3M3
WLM Juw b a wai i.3 Issue 1 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 20 of 21 Pusuc senvics comeAmy or cotonApo O
V 0FFSITE ASSESSMENT EQUIPMENT AND FACILITIES l Detector ndividual Functional Applicability 1.
Geophysical Monitoring Meteorological i
National '"ather Service Denver Weather forecasting Stapleton Airport 2.
Radiological Monitors Environmental Monitoring Measure radiation dose Radiation monitoring rate (operated by stations (12 TLD locations contract with between one and ten-miles Colorado State from reactor: 12 locations University) between ten and fourteen miles from reactor)
Fixed Air Sampling Stations Measure particulates and radioiodines (operated by contract with Colorado St.atp University)
Colorado State University Ge-Li Detector Gamma spectrometry for isotopic identification and analysis NaI(T1) Detector Gamma spectrometry for isotopic identification and analysis Radiochemistry Laboratory Chemical and radiological analysis.-
FOftM101372 22 3843 j
DERP Section 7.3 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION 2 of 21 Service
- pusuC BERVICE COMPANY OF COLORADO O
OFFSITE ASSESSMENT EQUIPMENT AND FACILITIES Individual Functional
^
' Detector Applicability Colorado Departmenc of Health Whole Body Counter Identification and quantification of inhaled or ingested radioisotopes.
Serves as backup to FSV System.
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FORM (D)372 22 3843
Issui 1 age 1 'f 8 o
0 Service
DEFUELING EMERGENCY RESPONSE PLAN: SECTION 8 MAINTAINING EMERGENCY PREPARE 0 NESS PONSIBLE THORIZED lfL pmc9 21 FEB 131991
[F E T VE TE DCCF NUMBER (S)
Q D-l7 31 O
I NCNCONTYtOi tan COPY WEHFY ISSUE STATUS l
mm sne mouen kQ-oowmol CENTER PfMOR TO USE FORMIDl372 22 3642 l
Utnr Juction O Issue 1 0 Serv lCG*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 8.0 MAINTAINING EMERGENCY PREPAREDNESS 8.1 ORGANIZATIONAL PREPAREDNESS To ensure that the FSV Emergency Response Organization is prepared, a program comprised of:
(1) personnel training; (2) participatio-in scheduled drills and exercises; and, (3) regular emergency plan review and evaluation by company specialists and PSC management has been established.
8.1.1 Training A training and annual retraining program is in effect to ensure that station personnel who actively participate in emergency situations are familiar with the contents and responses set forth in this DERP.
Training Procedure - Defueling Emergency Response Plan (TP-DERP) identifies specific training requirements for each major emergency position / function.
These training requirements are reflected by appropriate FSV training lesson plan numbers. The general requirements of the program O
are summarized in matrix form in TP-DERP. A brief V
discussion of the type of training being provided
- follows, a.
Basic Training and Indoctrination Each employee receives general instructions on the DERP and supporting emergency procedures.
Training sessions consisting of a review of the purpose, scope, emergency classifications, and required emergency response actions are conducted annually.
.. b.
Specialized Training for Key Emergency Organization personnel Specialized training, designed to cope with such uncertainties as an. emergency occurrence during backshift hours, is provided to key personnel involved in emergency response actions. This training includes instruction and review in the technical-and practical aspects of response activities, as well as
'" cross-subject" training to ensure the familiarity and flexibility necessary for n
personnel who could be assigned to a diversity g
of emergency response. functions._
FORMIDl3[2522 3843
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DERP Section 8 Issue 1 9'
0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Service
- PUBUC SERVICE COMPANY OF COLORADO O
For example, training for the Emergency Coordinator emphasizes:
review of emergency procedures, resources, and assignments; monitoring team functions; effects of meteorology on radiation exposure, and dose estimation techniques. The specific training matrix is fully presented in TP-DERP.
c.
Training for Participatina Agencies Station personnel are available to describe the special conditions and constraints involved in dealing with FSV emergency situations. The station conducts special training for members of the Platteville Volunteer Fire Department including familiarization with the station layout, the location and nature of fire hazards, the location, type, and availability of extinguishing equipment, and the special radiological considerations associated with fire fighting at the FSV.
Training is also made available for the Weld County Ambulance Service, Weld County Sheriff's Department personnel, St. Luke's Hospital personnel, and l O, -
others who may be called upon to render assistance.
Such training for non-PSC-personnel includes site access procedures, identification of station emergency personnel who will control such support forces, and a general DERP overview, as applicable., A-similar DERP overview is made available to local media representatives as well, d.
Training for Emergency Preparedness Staff
- 8.5.1*#*
Personnel assigned to the emergency planning effort attend various industry short courses and seminars to maintain current information concerning Emergency Planning _(EP) activities, whenever
- feasible, p
V FOPM tu 372 22 3643
DERP Section 8 Issue 1
- 9' 0 Service' Public FORT ST. VRAIN NUCLEAR GENERATING STATION rusuc sanvece courAny or cotonApo 8.1.2 Orills and Exercises Regular participation by station personnel in drills and exercises is scheduled to maintain emergency preparedness and test specific aspects of emergency plans, procedures, and equipment.
Evaluation of these drills and exercises is conducted, and changes found necessary to improve the DERP are adopted.
- 8.5.2*#*
Drills and exercises will be conducted in varying weather conditions whenever possible.
Documentation of drills and exercises will include
-weather conditions present to provide auditable records.
a.
Drills u
Instructional emergenc/ drills are conducted on a scheduled basis with emphasis placed upon orderly implementation of activities prescribed within the DERP and its implementing procedures. General schedule requirements are outlined in TP-DERP.
O V
Drill performince is critiqued by personnel acting as dri11-instructors who offer on-the-spot corrections to erroneous performance.
Each observer is assigned a specific area for evaluation and receives written instructions for detailing resp 6nse checks. The Vice President, Nuclear Operations and station supervisory personnel are provided written evaluations of drill performance based on the results of these critiques, including participant's comments, if available.
- 8.5.5*#* These evaluation reports are normally submitted within 30 days of exercise / drill completion, and no later than 90 days following completion.
Followeo action is then delineated to upgrade areas where deficiencies are noted.
FORM (0)712 22 3843
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DERP Section 8 Issue 1
- 9' 0 SGTVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO Drills for the station staff are conducted periodically throughout the year to:
(1) test response timing and familiarity with implementing procedures and methods; (2) test emergency equipment; and, (3) ensure that emergency organization personnel are familiar with their duties. Certain drills, i.e.,
fire, communications and notification, and medical emergency, are coordinated with offsite participating agencies.
Fire drills are conducted quarterly in accordance with plant technical specifications. These dril,ls include instruction in the handling of fire and rescue apparatus. Additional instruction is provided in fire prevention, fire safety, pre-fire planning, fire fighting,.
fighting electrical fires, and the use of emergency breathing apparatus.
Special fire drills with the Platteville Volunteer Fire Department are conducted annually to assure effsetive, coordinated action. -All fire drilla are coordinated
-and conducted by Nuclear Training and Support Department personnel.
Communication links and notif1 cation procedures with offsite agencies are tested on a monthly basis.
- 8.5.3*#*
Verification of personnel, emergency organization assignments, telephone numbers, and outside assistance contacts,.are performed quarterly.
Phone numbers are updated,'as needed, in the FSV Emergency Phone Book. Verification
-of emergency response facility communication links is accomplished
-quarterly.
Medical Emergenc> Drills with St. Luke's Hospital for treatment of contaminated persons are conducted on an annual basis.
In addition to these annual drills, the hospital conducts regular in-house emergency drills on the treatment and l
care of injured and contaminated persons.
I Drills involving Weld County Ambulance l
-Service are conducted on a semi-annual r'
basis.
l l
l FORMtD)772 22 3843
DERP Section 8 Issue 1 "9'
0 $9fVIC9' Pt;blic FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC ssRVICE COMPANY OF COLORADO O
Radiological Monitoring Drills are conducted annually fon personnel assigned to Radiological Monitoring Teams. These drills include operation of instruments, tests of field communications equipment, and interpretation of radiation readings.
Health Physics Drills are conducted semi-annually, generally in connection with joint exercises or radiation monitoring drills. The HP drills involve analysis of simulated or actual samples (including the drawing and analysis of primary coolant) with elevated radiation levels, both liquid and airborne, as well as direct radiation measurements in the envi ronmen',.
b.
Exercises An annual exercise of the DERP will be conducted to test the adequacy of implementing procedures and methods, test emergency equipment and communications networks, and ensure that emergency response personnel are familiar with their duties.
g 8.1.3 Emergency Planning Coordinator.
The Nuclear Training and Support Manager has overall responsibility and authority for emergency f
response planning. An Emergency Planning Coordinator (EPC) maintains continued coordination with state and local emergency planners on the status of emergency plans. The EPC participates in meetings aimed at maintaining plans current and accurate.
The EPC coordinates plan revisions based on evaluations resulting from exercises / drills.
8.2 REVIEW AND -UPDATING OF THE DERP The FSV DERP is reviewed and updated annually. The Nuclear Documents Unit maintains documentation pertaining to the annual review and updating. Special attention is devoted to maintaining effective communication channels, and ensuring up-to-date contact and notification lists.
OL FORM (D)372 22 3843 i
r -
,,. - ~
I DERP Section b Issue 1
'9' 0 Service
- Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO PSC emergency planning personnel review the DERP annually (or more frequently) and make recommendations for updating, as appropriate.
In addition, independent audits (see Section 8.4) of the various aspects of the emergency preparedness program are conducted annually. The results are considereo by PSC management in modifying aspects of the DERP.
Audit documentation is maintained for at least five years.
~~
Revised or updated emergency plans and procedures are handled in accordance with existing station document control procedures. These include making physical changes in text and distributing revised or new material to document holders.
8.3 MAINTENANCE AND INVENTORY Or EMERGENCY EQUIPMENT AND IUPPLIES Quarterly inspections of the operational readiness of items of emergency equipment and supplies are conducted on a departmental basis. Deficiencies noted during inspections are programmed for correction within specified time periods. The use of inspection procedures with checkoffs and followup actions ensures that equipment is ready for use.
Sufficient reserves of O
instruments / equipment are maintained to replace those undergoing calibration or repair.
Calibration of equipment is conducted at intervals recommended by suppliers, or PSC guidelines.
In addition, planned utilization of communications, first aid, fire fighting, and radiation detection-equipment during scheduled-drills further ensures the availability and operability of emergency equipment.
8.4 INDEPENDENT REVIEW OF THE EMERGENCY PREPAREDNESS PROGRAM
- 8.5.4*#*
In accordance with the Code of Federal Regulations, Part 10, Section 50.54 (t), the Quality Assurance Division, in conjunction with the site's Nuclear Facility Safety Committee, will conduct audits on an annual basis (more frequently, if needed) of the Defueling Emergency Response Plans for the site.
FORM (D)372 22 3843
utne section e Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Service
- PUBUC SERVICE COMPANY OF COLORADO 8.5 COMMITMENTS The step (s) and section(s) listed below'may not be deleted without issuance of comparable controls. The procedure itself, if initiated as a result of commitment corrective action, may not be deleted without issuance of comparable controls.
8.5.1 Section 8.1.1.d is in response to CAR 86-068.
8.5.2 Section 8.1.2, " drills and exercises", is in response to CAR 86-068.
j 8.5.3 Section 8.1.2, " communication links and notification", is in response to CAR 86-066.
8.5.4 Section 8.4 is in response to CAR 86-067.
8.5.5 Section 8.1.2, exercise / drill report time requirements are in response to QDR 87-077.
O i
f*
l FORM (Dl372 22 3043 r
~.
DERP Section 9
'I O SerVICO' Public FORT ST. VRAIN fjuCLEAR GENERATING STATION y gf 7 PUBUC SERVICE COMPANY OF COLORADO O
TITLE:
DEFUELING EMERGENCY RESPONSE PLAN: SECTION 9, RECOVERY "sS/
"S'S" rwk UTHORIZED RSSw PORD9i i FEB 131991 fire ECME DCCF NUMBER (S) hh \\2M
()
.g e
NON CONTROLLED COPt i
w w y ssue stAnis WITH SITE DOCUML17 CONTROL CENTER PRIOR 4
(
'ID USE I
FORM (D)372 22 3642
DERP Section 9 Issue 1 0Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 7 Service
- PUBUC SERVICE COMPANY OF COLORADO O
9.0 RECOVERY Recovery operations for FSV consist of those operhtions associated with the long term post-emergency efforts that follow a major incident.
These operations will be performed by station and other PSC personnel, contract experts and specialists, and qualified engineers-constructors under the direction of the pSC Recovery Organization, After termination of the emergency, (i.e., the plant is in a safe and stable condition) recovery actions are designed to:
(1) identify the extent of plant damage; (2) prepare specific plans and programs for station repair; (3) implement specific corrective action plans and programs; and, (4) return the plant-to a defueling/ decommissioning status.
The folloving general guidelines assist in determining whether the Emergency Response Organization should be terminated and the Recovery Organization established.
Radiation levels are stable or decreasing with time.
Releases of radioactive materials to the environment have ceased or are controlled within permissible license limits.
- Fire, flooding, or similar emergency conditions no longer constitute a hazard to the plant or station personnel.
Overall plant is in a stable condition.
Measures have been successfully instituted to correct or compensate for malfunctioning equipment.
NRC and State / local officials have been notified of intent to, terminate the Emergency Response Organization.
TSC Director has authorized transition from the Emergency Response Organization con figuration to the Recovery Organization and notifies personnel accordingly.
The Recovery Organization descr' bed in the following section will be activated following the termination of the emergency.
Manpower and equipment resources supporting the individual functional segments of the recovery organization will vary according to the severity of damage and specific situational needs.
O FORM (D)372 22 3M3
DERP Section 9 1ssue 1 0ServlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 7 PUBUC SERVICE COMPANY OF COLORADO O
9.1 RECOVERY ORGANIZATION Activation of an effective recovery operation will involve the transition of selected key technical personnel from emergency to recovery operations.
In a similar manner, management personnel involved in the emergency will be assigned to direct and coordinate recovery operations.
Function managers and technical personnel who served in Control Room and TSC positions during the emergency will typically form the nucleus of the Recovery Organization.
The Recovery Organization will be established to respond to a particular situation. A3 such a precise organization can not be fully defined.
A general Recovery Organization is depicted in Attachment 9.2.
The responsibilities and functions of these recovery managers are summarized as follows:
The Recovery Director - (Vice President, Nuclear Operations) has overall corporate responsibility for restoring the station to a
normal defueling/ decommissioning configuration and-is vested with the authority to commit corporate resources to accomplish the recovery.
The plant Operations Manager - (Manager, Nuclear
+
Production Division / Station Manager) responsible-for ensuring that _ repairs and modifications will optimize plant safety and providing..,ana. lyses,
- plans, and procedures in support of defueling/ decommissioning.
The Radeon/ Waste Manager (Superintendent of Radiation Protection and Chemistry) develops plans and procedures to process and control
- liquid, gaseous, and solid wastes to minimize adverse effects on the health.and safety of the public and station recovery personnel.
In addition, the Radcon/ Waste Manager coordinates the activities of staff health physicists and personnel engaged in waste treatment operations, The Quality Assurance Manager - (Manager, Quality
+
Assurance Division) assures-that the overall conduct of recovery operations is performed in tccordance with corporate policy and rules and regulations governing activities which may affect public health and safety.
l FoRMID)372 22 3643
DERP Section 9 Issue 1 l
0 SerVlCO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 7 PUBLIC SERVICE COMPANY OF COLORADO O
The Recovery News Director (Director, Media
+
Services) coordinates the flow df media information concerning recovery operations and acts as corporate spokesman concerning recovery activities.
An overview of topics which can be addressed during establishment of recovery operations is presented in.1.
9.2 RECOVERY EXPOSURE CONTROL The Manager, Nuclear Production Division / Station Manager will designate a technical group responsible for evaluating the advisability of initiating recovery and reentry.
Information on existing conditions, interviews with employees evacuated during the emergency, regulatory exposure guidelines, and counsel from recognized experts will be utilized in formulating decisions on reentry and recovery.
During recovery operations, actions will be preplanned to limit exposures.
Access to affected areas will be controlled and exposure to personnel documented.
Contaminated areas will be posted with radiation levels-and stay times based on results of surveys.
9.3 COMMITMENTS None e
k FORM (D):r72 22 3643
DERP Section 9.I 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue I SerVlCe*
PUBUC SERVICE COMPANY OF COLORADO Page 5 of 7 RECOVERY PLANNING TOPICS The following is an outline of suggested topics to be discussed'while entering into recovery operations.
This outline is not all inclusive, rather it is provided for general guidance.
I.
SUMMARY
OF ACCIDENT A.
Causes B.
Accident Chronology II.
STATUS OF PLANT AND PERSONNEL A.
Injuries / Contamination Cases B.
Radiation Exposure Summary C.
On-Site Contamination D.
Status of Plant. Systems / Facilities E.
Extent of Core Damage III. SAFETY CONCERNS A.
Re-Entry Requirements B.
Maintaining Stable Plant Conditions IV.
TENTATIVE REPAIR PLAN AND SCHEDULE
.A.
Major Steps Necessary to Restore to a
Defueling/ Decommissioning Phase t
B.
Evaluation of PSC Resources
~
C.
Licensing Considerations D.
Quality Assurance Considerations E.
Administrative Concerns F.
Logi stic s/Schedulir.g FORM (01372 22 36*3
DERP Section 9-.1 0Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 SerVlCG*
PUBUC SERVICE COMPANY OF COLORADO Page 6 of 7 O
V.
OFFSITE COORDINATION A.
Long Term Environmental Monitoring B.
Rad Waste Disposal and Considerations C.
Media Relations Coverage / Control VI.
CORPORATE RECOVERY-ACTIVITIES A.
Replacement Power Requirements B.
Insurance Coverage / Contacts C.
Reportability VII. SHORT TERM ASSIGNMENTS A.
Project Definition B.
Project Assignments C.
Location and Time of Next Organization Meeting O
1 FORM t0)372 22 3643
DERP Section 9.2 0Public FORT ST. VRAIN NUCLEA' GENERATING STATION Issue 1 Service
- PUBUC SERVICE COMP ANY OF COLORADO Page 7 of_7 O
RECOVERY ORGANIZATION I
RECOVERY l
l DIRECTOR l
1 I
i VICE PRESIDENT, 1 l
NUCLEAR I
l OPERATIONS l
1 1
l l
I l
NEWS CENTER l
l l
ADVISORY I-1 MANAGER I
l l
SUPPORT l
1 I
i i
l i DIRECTOR OF l
l l
l I MEDIA. RELATIONS) l l
STAFF l
i I
I I
I I
l I
l NT _ l IRXDCON/ WASTE ll QUALITY.l 10PERATIONS [
t MANAGER I l~ ASSURANCE l l MANAGER l l SUPT, 0F
-l l. MANAGER -1 IMGR,NUCLEARI l RA01ATION-1 IMGR, QUALITY l l PRODUCTION I l PROTECTION l l ASSURANCE.l,
1 OIVISION/l 1
AND 1
l DIVISION l l STATION MGRI l CHEMISTRY l 1
l O
+
FORM (Of 372 22 3643
DERP Section 10 0 Service
DEFUELING EMERGENCY RESPONSE PLAN, SECTION 10 LETTERS OF AGREEMENT AND SUPPORTING PLANS agieo~sia's
.g#
^rsoaizeo argg lSSEw ocac 9 21 FEB 131991 5' ATE"?b Sl}-9l DCCF NUMBER (S)
Ch. l 2 M 4
PT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR 1
TO USE FORM (D)372 22 3642
DERP Section 10 FORT ST VRAIN NUCLEAR GENERATING STATION Issue 1 0 Public Page 2 of 15 service
- PUBUC SERVICE COMPANY OF COLORADO O
10.1 LETTERS OF AGREEMENT This section contains copies of Letters of Agreement with the various local agencies and contract :upport organizations.
The current, up-to-date letters are filed in the FSV Records Retention Center; copies of the current documents, are also located in the FSV Emergency Planning files.
10.2 Hydrology and seismic data can be obtained through the U.S.
Department of Interior, Denver, CO.
The phone number is available in the FSV Emergency Phone Book, 10.3 Colorado State University will conduct environmental monitoring per WS-60-0001, Radiological Environmental Monitoring Program (REMP).
~
O l
FORM (0)372 %3643 A
OERP Section 10 OPublic ssue FORT ST. VRAIN NUCLEAR GENERATING STATION f
Service
- Pusuc senvice comeAmy or cotonApo O
TABLE 10-1 LIST OF INTERFACING PLANS AGENCY DOCUMENT TITLE State of Colorado, Division of Fort St. Vrain Radiological Disaster Emergency Emergency Response Plan Services (D00ES)
(State RERP)
Weld County Weld County Emergency Operations Plan and Weld County RERP Colorado Department of Health (in State RERP)
Platteville Fire Protection District Fort St. Vrain Emergency Response Plan Weld County Sheriff's Department Weld County Sheriff's Office Colorado State Patrol Emergency Response Plan for a Radiological Emergency at Fort St. Vrain Nuclear Electric Generating Station Weld County Office of Emergency Weld County Emergency Management Operatiorp Plan and Weld County RERP Weld County Health Department HealthDepartmini's' Response to Emergency at Fort St. Vrain.
USNRC Federal Radiological Emergency Response Plant and Region IV Incident Response Supplement to NUREG-0845
~
FEMA Federal-Radiological Emergency Response Plan FORM (DIT12 22 3643
DERP Section 10 Issue 1 0 SerVlCO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 15 PUBUC SERVICE COMPANY OF COLORADO U(
PPS-88-0132
(
"Unnersary Department of Radionor, and Radiaison Biology Foet Collins. Co6 credo 80523 oon4m.5380 January 5,1988 Mr. Owen J. Clayton Emergency Planning Coordinator Fort St. Vrain 16805 WCR 19S Platteville, CO 80651
Dear Mr. Clayton:
In response to your letter to me dated December 28. 1987, I am pleased to confirm that the staff and facilities of this department would be available to Public Service Company in the event of a radiological emergency at the Fort St. Vrain Nuclear Generating Station.
Colorado State University has conducted the radiation environmental V
surveillance program at the FSV reactor since 1969. This period includes the entire Dreoperational phase as well as the current operational phase. This program has been on a contractual basis with the University.
All personnel and facilities that are currently under contractyal obligation to the Dadiological Environmental Monitoring Program have been trained in proceduras to immediately respond to a non-normal radioactivity release. The details of this contractual response can be found in WS-60-001 Section 4.0.
A principle teaching program of the department is radiation protection and major researen programs are in the areas of environmental radioactivity and personal radiation dosimetry. The personnel in the radiation protection areas include three certified health physicists as well as two radioecologists. These would be available for assistance to reactor, state or governmental groups. In addition, the department has a full range of monitoring equipment which is continu--
ously available. A whole-body counter is in operation at the department main building which is less than 30 miles from FSV. The department also has expertise in agricultural considerations of food chain transport of any environmental radioactivity and the biological effects of ionizing radiation.
The personnel and resources of the department would be available to assist and or direct any radiation protection effort upon request by Public Service Company or the Colorado Department of Health.
Si erely.
p J me E. Johhsg1. Ph.D.
Q-P essor JEJ:nb FORMton372 22 3643
DERP Section 10 Issue 1 0 PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 15 SerVICO*
PUBLIC SERVICE COMPANY OF COLORADO
=r E
PPS-88-0128 a
W hud.
Controls for Environmental Pollution, Inc.
1925 Aosina e A C Bex 5351 e Santa Fe. New Mexico 67502 + etecnome SCS 982 9841 January 7,1988 Public Service Co. of Colorado 16805 WCR 191/2 Platteville, CO 80651 Attn: Owen J. Clayton p
Dear Mr. Clayton:
U i would like to introduce to you and your staff our full analytical capabilities. We have been serving the nuclear industry for over two decades.
Our laboratory provices complete environmental, bioassay and waste characterization programs for your type of industry.
In order to give you further background on our company, we are enclosing a brochure which outlines our power plant analytical capabilities.
I have enclosed our Letter of Agreement for 1988 for technical assistance for your company.
We are pleased to have this opportunity of introducing you to Controls for Environmental Pollution. Inc., and if we can be of any assistance in the future, please feel free to call upon us for information or assistance at 1-800,545-2188.
Very truly yours, CONTROLS FOR ENVIRONMENTAL POLLUTION, INC.
=.
James J. Mueller President JJM/jjs Enclosures FORM (o)372 22 3643
DERP Section 10 Issue 1 0SerVlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 15 PUBLIC SERVICE COMPANY OF COLORADO 9
Public Service Company of Colorado January 21,1987
Dear Mr. Clayton:
This letter will confirm that Controls for Environmental Pollution, Inc., has agreed to assist Public Service Company of Colorado in the event of an emergency situation with Fort St. Vrain Nuclear Generating Station.
This assistance will be in the form of direct participation by CEP employees both off-site and on-site on an "as needed basis".
Availability will be immediate for any assistance which can be performed at CEP's home office and within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> for assistance requiring travel to Fort St. Vrain or other Public Service Company of Colorado f acilities.
We would expect to provide assistance in the following general areas:
1.
Collecting and analyzing radiological environmental samples.
2.
Receiving and analyzing samples on an emergency basis.
3.
Assistance with health physics monitoring. '
4 Providing monitoring assistance and radiological monitoring.
5.
Analyzing urine and feces samples from Fort St. Vrain personnel.
()
6.
Post emergency write-up reports.
Following are the names and telephones numbers, both home and office, for persons who may be contacted to respond to a request for emergency assistance:
i James J. Mueller Bob Bates Offices (505) 982-9841 or Office (505)982-9841 or 1-800 545 2188 1-800-345 2188 Home (505) 471-0311 Home (505) 982-2316 Ellen LaRiviere Lisa Wilburn Offices (505) 982-9841 or Offices (505) 982-9841 or 1-800-545-2188 1-800 545-2188 Home:
(505) 983-5131 Home (505) 473-9220 You are hereby authorized to use this letter in support of any of your applications for licenses or approvals from federal, state or local agencies who may be involved with, or affected by, your emergency planning activities.
Very truly yours, CONTROLS FOR ENVIRONMENTAL POLLUTION, INC
/V f Ja es 3 Mueller
)
President 33Mid!
s FORM 101372 22 3643 1
1
DERP Section 10 Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 15
$9fVIC9' PUBLIC SERVICE COMPANY OF COLORADO R. S. Landauer, Jr. & Co.
PPS-88 0131 Om6aen of Tecntoos, incorporened Tech Ops 2 Science moea 06eneroco. Ilknose 00425-1584 To6eonene Q12) 7561t20 January 6, 1988 Mr. Owen J. Clayton Emergency Planning Coordinator Public Service Co. of Colorado 16805 WCR 19 1/2 Platteville, Colorado 80651
Dear Mr. Clayton:
Tech / Ops Landauer, Inc. has the capability of providing 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 7 days a week emergency processing.
There ars various methods available to send the film to us.
Fed e r a '. Express and Emery Airborne quarantee 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> delivery.
In addition most of the maior airlines provide a special delivery from airport to airport.
Upon receipt of the film (s) at our facility it is a matteg of a couple of hours to process, read and evaluate the dose.
We also hava emergency processing available at our El Secundo sales office.
The girl in the office has been thoroughly trained to process and compute exposures for film and TLD's.
We, at Tech / Ops.Landauer, Inc. are eager to help you in the event of a shut down or any other emergency condition.
If you have any further questions concerning these procedures, please do not hesitate to contact me.
Sincerely, Tech Ops Landauer, Inc.
l eannine MacDonald Mechnical Assistant Quality Assurance (v]
JMD/yls FORM (0)372 22 3643
DERP Section 10 Issue 1 0PubilC FORT ST. VRAIN NUCLEAR GENERATING-STATION Page 8 of 15 SerVlCe*
PusuC sERWCE COMPANY OF COLORADO PPS-88-0129 STONE G WEBSTER ENGINEERING CORPORATION 5555 GRssNWooo Pt.AEA BoULsVARo ENoLEWooo. CoLoRApo 80111 2113 aoonsee aLL co==seconos=cs to e o. oos emes. os= van. coLonano esan same
,w..-,...-
..m...~.
=,,,,,
. m......
O':"r *l "'....
Mr. R. O. Williams January 7, 1988 Vice President. Nuclear Operations Public Service Company of Colorado J. O. No. 13569.XX
~
2420 West 26th Avenue 1,tr. No.
S-T-23 Suite 100D k
Denver, Colorado 80211 AGREIMINT TO PROVIDE DtIRGENCY SUPPORT AND RECOVERY ASSISTANCE FORT ST. VRAIN NUCLEAR GDIIRATING STATION In the event of an emergency at Public Service Company of Colorado's (PSCC)
Tort St. Vrain Nuclear Generating Statha, Stone and Webster Engineering Corporation (SWEC) will provide engineering and/or operations support personnel to assist in accident mitigation, emergency plan implementation, and/or recovery activities, within the categories described in-Attachment No. 1.
PSCC and SWEC have already established the appropriate terms and conditions applicable to services identified in Attachment - No.1.
These terms and ccaditions are contained in our existing Continuing Services Agreement (PSCC Document No. 37754), dated January 2, 1980, amended on January 2, 1986.
In order to obtain the support listed in Attachment No.1, please contact Mr. R. S. Unks (boos ' phone 303-841-5060) or Mr. P.
T.
Ervin (home phone
~
303-690-8701).
Their office numbers are 303-741-7516 - and 303-741-7444 respectively t'
J. J. M.
lante Vice President Enclosure JJMP:RSU DSM cc:
T. J. Novachek O. J. Clayton FORM (D)372 22 3043 am- - - - - - _ _ - - -. _ -, - _
-a
---_a-
DERP Section 10 Issue 1 0SerylCO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 15 PUBUC SERVICE COMPANY OF CdLORADO ATTACMMENy NO. 1 Emeraenev Support Available Trem S'm'EC e
Tor Fort St. Vrain. Under the Terms ano concitiens Of Existina Contreet (PSC) Document No.
37754 1.
Assessment SVEC Personnel assist PSC, NSS5 vendor, other A/E personnel, or state / local agencies in off-site dose assessment, and assist PSC in assessing plant equipment das. age, performance, or operability.
2.
Enmineerinz/Desitn SVEC Personnel assist PSC, NSSS vendor or-other A/E personnel in engineering evaluations of accident consequences and in design of plant modifications or tosporary plant systems for nitigation er recovery.
3.
Procurement SWEC, acting as an agent for and on behalf of PSC. would assist in procurement of equipment required to sitigate or recover from an energency.
4.
Operations / Maintenance Suonert SWEC Personnel assist PSC Operations and Maintenance - personnel in rapid planning / procedure writing for emergency operations and maintenance activities.
SWEC personnel assist PSC Operations Personnel in planning and procedure writing for testing and.-cperation of. temporary syst % during the sitigation and initial recovery stages. Also could provide similar support on permanent systems when in the final recovery stages.
5.
Radiation Protection In addition to assisting in radiological dose assessments ites 1, - above.
SWEC personnel could assist PSC in executing control and sinimization of personnel exposures for operations requiring access or re entry during accident altigation er recovery. SVEC Rad Protection activities could also include engineering for temporary shielding as may be required for einimising personnel exposures.
6.
Quality Assurance SWEC personnel can be assigned to ' assist PSC in assuring an appropriate level of quality control is exercised over engineering, operations and maintenance activities during the recovery phase.
7.
Plannina ano Schedulig SWEC personnel would assist the PSC Recovery Manager in execution of overall and day to day scheduling and tracking of recovery activities.
. FORM (0)372 22 3643
OERP Section 10 Issue 1 0 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 15 Service
- PUBLIC SERVICE COMPANY OF COLORADO O
Platteville Fire Protection District P.O. Box 122 Platteville. CO 80651 (303) 785-2232 PPS-88-0546 2/4/88 Mr. Owen J. Clayton fort St. Vrain 16805 WCR 19}
Platteville Co. 80651
Dear Mr. Clayton:
This Letter is to update the present agreement between Public service and the Platteville Fire District. We have reviewed the present a;;reement and find it to be correct. The Platteville Fire Department agrees to continue response to Fort St. vrain for medical emergencies, fire emergencies and to assist as outlined in the emergency response plan.
If you need any additional information please feel free to contact us at 785-2232 O
.o Sincerely, c
i Glenn Hiller. Fire Marshal Platteville Fire District FORM (of 372 22 3643
DERP Section 10 Issue 1 0 SerVlCO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 15 PUBLIC SERVICE COMPANY OF COLORADO O
PPS.&8 0180 Johnstown Volunteer Fire Dept.
P O Bon f Johnstoun Colo 80534 January 14, 1988 Mr. Owen J.
Clayton Emergency Planning Coordinator Fort St. Vrain Nuclear Generating Station 16805 Weld County Road 19i Platteville, CO 80651
Dear Mr. Clayton:
This letter is to serve as notice that the Johnstown Volunteer Fire Department will be available to assist Fort St.
Vrain Nuclear Generating Station either for routine operations or during an emergency.
Please do not hesitate to notify us if we can be of service.
U J
CW M
(/h James C.
- Young, Jr., Chie t
Johnstown Volunteer Fire Department O
i FORM ID) 372.r.3643
DERP Section 10 Issue 1 0 Serv lC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 15 PUBUC SERVICE COMPANY OF COLORADO O
PPS.88 0300 ST ANTHONY HOSPIT L SYSTEMS C = a west sw aveNut. cEwsa CeccaAo0. ac2c4. ira, s29 3sii NORDt 2561 WEST 84ta avtNut. *ESTWiN$Tla COLOAACO. 80030 a i303i 426-2151 SUMMIT WEOeCAL CENTE4 PO 80x P3e. Fa'SCO COLORADO. 80443. i303i 668 3300 EMERGENCY MEDICAL CENTER PO Box 952. GAAN8v COLOAA00 60446. i303166L2503 00VOLAS A COOK Pressosat & Chet Executwo Otheer Jersaary 20, 1984 OWen J. Clayton Emmeguncy Plamirst Ocordinator Public service Qagiany 16805 M3t 191/2 PlattsV111a, CD 80651 Dear Mr. Clayttnt In respese to ycur latter of h 28, 1987, St. Anthcmy Hospital Systems' Fligst Far Life agrees to ccatirman with our comattaant to assist the Pelic servica Qupony of celerado at the 7bre St. Vrain Nuclear Ger==*47 Station as stated below.
st. Anthony thspital systems' Flight Fur Life agrees to respond to the Ptet St. Vrain Facility in Plattaville, Cblerado, at the reganst of the Wald 03unty ocumminaticrus Osntar for amargency aertical assistance.
Our Ozumanications M=, o r will verty to your Shift S@ervisce that Flight Ftic Life is (or is not) responding to the request by =1147 571-7436.
Per your policy, patients teso have m.M crritaminaticn ce rMiala"4=_1 714=*4mm will be L e4 to St. Ia.0ca's Hospital.
However, it is the W 47 Flight 18Jrse's h4=iM to dWYiate to another BMimi facility if thm =dimi omiition warrants.
A Health Physics 'Inctnician from Ftet St. Vrain may N the patiaEtt en the h=14* r if ecmditisms allow as determined by the pilot and flight nures.
Sincerely, Danial R. Reich Director, Flight Operaticns Mk cc: Baxtera Inckwced Arne Goehec Dr. mat +=m Cczmuunicatims Centar Dr. Drecen Operatiens Marsaal Dr. Ctxmar Films V
l ram ar.enreve.
FORMID)712 22 3N3
(
DERP Section 10 0 $9fVlCO*
Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pa 13 of 15 PUBUC SERVICE COMPANY OF COLORADO O
V PPS-88-0243
,YmM "lN:$?$*EN H.G. OLSON NUCLEAR ENGINEER k
January 13, 1983 Hr. R. O. Williams, Jr.
Vice President Nuclear Ooerations 1
Fort St. Vrain Nuclear Generating Station Public Service Comoany of Colorado 16305 Weld County Road 19 1/2 Platteville C0 30651
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Dear Mr. Williams:
In the event of a radiological emergency at Fort St. Vrain, I will be available to assist the olant's staff on problems relating to nuclear engineering and health physics.
I have been associated with Fort St. Vrain as a consultan[since initiation of the project. Throu Facility Safety Committee (NFSC) gh my membership on the Nuclear and my particioation in numerous HFSC audits. I have remained current on the operational status of the olant.
Very truly yours,
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H. G. Olson HGO:stw FORM (D)372 22 360
DERP Section 10 Issue 1 0 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 15 Serv'CO' PUBUC SERVICE COMPANY OF COLORADO O
PPS-88-0130 WESTERN RADIATION CONeULTANTS,INC. Raessen Meecuen / Evamanen M Hgene Empeyse / Wanagement Trawung 1306VAnned m 1702 Mai Street Fort Coens, em 80526 m Wyonnng82070 30lH42 3029 307 742 7127 t
January 6, 1988 lit. Owen J. Clayton Emergency Planning Coordinator Public Service Company of Colorado 16805 WCR 19 1/2 Platteville, CO 80451
Dear lir. Clayton,
In the event of a radiological emergency at the T'
.:, vrain teclear Generating Station I will be availab1'e to serve as ' radiation specialist' for Public Service Company at the State Energency Operations Center.
Ity current home and office telephone nanber ist (303)~412-3029.
incornly s,
Janet A. J on, PhD, CHP S
O FORMIOn372 22 3643
DERP Section 10 Issue 1 0 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 15 SerVlCO*
PUBUC SERVICE COMPANY OF COLORADO O
ESASCO CONSTRUccamoa4*tsCTORS INC.
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xco w wu s# santa ea cA sa gm es2-soss Ac.::aert E Pester PPS-88-0550
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February 12, 1988 Public Sarvice Company of Colorado 16805 WCR 13 1/2 Platteville, Colorado 80651 Attention:
Mr. Frank Novachek
Dear Mr. Novachek:
Ebasco Constructors Inc. is a subsidiary of Ebasco Services Incorporated, which is a full services engineering / construction firm with the capability of furnishing to Public Service Company of Colorado nuclear engineering, design, purchasing, procure-ment, and construction personnel.
Ebasco Constructors Inc. will be willing to assist Public Service Company of Co'.orado in the event of radiological emergency at the Fort Saint Vrain Nuclear Station.
In case of emergency, contact:
Mr. Robert E. Pester 3000 W. MacArthur Blvd.
Santa Ana, California 92704 (714) 662-4055 Sincerely, V J M, h S_ _ W 0
cc: File R.
Schwarz O'
R. Craun O. J. Clayton FORM (D)372 22 3643
DERP 5ection 11 Issue 1 age 1 of 2 0Public FORT ST. VRAIN NUCLEAR GENERATING f,TATION Service
- PUBUC SERVICE COMPANY OF COLO8tADO TITLE:
DEFUELING EMERGENCY RESPONSE PLAN, SECTION 11 MAFS PONSIBLE
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DERP Section 11 Issue 1 "9'
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FORM (0)372 22 3643
DERP Section 12 l
Issue 1 age 1 of 4 0Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION Service' PUBUC SERVICE COMPANY OF COLORADO v
TITLE:
DEFUELING EMERGENCY RESPONSE PLAN, SECTION 12 PROCEDURES THAT IMPLEMENT OR SUPPLEMENT THE PLAN PONSIBLE N
adfL RESw POR09 21 FEB 131991
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FOPM(D)372 22 3642
DERP Section 12 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 4 0Public Service
- PUBUC SERVICE COMPANY OF COLORADO O
APPENDIX 0 Implements /
Procedure Designation Supplements RERP and Title Section No.
FEV Administrative Procedures 4
G-5 Personnel Emergency Response 6
G-7 FSV Project Personnel Training and Qualification Programs 8
P-8 Fire Fighting and Prevention 5,6 Q-18 QA Monitoring and Audit Program 8
Health Physics Procedures HPP-915 RERP Inventory List 6,7 Health Physics activities are described within the Health Physics Procedures (HPPs).
Radiochemistry Procedures Radiochemistry activities are described within the Radiochemistry Procedures (RCPs).
FoftM(Of 372 22 3643
DERP Section 12 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 4 0Public Service
- PUBUC SERVICE COMPANY OF COLORADO O
APPENDIX D Implements /
Procedure Designation Supplements RERP and Title Section No.
Surveillances SR-EP-3-Q Backup Heteorological Data Collection 6,7 and Evaluation SR-EP-4-M Emergency Communication System Test 4,5,8 SR-EP-5-Q DERP Phone List Verification -
4,5,8 Outside Company SR-EP-6-Q DERP Phone List Verification -
4,5,8 Company SR-EP-7-Q Emergency Communication Equipment 4,5,8 Check SR-EP-9-Q Maintenance of Radiological Emergency ALL Preparedness SR-EP-10-Q Personnel Accountability System Test 6,8 SR-EP-11-Q DERP Emergency Organization 4,5,6,7,8 Augmentation - Working Hours SR-EP-12-SA DERP Emergency Organization 4,5,6,7,8 Augmentation - Off-hours Procedure Manuals and Plans TP-DERP Training Procedure - Defueling 8
Emergency Response Plan Emergency Operating Procedures (EOPs)
All Sections 4,5,6 Abnormal Operating Procedures (AOPs)
All Sections 4,5,6 Station DERP Implementing Procedures All Procedures All O
FORM (Dl372 22 3643 Y.
DERP Section 12 I
Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 0 $9fVIC9' PUBUC SERVICE COMPANY OF COLORADO APPENDIX D Implements /
Procedure Designation Supplements RERP and Title Section No.
Medical Emergency Plan - FSV 5,6,7 Technical / Administrative Services Manager's Administrative Procedures (TASMAPs)
TASMAP-8 Personnel Emergency Response 6
Accountability TASMAP-M Scenario Development of Emergency 8
Preparedness Exercises Public Service Company RERP Public Information Plan 5,7,8,9 State of Colorado Fort St. Vrain Radiological Emergency Response Plan (State RERP) 5,6,7,8 Weld County Radiological Emergency Response Plan 5,6,7,8 Operations Order Book All
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O FORM (D)372 22 3643
DERP Section 13 Issue 1 age 1 of 7 0 Service
TITLE:
DEFUELING EMERGENCY RESPONSE PLAN, SECTION 13 O STINGS OF EMERGENCY KITS "5S[ "*'
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UTHORIZED nSjw 90Rc 9 21 FEB 131991 lF" 3-M e
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DERP Section 13 Issue 1
'9' 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION SerVlC9' PusuC SERVICE COMPANY OF COLORADO O
LISTINGS OF EMERGENCY KITS, PROTECTIVE EQUIPMENT AND SUPPLIES STORED AND MAINTAINED FOR EMERGENCY PURPOSES
- TABLE OF CONTENTS l
Title Page Technical Support Center Emergency Kits 3
Drum Decon Supplies and Anti s 4
i Survey Truck 4
Control Room Emergency Supplies 4
Health Physics Area Emergency Supplies 5
Decon Area Equipment List 5
First Aid Room Equipment List 6
i Emergency Respiratory Protective Equipment 7
o l
- NOTE:
This section contains general categories of equipment and supplies available. The most current issue of HPP-915 provides specific information on the contents of the Emergency Kits.
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- O fr FORM (D)T?2 22 3843
DERP Section 13 Issue 1 9'
0 Service
- PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC sERWCE COMPANY OF COLORADO TECHNICAL SUPPORT CENTER EMERGENCY KITS
- Keys - Survey Vehicle
- Recording materials
- Portable radio
- Protective clothing
- Dosimetry
- Sample bottles and plastic bags
- Exposure Records
- Radiological Health Handbook f
- Calculator with battery
- Polyethylene sheets
- Survey equipment and supplies
- Tapes and ribbons, i.e., masking, radiation
- Signs, i.e., warning, road
- Respiratory equipment
- First aid kit
- Yellow Rose
- Film Badges
- Flashlights /with batteries
- Miscellaneous Tools (screwdriver, allen wrench, wrenches)
- Masslin Cloth o
FORM (D)772 22 3843
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DERP Section 13 Issue 1 "9'
& Public FORT ST. VRAIN NUCLEAR GENERATING STATION WQF Sorylce*
PusuC sERWCE COMPANY OF COLORADO O
DRUM DECON SUPPLIES AND ANTI-C'S
- Protective clothing
- Decontamination supplies
- Sample bottles and plastic bags
- Tape, i.e., masking, radiation
- Wipo Envelopes j
SURVEY TRUCK
- Survey equipment and supplies
- Recording material
]
- Calculator with battery
- Stopwatch
- Radiation Boundary Tape
- Flashlight with batteries 6
- Maps 9
- Copies of procedure DERP-FIELD
- Compass CONTROL ROOM EMERGENCY SUPPLIES
- Dosimetry
- Respiratory equipment
- Implementing documents
- Controlled Distribution Set of station piping and instrument (P&I) drawings
- Controlled Distribution Set of station floor plan drawings
-(located in the drawing file outside of the Control Room)
- First aid kit FORM (D)372 4 22
- 3843
.__ _ _ _ _ _ _. _. _ =. _ _
DERP Section 13 Issue 1 0 $9fVlCO*
Public FORT ST. VRAIN NUCLEAR GENERATING GTATION Pusuc sanvecs COMPANY OF COLORADO HEALTH PHYSICS AREA EMERGENCY SUPPLIES
- Dosimetry
- Respiratory equipment
- Protective clothing
- Survey equipment
- Flashlights
- Batteries i
- Flashlight bulbs 1
l
- Poly bags, tape, survey r.heets, clipboard, pencils, chalk, radiation warning signs, barrier tape, and wipes preloaded in envelopes
- Implementing documents
)
i DECON AREA EQUIPMENT LIST *
- Protective clothing l
- Decontamination supplies l
- Sample bottles and plastic bags i
i
- Exposure Records
- Tapes, i.e., masking, radiation i
- Bandages j
- Film Badges
- First Aid Kit
- NOTE: Located in Health Physics Area 4
.t ).
4 FORMIDl372 22 3043 I
l
DERP Section 13 Issue 1 O'
0 Service
FIRST A10 ROOM EQUIPMENT LIST *
- Instrument and first aid supply cabinet
- Trauma kit (located in Shif t Supervisor's Of fice)
- Canvas stretcher
- Wire basket stretcher
- Crutches d
- NOTE:
Located on Level Five (5), adjacent to West Entrance.
Health Physics does not inventory this equipment.
O r
FORM (D)372 22 3643
DERP Section 13 l
Issue 1 A Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION
'9' M17 Service
- PUBUC SERVICE COMPANY OF COLORADO O
EMERGENCY RESPIRATORY PROTECTIVE EQUIPMENT
- Health Physics
- Four Scott air packs Turbine Deck, El 4829, Fire Station
- Six Scott air packs Building 10. El 4839, Offices
- Five Scott air packs Outside Auxiliary Electric Room
- Two Scott air packs El 4791, Fire Station
- Six Scott air packs Central Alarm Station
- Two Scott air packs Search and Identification Building
- Five Scott air packs a
- Five Scott air packs NOTE: Scott air packs may be shown on individual center inventory lists also.
k FORM (ol372 22 360
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