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Revised Defueling Emergency Response Plan,Including Section 1 Definitions,Section 2 Scope & Applicability,Section 3 Summary of Fsv Derp,Section 4 Emergency Classifications & Section 5 Emergency Organization
	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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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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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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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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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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. 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.

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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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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.

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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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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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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

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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

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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.

o PORM 101 F12 + 22 3M3

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 /

~

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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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

~

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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

~

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

~

27.0 x 10 ' vC1/cc j

d) RIS 7325-2 indicating

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

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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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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

\\s /

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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

d) RIS 6212 AND RIS 6213.

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

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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.

O v

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 0.00111 hours 6.613757e-6 weeks 1.522e-6 months 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

(10 CFR 73.71).

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.

I

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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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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.

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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

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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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

s

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(

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , showing no voltage.' #

f I

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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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , 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.___.-

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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.

~

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

- -,. - - ~

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

_ _ ~

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.

TECHNICAL SUPPORT CENTER 1.

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

. =.

~ -

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

Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO c.

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

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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)

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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

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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

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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

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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

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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

Public FORT ST VRAIN NUCLEAR GENERATING STATION Page 3 of 21 PUBUC SERVICE COMPANY OF COLORADO O

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

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 21 PUBUC SERVICE COMPANY OF COLORADO O

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

Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 21 PUBUC SERVICE COMPANY OF COLORADO O

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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m FORM (Dl372 22 36tl

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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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2

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

.o l

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.

1 I

Ponutom2 22 see l

.. ~

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

_ _ _ _ _ _ _ ~.

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

_ _ _ _ ~ _ - - -.

DERP Section 7 Issue 1 89' 0 Service

Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO 2.

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.

row toim.m.see

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.

0 v

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

~

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

Mill 10) U2

22

M43

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

PRIMARY AND SECONDARY COMMUNICATION LINKS l PSC MEDIA 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

Public FORT ST VRAIN NUCLEAR GENERATING STATION Page 9 of 21 Pusuc sERWCE COMPANY OF COLORADO O

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.

l O

.g l

O FORM (o)372 22 3043 I

e r.-

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

i l

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

.o O

l FORM (01372 22 3043 l

l

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

l l

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

.g i

4 l

O 1

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.

1 h

V E

FORM (D)372 22 3843

Issui 1 age 1 'f 8 o

0 Service

Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO TITLE:

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

/

./

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

1. - 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.

1. - 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.

1. - 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

.. /

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.

1. - 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

1. - 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

e PT, ST. VRAIN I

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.

Initiating Events C.

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

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

Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION 1 of 15 PURUC SERVICE COMPANY OF COLORADO TITLE:

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 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , 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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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..-,...-

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. 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

(~h

,y

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,

~

i c

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.

'5TvE@c

- -g g a we e e a44sce saavets '

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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PORC EFFECTIVE REVIEW POIC 9 21 FEB 131991 DATE 3 19 $ \\

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COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR TO USE FOfiM(D)372 22 3642

DERP Section 11 Issue 1 "9'

U 0 $9fVICO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PCBLIC SERVICE COMPANY OF COLORADO EMERGENCY Pl.ANNING ZONE

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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

'((TE' "'3.aA.qi DCCF NUMBER (S) h&l2%

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dr hw

.m FT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR

/N TO USE q)

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

~

O FORM (D)372 22 3643

DERP Section 13 Issue 1 age 1 of 7 0 Service

Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC saRWCE COMPANY OF COLORADO O

TITLE:

DEFUELING EMERGENCY RESPONSE PLAN, SECTION 13 O STINGS OF EMERGENCY KITS "5S[ "*'

8Adns(--

UTHORIZED nSjw 90Rc 9 21 FEB 131991 lF" 3-M e

TE occF c

-l2.Sl O

NUMBER IS)

O FT. ST VRA!N NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT O-CONTROL CENTER PRIOR TO USE -

FORM (01372 22 3M2 i

ny,t,,

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r

. - +. -.

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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.

a

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

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

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

Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO O

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

Technical Support Center

- Five Scott air packs NOTE: Scott air packs may be shown on individual center inventory lists also.

k FORM (ol372 22 360

. _ - - - _

ML20072V529: Difference between revisions

Latest revision as of 04:09, 15 December 2024

Contents

Text

SUMMARY

1.1 ASSESSMENT

SUMMARY

SUMMARY

Response

6.2 ASSESSMENT

7.3 ASSESSMENT

SUMMARY

Dear Mr. Clayton:

Dear Mr. Clayton:

Dear Mr. Clayton:

Dear Mr. Clayton:

Dear Mr. Clayton:

Dear Mr. Clayton:

Dear Mr. Williams:

Dear lir. Clayton,

Dear Mr. Novachek:

Navigation menu

@@ Line 16: / Line 16: @@
 =Text=
-{{#Wiki_filter:.  ._                  . -
+{{#Wiki_filter:.
-                                 .                                         e.mm       m.
+Publ.
-Publ.ic Service'                                                    g;-gc*-
+Service' e.mm m.
+ic g;-gc*-
 Denver, Co 80201 0840 16805 WCR 19 1/2, Platteville, Colorado ~80651 1
-April 12, 1991 Fort St. Vrain Unit No. 1 P-91124 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk                                                               ;
+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.
-Mail Stop P1-37                                                                           -
+DOCKET NO:
-Washington, D.C. 20555 DOCKET NO:       50-267 SUBJ2CT: DEFUELING EMERGENCY RESPONSE PLAN - PLANT PROCEDURE DISTRIBUTION Gr.n tl emen :
+-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)
+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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+T
-P-91124 Page 2 April 12,1991 In accor'ance d     with 10CFR50.54(q), we have determined that the changes in these issues do not decrease the effectiveness of the Fort St.
+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
+.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
 l l
-t 1
+t 03/29/91 1
-/29/91 Pubile                                  FORT ST. VRAIN NUCLEAR GENERATING STATION                                                         *V7 L
+*V7 L Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION
-                                   $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:                                                                       -
+$9tVIC9' PUBUC SERVICE COMPANY OF COLORADO DEFUEdiiG EMERGEN^i RESPCNSE PuW - PUNT ISSUE EFFECTIVE NO.
-l                                                      Section 1 Definitions                     1           03-29-91 1 DERP Section 2                                      Defueling Emergency Response Plan:
+SUBJECT NUMBER DATE l
-I                                                     Section 2 Scope and Applicability,        1           03-29-91 l DERP Section 3                                      Defueling Emergency Response Plan:
+Table of Contents 1'
-                                                    Section 3 Summary of the FSV DERP         1           03-29-91 l DERP Section 4                                     Defueling Emergency Response Plan:
+-29-91 1
-I                                                    Section 4 Emergency Classifications       1           03-29-91                                       -
+Introduction 1
-l DERP Section 5                                     Defueling Emergency Response Plan:
+-29-91 J
-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 DERP Section 1 Defueling Emergency Response Plan:
-l                                                    Section 7 Emergency Facilities                                                            .
+l Section 1 Definitions 1
-I                                                    and Equipm'ent                            1           03-29-91 4
+-29-91 1 DERP Section 2 Defueling Emergency Response Plan:
-DERP Section 8                                     Defueling Emergency Response Plan:
+I Section 2 Scope and Applicability, 1
-I                                                    Section 8 Maintaining Emergency l                                                    Preparedness                               1          03-29-91 l DERP Section 9                                    Defueling Emergency Response Plan:
+-29-91 l DERP Section 3 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                                                                 ~
+Section 3 Summary of the FSV DERP 1
-,                       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
+-29-91 l DERP Section 4 Defueling Emergency Response Plan:
+I Section 4 Emergency Classifications 1
+-29-91 l DERP Section 5 Defueling Emergency Response Plan:
+I Section 5 Emergency Organization 1
+-29-91 1 OERP Section 6 Defueling Emergency Response Plan, i
+Section 6 Emergency Measures 1
+-29-91 l DERP Section 7 Defueling Emergency Response Plan:
+l Section 7 Emergency Facilities I
+and Equipm'ent 1
+-29-91 4
+DERP Section 8 Defueling Emergency Response Plan:
+I Section 8 Maintaining Emergency l
+Preparedness 1
+-29-91 l DERP Section 9 Defueling Emergency Response Plan:
+I Section 9 Recovery 1
+-29-91 l DERP Section 10 Defueling Emergency Response Plan, l
+Section 10 Letters of Agreement
+~
+l and Supporting Plans 1
+-29-91 l DERP Section 11 Defueling Emergency Response Plan, 1
+Section 11 Maps 1
+-29-91 l DERP Section 12 Defueling Emergency Response Plan, l
+Section 12 Procedures That i
+Implement or Supplement the Plan 1
+-29-91 l DERP Section 13 Defueling Emergency Response Plan, l
+Section 13 Listings of Emergency Kits 1
+-29-91 FORM (D1372 22 3643
-l-                                                                            Issue 1                   i Public            FORT ST. VRAIN NUCLEAR GENERATING STATION 39' OSerVlCOSPUBUC SERVICE COMPANY OF COLORADO TITLE:         DEFUELING EMERGENCY RESPONSE PLAN: INTRODUCTION "S''''
+l-Issue 1 39' OSerVlCOS Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO TITLE:
-EST                  Dxfao+
+DEFUELING EMERGENCY RESPONSE PLAN: INTRODUCTION EST "S''''
-UTHORIZED PORC                                                             EFFECTIVE REVIEW                    PORC 9 21 FEB 131991                   DATE          3 19-SI DCCF NUMBER (S)         hh-l 2 24 O                                                                                                .
+Dxfao+
-i FT. ST. VRAIN NOt+CDNTftOd60 000s VERIFY $8iw :il ATUS WITH 'T0 MuMENT CONTROL C6NTC6 PRIOR TO UBC            ,                                                         ,
+UTHORIZED PORC EFFECTIVE REVIEW PORC 9 21 FEB 131991 DATE 3 19-SI DCCF NUMBER (S) hh-l 2 24 O
-FORM (Ol372 22 3642
+FT. ST. VRAIN i
+NOt+CDNTftOd60 000s VERIFY $8iw :il ATUS WITH 'T0 MuMENT CONTROL C6NTC6 PRIOR TO UBC FORM (Ol372 22 3642
-DERP Introduction Issue 1              -
+DERP Introduction Issue 1 O Service
-Public            FORT ST. VRAIN NUCLEAR GENERATING STATION                                    Page 2 of 2 O Service
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 2 PUBLIC SERVICE COMPANY OF COLORADO O
-* PUBLIC SERVICE COMPANY OF COLORADO O                        INTRODUCTION                                                             ,
+INTRODUCTION The Fort St.
-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).
+Vrain (FSV) Nuclear Generating Station is owned and operated by the Public Service Company of Colorado (PSC).
-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                                                   -
+It is a High Temperature Gas-Cooled Reactor (HTGR) rated at 330 Mw (net).
-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.
+FSV began commercial operation on July 1,1979 and ended operations on August 29, 1989.
-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-                                       .
+FSV is located near Platteville, Colorado, approximately 40 miles north of Denver.
-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.
+The Defueling Emergency Response Plan (DERP) has been reviewed and approved by the Nuclear Regulatory Commission (NRC),
-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
+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
 I O
 FORM (o)372 22 3043 1
-war  ,ov.. v.
+war
-Contents FORT ST. VRAIN NUCLEAR GENERATING STATION           1 of 4 O Public Service
+,ov..
-* PUBLIC SERVICE COMPANY OF COLORADO TITLE:                                                              DEFUELING EMERGENCY RESPONSE PLAN: TABLE OF CONTENTS RESPONSIBLE                                                                              AUTHORIZED h
+v.
-FOR:                                                                               $     BY:
+Contents O Public FORT ST. VRAIN NUCLEAR GENERATING STATION 1 of 4 Service
-NTHORIZED                                                                                                                                         ,
+* PUBLIC SERVICE COMPANY OF COLORADO TITLE:
-      "C                                                                                                                           e R    ew                                                                         PORD 921 FEB 131991                   [FF A'TE      b4%
+DEFUELING EMERGENCY RESPONSE PLAN: TABLE OF CONTENTS RESPONSIBLE AUTHORIZED h
-OCCF NUMBER (S)                                                         hO-k113 n
+BY:
-U                                                                                                                                                .
+FOR:
+NTHORIZED "C
+PORD 921 FEB 131991
+[FF b4%
+e R
+ew A'TE OCCF hO-k113 NUMBER (S) n U
 FT. ST. VRAIN NON-CONTROU ED Coei VERIFY essuf s! ATUS WITH 9 tit thAUMENT CONTAOL CEMTE: o'OR TO USE O
-_                                                            .                          _t FORM (El772 22 3tM2
+_t FORM (El772 22 3tM2
-OtHP laule of Contents Public            FORT ST. VRAIN NUCLEAR GENERATING STATION            2 of 4 O service
+OtHP laule of Contents O service
-* PusuC SERVICE COMPANY OF COLORADO A)
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION 2 of 4 PusuC SERVICE COMPANY OF COLORADO A)
-(--                                       TABLE OF CONTENTS INTRODUCTION                                                         -
+(--
-.0 DEFINITIONS 2.0 SCOPE AND APPLICABILITY 3.0
+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
+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
-()          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
+.0 EMERGENCY ORGANIZATION 5.1 Normal Station Organization 5.2 Onsite Emergency Organization 4
-;                             5.2.4 PSC Headquarters Support 5.3   Offsite Emergency Support 5.3.1 Local Services Suppcrt                                                -
+.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
-.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 l
 FoftMto)372 22 3643
-UtKr 18D10 of Contents
+UtKr 18D10 of Contents Issue 1 Pyhll3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 4 0.
-                          ,                      -"                                                                  Issue 1 Pyhll3                   FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 4
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-A "p 'x l                                                               6.4.1 Protective Cover and Personnel Ac'countab111ty N
+'x 6.4.1 Protective Cover and Personnel Ac'countab111ty l
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+N 6.4.2 Use of.Onsite Protective Equipment and Supplies W;f
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+;;$ hf 6.4.3 Contamination Control Measures t
-                                            ,'                  6.4.3  Contamination Control Measures
+Jhihh @y;p <16.5 Aid to Affected Personnel qq a hWd
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+@M M kr b M c M r,,6.5.4; Medical Transportation asi
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+* 6.5.3 Medical Treatment MMwg
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+ng 7s V Mo V iJ ''2711.1 Technical Support Center (TSC)
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+@ JMM Offsite Systems and Equipment Support
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+$w-Di 3$ D$OL8.1 - Organizational Preparedness 7
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+we sw"y y CJ yta 8.1.1 Training ci M."
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+r y-%g' l M4!E
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+l pap & 4 f.:8.2 Review and Updating of the OERP flyM
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+.3 Maintenance and Inventory of Emergency Equipment and
-      ,g _
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-f@                                         ' 8.4      Independent Review of the Emergency Preparedness Program
+' 8.4 Independent Review of the Emergency Preparedness Program
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-UtKP l& Die of Contents Issue 1 Pubile            FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 0 service
+UtKP l& Die of Contents Issue 1 0 service
-* PusuC SERVICE COMPANY OF COLORADO 9.0 RECOVERY 9.1    Recovery Organization 9.2    Recovery Exposure Control 10.0 LETTERS OF AGREEMENT AND SUPPORTING PLANS 11.0 MAPS 12.0 PROCEDURES THAT IMPLEMENT OR SUPPLEMENT THE PLAN 13.0 LISTINGS OF EMERGENCY KITS O                                                                                                                                                .
+* Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 PusuC SERVICE COMPANY OF COLORADO 9.0 RECOVERY 9.1 Recovery Organization 9.2 Recovery Exposure Control 10.0 LETTERS OF AGREEMENT AND SUPPORTING PLANS 11.0 MAPS 12.0 PROCEDURES THAT IMPLEMENT OR SUPPLEMENT THE PLAN 13.0 LISTINGS OF EMERGENCY KITS O
-FORM (0)372 22 3643 w     - - - .    .
+FORM (0)372 22 3643 w
-UCl\r OttG L l ull A Issue.1 age 1 of 4 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service'                 PusuC SERVICE COMPANY OF COLORADO                                               .
+UCl\\r OttG L l ull A Issue.1 age 1 of 4 0 Service' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO TITLE:
-TITLE:           DEFUELING EMERGENCY RESPONSE PLAN: SECTION 1 DEFINITIONS I
+DEFUELING EMERGENCY RESPONSE PLAN: SECTION 1 DEFINITIONS FONSIBLE UTHORIZED PORC EFFECTIVE REVIEW PORC 9 21 FEB 131991 DATE 3-2A - @
-FONSIBLE UTHORIZED PORC                                                             EFFECTIVE REVIEW                    PORC 9 21 FEB 131991                   DATE          3- 2A - @
+OCCF NUMBER (S!
-OCCF NUMBER (S!         hh - \ 2.25
+hh - \\ 2.25
-                                                                         .g   .
+.g FT. ST. VRAIN NON-CONT 9OLLED CQr's VERIPr ib a
-FT. ST. VRAIN NON-CONT 9OLLED CQr's VERIPr ib a    ' ATUS WITH Sff1. ' AMMENT CONTROu CENTER FRIOR TO USE O
+' ATUS WITH Sff1. ' AMMENT CONTROu CENTER FRIOR TO USE O
-i                                                               ,
+i FORM (D)372 22 3642
-FORM (D)372 22 3642
+/.
-                                                               /.
-DERP Section 1 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 4 0Public SerVlCO*          PUBUC SERVICE COMPANY OF COLORADO                                            I t
+DERP Section 1 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 4 0Public SerVlCO*
+PUBUC SERVICE COMPANY OF COLORADO
 (
-.0 DEFINITIONS The following are selected terms commonly used in this Defueling    '
+t 1.0 DEFINITIONS The following are selected terms commonly used in this Defueling Emergency Response Plan (DERP).
-Emergency Response Plan (DERP).
-.1     ASSESSMENT ACTIONS Actions taken during, or after, an accident to obtain and i                       process information necessary to          implement     specific                  ,
+==1.1 ASSESSMENT==
-emergency measures.
+ACTIONS Actions taken during, or after, an accident to obtain and i
-.2     ACCOUNTABILITY Process of identifying missing, onsite personnel.
+process information necessary to implement specific emergency measures.
-.3     ALERT i
+.2 ACCOUNTABILITY Process of identifying missing, onsite personnel.
+.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.
-.4     COLORADO DEPARTMENT OF HEALTH (COH) 4                       The state agency with primary resp'onsibility for carrying
+.4 COLORADO DEPARTMENT OF HEALTH (COH)
-,                       out radiological emergency assessment actions and for                      -
+The state agency with primary resp'onsibility for carrying 4
-providing     Protective Action        Recommendations to the Governor or his designee.
+out radiological emergency assessment actions and for providing Protective Action Recommendations to the Governor or his designee.
-.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.
+.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.
-.6     CONTROL ROOM (CR)
+.6 CONTROL ROOM (CR)
-The CR operates under the direction of a Shift Supervisor.                 -
+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
+It is the-primary point at which plant conditions are monitored and controlled and corrective actions taken to a.
-: a.                      mitigate an abnormal occurrence. . It is the location where
+mitigate an abnormal occurrence.. It is the location where initial assessment and classification of. an incident is initiated.
-;                       initial   assessment and classification of. an incident is initiated.                                                                          ,
+.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.
-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.                            -
+FORM (D)372 22 3M3
-FORM (D)372 22 3M3 l
-DERP Section.1       )
+DERP Section.1
-Issue'1              l Public              FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 4 -
+)
-O SerVICO'PUBUC SERVICE COMPANY OF COLORADO
+Issue'1 l
-. 1 0 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.
+O SerVICO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 4 -
-EALs can also be referred to as " initiating events" for                    ,
+PUBUC SERVICE COMPANY OF COLORADO 0
-those     events     severe   enough   to  cause   an     event classification.
+. 1 1.8 EMERGENCY ACTION LEVELS (EAL's) 1 l
-.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.
+Para.ieters or symptoms used to designate a particular l
-.10 EMERGENCY PLANNING ZONE (EPZ)                                              .
+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.
-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.
+EALs can also be referred to as " initiating events" for those events severe enough to cause an event classification.
-!                 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
+.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.
+.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.
+.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.
-.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.
+.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
-.13 PLUME A    distribution      of    radioactive material carried by               -
+take precautionary and constructive steps to prevent a i
-,(('                       prevailing winds.
+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.
+.13 PLUME
+('
+A distribution of radioactive material carried by
+,(
+prevailing winds.
 FORM (0)372 22 3643
-UcKF dection i Issue 1-FORT ST. VRAIN NUCLEAR GENERATING STATIONPage 4 of 4
+UcKF dection i Issue 1-Public FORT ST. VRAIN NUCLEAR GENERATING STATIONPage 4 of 4 SOfVICe*
-   ,        Public SOfVICe*            PUBUC SERVICE COMPANY OF COLORADO 1.14 PROTECTIVE ACTION GUIDES (PAG's)
+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                      -
+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.
-Agency (EPA),
+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),
 .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.
+Recommendations made to appropriate state / local officials (i.e.,
-.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.
+shelter) to prevent or minimize radiological exposure after an actual or projected release of radioactive material.
+.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.
 .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.
+The TSC is located adjacent to the Reactor Building in the Technical Support Building. This building is within. easy walking distance to the CR.
-,O                                                                                                -
+.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.
-U FORM (o)372 22 3643
+,O U
-                                                                               ~~
+FORM (o)372 22 3643
+~~
 w fir scwwawo a Issue 1 "9'
-Public             FORT ST. VRAIN NUCLEAR GENERATING STATION 0SerVlCe*                  PusuC SERVICE COMPANY OF COLORADO em l
+SerVlCe*
-h            TITLE:         DEFUELING EMERGENCY RESPONSE PLAN: SECTION 2 SCOPE AND APPLICABILITY                 ,
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO emh TITLE:
-ESPONSIBLE guTaoRizE         MM                                              '"'
+DEFUELING EMERGENCY RESPONSE PLAN: SECTION 2 l
-ldiw                    ponc 9 21 FEB 131991                  $'lTE         3. a.q. q i DCCF NUMBER (S)        O' l 2. 2.b l
+SCOPE AND APPLICABILITY ESPONSIBLE guTaoRizE MM ldiw ponc 9 21 FEB 131991
+$'lTE
+: 3. a.q. q i DCCF NUMBER (S)
+O' l 2. 2.b l
 (
-FT. ST. VRAIN NON-CONTPOd SD                                                                        '
+FT. ST. VRAIN NON-CONTPOd SD Coe-VERIFY tS%
-Coe-VERIFY tS%        'ATUS WITH SITL DOCUMENT CONTROL CENTER PRIOR n
+'ATUS WITH SITL DOCUMENT CONTROL CENTER PRIOR TO USE n
-U TO USE                                                                                     .
+U j
-j         FORM (D)372 22 3642
+FORM (D)372 22 3642
-DEko Section 2 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION   P age 2 of 2      j Public 0SerVlCO* PUBUC SERVICE COMPANY OF COLORADO                                                i l
+DEko Section 2 Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION age 2 of 2 j
-I I
+P 0SerVlCO* PUBUC SERVICE COMPANY OF COLORADO I
-l b                                2.0 SCOPE AND APPLICABILITY 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              '
+I b
-established to ensure that these corrective actions are executed properly and effectively.
+.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.
+The PSC emergency organization that would be established to respond to an accident at FSV.
-: 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 i
+The notification process that would be used to alert the various organizations of the accident.
-O                                        the plan, categorize the specific type of er.:ergency according to 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.
+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.
 l l
 l.
@@ Line 247: / Line 323: @@
 FORM (Ol372 22 3643
-DERP Section 3 l
+DERP Section 3 Public FORT ST. VRAIN NUCLEAR GENERATING STATION l
-Public             FORT ST. VRAIN NUCLEAR GENERATING STATION                       ) gf 3 SerVIC9'           PUBUC SERVICE COMPANY OF COLORADO
+) gf 3 SerVIC9' PUBUC SERVICE COMPANY OF COLORADO
 (^)
-TITLE:          DEFUEL'ING EMERGENCY RESPONSE PLAN: SECTION 3
+TITLE:
+DEFUEL'ING EMERGENCY RESPONSE PLAN: SECTION 3
 ==SUMMARY==
 OF THE FSV DERP i
-SPONSIBLE
+SPONSIBLE age (
-                    ^"" "'z" v                  age (                                                                                .
+^"" "'z" v
-                       "                                                                      EF ECTIVE REiSw                       PORC 9 2 i FEB 131991                            Te DCCF NUMBER (S)         hO~ \ 2,2 9 O                                                                                                                    .
+REiSw PORC 9 2 i FEB 131991 EF ECTIVE Te DCCF NUMBER (S) hO~ \\ 2,2 9 O
-FT. ST. VRAIN NON-CONTA0dFD CON VERIFY ISSUE 9 t ATUS WITH SITE DOCUMENT CONTROL CENTER DA'OR
+FT. ST. VRAIN NON-CONTA0dFD CON VERIFY ISSUE 9 t ATUS WITH SITE DOCUMENT CONTROL CENTER DA'OR TO USE FORM (D)372 22 3642 c._._......_.....
-* TO USE FORM (D)372 22 3642 c._._......_.....
 }
-DERP Section 3 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION                     Page 2 of 3 0Public
+DERP Section 3 Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 3
-                      $9fVlC9'              PUBUC SERVICE COMPANY OF COLORADO O
+$9fVlC9' PUBUC SERVICE COMPANY OF COLORADO O
-v                  3.0
+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.
+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
+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.
-                                   ~
+~
-State RERP.
 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                                                         .
+Sections 4.0 thru 8.0 of the FSV DERP provide specific detail on the emergency preparedness program.
-the emergency preparedness program.            The contents of these sections are summarized below:                                                                                                        3 Section 4.0 - Emergency Classifications Describes emergency classifications, initiating events,                                                            ,
+The contents of these sections are summarized below:
-emergency action levels (EAL's), and corresponding PSC actions in response to each emergency classification.
+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                                      ~
+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.
-Technical    Support Center (TSC) and the Control Room (CR).
+Proviston is made for two onsite emergency control centers:
-This section also indicates specific assignments                                  of personnel       to emergency billets and notes local                       and contract support service arrangements.
+the Technical Support Center (TSC) and the Control Room (CR).
-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.
+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           l e
+DERP Section 3 Pubils FORT ST. VRAIN NUCLEAR GENERATING STATIOlJ e
-Pubils                FORT ST. VRAIN NUCLEAR GENERATING STATIOlJ 3 f3 "g
+"g $9fVIC9'
-             ,N $9fVIC9'                     Pusuc senvms COMPANY OF COLORADO                                                                 l 1
+,N 3 f3 Pusuc senvms COMPANY OF COLORADO l
-Section 7.0 - Emergency Facilities and Equipment                                        ,
+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.
-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.
+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.
+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                                                                                       >
+Section 9.0 - Recovery
-Defines,                       in     general    terms,       a   recovery plan and organization.
+: Defines, in general
+: terms, a
+recovery plan and organization.
 Section 10.0 - Letters of Agreement and Supporting Plans
-(                            Includes copies of Letters of Agreement with various local 5
+(
-agencies and contract support organizations.                                                        .
+Includes copies of Letters of Agreement with various local 5
-Section 11.0 - Maps includes                       a    map    of    the    EPZ,      geographical        area identification designations, and environmental dosimetry locations.
+agencies and contract support organizations.
-Section 12.0 - Procedures That Implement or Supplement the P.!a n A listing of procedures which implement or supplement the plan.                                                                                               .
+Section 11.0 - Maps includes a
-Section 13.0 - Listings of Emergency Kits A listing of emergency kits, protective equipment, and                                                        ;
+map of the
-supplies stored and maintained for emergency purposes.                                                        !
+: EPZ, geographical area identification designations, and environmental dosimetry locations.
-                                                                                                                                            -1 FORM (D)3rJ 22 3843 I
+Section 12.0 - Procedures That Implement or Supplement the P.!a n A listing of procedures which implement or supplement the plan.
-l
+Section 13.0 - Listings of Emergency Kits A listing of emergency kits, protective equipment, and supplies stored and maintained for emergency purposes.
+-1 FORM (D)3rJ 22 3843
 Issue 1 "9'
-Pubils                     FORT ST. VRAIN NUCLEAR CENERATING STATION lA               S ervice'                 rusuC SERVICE COMPANY OF COLORADO TITLE:                      DEFUELING EMERGENCY RESPONSE PLAN: SECTION 4 EMERGENCY CLASSIFICATIONS l
+Pubils FORT ST. VRAIN NUCLEAR CENERATING STATION l A ervice' S
-PONSIBLE UTHORIZED
+rusuC SERVICE COMPANY OF COLORADO TITLE:
-                                                                                                      'C7'V" nSSw                                            PGC 9 21 FEB 131991                  D7TE          Ea4 DCCF NUMBER (S)                           hO - l 2.2 R Q                                                     .
+DEFUELING EMERGENCY RESPONSE PLAN: SECTION 4 EMERGENCY CLASSIFICATIONS PONSIBLE UTHORIZED nSSw PGC 9 21 FEB 131991 D7TE Ea4
-l                                                                                                   .       .
+'C7'V" DCCF NUMBER (S) hO - l 2.2 R
+! Q l
 t I
 N i
+FT. ST VRAIN-NON-CONTROLLED CCWs i
-!                                  FT. ST VRAIN-NON-CONTROLLED CCWs i                                  VERIFY SStlE St ATUS
+VERIFY SStlE St ATUS WITH SITE ONUMENT j (QN CONTROL CENTER PR'OR TO USE au & n.n.-
-,                                   WITH SITE ONUMENT j (QN                            CONTROL CENTER PR'OR                                                                       .
-TO USE au & n.n.-
-DERP Section 4 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION                         Page 2 of 76 0Pubil3  Service
+DERP Section 4 Issue 1 0Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 76 Service
-* PusuC ssRVICE COMPANY OF COLORADO O        4 . 0,   EMERGENCY CLASSIFICATIONS                                 ,
+* PusuC ssRVICE COMPANY OF COLORADO O
-Emergencies      are     classified into two categories.. The classification system results in responses and procedures that are both timely and appropriate for each emergency condition.
+. 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                                   -
+l 4.1 CLASSIFICATION The following are the descriptions of the two classifications used in the system.
-parenthesis after the classification title.
+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.
 .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                                       .
+This classification applies to situations where O
-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.                                   ,   ,
+unusual events are in process, or have occurred, which indicate a potential for degradation of the level of safety of the plant.
-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                .
+No releases of radioactive material requiring offsite response or monitoring tre expectec unless further degradation of safety systems occur.
-officials are promptly notified- of an unusual event.
+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.
-Attachments        B1     through B14 outline initiating events and response actions for the NOTIFICATION OF AN UNUSUAL EVENT class of incident.
+-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.
-O              .
+State officials are promptly notified-of an unusual event.
-FORMtDl372 22 3M3 l
+Attachments B1 through B14 outline initiating events and response actions for the NOTIFICATION OF AN UNUSUAL EVENT class of incident.
-                                                 -./-,-.       -      _              _  - _ - . .           , . - -
+O FORMtDl372 22 3M3 l
+-./-,-.
-DERP Section 4 Issue 1 Pubila         FORT ST. VRAIN NUCLEAR CENERATING STATION         Page 3 of 76 0 Service'                      PUBUC SERVICE COMPANY OF COLORADO O                                 4.1.2 ALERT (" CONDITION GREEN")          ,
+DERP Section 4 Issue 1 0 Service' Pubila FORT ST. VRAIN NUCLEAR CENERATING STATION Page 3 of 76 PUBUC SERVICE COMPANY OF COLORADO O
-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                     ;
+.1.2 ALERT (" CONDITION GREEN")
-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 such modification has not already been accomplished                    {'
+This classification comprises events which are in l
-by automatic protective systems.
+process, or have occurred, which involve an actual or potential, substantial degradation of the level i
-Declaration of an ALERT will trigger prompt initial             .
+cf safety of the plant.
-and follow-up notification to offsite authorities.                     6 If applicable, updated meteorological inform tion,                    ;
+Any releases of j
-verification of releases by surveys, and projected radiological effects on offsite areas will be provided to local and state authorities,    The ALERT
+radioactive materials are expected to represent j
+small fractions of the EPA Protective Action Guide limits.
+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
+{
+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.
+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
 /~
-'                                          status is maintained until the event is declared to be terminated.                                                   .
+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.                                 ,    ,
+Attachments B1 through B14 outline initiating events and response actions for the ALERT class of i
+incident.
 .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.
+Items / Situations constituting Non-Emergency Events are specified in 10 CFR 50.72.
-colors to Non-Emergency Events.                                          . 4 i
+The following are descriptions of the two categories. The State-RERP does not assign.
-Fonu toim.m.sec                                                                                       ;
+colors to Non-Emergency Events.
+i
+Fonu toim.m.sec
-                                                                                                      -                          DERP Section 4 Issue 1 Pub ll3                            FORT ST. VRAIN NUCLEAR CENERATING STATION                           Page 4 of 76 0 Service
+DERP Section 4 Issue 1 0 Service
-* Pusuc sanwes courAmy or cotonAno 4.2.1 ONE-HOUR REPORT                                                  ,
+* 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.
-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                                          -
+Attachments B1 through B14 outline initiating events for one-hour reports,
-duties, or any event that results in a major loss of      emergency                assessment        capability           or communications capability.
+.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
-Attachments              B1   through B14 outline              initiating      -
+resulted in the plant being seriously degraded or being in an unanalyzed condition, any event that j
-events for one-hour reports,                                                                       i
+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
-.i                                                                                                                                                               !
+transportation of a radioactively contaminated
-;                                    4.2.2 FOUR-HOUR REPORT If not reported as a declaration of an Emergency                                    .
+: person, or any event for which a news release is 4
-i Class or as a one-hour report, the licensee shall                                                  !
+planned or notifications to o t he r -- government agencies have been or will be made.
-notify the NRC as                 soon as practical and in all                                     !
+l 4.3 SPECTRUM OF p0SSIBLE ACCIDENTS A,ND INITIATING EVENTS
-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 j  ,
+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.
-being in an unanalyzed condition, any event that                                     .
+These accidents reflect the design
-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.
+characteristics of an HTGR and are addressed in Attachments 81 through B14'. from the viewpoint of initiating
-l                            4.3     SPECTRUM OF p0SSIBLE ACCIDENTS A,ND INITIATING EVENTS
+: events, alarm actuation and/or associated readings, and consequent incident classification.
-                                                                                                                                                   ~
-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
- ?
-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 Pubilg                     FORT ST. VRAIN NUCLEAR CENERATING STATION                     Issue 1 0 Service
+DERP Section 4 Attachment A 0 Service
-* rusuc sanvecs comeAmy or cotonAno                             Page 5 of 76
+* Pubilg FORT ST. VRAIN NUCLEAR CENERATING STATION Issue 1 rusuc sanvecs comeAmy or cotonAno Page 5 of 76
-'O                                                                                              '
+'O ALERT CLASS DESCRIPTION:
-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.
-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                                    .
+(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.
-confirmatory radiation monitoring if required, and (2)       provide offsite authorities current status information.
+O
-O                                                                                                                           .
+.g d
-                                                                                                         . .g    .
+1
-d 4
+i O
-* 1 i
+V 4
-OV                   .
+MIDl372 22 243
-MIDl372 22 243
-DERP Section 4 Attachment A FORT ST. VRAIN NUCLEAR GENERATING STATION      Issue 1 OPublic Service
+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
+* 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                                                       -
+Unusual events are in process or have occurred which indicate a potential degradation of tb? level of safety of the plant.
-systems occurs.
+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,                                                                   .
+(1) assure that the first step in any response later found to s
-(2)       bring the operating staff to a state of readiness, and (3)       provide systematic handling of unusual event information and decision-making.
+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  .
+t PoMM(01372 22 3083 '
-PoMM(01372 22 3083 '
-DERP Section 4 Attachment A Pubila                            FORT ST. VRAIN NUCLEAR GENERATING STATION               Issue 1 0 Service
+DERP Section 4 Attachment A 0 Service
-* PusuC saRVDCE COMPANY OF COL.ORADO                                                    Page 7 of 76 0                                                                                           .
+* 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          .
+NON-EMERGENCY EVENT:
-CLASS DESCRIPTION:
+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                 -
+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.
-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",
+(1)
-e
+To ensure compliance with 10CFR Part 50,72(b)(1) "One-hour reports",
-* o              ,
+e o
 FORMIDl372 22 3M3
-                                    ------y  y .-          -m     -. s                                            ,e   %
+------y y
+-m s
+-e-
+,e w
+w-v
-DERP Section 4 Attachment A FORT ST. VRAIN NUCLEAR GENERATING STATION                                         Issue 1 OPublic SerVICO'                                         PusuC SERVICE COMPANY OF COLORADO                                                 Page 8 of 76 O
+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:
+NON-EMERGENCY EVENT:
-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                                                                                   -
+FOUR-HOUR REPORT CLASS DESCRIPTION:
-of any of the items / situations identified within this procedure as 4 Hour Reports.
+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)        .
+(1)
-                                                   "Four-hour reports".
+To ensure compliance with 10CFR Part 50.72(b)(2)
-O                                                                                                                                                          .
+"Four-hour reports".
-d FORMtol372 22 3M3
+O d
+FORMtol372 22 3M3
-DERP Section 4 Attachment B1 Publia                                                                  FORT ST. VRAIN NUCLEAR GENERATING STATION       Issue 1 0 Service
+DERP Section 4 Attachment B1 0 Service
-* PusuC SERVICE COMPANY OF COLORADO                                                                                   Page 9 of 76 O                                                                                                                     '
+* 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 /
+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.
+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.
+Bl.2 Evacuation of control Inability to monitor shutdown room accompanied by count rate.
-f                      inability to locally
+f inability to locally
-\
+\\
-control shutdown systems                                                                                                     ,
+control shutdown systems within I hour.
-within I hour.
+o PORM 101 F12 + 22 3M3
-o                                                                                                                                                      -
-PORM 101 F12 + 22 3M3
-DERP Section 4 Attachment B1 Publia            FORT ST. VRAIN NUCLEAR CENERATING STATION                                           Issue 1 0 Service
+DERP Section 4 Attachment B1 0 Service
-* Pusue sanvoca COMPANY OF COLORADO                                                                           Page 10 of 76 O                                                                                                                        Page 2 of 5 EETIVITY NOTIFICATION OF UNUSUAL EVENJ Emergency Action Level
+* 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 /
-Typical Indication /
+~
 Initiatino Event _ _ _
-Bl.3 Evacuation of Control Room                           As deemed necessary by anticipated or required                         Shift Supervisor.
+Bl.3 Evacuation of Control Room As deemed necessary by anticipated or required Shift Supervisor.
 with control of shutdown systems established from local stations.
-O                                                                                                                                                   .
+O a
-                                                                                                                                 #    a 4
+f~~\\
-f~~\                                                                                                                                                      .
+U PORM(D)372 213M3
-U                                 .
-PORM(D)372 213M3
-=.-   .   .    -.-_      ___ - -._- -- __-               .    ---.         .. _              .     . - - . - .        -.
+=.-
-DERP Section 4 Attachment B1 FORT ST. VRAIN NUCLEAR GENERATING STATION            Issue 1 OPubilg   Service
+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                                                                           '
+* 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 /
+Emergency Action Level Typical Indication /
-Initiating Event Bl.4 Any deviation from                                Any deviation from a Tech-                       -
+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).
-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,                  ,
+health and safety, and no action consistent with Technical Specifications wnich can provide adequate or equivalent protection is immediately apparent.
-as a minimum, by a senior licensed operator.)
+(The action should be epproved, as a minimum, by a senior licensed operator.)
 B1.5 Any event or condition that results in the Q
-V condition of the plant, including its principle                                                                   ,
+condition of the plant, V
-safety barriers being                                               .
+including its principle safety barriers being seriously degraded; or results in the plant being:
-seriously degraded; or results in the plant being:
+a) In an unanalyzed a) As determined.
-a) In an unanalyzed                                                '
+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) As determined.
+of the plant; or, c) In a condition c) As determined, not covered by the plant's operating and i
-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.
+emergency operating procedures, n
-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 Attachment 81 Pubil?,               FORT ST. VRAIN NUCLEAR GENERATING STATION               Issue 1 OService*                     PusuC ssRVlCE COMPANY OF COLORADO                      Page 12 of 76 O                                                                               ' '
+DERP Section 4 1 OService*
-Page 4 of 5 REACTIVITY                             .
+Pubil?,
-ONE HOUR NON-EMERGENCY EVENT (sj                                                   !
+FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC ssRVlCE COMPANY OF COLORADO Page 12 of 76 O
-Emergency Action Level                           'ypical Indication /
+Page 4 of 5 REACTIVITY ONE HOUR NON-EMERGENCY EVENT (sj Emergency Action Level
-lnitiating Event                                                i Bl.6 Any event that compromises                  a) Fire posing undue                                            l 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.                                                                               '
+'ypical Indication /
-O                                                                                                                           .
+lnitiating Event i
-e
+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.
-* l l
+i radioactive releases.
-                                                                                                                            -
+O e
-PoRM(D)372 22 3843 1
+l 0
-                                                                   ,           .      -                                   f _   _.-
+PoRM(D)372 22 3843 1
+f
 l
-}                                                                                   DERP Section 4 Attachment B1 Pubilg               FORT ST. VRAIN NUCLEAR GENERATING STATION           Issue 1 0 service
+}
-* Pusuc SERV CE COMPANY OF COLORADO                   Page 13 of 76 Page 5 of 5 REACTIVITY                            ,
+DERP Section 4 Attachment B1 0 service
-FOUR HOUR NON-EMERGENCY EVENT (s)
+* 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 /
+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.
+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             .
+Engineered Safety Feature, including the a)
-protective action takes place, nor is required, b)    Actuation of the afore-mentioned systems which result from, and are a    -
+Only one of three channels Plant Protective System.
-s                                                            part of, the planned                  .
+tripped manually or auto-matica11y, but no final protective action takes place, nor is required, b)
-sequence during surveil-lance testing.
+Actuation of the afore-mentioned systems which result from, and are a s
-Bl.8 Any event or condition that alone could have                                        '
+part of, the planned sequence during surveil-lance testing.
-prevented the fulfill-ment of the safety function of structures or systems that are needed to:
+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.
+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.
-O                                                                                                      -
+O V
-V           .
 FOftM(D)372 22 3643
-  -   -  -- ___-                   - . - - _ _ .              --   . - . .       - . . . .     - . -     =   .        . _ -        -
+=
-DERP Section 4 Attachment B2 Pubilg                   FORT ST. VRAIN NUCLEAR CENERATING STATION                    Issue 1 O Service
+DERP Section 4 Attachment B2 O Service
-* PusuC ssRVICE COEPANY OF COLORADO                            Page 14 of 76 O                                                                                            ~
+* Pubilg FORT ST. VRAIN NUCLEAR CENERATING STATION Issue 1 PusuC ssRVICE COEPANY OF COLORADO Page 14 of 76 O
-Page 1 of 5 PRIMARY SYSTEM ALERT EAL Emergency Action level                                Typical Indication /
+Page 1 of 5
-Initiating Event B2.1 Calculated bulk core                                  CMG-4.                                                 -
+~
+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.
+B2.2 Non-isolable primary Shift Supervisor coolant leakage through a determination that laakage steam generator REHEAT is non-isolable, or EES section.
-.3 Fire affecting or                                     a) Fire pump 1A start;                          .
+.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.
-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.                                   .
+c) Various alarms according to affected safety x
-d) Shift Supervisor determines fire beyond capability of station staff. ,     ,
+system.
-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                       .
+d) Shift Supervisor determines fire beyond capability of station staff.,
-meter readings on area or process monitors.
+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.
 t
-     '')                                                                                                                             .
+'')
-    \~-)                    .
+\\~-)
 FORM (D13T2 22 3M3
-DERP Section 4 Attachment B2 Pubila             FORT ST. VRAIN NUCLEAR GENERATING S1 ATION                                      lssue 1 0 Service
+DERP Section 4 Attachment B2 0 Service
-* Pusuc sanvr. courAny or cotonAno                                                             Page 15 of 76 O                                                                                                     Page 2 of 5 PRIMARY SYSTEM ALERT EAL Emeroency Action Level                                                 Typical Indication /
+* Pubila FORT ST. VRAIN NUCLEAR GENERATING S1 ATION lssue 1 Pusuc sanvr. courAny or cotonAno Page 15 of 76 O
-Initiating Event B2.5 Radiological effluents                                                a) RIS 7324-1 indicating                      .
+Page 2 of 5 PRIMARY SYSTEM ALERT EAL Emeroency Action Level Typical Indication /
-exceed 10 times technical                                            22.5 x 10 8 pCi/cc specifications instantan-eous limits,                                                     b) RIS 7324-2 indicating
+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
-                                                                                                ~
+~
 .5 x 10 8 pC1/cc c) RIS 7325-1 Indicating
-                                                                                                ~
+~
-.0 x 10 ' pCi/cc d) RIS 7325-2 indicating
+.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                          ,
+~
-e) RIS 73437-1 indicating
-                                                                                                ~
 .0 x 30 ' pC1/cc I-131.
-f) RIS 4802 indicating                      -
+f) RIS 4802 indicating 2 7.0 x 10'' pC1/cc I-131.
-7.0 x 10'' pC1/cc I-131.
 g) RIS 4803 indicating,
-                                                                                                  ~
+~
-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 hour.
+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 hour.
 i FORM (D)372 22 3043
-DERP Section 4 Attachment B2 FORT ST. VRAIN NUCLEAR GENERATING STATION                           Issue 1 0Pubilg $9fVICO'            Pusuc sERWCE COMPANY OF COLORADO                                   Page 16 of 76 PRDIARY SYSTEM NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level                              Typical Indication /
+DERP Section 4 Attachment B2 0Pubilg FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1
-Initiating Event B2.7 Any radiological                                   Alarms on:                                                         -
+$9fVICO' Pusuc sERWCE COMPANY OF COLORADO Page 16 of 76 PRDIARY SYSTEM NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level Typical Indication /
-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                                                             .
+Initiating Event B2.7 Any radiological Alarms on:
-RIS 4803                                                             l RIS 73437-1, 2                                                       i B2.8 Indication of minor                                a) 25% increase in                                                   j fuel damage detected                                  circulating activity                                         l in primary coolant.                                   from previous                                                I conditions,                                                  l B2.9 Evacuation of Control                              As deemed necessary by Room anticipated or O                  required, with control of shutdown systems Shift Supervisor established from local stations.
+release resulting in RIS 7324-1 offsite effluent in RIS 7324-2 excess of Technical RIS 7325-1 Specification limits.
-                                                                                                      .g   .
+RIS 7325-2 RIS 4801 RIS 4802 RIS 4803 RIS 73437-1, 2 B2.8 Indication of minor a) 25% increase in j
-O U             .
+fuel damage detected circulating activity in primary coolant.
-FORM (Dl372 22 3M3
+from previous conditions, B2.9 Evacuation of Control As deemed necessary by O
-: w.                                     9- us.-w-w   y..   - + -*   -    m                        .a   --Aa
+Room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations.
+.g O
+U FORM (Dl372 22 3M3 w.
+-us.-w-w y..
+- + -*
+m
+.a
+--Aa
-DERP Section 4 Attachment B2 Pubils           FORT ST. VRAIN NUCLEAR GENERATING STATION          Issue 1 0SerVlCe*                   Pusuc saRVICE COMPANY OF COLORADO                 Page 17 of 76 O                                                                    ,      Page 4 of 5 PRIMARY SYSTEM ONE HOUR NON-EMERGENCY EVENT (s)
+DERP Section 4 Attachment B2 0SerVlCe*
-EAL Emergency Action Level                   Typical Indication /
+Pubils FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc saRVICE COMPANY OF COLORADO Page 17 of 76 O
-Initiating Event B2.10 Any event or condition                                                                     -
+Page 4 of 5 PRIMARY SYSTEM ONE HOUR NON-EMERGENCY EVENT (s)
-that results in the condition of the plant, including its principle safety barriers being seriously degraded; or                                '
+EAL Emergency Action Level Typical Indication /
-results in the plant being:
+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.
+a) In an unanalyzed a) As determined.
-condition that significantly                                                                 -
+condition that significantly compromises plant safety; b) In a condition b) Winds experienced in that is outside excess of FSAR design O
-compromises plant safety; b) In a condition                   b) Winds experienced in that is outside                     excess of FSAR design O                    the design basis of the plant; or, levels, c) In a condition                   c) As determined, not covered by the plant's                                           ,,   .
+the design basis
-operating and emergency operating procedures.
+: 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                           _
+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.
-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.
-l 0                                                                                                        -
+conmoim.m.ma
-conmoim.m.ma
-DERP Section 4 Attachment B2 FORT ST VRAIN NUCLEAR CENERATING STATION                              Issue 1 OPublic           Service
+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   .
+* 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 /
+E_AL Emergency Action Level Typical Indication /
-Initiating Event B2.12 Any unanticipated event                                Reactor scrams and automatic                                       -
+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:
-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)
-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                                  .
+Only one of three channels Plant Protective System, tripped manually or auto-matically, but no final protective action takes place, nor is required, b)
-place, nor is required, b)    Actuation of the afore-mentioned systems which rer?llt from, and are a part of, the planned Os                                                                                           sequence during surveil-                                  .
+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:
-lance testing B2.13 Any event or condition that alone could have                                                       #
+a) Remove residual heat a) Incorrect valve lineup which results in isolation of all reactor decay heat
-* prevented the fulfill-ment of the safety function of structures or systems that are needed to:
+: removal, b) Mitigate the conse-quences of an accident.
-a) Remove residual heat                      a) Incorrect valve lineup which results in isolation                                   _
+R U
-of all reactor decay heat removal, b) Mitigate the conse-quences of an accident.
+.1 l
-,    R                                                                                                                                                        -
-U                                   .
-                                                                                                                                                                               .1 l
 PomM(Dl372 22 3043
-        -_- ..-                  - , . - - - ,                                    -      _.                      ,. . - . - -        .- ,   ~.                   - - - - . . .
+~.
-DERP Section 4 Attachment 83 Pubil3                FORT ST. VRAIN NUCLEAR GENERATING STATION                        Issue 1 0 Service
+DERP Section 4 3 0 Service
-* Pusuc sanvece comeAmy or cotonAm                                 Page 19 of 76 O                                                                                                      '
+* 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                                 .
+Page 1 of 5 SECONDARY SYSTEM ALERT Emergency Action Level Typical Indication /
-ALERT Emergency Action Level                                     Typical Indication /
+Initiating Event B3.1 Calculated bulk core CMG-4.
-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.
+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;                           .
+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.
-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.,,
-d) Shift Supervisor determines fire beyond capability of station staff., ,     ,
+B3.4 Evacuation of control Inability to monitor shutdown room accompanied by count rate.
-B3.4 Evacuation of control                                 Inability to monitor shutdown room accompanied by                               count rate.
+inability to locally control shutdown systems within 1 hour.
-inability to locally control shutdown systems i
+i PoRMIDIT12 22 3ec l
-within 1 hour.
+g-a w
-PoRMIDIT12 22 3ec l
+er
-g-     -    --
+'T*try
-a        w         er 'T*try           > 'w           M          J       N'F'
+'w M
+J N'F'
-DERP Section 4 Attachment B3 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                            lssue 1 0Publia Service
+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                                                                                 '
+* 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.
+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.
-O                                                                                                                                              .
+O e
-e s
+s O
-O                                                                                                                                                  .
 PoRM(D)372 22 3ec
-DERP Section 4 Attachment 83 Public             FORT ST. VRAIN NUCLEAR GENERATING STATION                         Issue 1 0 Service
+DERP Section 4 3 0 Service
-* PusuC saRWCE COMPANY OF COLORADO                                              Page 21 of 76 O
+* 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)
+Page 3 of 5 SECONDARY SYSTEM ONE HOUR NON-EMERGENCY EVENT (s)
-Emergency Action Level                           Typical Indication /
+Emergency Action Level Typical Indication /
-Initiating Event 83.7 Any event or condition                                                                                     -
+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:
-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.
-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
-condition that significantly compromises plant safety; b) In a condition                      b) Winds experienced in that is outside                      excess of FSAR design the design basis O                                of the plant; or, levels, c) In a condition                      c) As determined, not covered by the plant's operating and                                                        #
+the design basis
-emergency operating procedures, 4
+: 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
+FORM (D)372 22 3SO s
-                    -         -     s                -     _-.          __        , _ _ --     ,                        . . . .     . -
-DERP Section 4 Attachment B3 FORT ST. VRAIN NUCLEAR GENERATING STATION                                 Issue 1 OPubila Service
+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                                                                                                                    ,
+* 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 /
+Emergency Action Level Typical Indication /
-Initiatino Event B3.8 Any unanticipated event                                                                      Reactor scrams and automatic                   -
+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.
-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:
-sequence, that results in manual or automatic actuation of an                                                                                 EXCEPTIONS:
+Engineered Safety Feature, including the a)
-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             <
+Only one of three channels Plant Protective System, tripped manually or auto-matically, but no final protective action takes place, nor is required.
-place, nor is required.                     4 b)     Actuation of the afore-                      ,
+b)
-mentioned systems which result from, and are a O                                                                                                              part of, the planned sequence during surveil-              .
+Actuation of the afore-mentioned systems which result from, and are a O
-lance testing B3.9 Any event or condition that alone could have                                                                                           ,,    ,
+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:
-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.
-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         .
+.o PoRM(D)F12 22 300
-PoRM(D)F12 22 300
-DERP Section 4 Attachment B3 Pubilg              FORT ST. VRAIN NUCLEAR GENERATING STATION              Issus 1 O Service
+DERP Section 4 Attachment B3 O Service
-* Pusuc sanvice courAmy or cotonApo                      Page 23 of 76 O                                                                                '
+* 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 /
+Emergency Action Level Typical Indication /
-Initiating Event B3.10 Any unplanned radiological                    As determined by analysis                    -
+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
-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 hour Non-Emergency event per 10CFR50.72(b)(2)(vi),
-                           " State Advisory". This in turn requires a 4 hour Non-Emergency event per 10CFR50.72(b)(2)(vi),
+NOTE:
-NOTE:    Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR20.403.
+Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR20.403.
 r e
-o                                                                                                               -
+o l
 FORM'D)372 22 300 l
-l I                                                    .     . . - . - . .
+I
-DERP Section 4 Attachment B4 Public              FORT ST. VRAIN NdCLEAR GENERATING STATION                                      Issue 1 0 SerVIC9'                   Pusuc sanwcs COMPANY OF COLORADO                                               Page 24 of 76 O                                                                                                Page 1 of 6 PCRV INTEGRITY ALERT Emergency Action Level                                 Typical Indication /
+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
-Initiating Event B4.1 Non-isolable primary                               Shift Supervisor                                                       -
+Page 1 of 6 PCRV INTEGRITY ALERT Emergency Action Level Typical Indication /
-coolant leakage through a                       determination that leakage steam generator REHEAT                           is non-isolable.
+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                                          .
+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.
-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
+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.
-* radioactive materials.
+Area Monitors (Increase by factor of 1,000 over normal.)
-Area Monitors (Increase by factor of 1,000 over normal.)                          Alarms with corresponding meter readings on area or process monitors.
+Alarms with corresponding meter readings on area or process monitors.
 FORM (D)372 22 3H3
-DERP Section 4 Attachment B4 Pub!!c            FORT ST. VRAIN NUCLEAR GENERATING STATION           Issue 1 O Service
+DERP Section 4 Attachment B4 O Service
-* Pusue saRVICs COMPANY OF COLORADO                                Page 25 of 76 O                                     '                         ~
+* Pub!!c FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusue saRVICs COMPANY OF COLORADO Page 25 of 76 O
-PCRV INTEGRITY ALERT Emergency Action Level                      Typical Indication /
+~
-Initiating Event d
+PCRV INTEGRITY ALERT Emergency Action Level Typical Indication /
-B4,4 Radiological effluents                 a) RIS 7324-1 indicating                        -
+Initiating Event B4,4 Radiological effluents a) RIS 7324-1 indicating d
-                                                                       ~
+~
-                   exceed 10 times technical             22.5 x 10 8 uti/cc i                      specifications instantan-eous limits,                      b) RIS 7324-2 indicating
+exceed 10 times technical 22.5 x 10 8 uti/cc i
-                                                                       ~
+specifications instantan-eous limits, b) RIS 7324-2 indicating
+~
 .5 x 10 8 uti/cc c) RIS 7325-1 indicating
-                                                                       ~
+~
-;                                                           27.0 x 10 ' vC1/cc j                                                       d) RIS 7325-2 indicating
+.0 x 10 ' vC1/cc j
-'                                                                      ~
+d) RIS 7325-2 indicating
+~
 .0 x 10 ' pCi/cc e) RIS 73437-1 indicating
-                                                                       ~
+~
 .0 x 10 ' uCi/cc I-131.
-f) RIS 4802 indicating                       -
+f) RIS 4802 indicating
-                                                                         ~
+~
-l                                                           2 7.0 x 10 ' pCi/cc I-131.
+l 2 7.0 x 10 ' pCi/cc I-131.
-                                                       g) RIS 4803. indicating
+g) RIS 4803. indicating 3
-                                                                         ~
+~
 2.5 x 10 8 uCi/cc I
 l l
-Q                                                                                                 .
+Q 1
-V           .
+V
 .g FORM (D)372 22 3843
-                                                                           /
+/
-                                                                 ,.Y.            .            --
+,.Y.
-  . __       -.           - -       -           ..               .                -=               ..
+-=
-DERP Section 4 Attachment B4                        l Public             FORT ST. VRAIN NUCLEAR GENERATING STATION                                               Issue 1                             l OService*                  Pusuc senveces comeAmy or cotonApo                                                      Page 26 of 76 O                                                                                                   ~
+DERP Section 4 Attachment B4 OService*
-Page 3 of 6 PCRV INTEGRITY NOTIFICATION OF UNUSUAL EVENT Emergency Action Level                                                  Typical Indication /
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 l
-Initiating Event NONE IDENTIFIED                                                                                                l s  .
+Pusuc senveces comeAmy or cotonApo Page 26 of 76 O
-l o                                                                                                                                                           -
+Page 3 of 6
-FORM (Dl372 22 3043
+~
-       -,       -             ~ -.-                 _ . . _ . _ _ . . _ _ . , _ , . . - ,
+PCRV INTEGRITY NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
+Initiating Event NONE IDENTIFIED l
+s l
+o FORM (Dl372 22 3043
+~
-DERP Section 4 Attachment B4 Public               FORT ST. VRAIN NUCLEAR GENERATING STATION                 Issue 1 0 Service
+DERP Section 4 Attachment B4 0 Service
-* Pusuc senvece courAmy or cotonAno                         Page 27 of 76 O                                                                           ,
+* 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 /
+Emergency Action Level Typical Indication /
-Initiating Event B4.5 Any event or condition                                                                                   -
+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:
-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.
-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.
-condition that significantly                                                                            -
+A of the plant; or c) In a condition c) As determined, not covered by the plant's operating and emergency operating procedures.
-compromises plant safety; b) In a condition                    b) Winds experienced in that is outside                         excess of FSAR design the design basis                        levels.
+l O
-A                         of the plant; or                                                                          .
+%.J FORM (D)372 22 3043
-c) In a condition                    c) As determined, not covered by the plant's                                                    ,
-operating and emergency operating procedures.
-l l
-O
-%.J l
-I FORM (D)372 22 3043
-DERP Section 4 Attachment B4 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION               lssur,1 0SerVICO* PusuC s&RVICE COMPANY OF COLORADO                                      Page 28 of 76 O
+DERP Section 4 Attachment B4 0SerVICO*
-    \s /                                                                                                                     .
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION lssur,1 PusuC s&RVICE COMPANY OF COLORADO Page 28 of 76 O
-Page 5 of 6                        i PCRV INTEGRITY                                                        I
+\\s /
-* l FOUR HOUR WON-EMERGENCY EVENT (s)
+Page 5 of 6 PCRV INTEGRITY FOUR HOUR WON-EMERGENCY EVENT (s)
-Emergency Action Level                        Typical Indication /                                        l Initiating Event B4.6 Any unanticipated event                  Reactor scrams and automatic                     -
+Emergency Action Level Typical Indication /
-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:
+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:
+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
+Feature, d ici rif rn the a)
-'                                                                       protective action takes                -
+Only one of three channels Plant Pre',.tive :/ stem.
-place, nor is required, b)     Actuation of the afore-mentioned systems which result from, and are a
+tripped manually or auto-matically,-but no final protective action takes place, nor is required, b)
-      'N                                                                part of, the planned sequence during surveil-                .
+Actuation of the afore-mentioned systems which result from, and are a
-lance testing i
+'N part of, the planned sequence during surveil-lance testing i
 FOMM(0)372 22 3643 6
-DERP Section 4 Attachinent B4 Public             FORT ST. VRAIN NUCLEAR GENERATING STATION        lssue 1 0 $9rVlC9'                  Pusuc senvece COMPANY OF COLORADO                Page 29 of 76 O
+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)
+V Page 6 of 6 PCRV INTEGRITY FOUR HOUR NON-EMERGENCY EVENT (s)
-Emergency Action Level                        Typical Indication /
+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 hour Non-Emergency event per 10CFR50.72(b)(2)(vi).                                                  -
+Initiating Event B4.7 a)
-b)    Any airborne radioactive release that exceeds 2 times the applicable concentrations of the limits specified in Os                       Appendix B, Table II of                                                 .
+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".
-CFR20 in unrestricted areas when averaged over a time neriod of one hour.
+This in turn requires a 4 hour Non-Emergency event per 10CFR50.72(b)(2)(vi).
-Any liquid effluent release c) that exceeds 2 times the limiting combined MPC (see Note 1 of Appendix B of 10CFR20) at the roint of entry.into
+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                                              .
+unrestricted area) for all radionuclides except tritium and dissolved noble-gases, when averaged over a time period of one hour.
-radionuclides except tritium and dissolved noble-gases, when averaged over a time period of one hour.
+NOTE:
-NOTE:    Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR10.403.
+Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR10.403.
 i
-  /-~                                                                                                .
+/-~
 FORM (Dl372 22 3843
-DERP Section 4       '
+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
-Attachment B5 Public         FORT ST, VRAIN NUCLEAR GENERATING STATION        Issue 1 0SerVlC9'                   PUBUC SERVICE COMPANY OF COLORAM                 Page 30 of 76 O
+Page 1 of 8 RADIOACTIVITY CONTROL ALERT Emergency Action Level Typical Indication /
-* 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.
-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        -
+B5.2 Damage to spent fuel a) Visual observation.
-a) Visual observation.
+resulting in release of radioactivity to plant b)' Area radiation monitor environs.
-resulting in release of radioactivity to plant            b)' Area radiation monitor environs.                             alarms.
+alarms.
-B5.3 High radiation levels or            CAM (s) alarm                             -
+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.
-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                ,
+Area Monitors (Increase by factor r3 of 1,000 over normal.)
-monitors.
+Alarms with correspending meter U
-FORM (D)772 22 3843                                                                               l
+readings on area or process monitors.
+FORM (D)772 22 3843
-DERP Section 4 Attachment B5 Public           FORT ST. VRAIN NUCLEAR GENERATING STATION            Issue 1 0$9TVIC9'                PUBUC SERVICE COMPANY OF COLORADO                    Page 31 of 76 Page 2 of 8 RADIOACTIVITY CONTROL ALERT Emergency Action Level                      Typical Indication /
+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                       .-
+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.
-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
+,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
-  ,3                                                      27.0 x 10'' pCi/cc I-131.
+l d I
-f) RIS 4802 indicating                       -
+FORM (D)772 22.%43
-7.0 x 10'' pCi/cc I-131, g) RIS 4803 indicating 2 2.5 x 10 2 pC1/cc O
-l d             .
-I 1
-FORM (D)772 22.%43
-DERP Section 4         l Attachment B5 Publia           FORT ST. VRAIN NUCLEAR GENERATING STATION           Issue 1 OService*                 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 /
+DERP Section 4 Attachment B5 OService*
-Initiating Event B5.5 Any radiological                          1. Alarms 01:                                   -
+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 /
-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                 -
+Initiating Event B5.5 Any radiological
-release resulting in                   with inatiility to prevent offsite effluent in                    discharge offsite.
+: 1. Alarms 01:
-I                      excess of Technical Specification limits,               b) As determined by station personr,el.
+release resulting in RIS 7324-1 offsite effluent in RIS 7324-2 excess of Technical RIS 7325-1 Specification limits.
-O(_,/     B5.7 Indication of minor                       a) 25% increase in                         .
+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.
-fuel damage detected                   circulating activity in primary coolant.                    from previous conditions.
+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.
 f
 i
 l l
-t'                                                                                                      .
+t' l
-l FORM (Dl772 22 3843
+FORM (Dl772 22 3843
-DERP Section 4 Attachment B5 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION             Issue 1 OSerVICe* 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 /
+DERP Section 4 Attachment B5 OSerVICe*
-Initiating Event B5.8 Serious fire at the                    a) Any of various alarms                         -
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC SERVICE COMPANY OF COLORADO Page 33 of 76 o
-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.
+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.
+B5.9 Any serious radiological As occurring.
-exposure of plant personnel                                                     -
+exposure of plant personnel or the transportation to offsite facilities of contaminated personnel who may have been injured.
-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                                                             .
+x call to be made in a timely manner.)
-timely manner.)
+B5.10 Accidents that may a) Abnormal radiation levels involve plant spent reported from cask.,
-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.
-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 Public           FORT ST, VRAIN NUCLEAR GENERATING STATION        Issue 1 O Service
+DERP Section 4 Attachment B5 O Service
-* Pusuc SERVICE COMPANY OF COLORADO                             Page 34 of 76 Page 5 of 8 RADIOACTIVITY CONTROL NOTIFICATION OF UNUSUAL EVENT Emergency Action Level                     Typical Indication /
+* 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                    --
+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:
-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
 d) RIS 6212 AND RIS 6213.
-NOTE:   Use ELC0 8.1.1 Technical Specification Limits
+NOTE:
-.   ,d                      as basis.                                                             ,
+Use ELC0 8.1.1 Technical Specification Limits
+,d as basis.
 i 1
 o I
 i i
-l I
+l FORM (D)372 22 3H3
-l l
-FORM (D)372 22 3H3
-DERP Section 4 Attachment B5 Public           FORT ST. VRAIN NUCLEAR GENERATING STATION           Issue 1 0 Service
+DERP Section 4 Attachment B5 0 Service
-* Pusuc senvece comeAny or cotonAno                  Page 35 of 76 A
+* 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)
-V                                                                             Page 6 of 8 RADIOACTIVITY CONTROL ONE HOUR NON-EMERGENCY EVENT (s)
+Emergency Action Level Typical Indication /
-Emergency Action Level                      Typical Indication /
+Initiating Event B5.12 Any event that compromises a) Fire posing undue safety of the plant, or personnel hazard.
-Initiating Event B5.12 Any event that compromises            a) Fire posing undue                              -
+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.
-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.
-                                                                             ~1
+~1
-(''~                                                                                                   .
+(''~
 N' FOftM(Ol372 22 3ec
-l DERP Section 4 Attachment B5 FORT ST. VRAIN NUCLEAR GENERATING STATION                                            Issue 1 0Public $9fVIC9'           PUBUC SERVICE COMPANY OF COLORADO                                                    Page 36 of 76
+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 RADIOACTIVITY CONTROL FOUR HOUR NON-EMERGENCY EVENT (s)
+~
-Emergency Action Level                                                          Typical Indication /
+Page 7 of 8 FOUR HOUR NON-EMERGENCY EVENT (s)
-Initiating Event B5.13 Any event or condition                                                                                                   -
+Emergency Action Level Typical Indication /
-that alone could have prevented the fulfill-ment of the safety function of structures or systems that are needed to:
+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          .
+a) Control the release of a) Liquid waste monitor setpoints radioactive material; or, raised for liquid waste release completed.
-sump release started. Setpoints not reset.
+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.
+A B5.14 Any event requiring the As occurring.
-V                  transport of a radio-actively contaminated person to an offsite medical facility for treatment.
+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.
+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.
 O v
 FORM (Dl372 22 3M3
-DERP Section 4 Attachment B5 Pubile                                                     FORT ST. VRAIN NUCLEAR GENERATING STATION                            Issue 1 0 SerVlCG*PusuC SERVICE COMPANY OF COLORADO                                                                                           Page 37 of 76 RADI0 ACTIVITY CONTROL FOUR HOUR NON-EMERGENCY EVENT (s)
+DERP Section 4 Attachment B5 0 SerVlCG*
-Emergent / Action level                                                                Typical Indication /
+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)
-Initiating Event B5.16 a) Any unplanned radio-                                                          As determined by analysis                                     --
+Emergent / Action level Typical Indication /
-logical release which              and evaluation does not constitute classification of a NOVE                                                                             3 will require notification to the Colorado Department                                                                             )
+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 hour 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                                                               ,
+b) Any airborne radioactive release that exceeds 2 times the applicable concentrations of the limits specified in O
-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. ,
+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                                                                  _
+unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour.
-and dissolved noble gases, when averaged over a time period of one hour.
+NOTE:
-NOTE:                 Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(2) of 10CFR20.403, o                                                                                                                                                           -
+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 Pubile              FORT ST, VRAIN NUCLEAR GENERATING STATION        Issue 1 0 service
+DERP Section 4 Attachment B6 0 service
-* PUSUC SERVICE COMPANY OF COLORADO                Page 38 of 76 Page 1 of 5 p
+* 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 /
+ALERT EAL Emergency Action level Typical Indication /
-Initiating Event B6.1 Calculated bulk core                      CMG-4                                       --
+Initiating Event B6.1 Calculated bulk core CMG-4 temperature reaches 760 'F without PCRV liner cooling.
-temperature reaches 760 'F without PCRV liner cooling.
+B6.2 Damage to spent fuel a) Visual observation.
-B6.2 Damage to spent fuel                      a) Visual observation.
+resulting in relesse of radioactivity to plant b) Area radiation monitor
-resulting in relesse of radioactivity to plant               b) Area radiation monitor environs,                                  alarms.
+: environs, alarms.
-.3 Actual or attempted loss,                 As reported and/or confirmed             .
+.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.
-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
-irradiated spent fuel that have the potential to degrade public health and safety G               (10 CFR 73.71).
+(10 CFR 73.71).
-i l
+i FORM (D)772 22 3643 eaY
-l FORM (D)772 22 3643 eaY
-DERP Section 4 Attachment B6 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION                 Issue 1 O $9fVICO' Pusuc ssRVICE COMPANY OF COLORADO                                       Page 39 of 76 1
+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-U .
+,q-1 U
-Page 2 of 5 FUEL 1                                                                                          '
+Page 2 of 5 FUEL 1
-NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level                       Typical Indication /
+NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level Typical Indication /
-Initiating Event B6.4 Indication of minor                         a) 25% increase in                                          -
+Initiating Event B6.4 Indication of minor a) 25% increase in fuel damage detected circulating activity in primary coolant.
-fuel damage detected                       circulating activity in primary coolant.                        from previous conditions.
+from previous conditions.
-B6.5 Accidents involving                         a) Abnormal radiation levels plant spent fuel                           reported from cask, shipments or plant radioactive                      b) Cask breached.
+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                    -
+c) As occurring or reported by shipper.
-by shipper.
 I
-!O                                                                                                            .
+!O t
-t i
+i i
-i
+l
-* 4 l
 a i
-b
+bO)
-* O)            -
 FORM (D)372 22 384 -
-DERP Section 4 Attachment B6 PubilC          FORT ST. VRAIN NUCLEAR GENERATING STATION       Issue 1 0SerVIC9'               PUBUC SERVICE COMPANY OF COLORAM                Page 40 of 76 Page 3 of 5 ONE HOUR NON-EMERGENCY EVENT (s)
+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 /
+EAL Emergency Action Level Typical Indication /
-Initiating Event B6.6 Any deviation from                  Any deviation from a Tech-                  -
+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).
-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
+public health and safety, and no action consistent with Technical Specifica-tions which can provide adequate or equivalent protection is immediately apparent.
-* with Technical Specifica-tions which can provide adequate or equivalent protection is immediately apparent.   (The action should           -
+(The action should be approved, as a minimum, by a senior licensed operator.)
-be approved, as a minimum, by a senior licensed operator.)
+B6.7 Fire involving As occurring or reported shipping cask, breach by shipper.
-B6.7 Fire involving                      As occurring or reported shipping cask, breach           by shipper.
+\\m not determined.
-  \m                  not determined.                                                           .
 s 1
 FOM(ol372 22 3643
-DERP Section 4 Attachment B6 FORT ST. VRAIN NUCLEAR GENERATING STATION               Issue 1 OPublic SerVICG'           PUBUC SERVICE COMPANY OF COLORADO                       Page 41 of 76
+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 /
+EAL Emergency Action Level Typical Indication /
-Initiating Event B6.8 Any event or condition                                                                     --
+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:
-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.
-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
-condition that significantly                                                                   -
+: levels, of the plant; or, c) In a condition c) As determined, not covered by the plant's operating and emergency operating procedures.
-compromises plant safety; b) In a condition                          b) Winds experienced in that is outside                           excess of FSAR design the design basis                          levels, Os                 of the plant; or,                                                                 ,
+O FORM (Ol372 22 3H3
-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
+DERP Section 4 l
-* Pusuc sanvice comeAny or cotonApo                                   Page 42 of 76 O                                                           ,                           Page 5 of 5 FUEL FOUR HOUR NON-EMERGENCY EVENT (s)
+Attachment B6 l
-EAL Emergency Action Level                 Typical Indication /
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
-Initiating Event B6.9 Spent fuel shipping                   As occurring or reported vehicle delayed WITH              by shipper, media coverage.
+* Pusuc sanvice comeAny or cotonApo Page 42 of 76 O
-B6.10 Public protest of spent              As occurring or reported fuel shipment WITH media         by shipper, coverage.
+Page 5 of 5 FUEL FOUR HOUR NON-EMERGENCY EVENT (s)
-B6.11 Cask out of position,                As occurring or reported breach not determined.           by shipper.                                                  -
+EAL Emergency Action Level Typical Indication /
-j     .
+Initiating Event B6.9 Spent fuel shipping As occurring or reported vehicle delayed WITH by shipper, media coverage.
-FORM (olW2 22 3643
+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 FORT ST VRAIN NUCLEAR GENERATING STATION                                         Issue 1 0Public                              Service
+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                                                                                                                                                       '
+* PUBUC SERVICE COMPANY OF COLORADO Page 43 of 76 O
-MOISTURE INGRESS ALERT EAL Emergency Action level                                                                                          Typical Indication /
+MOISTURE INGRESS ALERT EAL Emergency Action level Typical Indication /
-Initiating Event B7.1 High radiation levels or                                                                                       CAM (s) alarm                                -
+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.
-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.
+Area Monitors (Increase by factor of 1,000 over normal.)
-I O                                                                                                                                                                                    .
+Alarms with corresponding meter readings on area or process monitors.
-                                                                                                                                                                 .g  .
+I O
-FORM (Ol372 22 3843
+.g 6
+FORM (Ol372 22 3843
-l                                                                            DERP Section 4 Attachment B7 FORT ST. VRAIN NUCLEAR GENERATING STATION          Issue 1 OPublic $9fVlCe*    Pusuc senvecs COMPANY OF COLORADO                  Page 44 of 76 O                                                               '
+l
-MOISTURE INGRESS NOTIFICATION OF UNUSUAL EVENT EAL Emergency Action Level                  Typical Indication /
+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 O
-O                                                                                            l FORM (D)372 22 3M3 l
+FORM (D)372 22 3M3
-I
-DERP Section 4 Attachment B7 Public             FORT ST. VRAIN NUCLEAR GENERATING STATION         Issue 1 O $9fVIC9' PusuC saRVICs COMPANY OF COLORADO                                 Page 45 of 76 O
+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 /
+EAL Emergency Action Level Typical Indication /
-Initiating Event B7.2 Any deviation from                     Any deviation from a Tech-                    -
+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),
-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            .
+public health and safety, and no action consistent with Technical Specifica-tions which can provide adequate or equivalent protection is immediately apparent.
-be approved, as a minimum, by a senior licensed operator.)
+(The action should be approved, as a minimum, by a senior licensed operator.)
-O                                                                                                                  .
+O e
-e i
+i O
-l OU FORM lD1372 22 3643
+U FORM lD1372 22 3643
-DERP Section 4 Attachment B7 Public             FORT ST. VRAIN NUCLEAR GENERATING STATION                Issue 1 OService*                   Pusuc sanvice comeAny or cotonAno                        Page 46 of 76 O
+DERP Section 4 Attachment B7 OService*
-* MOISTURE INGRESS FOUR HOUR NON-EMERGENCY EVENT (s)
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Pusuc sanvice comeAny or cotonAno Page 46 of 76 O
-EAL Emergency Action Level                    Typical Indication /
+MOISTURE INGRESS FOUR HOUR NON-EMERGENCY EVENT (s)
-Initiating Event B7,3 Any unanticipated event                  Reactor scrams and automatic                         -
+EAL Emergency Action Level Typical Indication /
-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:
+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                    .
+Engineered Safety Feature, including the a)
-place, nor is required, b)     Actuation of the afore-mentioned systems which result from, and are a part of, the planned O'                                                          sequence during surveil-                    .
+Only one of three channels Plant Protective System, tripped manually or auto-matically, but no final protective action takes place, nor is required, b)
-lance testing 1
+Actuation of the afore-mentioned systems which result from, and are a O'
-l l
+part of, the planned sequence during surveil-lance testing 1
-                                                                                                               .I I
 l l
+.I l
 FORM (D)712 22.;M43
-DERP Section 4 Attachment 88 Public                FORT ST, VRAIN NUCLEAR GENERATING STATION           Issue 1 OService*                     PusuC SERVICE COMPANY OF COLORADO                   Page 47 of 76 O                                                                      '
+DERP Section 4 8 OService*
-PLANT PROTECTIVE SYSTEM ALERT Emergency Action Level                         Typical Indication /
+Public FORT ST, VRAIN NUCLEAR GENERATING STATION Issue 1 PusuC SERVICE COMPANY OF COLORADO Page 47 of 76 O
-Initiating Event B8,1 Evacuation of control                     Inability to .nonitor shutdown                            -
+PLANT PROTECTIVE SYSTEM ALERT Emergency Action Level Typical Indication /
-room accompanied by                  count rate.
+Initiating Event B8,1 Evacuation of control Inability to.nonitor shutdown room accompanied by count rate.
 inability to locally control shutdown systems within 1 hour.
-O                                                                                   .
+O
-                                                                                   .e   .
+.e l
 l l
-l l
+l O
-O FORM (D)372 22 3H3
+FORM (D)372 22 3H3
-DERP Section 4 Attachment B8 FORT ST. VRAIN NUCLEAR GENERATING STATION      Issue 1 0 Pubilg                          service
+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                                                                                                  ''
+* PusuC SERVICE COMPANY OF COLORADO Page 48 of 76 O
-PLANT PROTECTIVE SYSTEM NOTIFICATION OF UNUSUAL EVENT Emergency Action Level                   Typical Indication /
+PLANT PROTECTIVE SYSTEM NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
-Initiating Event B3.2 Evacuation of Control               As deemed necessary by                         -
+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.
-Room anticipated or              Shift Supervisor required, with control of shutdown systems established from local stations.
 T j
-O                                                                                                                         .
+O
-                                                                                                      .e  .
+.e b
-b                                                                                                                                a U
+a U
 FORM (Ol372 22 3043 j_'
-DERP Section 4 Attachment 88-Public           FORT ST. VRAIN NUCLEAR GENERATING STATION          Issue 1 0 SerVICO*PUBUC SERVICE COMPANY OF COLORADO                                 Page 49 of 76 O                                                                 '
+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 /
+Emergency Action Level Typical Indication /
-Initiating Event B8.3 Any deviation from                    Any deviation from a Tech-                       -
+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).
-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            .
+public health and safety, and no action consistent with Technical Specifica-tions which can provide adequate or equivalent protection is immediately apparent.
-be approved, as a minimum, by a senior licensed operator.)
+(The action should be approved, as a minimum, by a senior licensed operator.)
-.4 Any event that results                a) Loss of significant O,                in a major loss of emergency assessment portion of Control Room indication.                              .
+.4 Any event that results a) Loss of significant O,
-capability, offsite response capability,              b) Loss of Emergency or communications                     Notification System, capability.
+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.
-                                                                                                 .
+(c) 1 I
-(c) 1 I
+L ron m oi m.22 3.o l
-L     ron m oi m .22 3.o                                                                                   1 l                                                                                                          \
+\\
-l                                             -     -            .                   .       .          -.
+l
-DERP Section 4 Attachment B8 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION       Issue 1 0 service
+DERP Section 4 Attachment B8 0 service
-* Pusuc senvics COMPANY OF COLORADO               Page 50 of 76 PLANT PROTECTIVE SYSTEM FOUR HOUR NON-EMERGENCY EVENT (s)
+* 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 /
+Emergency Action Level Typical Indication /
-Initiating Event B8.5 Any event, found while                Determination as result of                                             -
+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.
-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.
-plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that signifi-                                                   ,
+O t
-cantly compromises plant safety.
+n U
-O                                                                                            .
-t n
-U          .
 FORM (o)372 3 3643
-DERP Section 4 Attachment B9 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION                                                     Issue 1 0$9fVIC9'               Pusuc sanvtes COMPANY OF COLORADO                                                             Page 51 of 76 a                                                                                                                    Page 1 of 4 FIRE ALERT Emergency Action Level                     Typical Indication /
+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
-Initiating Event B9.1 Fire affecting or                     a) Fire pump 1A start;                                                                      .
+Page 1 of 4 FIRE ALERT Emergency Action Level Typical Indication /
-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.
+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.
-.2 Evacuation of Control                 Inability to monitor shutdown Room accompanied by              count rate.
+.2 Evacuation of Control Inability to monitor shutdown Room accompanied by count rate.
 inability to locally p
-V control shutdown systems within 1 hour.                                                                                                            ,
+control shutdown systems V
+within 1 hour.
 s
 (~.
@@ Line 1,009: / Line 1,086: @@
 FORMtol372 22 3643
-DERP Section 4 Attachment 89 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION        Issue 1                   l OService*                                                                 Page 52 of 76 PUBUC SERVM:E COMPANY OF COLORADO Page 2 of 4
+DERP Section 4 9 OService*
-  .                                             FIRE NOTIFICATION OF UNUSUAL EVENT Emergency Action Level                      Typical Indication /
+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                        -
+Initiating Event 89.3 Fire within the a) Any of various alarms plant lasting more on Fire Control Alarm than 30 minutes.
-plant lasting more                   on Fire Control Alarm than 30 minutes.                      Panel; b) Fire Pump 1A auto start; c) Verbal reports.
+Panel; b) Fire Pump 1A auto start; c) Verbal reports.
-.4 Evacuation of Control                  As deemed necessary by Room anticipated or               Shift Supervisor                            -
+.4 Evacuation of Control As deemed necessary by Room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations.
-required, with control of shutdown systems established from local stations.
 (::)
 FORM (D)372 E 3843
-DERP Section 4 Attachment 89 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION         Issue 1 0 service
+DERP Section 4 9 0 service
-* PUBUC SERVICE COMPANY OF COLORADO                 Page 53 of 76 O                                                                  ,
+* 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 /
+Emergency Action Level
-Initiating Event 89.5 Any event that results                 a) Loss of significant                          -
+. Typical Indication /
-in a major loss of                    portion of Control Room emergency assessment                   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, offsite response capability, b) Loss of Emergency or communications Notification System.
 capability.
 c) Loss of all offsite communication systems.
-.6 Any event that compromises             a) Fire posing undue                       -
+.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
-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,               .
+conduct of plant activities, concentrations in excess
-gas releases, or                       Table I, Column 1.-
+/
+including fires, toxic of 10 CFR 20, Appendix B, gas releases, or Table I, Column 1.-
 radioactive releases.
-.7 Fire involving shipping                As occurring or repor3ed.
+.7 Fire involving shipping As occurring or repor3ed.
-cask, breach not                   by shipper, determined.
+cask, breach not by shipper, determined.
 l
-   ~~\                                                                                               -
+~~\\
 (G i
 FOHMIDl372 22 36C
 DERP Section 4
-                                                                           ' Attachment 89 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 OPublic   SGTVICO*       PUBUC SERVH:E COMPANY OF COLORADO                 Page 54 of.76 Page 4 of 4
+' Attachment 89 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 SGTVICO*
-,                                          FIRE FOUR HOUR NON-EMERGENCY EVENT (s)
+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 /
+Emergency Action Level Typical Indication /
 Initiating Event NONE IDENTIFIED
-                                                                        .c l
+.c O
-O            .
 FORM (01372 22 3sc
-DERP Section 4 Attachment B10 Public              FORT ST. VRAIN NUCLEAR GENERATING STATION           Issue 1                l G$9fVIC9'                  PUBUC SERWCE COMPANY OF CO'. ORAM                   Page 55 of 76          i O                                                                                                       ;
+DERP Section 4 Attachment B10 G$9fVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 l
-ELECTRIC p0WER ALERT Em gency Action Level                        Typical Indication /
+PUBUC SERWCE COMPANY OF CO'. ORAM Page 55 of 76 i
-Initiating Event B10.1 Fire affecting or                      a) Fire pump 1A start.                          -
+O ELECTRIC p0WER ALERT Em gency Action Level Typical Indication /
-potentially affecting equipment, components,              b) Fire Control Alarm or instrumentation                       Panel.
+Initiating Event B10.1 Fire affecting or a) Fire pump 1A start.
-required to maintain a safe shutdown condition.           c) Various alarms according to affected safety system, d) Shift Supervisor determines fire beyond capability                 ,
+potentially affecting equipment, components, b) Fire Control Alarm or instrumentation Panel.
-of station staff.
+required to maintain a safe shutdown condition.
-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 hours,                 alarm accompanied by 4 KV bus O                                                   undervoltage, 480V bus under-voltage, AJ Diesel Trouble al a rnis .
+c) Various alarms according to affected safety
-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 hours,                           showing no voltage.' #                              f I
+: system, d) Shift Supervisor determines fire beyond capability of station staff.
-o                                                                                                  -
+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 hours, 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 hours, showing no voltage.' #
+f I
+o
+~
 FORM (01372 22 3H3
-l DERP Section 4 Attachment BIO Pubilg                                          FORT ST. VRAIN NUCLEAR CENERATING STATION                      !ssue 1 0SerVICG* Pusuc sanvu:a COMPANY OF COLM                                                                               Page 56 of 76 O                                           -
+l DERP Section 4 Attachment BIO 0SerVICG*
-Page 2 of 4 ELECTRIC p0WER NOTIFICATION OF UNUSUAL EVENT Emergency Action Level                                                                Typical Indication /
+Pubilg FORT ST. VRAIN NUCLEAR CENERATING STATION
-Initiating Event B10.4 Loss of offsite power OR                                             -
+!ssue 1 Pusuc sanvu:a COMPANY OF COLM Page 56 of 76 O
-KV OCB trips AND RAT                     -
+Page 2 of 4 ELECTRIC p0WER NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
-onsite AC power                                         undervoltage/lossTf power ct.pability.                                           alarm accompanied by 4 KV bus undervoltage. OR both Diesel Generators AND the ACM Diesel inoperabTe'.
+Initiating Event B10.4 Loss of offsite power OR 230 KV OCB trips AND RAT onsite AC power undervoltage/lossTf power ct.pability.
-B10,5 Indication or alarms                                                            Data Logger Alarm / Alarm on radiological effluent                               Summary indication of non-monitors not functional,                               operational alarm or indication on:
+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
+DERP Section 4 Attachment B10 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
- !                                       FORT ST. VRAIN NUCLEAR GENERATING STATION                                  Issue 1 OPublic Service
+* PusuC SERVICE COMPANY OF COLORADO Page 57 of 76 0
-* 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 /
+Emergency Action Level Typical Indication /
-Initiating Event                                                             l B10.6 Any event or condition                                                                                                 -
+Initiating Event B10.6 Any event or condition that results in the condition of the plant,
-that results in the condition of the plant,                                                                                                       )
+)
-including its principle                                                                                                       ;
+including its principle safety barriers being 1
-safety barriers being                                                                                                         1 seriously degraded; or                                                                                                        l results in the plant being:                                                                                                   ;
+seriously degraded; or l
-i a) In an unanalyzed                                 a) As determined, condition that significantly                                                                                                -
+results in the plant being:
-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 capability, offsite response capability, indication.
+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
-b) Loss of Emergency or communications                                    Notification System, capability, c) Loss of all offsi,te, communication systems.
+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 FORT ST. VRAIN NUCLEAR GENERATING STATION                       Issue 1 OPublia
+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
+$9fVICO' PusuC saRVN:s COMPANY OF COLORADO Page 58 of 76 O
-* ELECTRIC POWER FOURHOURNON-EMERGENCYEVENT(sj Emergency Action Level                                           Typical Indication /
+ELECTRIC POWER FOURHOURNON-EMERGENCYEVENT(sj Emergency Action Level Typical Indication /
-Init.ating Event                _
+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:
-B10.8 Any unanticipated event                                    Reactor scrams and automatic                              -
+Engineered Safety Feature, including the a)
-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:
+Only one of three channels Plant Protective System.
-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             .
+tripped manually or auto-matically, but no final protective action takes place, nor is required, b)
-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-              .
+Actuation of the afore-mentioned systems which result from, and are a O
-lance testing.
+part of, the planned sequence during surveil-lance testing.
-                                                                                                                                                                          .4   .
+.4
 ?
 O PORMtD)372 22 3M3
-DERP Section 4 Attachment Bil Public              FORT ST. VRAIN NUCLEAR GENERATING STATION                            Issue 1 0 Service
+DERP Section 4 Attachment Bil 0 Service
-* Pusuc saRVICE COMPANY OF COLORADO                                                      Page 59 of 76                         l O
+* 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 /
-V                                                                                          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:
-Initiating Event B11.1 Severe natural phenom-                                                                                               -
+a) earthquake exceeding a) Seismic recorder operate Operating Basis (2.05 g)
-enon being experienced or projected, such as:
+Earthquake levels; (probably cannot be determined within two hours - call to be made in a timely manner.)
-a) earthquake exceeding                   a) Seismic recorder operate Operating Basis                              (2 .05 g)
+b) flood near design b) As Reported level; or, c) tornado striking facility.
-Earthquake levels; (probably cannot be determined within two hours - call to be made in a timely manner.)                                                                                 .
+c) As Reported I
-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 Pubila                     FORT ST. VRAIN NUCLEAR GENERATING STATION                        !ssue 1 0 Service
+DERP Section 4 Attachment Bil 0 Service
-* Pusuc sanvece comeAny or cote                                     P89e 60 of 76 O
+* Pubila FORT ST. VRAIN NUCLEAR GENERATING STATION
-* Page 2 of 4 NATURAL PHENOMENON NOTIFICATION OF UNUSUAL EVENT Emergency Action Level                                               Typical Indication /
+!ssue 1 Pusuc sanvece comeAny or cote P89e 60 of 76 O
-Initiating _ Event B11.2 Natural phenomenon that                                                                                                ..
+Page 2 of 4 NATURAL PHENOMENON NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
-may be experienced or threatened that                                                                                                    I represent risks beyond normal levels:
+Initiating _ Event B11.2 Natural phenomenon that may be experienced or threatened that represent risks beyond normal levels:
-l a) earthquake                                           a) Seismic Recorder operates                                  I J
+a) earthquake a) Seismic Recorder operates J
-b) floods                                               b)-d) As visually observed                                    i by, or reported to,                                   i c) tornados                                                     station personnel,                                    i l
+b) floods b)-d) As visually observed by, or reported to, i
-d) extremely high winds                                                                                               j i
+c) tornados station personnel, i
-O                                                                               .
+d) extremely high winds j
-j   .
+i O
-FORM (D)lrf2 22 3843
+j FORM (D)lrf2 22 3843
-* DERP Section 4 Attachment B11 1
-Pubil3                    FORT ST. VRAIN NUCLEAR GENERATING STATION                                   1ssue 1             l 0 $9tVIC9'                       Pusuc senvecs COMPANY OF COLORADO                                           Page 61 of 76 O
+DERP Section 4 Attachment B11 0 $9tVIC9' Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 1 l
-* Page 3 of 4 RATURAL PHENOMENON ONE HOUR NON-EMERGENCY EVENT (s)
+Pusuc senvecs COMPANY OF COLORADO Page 61 of 76 O
-Emergency Action Level                                       Typical Indication /
+Page 3 of 4 RATURAL PHENOMENON ONE HOUR NON-EMERGENCY EVENT (s)
-Initiating Event B11.3 Any event or condition                                                                                               -
+Emergency Action Level Typical Indication /
-that results in the condition of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:
+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.
+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 the safety of the plant                              completing requisite O                             or significantly hampers site personnel in the assignments.                                               ,
+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
-performance of duties necessary for the safe conduct of plant activities.
+the safety of the plant completing requisite or significantly hampers assignments.
-                                                                                                                        . 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.
+site personnel in the performance of duties necessary for the safe conduct of plant activities.
-necessary for the safe                                   resulting in onsite.
+. 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.
-conduct of plant activities                              concentrations'in excess including--fires, toxic                                  of 10 CFR 20, Appendix B,
+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.
+~
+gas releases, or Table I, Column 1.
 radioactive releases.
-O                                                                                                                                               '
+O conmoim.m.see..
-conmoim.m.see ..
+/
-                                                                                                                 /
+~
-                       . , .      ~   ,.                    .                                                 .2
+.2
-DERP Section 4 Attachment 811 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                         Issue 1 0Pubil3Service
+DERP Section 4 11 0Pubil3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
-* Pusue sanwes courAmy or cotonAno                                                                 Page 62 of 76 l
+* Pusue sanwes courAmy or cotonAno Page 62 of 76 l
-* Page 4 of 4 NATURAL PHENOMENON FOUR HOUR NON-EMERGENCY EVENT (s)                                                                                         ,
+Page 4 of 4 NATURAL PHENOMENON FOUR HOUR NON-EMERGENCY EVENT (s)
-Emergency Action Level                                                         Typical Indication /
+Emergency Action Level Typical Indication /
 Initiating Event NONE IDENTIFIED t
-O                                                                                                           -
+O
-                                                                                                                                                .g .
+.g Iv FMM(D)372 22 3043
-v I
-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
+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 /
+Page 1 of 6 SECURITY ALERT Emergency Action Level Typical Indication /
-Initiating Event B12.1 Complete or imminent loss              As reported and/or confirmed                         -
+Initiating Event B12.1 Complete or imminent loss As reported and/or confirmed of physical control of by the LSO or by any member
-of physical control of            by the LSO or by any member facility,                          of the Security Force.
+: 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.
+B12.2 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                     .
+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 hours.
-l that an act of sabotage or        by the LSO theft will be attempted           or by any member of the within 48 hours.                  Security Force.
+Security Force.
-B12.4 Any act which has the                  As reported and/or confirmed O                      apparent intent of destroying or disrupting operation.
+B12.4 Any act which has the As reported and/or confirmed O
-by the LSO or by any member of the Security Force.
+apparent intent of by the LSO l
-l B12.5 Actual or attempted loss,              As reported and/or confirmed theft, diversion, or              by shipper, LSO, Control, Room, or                      -
+destroying or disrupting or by any member of the operation.
-sabotage of shipments of          any member of the Security force.
+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                                       .
+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.
-for affecting the safe            or by any member of the or routine operation of           Security Force.
 a facility.
-("%                                                                                                          .
+("%
-d                .
+d PORM{01772 22 3M3
-PORM{01772 22 3M3
-DERP Section 4 Attachment B12 FORT ST. VRAIN NUCLEAR GENERATING STATION       issue 1 0Pubil3 Service
+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                                                            '
+* Pusuc sanwen comeAwy or cotonAno Page 64 of 76 O
-Page 2 of 6 SECURITY ALERT Emergency Action Level                      Typical Indication /
+Page 2 of 6 SECURITY ALERT Emergency Action Level Typical Indication /
-Initiating Event B12.7 Mass demonstration or                 As reported and/or confirmed                  .
+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.
-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                  .
+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.
-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 hours, Security Force.
-B12.9 Unavailability of the O                minimum number of security personnel for periods As reported and/or confirmed by the LSO or by any member of the exceeding 2 hours,               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.
-B12.10 Unexplained explosion                 As reported and/or confirmed or fire within the               by the LSO            #    '
+plant safety.
-protected or vital               or by any member of the areas that could effect          Security Force.
+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.
-* 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.
+B12.12 A kidnapping with a As reported and/or confirmed demand for SNM as by the LSO ransom.
-O                                                                                                .
+or by any member of the Security Force.
-V           .
+O V
-                                                                 ^
+^
 FORM (D)372 22 3M3 s
-DERP Section 4 Attachment B12 Pubil9            FORT ST. VRAIN NUCLEAR GENERATING STATION              Issue 1 0 Service
+DERP Section 4 Attachment B12 0 Service
-* Pusuc senvms cowAny or cotonAno                        Page 65 of 76 O
+* 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 /
+Page 3 of 6 SECURITY NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
-Initiatina Event                                               '
+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.
-B12.13 Actual, potential, or                    As reported and/or confirmed                              .
+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).
-unconfirmed acts of                   by the LSO sabotage that do not                  or by any member of the have the potential, or                Security Force.
+or by any member of the l
-have not adversely offected the routine or operations of the fae'lity, l
+Security Force.
-.14 Attemptea or actual                      As reported and/or confirmed theft of Special Nuclear              by the LSO                                           ,
+B12.15 Attempted or actual As reported and/or confirmed intrusions of unauth-by the LSO r
-l Material (SNM).                       or by any member of the                                        l Security Force.                                                !
+orized persons, weapons, or by any member of the explosives or other 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.
-devices into the protected area due to a failure of equipment or procedures when no malevolent intent is                                           # '
+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.
-confirmed or suspected.
+Security Force.
-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.
+.17 Less of a major portion As reported and/or confirmed-
-.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.
-of a physical security                by the LSO system that is                        nr by any member of the compensated.                          Security Force.
+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.
+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.
-O                                                                                                                              -
+Security Force.
-V Ponu toim.m.see
+O V
+Ponu toim.m.see
-DERP Section 4 Attachment 812 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                issue 1 OPublia Service
+DERP Section 4 12 OPublia FORT ST. VRAIN NUCLEAR GENERATING STATION issue 1 Service
-* Pusuc senwes comeAmy or cotonAm                                                                                          Page 66 of 76 O                                                                                                                                                                      '
+* Pusuc senwes comeAmy or cotonAm Page 66 of 76 O
-Page 4 of 6 SECURITY NOTIFICATION OF UNUSUAL' EVENT Emergency Action Level                                                                              Typical Indication /
+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                                .
+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.
-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.
-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 secondary alarm station O                                   when cause is known and is not considered sabotage.
-by the LSO or by any member of the 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.-
+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                          .
+O
-                                                                                                                                                                                                                     ~
+~
 PORM(Dl372 22 3M3
-OERP Section 4 Attachment 812 FORT ST. VRAIN NUCLEAR GENERATING STATION                          Issue 1 0PublicService
+OERP Section 4 12 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 Service
-* PUBUC SERWCE COMPANY OF COLORADO                                   Page 67 of 76 O
+* PUBUC SERWCE COMPANY OF COLORADO Page 67 of 76 O
 SECURITY ONE HOUR NON-EMERGENCY EVENT (s)
-Emergency Action level                                         Typical Indication /
+Emergency Action level Typical Indication /
-Initiating Event B12.25 As Reported By a                                                                                    -
+Initiating Event B12.25 As Reported By a Lead Security Officer (LS0) or the Security Supervisor O
-Lead Security Officer (LS0) or the Security Supervisor O                                                                                                             .
+o l
-o .
+FORM (o)772 22 3M3
-l FORM (o)772 22 3M3
-DERP Section 4 Attachment B12 FORT ST. VRAIN NUCLEAR GENERATING STATION                   Issue 1 0Public Service
+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                                                                                '
+* Pusuc sanyms couramy or cotonAno Page 68 of 76 O
 SECURITY FOUR HOUR NON-EMERGENCY EVENT (s)
-Emergency Action Level                         Typical Indication /
+Emergency Action Level Typical Indication /
-Initiating Event B12.26 As Reported By a                                                                             .
+Initiating Event B12.26 As Reported By a Lead Security Officer (LS0) or the Security Supervisor O
-Lead Security Officer (LS0) or the Security Supervisor O                                                                                                     e r
+e r
-* O          .
+O PoRM(D)372 22 3843 m.
-PoRM(D)372 22 3843
+_m._
-: m. _m._  __m ._..__._:_m.___.- - _.-
+__m
+._..__._:_m.___.-
-   - . . _ _ .         . - . _ - _               ~ -        .    .-.    ._.       -.              _
+~ -
-DERP Section 4 Attachment B13           i Public                    FORT ST. VRAIN NUCLEAR GENERATING STATION             Issue 1                  !
+DERP Section 4 Attachment B13 i
-OSerVlCe*                              Pusuc sanvsca COMPANY OF COLORADO                     Page 69 of 76 O
+OSerVlCe*
-v Page 1 of 4 OTHER HAZARDS ALERT
+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 /
+Emergency Action Level Typical Indication /
-Initiating Event B13.1 Damage to spent fuel                        a) Visual observation.                             -
+Initiating Event B13.1 Damage to spent fuel a) Visual observation.
-resulting in release of radioactivity to plant                     b) Area radiation monitor environs.                                      alarms.
+resulting in release of radioactivity to plant b) Area radiation monitor environs.
-B13.2 Severe natural phenom-                      a) Seismic recorder operate enon being experienced                         (2.05 g) or projected, such as:
+alarms.
-b) As Reported a) earthquake exceeding Operating Basis             c) As Reported                                 .
+B13.2 Severe natural phenom-a) Seismic recorder operate enon being experienced (2.05 g) or projected, such as:
-Earthquake levels; b) flood near design level; or, i                     c) tornado striking facility.
+b) As Reported a) earthquake exceeding Operating Basis c) As Reported Earthquake levels; b) flood near design level; or, c) tornado striking facility.
-B13.3 Other hazards being                         As reported by, or to, experienced or projected                   station personnel, such as:
+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                                                             ,
+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.
-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.
-B13.4 Other plant conditions                      As deemed necessary by warranting precautionary                    Shift Supervisor.
 activation of the TSC.
-O v                 .
+O v
-  . FORM (D)372 22 3M3
+. FORM (D)372 22 3M3
-DERP Section 4 Attachment B13 FORT ST. VRAIN NUCLEAR GENERATING STATION                                 Issue 1 0Public Service
+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
+* PusuC sanWCa COMPANY OF COLORADO Page 70 of 76 O
-OTHER HAZARDS NOTIFICATION OF UNUSUAL EVENT Emergency Action Level                                                     Typical Indication /
+OTHER HAZARDS NOTIFICATION OF UNUSUAL EVENT Emergency Action Level Typical Indication /
-Initiating Event B13.5 Unusual Hazards                                                      As visually observed by,                      .
+Initiating Event B13.5 Unusual Hazards As visually observed by, Experienced:
-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,                                                                                       ,
+or reported to, station personnel, a)
-c)    Onsite or near site plant related accidents that could result in the uncontained release                                                            '
+Aircraft crash on site or near the site that is subject to public concern because of possible detrimental effect on the plant; b)
-of toxic material or spills of flammable materials,                                                                                        <
+Onsite explosions or near site explosions that may be subject to public concern because of possible O
-B13.6 Accidents involving                                                   a) Abnormal radiation levels plant spent fuel                                                      reported from the cask, shipments or radioactive waste shipments,                                                  b) Cask breached,                          ,
+detrimental effect on the plant; or, c)
-c) As occurring or reported by shipper, O          .
+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 Attachment 813 FORT ST. VRAIN NUCLEAR GENERATING STATION                            Issue 1 0Pubila $9fVIC9'                     Pusuc saRVICs COMPANY OF COLORAM                                     Page 71 of 76 O
+DERP Section 4 13 0Pubila FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1
-* Page 3 of 4 OTHER HAZARDS ONE HOUR NON-EMERGENCY EVENT (s)
+$9fVIC9' Pusuc saRVICs COMPANY OF COLORAM Page 71 of 76 O
-Emergency Action Level                                            Typical Indication /
+Page 3 of 4 OTHER HAZARDS ONE HOUR NON-EMERGENCY EVENT (s)
-Initiating Event 813.7 Any natural phenomenon                                      Extremely high winds or                                   .
+Emergency Action Level Typical Indication /
-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.
+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.
+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.
+capability, offsite response capability, b) Loss of Emergency or communications Notification System.
-s                         capability.                                                                                                  '
+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; '
+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.
+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.                                                                                       ~
+radioactive releases.
-l l
+~
-O                   .
+O FoAMiol372 22 3M3
-FoAMiol372 22 3M3 l
-DERP Section 4 Attachment B13 Pubils          FORT ST. VRAIN NUCLEAR GENERATING STATION                         Issue 1 0 Service
+DERP Section 4 Attachment B13 0 Service
-* Pusuc senvics COMPANY OF COLORADO                                 Page 72 of 76 O                                                                                     '
+* 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 /
+Emergency Action Level Typical Indication /
-Initiating Event B13.10 Any event or situation,                          a) On-site fatality for which                            -
+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.
-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.
+B13.11 Any event requiring the As occurring.
-O                        transport of a radio-actively contaminated person to an offsite
+O transport of a radio-actively contaminated person to an offsite
-                          . edical facility for treatment.
+. edical facility for treatment.
-*
 ('')T
- \                    .
+\\
 MMM(Dl3D.M.NG
-DERP Section 4 Attachment B14 Pubil3       FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                    Issue 1 OService*                    Pusuc sanvoca comeAmy or cotonApo                                                                            Page 73 of 76 O                                                                                                                             '
+DERP Section 4 Attachment B14 OService*
-PERSONNEL INJURY ALERT EAL Emergency Action level                                              Typical Indication /                 ~
+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                                               .
+NONE IDENTIFIED O
-e
+e e
-                                                                                                                                                     $    e 9
+0
-                         .
 PORMID)372 22 3M3
-DERP Section 4 Attachment B14 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION      Issue 1 O$9FVlCO'PusuC SERVICE COMPANY OF COLORADO                             Page 74 of 76 O            '                                              '
+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 /
+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.                             -
+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                                                                                       .
+O 4
-O          .
+O FORM (D)372 22 3M3 i
-FORM (D)372 22 3M3 i
+../
-                                           ../
-           -      __              . . - _ .                 ~ . .                   - _- -        . _ _ _ -   _         . _ - .. -   ._    . . -
+~..
-DERP Section 4                     l Attachment B14 FORT ST. VRAIN NUCLEAR GENERATING STATION                           Issue 1                           l 0Publia     Service
+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
+* PusuC sERWCE COMPANY OF COLORADO Page 75 of 76 l
-* PERSONNEL INJURY ONE HOUR NON-EMERGENCY EVENT (s)
+O PERSONNEL INJURY ONE HOUR NON-EMERGENCY EVENT (s)
-EAL Emergency Action Level                                            Typical Indication /
+EAL Emergency Action Level Typical Indication /
-I Initiating Event NONE IDENTIFIED O                                                              -
+Initiating Event NONE IDENTIFIED O
-t
+t b) l l
-* l l
-b)
 FORM (D) 372 + 22 3043 i-
-                                                                                         .                        DERP Section 4 Attachment B14 FORT ST. VRAIN NUCLEAR GENERATING STATION                           lssue 1 OPublic  $9fVICO'                     Pusuc saRVICE COMPANY OF COLORADO                                   Page 76 of 76 O
+DERP Section 4 Attachment B14 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 1
-* Page 4 of 4 PERSONNEL INJURf FOUR HOUR NON-EMERGENCY EVENT (s)
+$9fVICO' Pusuc saRVICE COMPANY OF COLORADO Page 76 of 76 O
-EAL Emergency Action Level                                     Typical Indication /             s Initiating Erent 814.2 Any event or situation,                                  a) On-site fatality for which                                   . .
+Page 4 of 4 PERSONNEL INJURf FOUR HOUR NON-EMERGENCY EVENT (s)
-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                           -
+EAL Emergency Action Level Typical Indication /
-release is planned or                                     for an unrestricted area, notification to other                                     but requiring report to government agencies has                                   the State.
+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.
+D B14.3 Any event requiring the As occurring.
 transport of a radio-actively contaminated person to an offsite medical facility for treatment.
-   /
+/
 e l
-       .PORMID)372 22.N43
+.PORMID)372 22.N43
-                       -.               . _ . - .         . . -       _                      _      , . .           .__ ..s. ._. _ _            _ _
+..s.
 U t nr St:C t10fl D
-                                                                                   !ssue 1 age 1 of 13 Public                FORT ST. VRAIN NUCLEAR GENERATING STATION
+!ssue 1 age 1 of 13
-     @ Service
+@ Service
-* Pusuc sunvece courAmy os cotonAno TITLE:          DEFUELING EMERGENCY RESPONSE PLAN: SECTION 5 EMERGENCY ORGANIZATION                  .
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc sunvece courAmy os cotonAno TITLE:
-PONSIBLE UTHORIZED REOSw                         PORC 9 21 FEB 131991                 57TE           S M 41 DCCF NUMBER (S)         Qh 122.9 O                                                                                                       .
+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
+CONTROL CENTER PRIOR TO USE FORM (D)372 22 3642
-DERP Section 5                        1 Issue 1 Page 2 of 13 Public                                FORT ST. VRAIN NUCLEAR GENERATING STATION O Service
+DERP Section 5 Issue 1 Page 2 of 13 O Service
-* PUBUC SERVICE COMPANY OF COLORADO 5.0 EMERGENCY ORGANIZATION 5.1            NORMAL STATION ORGANIZATION The             Normal                  Shift      Organization           is depicted in                          -
+* 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
-Attachment 5.1. Additional information is provided in the station                  Technical                 Specifications.                 Duties      and responsibilities of operating personnel are set forth in station administrative procedures.                                                                                            ,
+-.1.
-.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                                                              '
+Additional information is provided in the station Technical Specifications.
-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.)
+Duties and responsibilities of operating personnel are set forth in station administrative procedures.
-In this interim capacity as Emergency Coordinator, he is responsible for:                         1) classification and declaration of the
+.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.
-* 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.
+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 may confer with FSV and PSC management.for advice or concurrence                    with         initial         accident          classification.                         ~
+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.
-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.
+(If during an event the Shift Supervisor is unable to perform as Emergency Coordinator, the most senior Reactor Operator assumes that role.)
-O v                       .
+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
-..   - . - . - , , ,                          - - , . - - ~                 -               . ,      , - .     . . -     -                -     -. -
+- -,. - - ~
 DERP Section 5 Issue 1
-                                                                                                        #9' Public               FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service
+#9' 0 Service
-* 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.
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc sanvice courAmy or cotonApo O
-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.
+The Emergency Coordinator is responsible for initially classifying the incident, providing PARS, initiating corresponding emergency
-Attachment 5.3 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.                                      ,
+: actions, notifying offsite authorities of the
-.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                           -
+: incident, and establishing communications with the TSC.
-the ERO is activated (Attachment 5.3).
+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.
+.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                                -
+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.
-listing of qualified personnel                    for the various positions may be obtained from the FSV Emergency Phone Book maintained by the Emergency Planning Coordinator.
+a.
-: a.          The TSC Director - (Vice President, Nuclear Operations) is in command of PSC emergency operations.        Duties       and     responsibilities include direction and coordination of:
+The TSC Director - (Vice President, Nuclear Operations) is in command of PSC emergency operations.
-: 1. Emergency response functions.
+Duties and responsibilities include direction and coordination of:
-       - Foam (D)372 22 3M3 i
+.
+Emergency response functions.
+- Foam (D)372 22 3M3 i
-  . _ . . . _ . _   _               __  - _ _ .      .__                           __ __.                      __ _. ._                   ._ _.            _ _ ~
+_ _ ~
 DERP Section 5 Issue 1
-                                                                                                                                      #9' Public      FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service
+#9' 0 Service
-* PUBUC SERVICE COMPANY OF COtORADO O                                        2. Transmitting plant status updates and radiological release data to appropriate offsite agencies.                                                                ,
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COtORADO O
-: 3. Ensuring                           adequate                   administrative, technical, and                             logistic                support               is                       !
+.
-available.                                                                                                        '
+Transmitting plant status updates and radiological release data to appropriate offsite agencies.
-: 4. Ensuring.                       continuity                    of        emergency                             ,
+.
-organization resources.
+Ensuring adequate administrative, technical, and logistic support is available.
+.
+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                       I emergency, terminating the emergency or                                                                    ,
+Notifying the state and local agencies of any PARS.
-de-escalating the event classification.                                                                            l
+.
-: 7. The TSC staff, which is responsible for collecting and analyzing the technical information necessary for assessment of
+Declaring a
-,                                                     plant operational aspects.
+particular class of emergency, terminating the emergency or de-escalating the event classification.
-,                                               8. Providing technical counsel in support of                                                    ,
+.
-the CR.
+The TSC staff, which is responsible for collecting and analyzing the technical information necessary for assessment of plant operational aspects.
-: 9. Assessment                            of     radiological                    release consequences.                                                             *     *
+.
+Providing technical counsel in support of the CR.
+.
+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
+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.
+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                      .
+Establishing radiological control' areas as directed.
-implementing recommended corrective actions.                                                                        ' '
+b.
-FORM (Ol372 22 3043
+The 'CR Director
-                                                             . , - , _ , - - , . _                 - . . _ _                  _                      -_,,_ m.
+- (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 Public                    FORT ST. VRAIN NUCLEAR GENERATING STATION 0$9fVlC9'                                    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                                                                  "
+DERP Section 5 Issue 1 age 5 of 13 0$9fVlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pusuc SERVICE COMPANY OF COLORADO O
-important events, decisions, and actions                                                    that occurred in response to the emergency situation.
+.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
+a.
-: 1.             Plant Control                                                                           l The Shift Supervisor is responsible for                                          '
+CONTROL ROOM (CR) 1.
-overall plant control and directs plant operations to terminate the incident, regain plant             control,        and         minimize accident consequences.
+Plant Control The Shift Supervisor is responsible for overall plant control and directs plant operations to terminate the incident, regain plant
-O                                                                                        plant Operations V
+: control, and minimize accident consequences.
-.
+OV 2.
-The Reactor Operators have been trained to assist the                 Shift Supervisor in implementing plant corrective actions.
+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.
+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.
-O                             .
+If available, a licensed operator is utilized.
-l l
+O l
-FORMID)372 22 3M3
+l FORMID)372 22 3M3
-  .. . , _     , - . . , _ . . . -        , _ , . _ , . - . , _ _ - . . - _ . , _ . , _ _ _                    . . - - . _ .       . _ ~ . . _ ,                    . . , - .
+~.. _,
-DERP Section 5 Issue 1 Pub;!c                       FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 13 0 Service
+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                                                       '
+Technical Assistance The Technical Advi[or (TA) provides technical analysis / advice and recomnfends corrective actions necessary to bring the 1
-corrective actions necessary to bring the                                                          1 plant to a safe and stable condition.                                                              !
+plant to a safe and stable condition.
-The TA may also perform dose assessment evaluations in support of the                                     plant operations staff.                                                                      ,
+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.                                                                  ,
+Health Physics The onshift HP technician will provide HP, radiological assessment, and hazards control support to the Control Room.
-: b. TECHNICAL SUPPORT CENTER
+Once the TSC is activated he will be supported by additional HP personnel, and will coordinate activities with the TSC HP Coordinator.
-: 1. Engineering & Technical Analysis Team Personnel                     in this group perform core O                                                              physics analyses, provide electrical .and mechanical                             engineering,          procedures
+b.
-* 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                                          -
+TECHNICAL SUPPORT CENTER 1.
-FSV security force.
+Engineering & Technical Analysis Team Personnel in this group perform core O
-: 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.
+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.
-FORM (D)T12 22 3843                                                                                                                                  i
+.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.
+.
+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
+. =.
+~ -
-Otxe section o Issue 1 age 7 of 13 PubilC                               FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service * ' PUBUC SERVICE COMPANY OF COLORADO
+Otxe section o Issue 1 age 7 of 13 0 Service
-: 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.
+* PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION
-: 4. Auministrative & Logistics Support
+' PUBUC SERVICE COMPANY OF COLORADO 3.
-* This group will provide needed technical
+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.
-* 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.                                                               '
+Auministrative & Logistics Support This group will provide needed technical documents, communications and analytical equipment, clerical assistance, and other support for the ERO.
-: 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                                                                                .,       .
+Computer Services Technical support in the areas of' computer hardware and software development / modification will be provided.
-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.                                                            -
+.
-.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.
+TSC Core This group is responsible for maintaining personnel accountability, including O
-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.
+personnel contamination surveys / exposure
+: records, and formation / dispatch of corrective action
-* Q            .
+: 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.
+.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.
+Q
 i t
 FORM (D)372 22 443 '
-_ ~ _ . . _ , . - _ _ _ _ _ _ _ _ _ _ - - ,                               _ __      ._. , .-                                         . _ .
+~
+_ ~ _.. _,. - _ _ _ _ _ _ _ _ _ _ - -,
-DERP Section 5 Issue 1 age 8 of 13 Public           FORT ST. VRAIN NUCLEAR GENERATING STATION 0 $9fVIC9'                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                                                         ;
+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
-available from outside companies includes ambulance                                                       l service to transport injured and/or cor.taminated personnel,                                   medical     treatment,     and    hospital              ,
+service to transport injured and/or cor.taminated personnel, medical treatment, and hospital facilities for station personnel who require such assistance.
-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.
+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. Attachment 5.4 lists these agencies by the type of service.
+Letters of agreement for these services are contained in Section 9..4 lists these agencies by the type of service.
-3.2 Contract Support                                                                                       ,
+3.2 Contract Support Specialized assistance from contractors may also be requested in an emergency situation.
-Specialized assistance from contractors may also be requested in an emergency situation.                                           Contract support may include construction, dosimetry and laboratory analysis, and decontamination and                                                              '
+Contract support may include construction, dosimetry and laboratory analysis, and decontamination and rad-waste disposal assistance.
-rad-waste disposal assistance.                                      Provisions have O.,                                    been made for selected contract support firms -to provide this assistance, on request.
+Provisions have O.,
-* 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                                                     '
+been made for selected contract support firms -to provide this assistance, on request.
-fc11owing agencies will be notified / requested to provide assistance, as necessary:
+.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.
-: a. The Nuclear Regulatory Commission, Office of Inspection and Enforcement, Region IV, via the NRC Incide.c Response Center in Bethesda, MD.
+The fc11owing agencies will be notified / requested to provide assistance, as necessary:
-: b. The Departrent of Energy (DOE) - Radiological Assistance 'eams (RAT), Idaho Falls, Idaho and Rocky                                F%ts,      Colorado; Aerial Monitoring
+a.
- ,                                                System (AMS),Las Vegas, Nevada.                                       00E will
+The Nuclear Regulatory Commission, Office of Inspection and Enforcement, Region IV, via the NRC Incide.c Response Center in Bethesda, MD.
-(                                             acM vate                                  the     Interagency       Radiological
+b.
-* Assistance Plan (IRAP) as necessary.
+The Departrent of Energy (DOE) - Radiological Assistance 'eams (RAT), Idaho Falls, Idaho and Rocky F%ts, Colorado; Aerial Monitoring System (AMS),Las Vegas, Nevada.
+E will
+(
+acM vate the Interagency Radiological Assistance Plan (IRAP) as necessary.
 FORM 101372 22.ud3
-DERP Section 5 Issue 1 Public              FORT ST. VRAIN NUCLEAR GENERATING STATION #9' 0 Service
+DERP Section 5 Issue 1
-* PUBUC SERVICE COMPANY OF COLORADO
+#9' 0 Service
-: c. Federal Emergency Management Agency (FEMA),                            i Region VIII, Denver, Colorado.                                        '
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBUC SERVICE COMPANY OF COLORADO c.
-: d. Upon request by the State of Colorado,'the          -
+Federal Emergency Management Agency (FEMA),
-i Federal Radiological Emergency: Response Plan                         '
+Region VIII, Denver, Colorado.
-(FRERP) will be activated, with response from numerous federal agencies with _ emergency resources.
+d.
-.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,-
+Upon request by the State of Colorado,'the i
-assigned responsibilities, capabilities, and activation                     ,
+Federal Radiological Emergency: Response Plan (FRERP) will be activated, with response from numerous federal agencies with
-and communicatior arrangements, refer to the State RERP.
+_ emergency resources.
+.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.
+With no offsite consequences, PSC does not expect / rely l
+upon activation of the State RERP te support a Fort St.
+,~
 Vrain emergency.
-* 4      .
-?                                                                                                                    1 1
+?
 l.
-O                                                                                                             -
+O FORM (ol772 22-3643
-l l
-FORM (ol772 22-3643
-DERP Section 5 Attachment 5.1 Public                        FORT ST VPAIN NUCLEAR GENERATING STATION 10 of 13 0 SerVlCO'                            PUBUC BERVICE COMPANY OF COLORADO O
+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
+l SHIFT SUPERVISOR l l TECHNICAL ADVISORI
-                                                                                                                              )
+.......I (SRO)
-                        . . . . . . .I                    (SRO)         [**j                        l
+[**j l
-_l                 (1)   l    I                (1)* I                      .
+)
-II                           I    I                      I l
+_l (1) l I
+(1)* I II I
+I I
+l l
 l l
-l                                   ll                                 l    LEAD SECURITY      l l     HP TECHNICIAN ll                                                 l        OFFICER       I I                             (1)   Il                                 I                (1)    l l                                   ll                                 l                       I I
+ll l
-* l I
+LEAD SECURITY l
-ll       REACTOR OPERATOR l       l SECURITY GUARDS l l_l             (RO)         lul                         l ll                   (1)**l      !                      I g                                           j l                          I    l                      I
+l HP TECHNICIAN ll l
-                 .                           i l
+OFFICER I
-l lEQUIPMENT OPERATORS l l_I                   (2)    l II
+I (1)
-* I I
+Il I
-I i
+(1) l l
-l l AUXILIARY TENDERS l l_I                  (2)**l I                       I NOTES.
+ll l
-SR0                        SENIOR REACTOR OPERATOR.
+I I
-R0                         REACTOR OPERATOR.
+l I
-HP                         HEALTH PHYSICS TECHNICIAN TECHNICAL ADVISOR IS ON CALL 24 HOURS PER DAY AND WILL REPORT TO THE CONTROL ROOM WITHIN 1 HOUR.
+l l REACTOR OPERATOR l l SECURITY GUARDS l l_l (RO) lul l
+l l (1)**l I
+g j
+l I
+l I
+i l
+l lEQUIPMENT OPERATORS l l_I (2) l II I
+I I
+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
+LINE OF AUTHORITY COMMUNICATION 9
-        ********                   COMMUNICATION 9                                                                                                                           '
 FORM (0)?72 22 3643
-                                .=.-       _ - . . .              ..                -    _
+.=.-
-DERP Section 5         '
+DERP Section 5
-Attachment 5.2 3
+'.2 3
-Public                    FORT ST VRAIN NUCLEAR GENERATING STATION e M 13 O Service
+O Service
-* PUBUC SERVICE COMPANY OF COLORADO EMERGENCY ORGANIZATION            .
+* Public FORT ST VRAIN NUCLEAR GENERATING STATION e
-(NOTIFICATION OF UNUSUAL EVENT)
+M 13 PUBUC SERVICE COMPANY OF COLORADO EMERGENCY ORGANIZATION (NOTIFICATION OF UNUSUAL EVENT)
-Fort St. Vrain Nuclear Generating Station                               '
+Fort St. Vrain Nuclear Generating Station l
-l   SHIFT SUPERVISOR
+SHIFT SUPERVISOR
-* l       l TECHNICAL ADVISOR l l           (SRO)          l"l                       l l                 1,2,3    l   l                8 l                     ,
+* l l TECHNICAL ADVISOR l l
-I                          I   l                     1 l
+(SRO) l"l l
+l 1,2,3 l
+l 8 l I
+I l
+l
+l l
+l
+~
+l HP TECHNICIAN l l
+REACTOR OPERATOR l l
+LEAD SECURITY l l
+I"l (SRO) 1"l OFFICER l
+l
+,6 l l
+l l
+,7 l 1
+l 1
+I
+I l
+I I
+I I
+I I
+i I
+l l
+EQUIPMENT l
+l l
 l l
-l         ~
+OPERATORS l
-l      HP TECHNICIAN l l                       REACTOR OPERATOR l        l    LEAD SECURITY l l                               I"l                  (SRO)            1"l        OFFICER       l 4
+l l SECURITY GUARDS I I
-l                      4,6 l l                                        l  l               6,7 l 1                               l          1                          1  I                     I l                           I                          ,
+,6 l l
-I                           I I                                        I                           I i                                        I                           l l          EQUIPMENT            l                       l                l                     l l          OPERATORS            l                       l                l SECURITY GUARDS I I                      5,6 l O       l                               1 l
 l l
+O l
+l
 l l
 l l
-l l AUXILIARY TENDERS]
+l AUXILIARY TENDERS]
-I                5,6 l l                                               '
+I 5,6 l l
 NOTES:
-EMERGENCY COORDINATOR ON CALL 24 HOURS A DAY, ONE HOUR MAXIMUM RESPONSE TIME
+EMERGENCY COORDINATOR ON CALL 24 HOURS A DAY, ONE HOUR MAXIMUM RESPONSE TIME 1
-!             1         PLANT OPERATIONS AND CONTROL 2         0FFSITE NOTIFICATION                                                                               ~
+PLANT OPERATIONS AND CONTROL 2
-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 "a***"                 COMMUNICATION FORMt01372 22 3643
+FFSITE NOTIFICATION
+~
+j 3
+PLANT CONDITION ASSESSMENT l
+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-Attachment 5.3     -
+DERP Section 5-.3 OPublic FORT. ST. VRAIN NUCLEAR GENERATING STATION -
-FORT. ST. VRAIN NUCLEAR GENERATING STATION -                                               g 33 OPublic Service
+g 33 Service
-* Pusuc saRvice comeAmy or cotonAno O                                                                                                                iuatoaa m mos El8ERGENCY RESPONBE ORGANIIATION
+* Pusuc saRvice comeAmy or cotonAno O
-* PORT ST.VRAIN NUCLEAR GE95 RATING STATION                                            .
+iuatoaa m mos El8ERGENCY RESPONBE ORGANIIATION PORT ST.VRAIN NUCLEAR GE95 RATING STATION TiensumoR w, NuotaAR opeRAroNo
-TiensumoR w, NuotaAR opeRAroNo
+~
-                                                                                                                           ,                                                                 ~
+l I
-l                                                                                 I ENORe & T80H ANALTOM                                                                                                coemk%.RooMo8WoToR TWoM ANALYSIB TEAMISSMS                                                                                                     opmAfteNS MANamR I
+ENORe & T80H ANALTOM coemk%.RooMo8WoToR TWoM ANALYSIB TEAMISSMS opmAfteNS MANamR I
-onesAsemeMeer                                                                                                      nANr comnoi.
+onesAsemeMeer nANr comnoi.
-NUCLEAR TIWee & OUppoRT My                                                                                                SHof SupEpMeoR i
+NUCLEAR TIWee & OUppoRT My SHof SupEpMeoR i
-HEALTH pmSICS coefDB64 tor                                                                                                 PLANT opWRAT1oM O                              SWPT. or RAotAftoN PRoTWoT1oM & OMWN5m                                                                                                       E I
+HEALTH pmSICS coefDB64 tor PLANT opWRAT1oM O
-ric com                                                                                 oneRAT 0 U ,oRr Tm NUCLEAR oPERAT1 oft $
+SWPT. or RAotAftoN E
-            " ' " "
+PRoTWoT1oM & OMWN5m I
-                                              "                                                                                   OO            "T'"*"'
+ric com oneRAT 0 U,oRr Tm NUCLEAR oPERAT1 oft $
-                                                                        ;                                                         O O
+"T'"*"'
-RamocMaasm                                                                                     U TECHNICAL ASBSTANCE '
+OO O
-O I                                                                                                                   O RaciocumNe m sury.                                                                                                     788""" "
+O U
-OO                                                      ,
+RamocMaasm TECHNICAL ASBSTANCE '
-I cowUr:M suncom Une of .^1%i;p NUC. CotAPUTER OWMOES O
+O I
-g                                                  .g TechniestSupporttoOperemons secuswrycooRoosArom NOTE: Onlyprimarypoetsonoareindlested. A seoupwryPuRoommL                                                                                         esmplete Noting of queNfled pereennel for the VerlOUS peshione mey 130 otilainell (fom O
+O RaciocumNe m sury.
-the PSV Emergency Phone Book .                    .
+""" "
-I                                                                                                             4                                              1 TeoHNtoAL SWpoRT CWffW                                                                                OCSITRob ROOM FORM (D)372 22 3tM3
+OO I
+cowUr:M suncom Une of.^1%i;p NUC. CotAPUTER OWMOES O
+g
+.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
+OCSITRob ROOM TeoHNtoAL SWpoRT CWffW FORM (D)372 22 3tM3
-              --                   _ _ .  -   . - . . . . -  -..       =          . - - -
+=
-DERP Section 5 Attachment 5.4 ssue Public               FORT ST. VRAIN NUCLEAR GENERATING STATION O $9fVICO*PUBUC SERVICE COMPANY OF COLORADO O
+DERP Section 5.4 ssue O $9fVICO*
-V LOCAL AGENCY AND CONTRACT SUPPORT SERVICES Fort St. Vrain Nuclear Generating Station Local Agency                               Support Service                                               .
+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,
-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                                     ,
+Fort Collins, Colorado Assistance.
-Contract Support                           Support Service Colorado State University                  Environmental Monitoring O,                Fort Collins, Colorado                    Assistance.                                                 ,
+Controls For Environmental Chemical-Radiochemical Pollution, Inc.
-Controls For Environmental                Chemical-Radiochemical Pollution, Inc.                            Laboratory. Analysis Santa Fe, New Mexico
+Laboratory. Analysis Santa Fe, New Mexico
-                                                                                   .g       .
+.g EBASCO Services, Inc.
-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
+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                                                                                  '
+San Angelo, Texas Consultant R. S. Landauer, Jr. & Co.
-i i    FORM (0)772 22 3643
+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 Public                                                        FORT ST VRAIN NUCLEAR GENERATING STATION                gf g O ServlCO' PUBUC SERVICE COMPANY OF COLORADO TITLE:                                             DEFUELING EMERGENCY RESPONSE PLAN, SECTION 6 EMERGENCY MEASURES PONSIBLE UTHORIZED                                                                                /
+DERP Section 6 O ServlCO' Public FORT ST VRAIN NUCLEAR GENERATING STATION gf g PUBUC SERVICE COMPANY OF COLORADO TITLE:
-PORC                                                                                                                                      EFFECTIVE REVIEW                                                                                                MNC 9 21 FEB 131991                 DATE       3 - 2.9 9l DCCF NUMBER (S)                                                                                 hO-l 7M O                                                                                                                                                                            .
+DEFUELING EMERGENCY RESPONSE PLAN, SECTION 6 EMERGENCY MEASURES PONSIBLE UTHORIZED
-r                                          FT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTBOL CENTER PP'OR TO USE FORM (D)772 22 3642
+/
+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
+DERP Section 6 FORT ST VRAIN NUCLEAR GENERATING STATION e1 0Public Service
-* PusuC SERVICE COMPANY OF COLORADO O       6.0 EMERGENCY MEASURES                                                                                                                                  .
+* PusuC SERVICE COMPANY OF COLORADO O
-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
+.0 EMERGENCY MEASURES Station emergency measures will be initiated upon, and recording to, incident classification.
-* or minimize radiological exposure, and sets forth measures to assist persons injured or exposed to radiation and radioactive material.
+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.
-.1                       ACTIVATION OF EMERGENCY RESPONSE ORGANIZATION                                                                                     ,
+.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 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                                                                                                =
+The emergency organization activated in each emergency classification is shown in Section 5.
-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
+The Shift Supervisor will immediately initiate action to limit the
-(                                             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.
+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 Public                                                              FORT ST VRAIN NUCLEAR GENERATING STATION                        Page 3 of 21 0 Service
+DERP Section 6 Issue 1 0 Service
-* PUBUC SERVICE COMPANY OF COLORADO O                                                                 NOTE: Activation                      of    the   FSV. Emergency        Response Organization is not required in a NOVE.
+* Public FORT ST VRAIN NUCLEAR GENERATING STATION Page 3 of 21 PUBUC SERVICE COMPANY OF COLORADO O
-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       -
+NOTE: Activation of the FSV.
-Health.                  Notification is authenticated by            either a call-back or the fact that the microwave link was used.
+Emergency
-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.
+===Response===
-Personnel / equipment augmentation -may vary according to specific circumstances.               The functions of the Emergency O-                                                                     Response Facilities (ERFs) include:                                                   -
+Organization is not required in a NOVE.
-Control Room Assessment of Plant Operating Conditions                   . . ,
+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.
-Implementing Corrective Actions Fire Fighting Direction Personnel Accountability (Initial)
+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 Public                                          FORT ST. VRAIN NUCLEAR GENERATING STATION                        Page 4 of 21 0 SGTVICe*Pusuc SERVICE COMPANY OF COLORADO O                                                   Technical Support Center                              ,
+DERP Section 6 Issue 1 0 SGTVICe*
-Command                                                          .
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 21 Pusuc SERVICE COMPANY OF COLORADO O
-Plant Systems Assessment Reactor Engineering Recommendation of Corrective Actions                                                -
+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)
-Dose Projections Health Physics Assessment Notification / Communications Protective Action Recommendations Offsite Communications                                                          .
+Emergency Response Emergency Repair / Damage Control Radiological Surveys Radiation Protection (Personnel Monitoring / Dosimetry /
-Personnel Accountability (Continued)
+~
-Emergency Response Emergency Repair / Damage Control Radiological Surveys
+Decontamination / Access / Reentry Control)
-                                                                                                                        ~
+Search and Rescue /First Aid Fire Brigade backup
-Radiation Protection (Personnel Monitoring / Dosimetry /
-Decontamination / Access / Reentry Control)                 ,    ,
+==6.2 ASSESSMENT==
-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.    '
+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.
+,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 Public                          FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                       Page 5'of 21 0 $9fVICO* 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.
+DERP Section 6 Issue 1 0 $9fVICO*
-FSV     also                                             has    an   extensive system for monitoring radioactive materials released to the environment (e.g.,
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5'of 21 PUBUC SERVICE COMPANY OF COLORADO O
-gaseous, process liquid, and reactor building ventilation
+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.
-* 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.                                     -
+Post-accident sampling is described in appropriate Health Physics and Radiochemistry procedures.
-These                        systems will                           monitor activity releases during-accident conditions.                                               In any accident where release: are not                         monitorable,                             emergency   procedures                        provide
+FSV also has an extensive system for monitoring radioactive materials released to the environment (e.g.,
-                                        " theoretical" worst-case relecse rates corresponding to the Design Base Accidents outlined in Section-14 of the
+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.
-* FSV Updated FSAR and the Defueling SAR.
+These systems will monitor activity releases during-accident conditions.
-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 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.
-in the TSC via plant computer links. In the-event that                                                                            -
+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.
-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.
+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                                  -
+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.
-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.
-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
+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                                                                                                                                                                            ,
+_h (d
-(d                                        implementing procedure- DERP-FIELD, Procedure).
+implementing procedure-DERP-FIELD, Field Monitoring Procedure).
-Field       Monitoring FORM (D)372 22 3643
+FORM (D)372 22 3643
-DERP Section 6 k
+k DERP Section 6 Issue 1 OPublic FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 2*
-Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                             Page 6 of 2*
+Service
-OPublicService
 * PUBUC SERVICE COMPANY OF COLORADO I
-Unmonitored releases are descrihed in detail                                                             in DERP
+Unmonitored releases are descrihed in detail in DERP
-                          -implementing procedure OERP-DOSE, Offsite Dese Calculation Methodology.                                                                                          *
+-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                                                                  -
+.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.
-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.
+PSC field monitoring teams primarily conduct air and ground surf ace radiation sampling.
-.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
+Environmental monitoring, as contracted with Colorado State University, prov' des more in-depth radiological monitoring concerning ground / water deposition and food chain impact.
-* information is centralized in the Control                                                           Room. The information provided by this instrumentation forms the basis for declaration of emergency' classes.
+.3 CORRECTIVE ACTIONS Station procedures contain steps for preventive and/or corrective actions to avoid or mitigate serious consequences of an incident.
-Corrective actions will                                                       also  involve _ response by the following organizations:
+Control and display of information is centralized in the Control Room.
-* 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.
+The information provided by this instrumentation forms the basis for declaration of emergency' classes.
-* Damage Control, Repair, and Decontamination                                                                    .
+Corrective actions will also involve _ response by the following organizations:
-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,-
+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            .
+O FoftM(Dl372 22 3643
-FoftM(Dl372 22 3643
-DERP Section 6 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                           Page 7 of 21 0Public SerVlCe*         PUBUC SERVICE COMPANY OF COLORADO 6.4  PROTECTIVE ACTIONS                                                                                                  .
+DERP Section 6 Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 21 SerVlCe*
-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.
+PUBUC SERVICE COMPANY OF COLORADO 6.4 PROTECTIVE ACTIONS Actions to protect station personnel,
-.4.1   Protective Cover and Personnel Accountability                                                                                                     -
+: visitors, and residents on FSV company property are the responsibility of the Shift Supervisor (as Emergency Coordinator) until he is relieved.
-: 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.                                                                                            .
+Measures for the protection of the general public are detailed in the State RERP.
-In addition, protective actions will be taken                                                                                                  ,
+.4.1 Protective Cover and Personnel Accountability a.
-for' these personnel                                                                                     in   other emergency situations                                               such                                      as     fires,    floods, and tornadoer                                    where                                                  personnel       safety     is N
+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.
-threatened.                                                       Notification of_-these personnel s
+In addition, protective actions will be taken for' these personnel in other emergency situations such as
-will be by actuation of plant alarm systems,                                                                                              ,
+: 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.
+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 FORT ST VRAIN NUCLEAR GENERATING STATION                                                    Page 8 of 21 0PublicSerVlCe*      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.
+DERP'Section 6 Issue 1 0Public FORT ST VRAIN NUCLEAR GENERATING STATION Page 8 of 21 SerVlCe*
-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.                      -
+PUBLIC SERVICE COMPANY OF COLORADO O
-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 Accountability FSV performs a " positive" accouatability, meaning that only personnel present in the protected area are accounted for.
-Personnel       response for accountability x_,                                                                           will not differ, regardless of time of                  .
+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.
-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 .
+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.
+' indicated on.their badges.
-Security      personnel    will   conduct the accountability process.         The protected area      accountability       stations     are         ,
+Security personnel will conduct the accountability process.
-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.
+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                                                                                                                                      .
+'s FORM (D)372 22 3643
-FORM (D)372 22 3643
-DERP Section 6            4 Issue 1 Public                                          FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                                              page 9 of 21 0SerVlCe*                                       - 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                                '
+DERP Section 6 4
-process                  will                          be   completed    within-30 minutes of the activation of                                             the alarm.
+Issue 1 0SerVlCe*
-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.                                              *
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION page 9 of 21
-: 2.            Security and Access Control Support           personnel                              reporting- to the station during an emergency-report to the O                                                                                                                                        badge cube.
+- PusuC SERVICE COMPANY OF COLORADO O
-relative to entering the plant will Any necessary instructions be        -
+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.
-posted at the badge cube entrance.                                                                  1
+The number and/or names of missing individuals will be reported to the Shift Supervisor by Security.
-: 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.                                         -
+This initial accountability process will be completed within-30 minutes of the activation of the alarm.
-necessary,- rescue personnel.                                   The teams:
+The TSC Director has responsibility for maintaining personnel accountability after the initial accountability process has been completed.
-                                                                                                                                       -will utilize OERP implementing procedure                                                                -
+Refer to Administrative Procedure G-5, Personnel Emergency Response, for specific details of the personnel accountability process.
-DERP-TEAMS,                             Emergency Team Formation and Direction, and will observe the' emergency exposure                                   limits       outlined        in Attachment 6.4.
+.
+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.
+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 Public         FORT ST. VRAIN NUCLEAR GENERATING STATION-                           Page 10 of 21 O$9fVIC9'              PusuC SERVICE COMPANY OF COLORADO O                                    b.      Offsite                       .
+DERP Section 6 Issue 1 O$9fVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION-Page 10 of 21 PusuC SERVICE COMPANY OF COLORADO O
-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.
+b.
-* The TSC Director will reco? mend any additional appropriate protective actions once. he has assumed control       of the emergency -resporse organization.
+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.
-Protective       actions for offsite areas are                                 -
+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.
-initiated by state / local        emergency response organizations as detailed in the State RERP.
+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 State of Colorado has adopted the EPA Protective Action Guides              for, initiating actions to protect the general public.                     Plans
+The TSC Director will reco? mend any additional appropriate protective actions once. he has assumed control of the emergency -resporse organization.
-,                                            .for activating state / local emergency. response agencies and performing various protective actions and services are specified in the State RERP.
+Protective actions for offsite areas are initiated by state / local emergency response organizations as detailed in the State RERP.
-.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 State of Colorado has adopted the EPA Protective Action Guides for, initiating actions to protect the general public.
-The types .of equipment, their criteria for-issuance, location, 'and means of distribution are                                              <
+Plans
-noted in Attachment 6.5.
+.for activating state / local emergency. response agencies and performing various protective actions and services are specified in the State RERP.
+.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                                       .
+FORM (o)372 22 3643
-DERP Section 6 Issue 1 Public                        FORT ST. VRAIN NUCLEAR GENERATING STATION                          Page 11 of 21 0 service
+DERP Section 6 Issue 1 0 service
-* PUBUC SERVICE COMPANY OF COLORADO O                                        6.4.3 Contamination Control Measures                                                         .
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 21 PUBUC SERVICE COMPANY OF COLORADO O
-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
+.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.
-* procedures.       The following is an outline of those procedural controls:
+Details-of contamination control measures for onsite areas are contained in station procedures.
-: 1. Radioactive Contamination of Personnel I
+The following is an outline of those procedural controls:
-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.
+Radioactive Contamination of Personnel I
-The    environment of personnel working within radiological control areas are
+Controls have been established to ensure that levels of removable contamination outside radiologically controlled areas will be maintained at less than allowable limits.
-.h i
+Emergency decontamination limits are established in DERP implementing procedure DERP-DECON, Emergency Decontaminatien Practices.
-v
+The environment of personnel working within radiological control areas are
-supervised personnel.
+. h i
-by    Health    Physics Radiation Work Permits-(RWPs)
+supervised by Health Physics (HP) v personnel.
-(HP) may be required for personnel in.such areas.             Specific         instructions, i
+Radiation Work Permits-(RWPs) 4 may be required for personnel in.such areas.
-precautions,        and   limitations are listed on RWPs.                            .,
+Specific instructions, i
-                                                                   . Protective        clothing is required for individuals entering contaminated areas.
+precautions, and limitations are listed on RWPs.
-Individuals leav.ing radiological control d
+. Protective clothing is required for individuals entering contaminated areas.
-areas are monitored for contamination upon de'parture, i
+Individuals leav.ing radiological control areas are monitored for contamination d
-* Quarterly         integrated accumulations of                       -
+upon de'parture, i
-l                                                                   radionuclides in the body vill not exceed 5
+Quarterly integrated accumulations of l
-accumulation levels which would result 2
+radionuclides in the body vill not exceed 5
-                                                                   .from exposure-to the maximum permissible
+accumulation levels which would result
-:                                                                   concentrations- (MPC) of radionuclides in-
+.from exposure-to the maximum permissible 2
-;                                                                   air or drinking water for occupational
+concentrations- (MPC) of radionuclides in-air or drinking water for occupational exposure as indicated in 10CFR20.103.
- !                                                                  exposure as indicated in 10CFR20.103.
+Food 'for emergency personnel will be provided from offsite sources.
-Food 'for emergency personnel will               be provided from offsite sources.
+p
-p                                                                                                                                       '
+!V FoRMID)372 22 3643
- !V FoRMID)372 22 3643
+-.~...-
-            . _ _ _ , - - _ _ . - _ . .             - .~.. .-                  - _ .              ._          _    _     _ . . . . . .
-DERP Section 6 Public     FORT ST. VRAIN NUCLEAR GENERATING STATION                         Pag      12 of 21
+DERP Section 6
 : 0. Service
-* Puntic senvice company or cotonAno
+* 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.
+Exposure to airborne concentrations
-: 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.
+higher than the MPC will be prevented or avoided.
-m
+If axposures are nbcessary, wearing appiopriate, properly f.i tted respiratory protective equipment will be required, as determined by HP.
-* Equipment            and        tools       will       be ty                                      unconditionally released for use outside                                       '
+Periodic air samples will be taken in selected operational and work areas to ensure that MPC levels are not exceeded.
-the area only if removable contamination                                   -
+.
-and radiation levels are less than the allowable limits.
+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.
-* 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                                    -
+If any equipment is found to be contaminated.and decontamination is not practical, the item will remain controlled.
-accordance with approved procedures.
+Emergency decontamination limits are established in DERP implementing procedure DERP-DECON, Emergency Decontamination Practices.
-l O                                                                                                                    .
+Equipment and tools will be m
-U FoflM(D)J72 22 3643
+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 FORT ST. VRAIN NUCLEAR GENERATING STATION                                  Pa     13 of 21 0  PubilC Service
+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                            .                 .
+* 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
-.5.1   Emergency Personnel Exposure Criteria
+: TSC, as required.
-* 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
+This information will be utilized in determining emergency team assignments.
-* recommendations of the EPA and are shown in Attachment 6.4.        Emergency                  workers will        carry self-reading dosimeters in addition to film badges.                                           <
+Criteria used for limiting doses to emergency workers are based on recommendations of the EPA and are shown in.4.
-Emergency     dosimetry services will                        be provided                      j through the services of an outside contractor.
+Emergency workers will carry self-reading dosimeters in addition to film badges.
-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                  -
+Emergency dosimetry services will be provided j
-consultation with the senior HP Representative at the TSC.
+through the services of an outside contractor.
-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                                     -
+Emergency dosimetry service response is provided on a 24-hour basis.
-badges and self-reading. dosimetric devices                               to emergency     personnel                 and assuring the ongoing accountability of each worker's dose.
+Every effort will be made to minimize emergency worker doses through the use of protective equipment and supplies.
-O                                                                                                                                                     '
+The TSC Director is responsible for emergency team assignments and may authorize emergency workers to receive doses in excess of 10CFR20 limits.
-I FORM (ol372 22*3643
+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         ,
+DERP-Section 6 OSerVlCe*
-Public         FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                 14 of 21 OSerVlCe*             PUBUC SERVICE COMPANY OF COLORADO O
+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.
-V                       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              -
+There are station personnel who are trained in first aid and decontamination procedures.
-to be contaminated (any detectable activity above background)                                   will    undergo    decontamination      in accordance with the appropriate HP Procedures.
+In addition, onsite decontamination areas are equipped with decontamination supplies and other specialized equipment.
-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.
+Personnel found to be contaminated (any detectable activity above background) will undergo decontamination in accordance with the appropriate HP Procedures.
-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.
+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.
-.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                                                  ;
+Each emergency team will include members trained in first aid.
-trained personnel will accompany contaminated patients                             to    the     hospital,    'if. possible.
+First aid kits are available at station locations in accordance with PSC policy specified in the General Instructions.
+.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.
 .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.
+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 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION                    Page 15 of 21       l 0 Service
+DERP Section 6 Issue 1 0 Service
-* PUBUC SERVICE COMPANY OF COLORADO                                                              ;
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 21 PUBUC SERVICE COMPANY OF COLORADO O
-O                                   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.
+Hospital staff at St. Luke'.s are trained to treat contaminated
-Communications      between      FSV and   fixed medical facilities are via commercial        telephone and are handled in accordance with the MEP-FSV.
+: patients, Following decontamination, personnel suspected
-.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.
+'to have ingested radionuclides will undergo whole body counting at PSC or CDH facilities.
-.6.1   The statements concerning field monitoring sampling                  '
+Communications between FSV and fixed medical facilities are via commercial telephone and are handled in accordance with the MEP-FSV.
-and applicable isotopes from NUREG 0654/ FEMA-REP-1, Rev. 1, Table 3, is a result of QDR 87-083.
+.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.
+.6.1 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.
 {'~
-r/                                                                                                       .
+r/
 s/
 m FORM (Dl372 22 36tl
-                                                             ,,       ,,       ,      .   -f
+-f
-DERP Section 6 Public             FORT ST VRAIN NUCLEAR GENERATING STATION                               u             i O $9TVICe*                 Pusuc sanvece COMPANY OF COLORADO                                    Page 16 of 21   i 1
+DERP Section 6 O $9TVICe*
-NOTIFICATION CALL SEQUENCE REQUIRED IN THE EVENT OF A NOUE OR ALERT l    WELO COUNTY          l l COMMUNICATIONS l                l STATE DERP l j
+Public FORT ST VRAIN NUCLEAR GENERATING STATION u
-l          l      CENTER             l       l    FAN 0UT    l l
+Pusuc sanvece COMPANY OF COLORADO Page 16 of 21 NOTIFICATION CALL SEQUENCE REQUIRED IN THE EVENT OF A NOUE OR ALERT l
-I
+WELO COUNTY l
-:                                     i
+l COMMUNICATIONS l l STATE DERP l j
-;                                     l           l   COLORADO l
+l l
-,                                     l           l DEPARTMENT l
+CENTER l
-;                                     l           l OF HEALTH l i                                     l i-                                    l l
+l FAN 0UT l
-l         l        -NRC      l l         l OPERATIONS l                                                     .
+l I
-l         l      CENTER      l i                                     I l
+i l
-l I CONTROL l          l         l NRC RESIDENT l l    ROOM    l                 l      INSPECTOR l                                                                     I
+l COLORADO l l
-!                                     i 2
+l DEPARTMENT l l
-l l       l ON-DUTY l l       l       TA      l l
+l OF HEALTH l
-.                                     l 4                                     I
+i l
-:                                     I       I       PLANT      l l       l MANAGEMENT l l      CONTACT     l a                                                                              *
+i-l l
-                                     *******l        EMERGENCY       l~ ~ ~ l NOTIFICATION l
+l l
-!                                             l PAGER SYSTEM l                l        FAN 0UT-  l-CALL LISTS l                  l Not required for a.NOUE
+-NRC l
-]                - - - - Alternate to the Emergency Pager System e
+l l OPERATIONS l 2
+l l
+CENTER l
+i I
+l l
+I CONTROL l l
+l NRC RESIDENT l l
+l ROOM l
+l INSPECTOR I
+i 2
+l l
+l ON-DUTY l l
+l TA l
+l l
+I 4
+I I
+PLANT l
+l l MANAGEMENT l l
+CONTACT l
+a
+*******l EMERGENCY l~ ~ ~ l NOTIFICATION l l PAGER SYSTEM l l
+FAN 0UT-l-
+l CALL LISTS l
+Not required for a.NOUE
+]
+- - - - Alternate to the Emergency Pager System e
 FORM (0)372 22 3643
-y                                    -
+y b
-b                                     _
+d e
-d                                     .
+t t
-e                                    _
+a n
-t t                                    a n                                   u
+u e
-(                                                                   e                                 l
+l
-                                                                  .m                                    a              e                     -
+(
-y            t               sp                                       v            .h r            s               ni                                       e .        Pt
+.m a
-                                 'a gi                      gou                                                    R s ns                      niq                                         e          Er                        _
+e
-n                s      is                i te                .                    b            Ro o   l
+.y t
-                              . e iza                       ra                  s                                     f           e asssc                                 oue                                                     e M    cumie                                                       m                      l l s               tll                 a                el            dts E i trhn                it                iab                 e        o        ri             nan 62        ir     gaa otl rs ua tc                nva oets
+sp v
-                                                                         . t        t        aw             ato Si 1     e  l saoa                     t            m rn g                     ,s        as             e      t n6 2        s    o        f          en                   eoo n                 sl         it              tec o           e    rto s do                              n s pi            i      re         dl              aha it    f    D     e ni yn ac                            oe          t      r od              eu             tt tn o            tadro                ml               ihha                o    itom.        ms             s e ce               el uai                                tttt               t                        e          hv em17             mpast sa                              a      is         i      n          lR              eti sc                                       g o nmee   ors ta                                                a Sh ce 1
+.h r
-dsdea ib r           iinw l                                                   hit twc Paue             nsnc                ae               t       en m tuntcey n.                                     e Rtsg             aeaee ev                              ntni                                                 ,et Etsa                  s nv r                           esor n npe mr                                       sco                        -
+s ni e.
-DAiP             ssl i               ad n
+Pt
-                                                         .vido s s o emu        no                  enr cap waast                                            t     i luoq       ot o uac da                          ydsei                  t        ce ra                   nd ers l
+'a gi gou R
-ns   e     e                 enarn a f s ivo       r fairr ts                            va ao                i      fdn                         uou qco
+s ns niq e
-                       ,cvor                            r o m d                      eno nb to euct                  uatl                   a        ac ea                   eci sseac to                         se          el          r     g                l sar ervn                ot           eaonnrmne y in ,e                         s st uty onv
+Er n
-                                                                                                            . n a roaie rn uthdk ra pi r
+s is i
-s oon b                       sti         ocr ci                e ta                                edrso                         ul s iao arsot ep                        he rs s                           uf rrt edt rero              h ty txl er y esf ata tea epoCl pos iope                e beo vnr                      iii t        mfr              p v             r              oo sft m      nyil         ni           r      td               r   l f fcb              fii emecw tosn i r hu osnne u oan s i l go o a ftn n              el       ooi o es tc
+te b
-                       .rtgr            ie f'n r c eo          tt i
+Ro l
-t wis sd rt       eit          l n
+. e iza ra s
+f e
+o asssc oue m
+l e
+M cumie l s tll a
+el dts E i trhn it iab e
+o ri nan t
+t aw ato gaa tc nva 62 ir otl rs ua oets Si 1
+e l saoa t
+m rn g
+,s as e
+t n6 2 s
+o f
+en eoo n sl it tec o
+e rto s do n s pi re dl aha i
+it f
+D e ni yn ac oe t
+r od eu tt tn o tadro ml tttt t
+ito ms s e ihha o
+ce el uai m.
+e hv em17 mpast sa a
+is i
+n Sh 1
+sc ib iinw n ors lR eti a
+l a
+hit ce dsdea r
+g o mee t
+twc Paue nsnc ae t
+en m tc n.
+e Rtsg aeaee ev ntni tun ey
+,et Etsa s nv r esor n npe mr sco ad
+.vido o emu no enr DAiP ssl i o uac da ydsei t
+luoq ot cap waast n
+s s t
+i ce ra nd r
+ers ns e e enarn a f s ivo uou l
+fairr ts va ao fdn i
+,cvor ct r o m d eno nb qco to eu uatl a
+ac ea eci sseac to se el r
+g l
+sar ervn ot rmne roaie rn eaonn y in,e s
+. n a st uty onv uthdk pi s oon b sti ocr ci ta ra r
+edrso ul s iao e
+arsot ep he rs s uf rrt edt rero h
+txl er y esf ata tea m
+nyil ty iope e beo vnr epoCl iii pos t
+mfr p v l
+f fcb fii r
+oo sft ni r
+td r
+emecw i r osnne u l go o a ftn tosn hu f'n c wis sd n
+oan s i n
+el ooi o es tc r
+i
+.rtgr ie eo tt t
+rt eit o
+l s sro wS pi e n u n on l sc ayt l
+S el oet theo l
+ete pta a
+i l N
+roMma l
+l atmr nim mur teds O
+ur Er e.
+l t p
+p nns aot ntee I
+st e nm ismit n oos s n easi T
+sn.ep ne w oua i sme no ti ut C
+eotho ot erq r s
+,ac od i
+A rcut ss shfer s eds s peer p o m ry mt o a pl a nye mro
+/,
+T edoo es a df e
+S lsTe r
+y ton t
+o nfk iobh rmah N
+,hato p
+eneos n tie t
+oi t
+E td au M
+rd l t isi i m,m azn arr e a ced l eia e.rdo lar el g s a yk h i
+S v
+nl te s sa ya uael E
+edoir ut iebvy a sto el t
+ta S
+esvt fcn rvorc f
+eat tal csic S
+l rnon oee oe un sd ane aero A
+noero sm i b g m Al e d n
+ft tl ese e s s ian icl iio t s pC y s tss nn nr a as edo oide tnge.
+i'n s mili m l co mns reh 4
+e ool oe s aonb mi t ios tite n cg imar eont aid l
+e shi i
+d vl n bia nawa i ioe dp atmy aerl e at oi ne gl t se Curb rreim tas idsih d looa sty ae asws nti tammt e rl t b s ush area l
+oou lecn e tc ea hl ei naoae o t
+l p tadl at ts ce i ttm d iec desno n dtl rl m ceb l ayas chn ahyor a aea ooo noru PdbDa Ati RT sCf H Rmc fcc Pp il s
+tn m
+s e
+o y
+m o
+e s
+R v
+s y
+r e
+g l
+t u
+s n
 o S
-s sro wS                           pi e     n u n             l on     l sc ayt el oet                                theo                a    ete          pta          i l           .
+s i
-N       roMma              l l atmr                 l nim mur teds O       ur Er                e.          l t          p           p nns aot ntee I       st sn.ep ne e    nm             ismit                    n oos s n easi T
+i r
-C       eotho ot w erq oua i sme r s           ,ac no      ti ut od       i A       rcut                 ss           shfer s eds s                                            peer p o m ry                                         o a                                         mro
+l s A r
-  /,         T            edoo es mt a df pl a nye e                      rmah N         ,hato r
+t i
-p y        eneos               n  o nfk tie iobh         t     oi        t E
+l y
-M      lsTerd              l t ton isi t                        td                    au e a ced                   l eia S                 el            i         g s a yk h            i m ,m              azn         arr S
+o g
-E e.rdo v
+n b
-edoir larut        . nl te iebvy a sto s sa                    ya uael el             t      ta S      l esvt fcn rvorc                                     f      eat         tal            csic S             rnon oee oe un                                           sd          ane aero A       noero                             tl ese           e ms s ian                                 icl iio t s pCtss            ysm snn i nr a b         g           Al e d                 n ft as edo oide tnge.
+a e e t
-aonb               i'n s    e ool oe s mili m l co mns                        reh        4
+n o
-* n cgaid l
+a C
-i mi      t ios                    tite                                imar       e shi eont d
+t ic v c i
-aerl e vl n       bia at nawane oi i ioe gl t        se dp atmy Curb rreim tas                        idsih                  d looa           sty                  ae t
+i r n n
-asws b       s nti ush area tammt e l
+t n
-rl oou lecn          ea hl     e eitc naoae         o             t    i ttm d iec                                     l p tadl at        ts        ce l ayas chn ahyor a aea ooo noru desno n                      dtl          rl m               ceb PdbDa               Ati           RT sCf H Rmc fcc                                        il      Pp
+g u e o
-                                                               <                                                                     s t
+r fn u
-n m                                 s                            e o                                 y                            m o                                 e                            s R
+o S u M
-y v
+o oo o
+l y e q p
+i c
+o e
+l et c
+i r s a
+R ca A
+d a n t
+nt a
+d o
+n t
+an l
+R n c e
+n l e e
+u m
+e
+~
+m n
+t o e n
+m l
+iu n
+n B
+t o
+s er o
+a i
 r s
-e           g l
+vt s
-t             u                            s            n o                  i             S                             s          i r                  l s A                r                                         -
+e s i
-t                   i             l                        y                o              g n                  b              a                       e e              t              n o                   a                                     v c             i              i C                    t            ic                       r n               n             t n             g                       u e               o             r fn                   u             o                     S u               M               o oo                  o            l y e q                          p i
+e n
-c             o                                       l e
+rs r
-et                  c            i r s               a            R ca                 A             d                        a n              t nt                                a                     d      o            n             t an                 l R                        n   c             e             n                           -
+p t
-l e                  e                                     u                 m             e l
+f v
-m              n             t                       o et              n             m                           ~
+s o
-iu                   n             n                     B                   o             s
+un e
-* er                  o             a                           i             r             s
+n i
-!                n vt rs s            !
+f n
-e sf            i e
+s i
-o    un r
+Si P
-e p
+I S o E
-n t                  v             s Si                  P i     f             n             s i
+A tc A
-t I
+2
-S o               E              A c      .                   .             .                      .     .           .              .
+J 4 5 6
-A    1                   2             J                      4 5               6              7
-                                                                                                    ~
+~
-i*              ;;J!! ;               ;!l        '.;3                 i1i;!                    ; '   !j'          '.!il                          ltjti          :   .,? '' , >        rb jr h,            i[!'               t!5$
+jr h,
-t s
+i[!'
-u m
+i*
-t n              r e                o id                e c               l p
+t!5$
-i n               i c
+;;J!! ;
-                                                                    ,                                                                                         e                n h                i t                r p
+;!l
-                                                                                                                                       f 1                                                                                                                                o                 e n6 2                                                                                                                                                      h e                t io t      f                                                                                                                                m tn o                                                                                                                                     i                h                                       ,
+'.;3 i1i;!
-ce                                                                                                                                        t                t em18                                                                                                                                                      i Sh        1                                                                                                                                e           . w ce                                                                                                                                     h t                 g Paue Rtsg                                                                                                                                                         n Etsa                                                                                                                                       t               i DA1P                                                                                                                                       a                 p y                                                                                                                                     e d                                                                                      e                               s                 e o                                                                                   b                                n               k b                      dy                                          n                                                   o e                  ea                            ,n           e                  d              .                i                 n lem ol u
+!j'
-dm n
+'.!il ltjti
-esr                       i to r sird tol n l
+.,?
-u tl o ob e                 is.
+rb tsu m
-c)         s i
+tn r
-hp                       mno mo xafie                              wfni                            ee n dr o w                                                er hm                                   i s s                  oid                             enco                           r eero es                              u       i eu                    cte                        sde- w                                                              nd               t co                    ecr                        tivf                                tvep                            oe c ds ue ea rae.
+e o
-lyeid d                 i nsiot ng n ao na l
+id e
-et y hanl iw                         i to cr c a e
+c l
-                                      /
+n p
-rg s'     sint vse                    t rceon   big snoe rit ap v i
+i ic e
-da              t        utoa                       sl             te                  gota                            eg t i                n      occn                        nadar                              ntai                             vn c oo             e     i eei                     oil up                            it ud                     ii                 e vt             m      vtrm                        ccuc                              kace                             tt               t                                            .
+n h
-a              m       eo r                           eoad                           e am                            cn o e           o       rree                     f ph v n                             envm                            ee rp or            C      P pb t                     I     ssea                          SaeI                             tm tu                                                                                                                   oe                          .
+i t
-s                                                                                                                  rl              te so np Pp                 cl
+rp 63 f
-                                                                                                                                                  .                  m ab ox                     s                              e-                               .            . ns                    i pa ie                       n d                            t                              n               os                 .              mv                                 .
+o
-t                      o      n,                                                     o                   e sP i e cm                   i as                           .au                             i                dc eR                                  i aor                   t             n             mc-                    l           t               ec               sE               wh cnro                       ua                      o r
+e n6 2 h
-a            -a sa poD oc ef            l        aaei imve                                  u                                              l a v              a              tt                     Ek                  t           c               bl               ro                 .
+io e
-ie              f        eel cl                              a              n           al -               o ut ty ts co             s vueua ishrt in.ml mn ao tC' va- '
+t t
-et -rot nr p r eb nl ed     ic      n tsstn.                          os n                                n oin ge ma o                    se            ait' e.                             ye rms fto  0C ienf len t                      ci od     l      i e knms                                                                                                                 o ri     b ' t          tyeinl                      sai tn.ms           nl              onl au                          nr ps po      u      c       oae oe aual oe
+f m
-                                                                                                                                                                       -imae dy r   P      A        rmsrrv p
+h tn o i
-crarv                          toeec.
+ce t
-arvra                           n(
+t em18 i
-a r
+e w
-eie           ratcie                            dieavs                           l n po y eh     l      d            eohvl evsivl                                               nvl            el dt'      a      e      dtttn ea        ren tentn                               m'nsyv a           t      e                  i as n
+Sh 1
-e'r ocen r     d                                                                                                       rt ma c rri. ao l
+ce h
-ed      e      n       ntyu o                                                                 oure oafr mn' ma' n
+Paue t
-e e
+g Rtsg n
-m nSrfri he a o ot sd s po t s cotdt t!ijol
+Etsa t
-                                                                                                                                                                 ;e           lswo o      G        m     l stta                   i smtas utaaae sd c              o       p.iiii                    kseiiie                             dii             ds               ti             ial       -
+i DA1P a
-e              c          )    vand               enl                 ndc nnddne                                    is                 cs                                          .
+p y
-R               e R        obdwoa N(aaHr          SCuiMra   eontoac     CMramt                ooanah imno                                  f i a                                  s l
+e d
-c fs oer do et               ;u dn ts ni               no ep
+e s
-                                                  )                                                                                                           e-m                                                                                                          ms dx e                                                                                                          mn ie
+e o
-                                                 .R
+b n
+k b
+dy n
+o n
+e ea
+,n e
+d i
+lem dm to r l
+e s.
+i u
+n sird u
+tl i
+tol n o ob c) s ol esr i
+hp mno xafie wfni ee n i s dr o w
+mo er hm s
+oid enco r es u
+i eu cte sde-w eero nd t
+co ecr tivf l
+tvep oe c ue rae.
+nsiot iw c a i
+d ng n et y to ds rg lyeid i
+ea ao na hanl cr e vse rceon snoe ap v
+/
+s' sint t
+big rit i
+da t
+utoa sl te gota eg t i
+n occn nadar ntai vn c oo e
+eei oil up ud e
+i it ii vt m
+vtrm ccuc kace tt t
+a m
+eo r eoad e am cn o e
+o rree f ph v n envm ee r ssea SaeI tm p
+or C
+P pb t I
+tu oe s
+rl te so Pp cl m ab np ox s
+e-
+. ns i pa ie n d t
+n os mv
+.a o
+e sP i e t
+o n,
+cm i as u
+dc eR i
+i ao t
+n mc-l t
+ec sE wh r
+cnro ua o
+a v
+a tt imve r
+u
+- sa oD oc ef l
+aaei a
+p l a Ek t
+c bl ro ie eel cl o ut ty in.ml a
+n al -
+nr p
+nl f
+ts vueua ao va- '
+mn tC' et -rot r eb co s
+ishrt t
+ic n
+ed tsstn.
+ait' e.
+ye fto nf len os n n oin ge ma o
+ci se e knms tn.ms rms 0C ie o
+od l
+i ri b
+' t tyeinl sai nl onl au nr ps po u
+c oae oe aual oe toeec.
+n( -ima r
+P A
+rmsrrv crarv arvra a
+e dy p
+eie ratcie dieavs l n r
+d eohvl evsivl nvl el po y eh l
+m'nsyv i as dt' a
+e dtttn tentn a
+t e
+n r
+d ea ren rt ma ocen l
+ed e
+n ntyu o e'r c a o oure oa mn' n
+e nSrfri he rri.
+t!ijol fr ma' e
+m a o ot sd s po t s cotdt
+;e lswo o
+G m
+stta i smtas utaaae sd c
+o p.iiii kseiiie dii ds ti ial l
+vand enl ndc nnddne is cs e
+c
+)
+R e
+obdwoa eontoac ooanah imn i a s
+R N(aaHr SCuiMra CMramt o f c fs l
+oe do r
+et
+;u dn ts ni no e-ep
+)
+m ms dx e
+mn ie
+.R oo c
+~
+(
+ci nn et io e
+ri i
+s d et o
+e
+en ha Dn v
+ro ti o
+n o e ac
+-d lei a
+-.
+b v
+fa t
+h a o sgor
+.ba t
+n 5
+b nn al a
+d a
+oi eg du s
+h-o
+.5 n
+it mn i p s
+t t 2 a d ts ii oo e
+. o 5'
+a ax i
+n ci tn vP s
+l
+.A s
+t
+.e ea e
+y e y
+y 5 e
+ht dh d
+d 5 d
+-se tn l
+et o
+o-o ek i
+t B d B
+d' b d ha ta co et e o e i i
+Tt Am i
+o o y l
+- r leo-o l
+r r
+j o y o y
+)
+)
+r h h -
+hh h
+h-a b
+- P W
+T W
+T' W
+T.
+- (
 (
-oo ci cnn                        ~
+s
-et io e                                                                                                          ri                    i s                                                                                                                d et o           1                                                              e                               en ha Dn n
+~
-v                               ro               ti o                                                                     o e                             ac                 -d leit         a     5-.                                                    b        v sgor fa                                            _
+,a lt; 4;
-h                                                               a o
+l:'
-                                                  .ba          t       n                  5                                          b                        nn               eg al                  a                                                      d       a                       oi du i p s
+ic4'
-s h-t o .5                               n                              it ts ii mn t 2                                 a d oo          e                                                                     n                       ci               tn vP         l       s                  1      .o                           5'      a                       ax                     i
+. i ;!'
-                                                 .A             y e s
+jI:i'
-y t                                                               .e         ea                                   .
+:i
-e                                                                     y 5                              e               ht dh          d      l                   d 5                                 d      2-                       se tn                                                        .
+,Iili j $lii 3!iI:iI.
-et          o                          o-                                 o                                ek                    i
+E1l i
-   -                                               t           B d                        B        d'                         b d                             ha ta co                i                                                              i                        Tt               Am e -ior                                                                                                                          .
+tk'
-j et l
-e or                      l                                   leo-    r o           o y                        o y                                o y                             )                )
-r          h h -                      hh                                  h       h-                       a               b
-                                                 - P           W      T                   W         T'                        W       T.                      (           - (
-s                                                                                                                                                                                                                       -
-                                                                                                                                               .                       -                   ~
-            ,a  ,
-lt;    4;                   ;!                    ic4'            . i ;!'             jI:i'                              ,Iili j $lii                                                    tk'
-O                                                                                       O                                               O DERP Section 6 Attachment 6.3   .
+O O
-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 emergency workers, include                                Al though respi rators and
+O DERP Section 6
-{i\
+*.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)
-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.
+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.
+(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
 a I
-_ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _                                              m                                                                                                   -
+m
 (
-         %                                                                                                                               V DIRP Section 6 Attachment 6.4 Issue 1 Page 20 of 21 Exposure Criteria for Emergency Workers *
+V DIRP Section 6.4 Issue 1 Page 20 of 21 Exposure Criteria for Emergency Workers *
-               . Situation                                             Whole Body                                    T hy ro l d * *
+. Situation Whole Body T hy ro l d *
-: 1. Emergency duties not related                                       5 Rem                                         25 Rem to protecting equipment, personnel, or the public.***
+* 1.
-: 2. Prevent extensive equipment                                      25 Rem (planned)                              125 Rem damage, further escape of effluents,                             12 Rem (unplanned) or cont rol fires.
+Emergency duties not related 5 Rem 25 Rem to protecting equipment, personnel, or the public.***
-: 3. Lifesaving missions, e.g., sea rch                                75 Rem                                        Unlimited ****
+.
+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".
+* Admini stered in accordance with DERP Implementing procs t'
-     ** Respiratory protection will be provided as necessa ry.
+%RP. MP, " Emergency Exposure Guidel ines".
-   *** 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.
+** Respiratory protection will be provided as necessa ry.
-  **** 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.
+*** 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
 i
-l DERP Sectioa 6 Attachment 6.5 Issue 1
+l DERP Sectioa 6
-(                                                                                                                                    Page 21 of 21 B
+'.5 Issue 1
+;(
+Page 21 of 21 B
 i
-                                                                                                                                                                                            +
++
-Use of Protective Iquipment and Supplies                                                                                       t l
+Use of Protective Iquipment and Supplies t
-Criteria for                                                                                                                           i 1 uts i pmen t                                  issuance                             l_oca t ion                            Means of Distribution                                    i
+l Criteria for i
-                                                                                                                                                                                            +
+uts i pmen t issuance l_oca t ion Means of Distribution i
-: 1) Full Faco Canister                        As needed by Emergency Teams ' in areas of high a) Selected Emergency Monitoring Mits a) Issued at TSC                                        ,
++
-Respi rator .
+: 1) Full Faco Canister As needed by Emergency a) Selected Emergency a) Issued at TSC Respi rator.
-airborne radioactivity                  b) Respiratory issue                    b) Picked up a t nea rest                              i Lockers-Turbine Deck.              station as directed                                'l by Health Physics Pe rsonne 8.                                         I
+Teams ' in areas of high Monitoring Mits 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
+airborne radioactivity b) Respiratory issue b) Picked up a t nea rest
-                                                       . excess ol' administratively                                                    Health Physics
+'l Lockers-Turbine Deck.
-                                                        ' set' levels                                                                   Personnel.
+station as directed by Health Physics Pe rsonne 8.
-c) Toxic . gas haza rd
+I
-: 3) Protective Clothing                       As needed in a rea s of                  a) Various Areas of                     a) Issued as needed by
+: 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
-( Cove ra l i s, Hood s, -             known contamination                             the station.                       Health Physics Boots; Cloves). '                                                              b) Emergency Kits .                        Personnel.
+.b) Issued as needed by
-b) Issued at TSC tt) Ai r-fed Respi rator                      Airborne radioactivity .                 a ) Cont ro l Room         .
+. excess ol' administratively Health Physics
-a) Used.as required by in excess of administratively           b) Respiratory issue                       ope ra to rs.
+' set' levels Personnel.
-s set" levels.                                    Lockers-Turbine Deck.           b) issued-by Health Physics 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.
 e e
 h
 s
-    .n.                          u          --    .-                  .
+.n.
-L,              '
+u L,
-                                                                                               . , -  --.n,_.,.      2 ---..x ,_ ; _     .    . . _ . , , _ _ . , ~~ - . ~ . . . _ , , .
+---..x
+.. _.,, _ _., ~~ -. ~... _,,.
+--.n,_.,.
-Issue 1 9'           2I Public            FORT ST. VRAIN NUCLEAR GENERATING STATION 0SerVIC9'                PUBLIC SERVICE COMPANY OF COLORADO TITLE:       DEFUELING EMERGENCY RESPONSE PLAN: SECTION 7 EMERGENCY FACILITIES AND EQUIPMENT      ,
+Issue 1 9'
-PONSIBLE 3" """ g)$L                                                                                            .
+I 0SerVIC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO TITLE:
-TlVE lgem                     PCEO 9 21 FEB 131991                 [F TE DCCF NUMBER (S)        h-/ 2.3 l
+DEFUELING EMERGENCY RESPONSE PLAN: SECTION 7 EMERGENCY FACILITIES AND EQUIPMENT PONSIBLE 3" """ g)$L lge PCEO 9 21 FEB 131991
-                                                                         .o l
+[F TlVE m
+TE DCCF NUMBER (S) h-/ 2.3 l
+.o l
 PT. ST. VRAIN NON CONTROLLED COPY VERIFY 188UE STATUS WITH SITE DOCUMENT O
-CONTROL CENTER PRIOR TO Ued FORMt01372 22 3642
+CONTROL CENTER PRIOR TO Ued FORMt01372 22 3642 m
-                                                      ,      ,      -     -        ..                 m
-DERP Section 7 Issue 1 Public           FORT ST VRAIN NUCLEAR GENERATING STATION 0 Service
+DERP Section 7 Issue 1 0 Service
-* PusWC SERWCE COMPANY OF COLORADO 7.0 EMERGENCY FACILITIES AND E0VIPMENT                                                                            i This section describes: emergency response facilities; onsite and offsite communication systems links; assessment facilities                                            1 andegyipment; protective {acilitiesandequipment;firstaid                               ,
+* Public FORT ST VRAIN NUCLEAR GENERATING STATION PusWC SERWCE COMPANY OF COLORADO 7.0 EMERGENCY FACILITIES AND E0VIPMENT This section describes:
-i and medical facilities; and damage control equipment and supplies.
+emergency response facilities; onsite and offsite communication systems links; assessment facilities andegyipment; protective {acilitiesandequipment;firstaid and medical facilities; and damage control equipment and supplies.
-.1   EMERGENCY RESPONSE FACILITIES                                                                 ,
+.1 EMERGENCY RESPONSE FACILITIES 7.1.1 Technical Support Center (TSC)
-.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
-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.
+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
+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.
-,                                              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,.
-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.
-* specifications, and procedures are maintained in the TSC.      Radiation monitoring equipment, protective clothing, communications equipment, protective breathing apparatus, and first-ai<l            -
+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.
-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.
-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                                       -
+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.
-convenient location, as directed.
 I
 Ponutom2 22 see l
-  -   . - . _            -    .         . . .       - - . _ . . . - - . . - - .   .-.       . . ~     - - . - - - - -            -
+.. ~
-DERP 5ection 7 4                                                                                                 Issue 1 Public                 FORT ST. VRAIN NUCLEAR GENERATING STATION 0 SGTVlC9'PusuC SERVICE COMPANY OF COLORADO 7.1.2 Control Room (CR)
+DERP 5ection 7 Issue 1 4
-Energency assessment eno contr61 is initially                                          ;
+SGTVlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO 7.1.2 Control Room (CR)
-directed from the CR by the Shift. Supervisor prior                                    ,
+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.
-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.
-.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.
+.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
-* 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.
+Communications between onsite and offsite consist of commercial telephones and dedicated microwave links.
-.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                                   -
+From the TSC, messages are relayed to designated agencies via Weld County, 000ES, and Colorado National Guard radio O
-used in the assessing situation.
+communication systems. Two-way radios will be used to maintain communications between the TSC and inplant teams.
-.3.1 Onsite Systems and Equipment
+Primary telephone and radio cennication links between the TSC and the CR shown in Attactment 7.1.
-: a. Geophysical data collection / analysis equipment is grouped into two categories:
+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.
+.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
-_ _ _ . . .            . . _ . . ._ _ . . _ _ _ _ _ . . . _ . .         __     .   .        - _ _ . _ _ _     . _ _ _ .       _ _ _ _ _ _ _ ~ .
+_ _ _ _ _ _ _ ~.
-DERP Section 7 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION 0PubilC             Service
+DERP Section 7 Issue 1 0PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION Service
-* Pusuc ssRWCa COMPANY OF COLORADO
+* Pusuc ssRWCa COMPANY OF COLORADO 1.
-: 1. Meteorological Monitors Information is obtained from installed instrumentation on the primary 60 meter metporological tower with readout in the                          ,
+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,
-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.
+tettperature, and temperature differential with height.
-: 2. Seismic Instruments Information is obtained from passive and active instruments giving absolute peak acceleration in three orthogonal m                                                                    directions. The system determines h
+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.
-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<-                 -
+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,-
+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
-   . .. - - .        -.    . _ _ _ _ ~ _ - - - .                        - .-         - . - . - . _ .          .- -      ..               .
+_ _ _ _ ~ _ - - -.
-DERP Section 7 Issue 1 89' Public                 FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service
+DERP Section 7 Issue 1 89' 0 Service
-* PusuC SERVICE COMPANY OF COLORADO
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO 2.
-,-                                                   2. Equipment Monitors J
+Equipment Monitors These monitors determine radiation levels J
-These monitors determine radiation levels in specific effluent streams. Redundant
+in specific effluent streams.
-             ,                        ,                    monjtorsareprovidedseparatepower sources.
+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 1                                                         scintillator which is coupled to a                                      '
+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.
+.
+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,
+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
-: 6. Emergency Stack Monitor (PING)
+: analyzer, 6.
-This device is a single unit containing                                  -
+Emergency Stack Monitor (PING)
-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.
+This device is a single unit containing particulate, iodine, and noble gas monitors to measure Reactor Building ventilation exhaust effluent during a i
-: 7. Reactor Building Ventilation Exhaust Stack Monitors This system monitors exhaust air from the reactor building for particulates, noble gas, and Iodine-131 contaminants.                                          -
+loss of power to the normal operating stack monitors.
+.
+Reactor Building Ventilation Exhaust Stack Monitors This system monitors exhaust air from the reactor building for particulates, noble gas, and Iodine-131 contaminants.
 row toim.m.see
 u w section /
-Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION 0Public     Service
+Issue 1 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Service
-* PUBUC SERVICE COMPANY OF COLORADO
+* PUBUC SERVICE COMPANY OF COLORADO c.
-: 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
+System Monitors detect and/or control problems within plant syst6ms.
-    ,                                                        .,                 monitorc plant parameters. Many of these                                        ,
+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,
+detectors are capable of initiating control actions to prevent or mitigate damage or release of radioactive material, d.
-: d.        Fire Protection Systems have been designated
+Fire Protection Systems have been designated to meet the criteria of 10CFRSO Appendix R.
-* 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.
-Specific information regarding Fire Detection / Suppression at FSV is contained in the FSV Fire Protection Program Plan,
+Radiation Analysis is cecoinplished using radiochemical laboratory equipment, radiation monitoring stations, and fixed air sampling stations to provide the capability for detailed, isotopic analysis.
-: 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.
-: f.       portable Survey Instruments provide flexibility and backup capability for radiation measurements in areas not served by installed monitors or where installed monitors O
+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.
+t may be inoperative.
 Specific equipment and their locations for FSV onsite radiological assessment is summarized in Attachment 7.2.
-                                                                                                                                                    .a    .
+.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).
-.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                                                    -
+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.
-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.
+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.
-v                                .
+v
 l FORM (Dl372 22 3843
-DERP Section 7 Issue 1 Public                FORT ST. VRAIN NUCLEAR GENERATING STATION 0 $9fVIC9'                     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      ,
+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 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.                               ,
+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.
-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.
+Portable radiation monitoring instrumentation, protective breathing apparatus, protective clothing, and portable lighting are available near the CR.
-First-aid treatment of injured individuals will be                              3 administered by trained personnel. Advanced medical care, if required, will be obtained by transporting the
+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.
-* individual (s) to St. Luke's Hospital and/or North Colorado Medical Center.
+In the event of an emergency, another first-aid area is provided in the HP access area.
-.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                 *
+First-aid treatment of injured individuals will be 3
-(SCBA) equipment is located strategically throughout the                         ~
+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.
+.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
+~
 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       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               -
+.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.
-weather or road conditions and is under the direct control of Emergency Planning personnel.
+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.
-.8       COMMITMENTS None O
+.8 COMMITMENTS None O
 Mill 10) U2
 * 22
 * M43
-Uthf bt Ction /
+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
-Attachment 7.1 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 21 0Public  SerVICO'                                     PusuC SERVICE COMPANY OF COLORADO Gi         l PRIMARY AND SECONDARY COMMUNICATION LINKS l PSC MEDIA                   l                                     l l                 CENTER      l                    *****************l CONTROL ROOM l                              l                                     I                   1 1                                                            I                i l                                                            I I                                                            I I               l                  . I                     I l                l TECHNICAL SUPPORT l                       l
+PRIMARY AND SECONDARY COMMUNICATION LINKS l PSC MEDIA l
-                                                                @pKcC9@@@@@@@l          -CENTER        l@@@@@X R *M " a
+l l
-                                                                @                l                     1                     @
+CENTER l
-                                                                @l ,'                        I                             l@
+*****************l CONTROL ROOM l
-                                                                @l                           I                             l@
+l I
-ONSITE                               @l                           l             CENTERS l@
+1
-                                                                @!                           l                               @
+I i
-                                                                @                            l                              ,@
+l I
-FFSITE                                @l                           l             AGENCIES l@
+I I
-                                                                @l                           l                             l@
+I l
-                                                                @l                           i                             10 l WELD COUNTY l                      l COLORADO DEPT,   l          lNRC OPERATIONS l ICOMMUNICATIONSj                    l    OF HEALTH     I          l      CENTER      l t                                                           CENTER I                           l       l                  l          l                  l_
+I I
-LEGEND:                                                  Primary Link Commercial Telephone Lines or Dedicated Microwave Lines            ,     .
+l l TECHNICAL SUPPORT l l
-                                                         ***n****ene*****   Secondary link PSC Radio System
+@pKcC9@@@@@@@l
-                                                         @@@@@: ga@@@@@@@ Backup Link Commercial Telephone Lines NOTEj, The TSC and CR also have the plant Gai-Tronics system available for their use.
+-CENTER l@@@@@X R *M " a l
-o                                                                                                                                         -
+I
-PORM(Dl372 22+3843
+l@
+@l,'
+I l@
+@l ONSITE
+@l l
+CENTERS l@
+l l
+FFSITE
+@l l
+AGENCIES l@
+@l l
+l@
+@l i
+l WELD COUNTY l l COLORADO DEPT, l
+lNRC OPERATIONS l ICOMMUNICATIONSj l
+OF HEALTH I
+l CENTER l
+t I
+CENTER l
+l l
+l l_
+LEGEND:
+Primary Link Commercial Telephone Lines or Dedicated Microwave Lines Secondary link
+***n****ene*****
+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 t
+DERP Section 7.2 t
-Attachment 7.2 Issue 1 Public           FORT ST VRAIN NUCLEAR GENERATING STATION Page 9 of 21 0 Service
+Issue 1 0 Service
-* Pusuc sERWCE COMPANY OF COLORADO O                            ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument                     Description and            Functional
+* Public FORT ST VRAIN NUCLEAR GENERATING STATION Page 9 of 21 Pusuc sERWCE COMPANY OF COLORADO O
-* System                        Location              Applicability          ,
+ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Description and Functional
-: 1. Geophysical Monitors Meteorological       Wind Speed Indicators              Measures wind speed @          -~
+* System Location Applicability 1.
-located on 60m tower               58m above ground north of the plant.                level and 10m above ground level.
+Geophysical Monitors Meteorological Wind Speed Indicators Measures wind speed @
-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.
+located on 60m tower 58m above ground north of the plant.
-O                                   Rain Gauge on 60m                  Measure precipitation        -
+level and 10m above ground level.
-tower.
+Wind Speed Indicator Measures wind direction located on 60m 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.
+@ 58m and 10m above north of the plant-Same ground level Instrument as previous
-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.
+: listing, Delta Temperature Sensors Measures temperature located on 60m tower differential between north'of the plant.
+m 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
+FORM (D)772 22 3M3 i
-;                                                                                                                  i
-UtKP bection /
+UtKP bection /.2 Issue 1 OService*
-Attachment 7.2 Issue 1 Public           FORT ST. VRAIN NUCLEAR GENERATING STATIONPage 10 of 21 OService*                 PUBUC SERVICE COMPANY OF COLORADO O                             ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument                         Description and                Functional
+Public FORT ST. VRAIN NUCLEAR GENERATING STATIONPage 10 of 21 PUBUC SERVICE COMPANY OF COLORADO O
-* System                                   location            Applicability             ,
+ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Description and Functional
-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                 -
+* 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.
-record on the glass.
-l I
-l O                                                                                                                 .
-                                                                                              .g   .
 l O
-FORM (o)372 22 3043 I
+.g l
+O FORM (o)372 22 3043 I
+e r.-
-utne section /
+utne section /.2 Issue 1 0SerylCO*
-Attachment 7.2 Issue 1 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 21 0SerylCO*                PUBLIC SERVICE COMPANY OF COLORADO O                         ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:              For monitor setpoints refer to the FSV Master Setpoint List.
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 21 PUBLIC SERVICE COMPANY OF COLORADO O
-Channel and' Radiation Transmitter         Description and              Control Number               Location                 Action                                  .
+ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
-: 2. Radiation Monitors Liquid Monitors
+For monitor setpoints refer to the FSV Master Setpoint List.
-                                                    ~
+Channel and' Radiation Transmitter Description and Control Number Location Action 2.
-RT6212 &           Radioactive liquid     10 ' uCi/mi (also, if RT6213             effluent monitors. cooling tower blowdown Reactor b dg.-         drops to < 1100 gpm),
+Radiation Monitors Liquid Monitors
-Elev. 4771'            closes HV-6212 &
+~
-HV-62249, trips transfer pump P-6202 & 6202S,                      '
+RT6212 &
-and trips reactor building sump pumps to prevent 1 X 10 ~7 pCi/ml MPC value at site
+Radioactive liquid 10 ' uCi/mi (also, if RT6213 effluent monitors.
-,                                                  perimeter from being exceeded. (ELCO 8.1.2)                     ,
+cooling tower blowdown Reactor b dg.-
-RT46211           Gas waste               No control action RT46212           compressor cooling water monitor.                                  #    '
+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                                                                                               -
+Elev 4740' O
 i l
 FORM tD)372 22 3643
-Attachment 7.2 Public                                                    FORT ST. VRAIN NUCLEAR GENERATING STATION                        12 of 21 0$9fylC9'                                                        PUBLIC SERVICE COMPANY OF COLORADO m
+...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.
+ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
-Channel and' Radiation Transmitter                                       Description and                                             Control Number                                                       Location                                       Action Gas Monitors (Plastic Beta Scintillators)
+For monitor setpoints refer to the FSV Master Setpoint List.
-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                             '
+Channel and' Radiation Transmitter Description and Control Number Location Action Gas Monitors (Plastic Beta Scintillators)
-room ventilators. Also, closes reactor supp.
+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                               -
+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.
-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.
-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.                           -
+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                                                                                                                                                    -
+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 Attachment 7.2 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                       13 of 21 0PublicServ lCO'             PUBLIC SERVICE COMPANY OF COLORADO O
+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:
-G ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:                 For monitor setpoints refer to the FSV Master Setpoint List.
+For monitor setpoints refer to the FSV Master Setpoint List.
-Channel and' Radiation Transmitter             Description and                Control Number                    Location                   Action                                                                                                        .
+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.
-RT73437-1             Reactor Plant            ELCO 8.8.1 -Close valve Ventilation Exhaust       FV6351, divert flow to lodine-131               gas waste vacuum tank.
+Monitor Loc:
-Monitor Loc:              Shutdown turbine building Sampler / Detector:       ventilation and place E1.,4916              the control room vent-Turbine Side          ilation on recirculation.
+Shutdown turbine building Sampler / Detector:
-Readout E1. 4829                                                                                                                              ,
+ventilation and place E1.,4916 the control room vent-Turbine Side ilation on recirculation.
-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                                                                                       '
+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.
-gas radioisotopes. A 2 inch by 2 inch NaI(T1) crystal is utilized as the detector for this monitor.
+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                          '
+RT73437-2 Reactor Plant Same automatic action Ventilation as RT73437-1.
-Ventilation               as RT73437-1.
 Exhaust Beta Particulate Monitor Loc:
 Samples / Detector:
-E1. 4916 Turbine Side                                                                                                                            ~
+E1. 4916 Turbine Side Readout
-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.
+~
+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 Attachment 7.2 Public           FORT ST. VRAIN NUCLEAR GENERATING STATION Pa          1 of 21 OSerVlC9'              PusuC ssRVICE COMPANY OF COLORADO O
+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.
+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)
+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 Reactor Plant Ventilation RT 4802 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
+RT 4801 Reactor Plant Ventilation Exhaust Beta Particulate Monitor Loc:
-                                                                                         .o Exhaust Iodine and Particulate Monitor Loc:
+E1, 4885, turbine side RT 4802 Reactor Plant Ventilation Exhaust Iodine Monitor Loc:
-Samples / Detector:     El. 4921 Turbine Side Readout                 El. 4829 Control Room RT 7325-2                  Reactor Plant Ventilation                                  -
+E1, 4885, turbine side RT 4803 Reactor Plant Ventilation Exhaust Noble Gas Monitor t
-Exhaust G-M Detector Loc:
+Loc: El. 4881, turbine side Reactor Building Ventilation Exhaust Stack Monitor RT 7325-1 Reactor Plant Ventilation
-Sampler / Detector:     El. 4921 Turbine Side Readout                 El. 4829 Control Room I
+.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 Attachment 7.2 Public           FORT ST. VRAIN NUCLEAR GENERATING STATION Pa                                                                      'fof21 I
+i DERP Section 7.2
-OService*                Pusuc sanvics company or coton4oo O
+'fof21 OService*
-ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:            For monitor setpoints refer to the FSV Master Setpoint' List.
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pa I
-Channel and' Radiation Transmitter                                    Description and Number                                             Location                                                                                                                ,
+Pusuc sanvics company or coton4oo O
-TSC Ventilation Monitor RIT 7937                           TSC Ventilation Inlet and TSC Ambient Atmosphere                                                                                                                      l Particulate, Iodine, Noble Gas Loc:
+ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
-Sampler / Detector:                        El. 4791
+For monitor setpoints refer to the FSV Master Setpoint' List.
-* TSC Building Readout                                    El. 4791 TSC Building O                                                                                                                                                           .
+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:
-                                                                                                                                                         .o       .
+Sampler / Detector:
-O l
+El. 4791 TSC Building Readout El. 4791 TSC Building O
-FORM (01372 22 3043 l
+.o O
-l   ,_                             - . .                   ___         . , . . ,     .,       . . . , _ .             _ _ _ _ _          _ _ _ . _ _ _ _ . ._          _ _ _ , _ . . . , . _ . _ _ . ,       _
+l FORM (01372 22 3043 l
+l
-DERP Section /                ;
+DERP Section /.2 Issue 1 0 Service
-Attachment 7.2                i Issue 1 Public            FORT ST. VRAIN NUCLEAR GENERATING STATION Page 16 of 21 0 Service
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 16 of 21 Pusuc sanvece comeAmy or cotonApo O
-* 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
+ONSITE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
-* 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                                              ,
+For monitor setpoints refer to the FSV Master Setpoint List.,
-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                                         <   -
+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
-R193251-5                Gas Waste Filters               4781 RT93251-6                Truck Bay                       4791 RT93252-6               Near South Stairwell            4791 RT93251-7               Core Support Filter             4781                                              -
+a'eazs1-2 set s vic 8,
-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
+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 /
+East Wall i
 l l
 I FORM (D)712 22 3043
-DERP Section 7 Attachment 7.2 Public                FORT ST. VRAIN NUCLEAR GENERATING STATION Pag 1 of 21 OSerVlCG*                         PUBUC SERVICE COMPANY OF COLORADO O
+DERP Section 7.2 OSerVlCG*
-ONS:TE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:             For monitor setpoint9 refer to the FSV Master Setpoint List.
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pag 1 of 21 PUBUC SERVICE COMPANY OF COLORADO O
-Channel and Radiation Transmitter                                                          Control                                ,
+ONS:TE ASSESSMENT EQUIPMENT AND FACILITIES NOTE:
-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
+For monitor setpoint9 refer to the FSV Master Setpoint List.
-* l RT9 251-4              General Office Area                 4816 l
+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
-l RT93250-5              Control Room                        4829 Technical Support Center Area Radiation Monitor RIA-7951               Technical Support Center           '4811
+'4811 3.
-: 3.         System Monitors Process Monitors affecting the Assessment of Radiological Accidents are shown in Attachments Cl-C14 of DERP Section 4.
+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 -
+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 /
+Uthr beCLlon /.2 Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION age 18 of 21 P
-Attachment 7.2 Issue 1 Public                FORT ST. VRAIN NUCLEAR GENERATING STATION                               P age 18 of 21 Service
+Service
-* rusuc sunvice comeAmy or cotonApo                                                                             '
+* rusuc sunvice comeAmy or cotonApo O
-O                                ONSITE ASSESSMENT EQUIPMENT AND FACILITIES                                                   ,                       l
+ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument.
-         ,             Instrument.               Description and                      Functional System                         Location                     Applicability l
+Description and Functional System Location Applicability 5.
-: 5. Facilities                                                                                                                        l Whole Body Counter                     Detect, identify, and                                          -
+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.
-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
+Fixed Air Sampling Sample particulates and Stations-Just Outside radiciodines(operated Security Fence by contract with Colorado State University)
-* inside owner controlled                StateUniversity) area.
+Emergency Lab Ge-Li Detector Multi-Channel, Analyzer 6.
-Fixed Air Sampling                   Sample particulates and Stations-Just Outside                  radiciodines(operated Security Fence                         by contract with Colorado State                                             .
+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
-University)
+Mueller Survey Meters:
-Emergency Lab                          Ge-Li Detector Multi-Channel, Analyzer
+radiation and contamination levels-O l
-: 6. Portable Survey Instruments Airborne Particulate                   Detect-airborne Monitors                               contamination Beta-Gamma Air                         Detect airborne Monitor                                radioactivity                                              -
+- FORM (D)372 22 3M3.
-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 /
+OtiRP Section /.2 Issue 1 0 Service
-Attachment 7.2 Issue 1 Public           FORT ST. VRAIN NUCLEAR GENERATING STATION Page 19 of 21 0 Service
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 19 of 21 Pusuc senvece comeAmy or cotonAno O
-* Pusuc senvece comeAmy or cotonAno O                                ONSITE ASSESSMENT EQUIPMENT AND FACILITIES
+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
-   .                    Instrumeqt              Description and              Functional               ,
+.g i
-System                    Location                 Applicability SAM-II Portable Multi-         Verification of airborne Channel Analyzers              I-131 levels in the field                .
+l
-Scintillation                  Determine gamma dose Counters                       rate Pancake Geiger-                Determine surface                              ,
+O 1
-Mueller Monitors               contamination levels                           !
+FORMlol372 22 3M3
-Proportional Counter           Determine alpha-beta-gamma contamination Hi and to Vol Air Samplers     Detect airborne iodine
-* and particulate contamination 4
-                                                                                         .g   .
-i 4
-l O                      .
-:                                                                                                                        1 FORMlol372 22 3M3
-WLM Juw b a wai i Attachment 7.3 Issue 1 Public                      FORT ST. VRAIN NUCLEAR GENERATING STATION Page 20 of 21 0 Service
+WLM Juw b a wai i.3 Issue 1 0 Service
-* Pusuc senvics comeAmy or cotonApo O
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 20 of 21 Pusuc senvics comeAmy or cotonApo O
-V 0FFSITE ASSESSMENT EQUIPMENT AND FACILITIES ndividual                                Functional l Detector                    '
+V 0FFSITE ASSESSMENT EQUIPMENT AND FACILITIES l Detector ndividual Functional Applicability 1.
-Applicability
+Geophysical Monitoring Meteorological i
-: 1.           Geophysical Monitoring                                                                            '
+National '"ather Service Denver Weather forecasting Stapleton Airport 2.
-l Meteorological                                                                                    i National '"ather Service Denver                    Weather forecasting Stapleton Airport l
+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)
-l
+Fixed Air Sampling Stations Measure particulates and radioiodines (operated by contract with Colorado St.atp University)
-: 2.           Radiological Monitors
+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.-
-                                                                                                                             )
-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 Attachment 7.3 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                2 of 21 0PublicService
+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
+OFFSITE ASSESSMENT EQUIPMENT AND FACILITIES Individual Functional
-    ^                     Individual                                             ''
+^
-Functional            *
+' Detector Applicability Colorado Departmenc of Health Whole Body Counter Identification and quantification of inhaled or ingested radioisotopes.
-                           ' Detector                                                                                                  Applicability Colorado Departmenc of                                                                                                                                            *'
-Health Whole Body Counter                                                                                                     Identification and quantification of inhaled or ingested radioisotopes.
 Serves as backup to FSV System.
-h                                                                                                                                                                       .
+h
-V            .
+V E
-E FORM (D)372 22 3843
+FORM (D)372 22 3843
-Issui 1 age 1o'f 8 Public              FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service
+Issui 1 age 1 'f 8 o
-* PusuC SERVICE COMPANY OF COLORADO TITLE:        DEFUELING EMERGENCY RESPONSE PLAN: SECTION 8 MAINTAINING EMERGENCY PREPARE 0 NESS PONSIBLE                     _
+Service
-THORIZED lfL                        pmc9 21 FEB 131991                   [F TE E T VE DCCF NUMBER (S)          Q D-l7 31 1
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC SERVICE COMPANY OF COLORADO TITLE:
-O                                                                                                       .
+DEFUELING EMERGENCY RESPONSE PLAN: SECTION 8 MAINTAINING EMERGENCY PREPARE 0 NESS PONSIBLE THORIZED lfL pmc9 21 FEB 131991
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+[F E T VE TE DCCF NUMBER (S)
-oowmol CENTER PfMOR kQ-              '
+Q D-l7 31 O
-TO USE FORMIDl372 22 3642 l
+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 Public                 FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Serv lCG*PUBLIC SERVICE COMPANY OF COLORADO 8.0 MAINTAINING EMERGENCY PREPAREDNESS 8.1  ORGANIZATIONAL PREPAREDNESS To ensure that the FSV Emergency Response Organization is                      ,
+Utnr Juction O Issue 1 0 Serv lCG*
-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.                                                                    -
+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.
 .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                   '
+Training Procedure - Defueling Emergency Response Plan (TP-DERP) identifies specific training requirements for each major emergency position / function.
-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                    .
+These training requirements are reflected by appropriate FSV training lesson plan numbers. The general requirements of the program O
-follows,
+are summarized in matrix form in TP-DERP. A brief V
-: a. Basic Training and Indoctrination Each employee receives general instructions on the DERP and supporting emergency procedures.
+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                       .
+.. b.
-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
+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                  .-
+'" cross-subject" training to ensure the familiarity and flexibility necessary for n
-g                                            of emergency response. functions._
+personnel who could be assigned to a diversity g
+of emergency response. functions._
 FORMIDl3[2522 3843
-                                                        /
+/
-                                                    ./                                 -
+./
-DERP Section 8 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION 9'
+DERP Section 8 Issue 1 9'
-Public  Service
+Public 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
+* PUBUC SERVICE COMPANY OF COLORADO O
-* meteorology on radiation exposure, and dose estimation techniques. The specific training matrix is fully presented in TP-DERP.
+For example, training for the Emergency Coordinator emphasizes:
-: 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                             ,
+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.
-training for members of the Platteville                                        ,
+c.
-Volunteer Fire Department including                                            l familiarization with the station layout, the                                   l location and nature of fire hazards, the location, type, and availability of extinguishing equipment, and the special                                  '
+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.
-radiological considerations associated with                                    ;
+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, -
-fire fighting at the FSV. Training is also                                     I 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,
+others who may be called upon to render assistance.
-: d. Training for Emergency Preparedness Staff
+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.
-                                          *#*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                                                                                                                  .
+Training for Emergency Preparedness Staff
-V               .
+*#*8.5.1*#*
-FOPM tu 372 22 3643
+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 Public                 FORT ST. VRAIN NUCLEAR GENERATING STATION #9' 0 Service'                    rusuc sanvece courAny or cotonApo 8.1.2 Orills and Exercises Regular participation by station personnel in
+DERP Section 8 Issue 1
-* drills and exercises is scheduled to maintain emergency preparedness and test specific aspects of emergency plans, procedures, and equipment.
+#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.                                                                                                                                  ,
+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.
+*#*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.
+-weather conditions present to provide auditable records.
-: a.                                   Drills u
+a.
-Instructional emergenc/ drills are conducted                                                             ,
+Drills u
-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.
+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
+O V
-* 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                                                             -
+Drill performince is critiqued by personnel acting as dri11-instructors who offer on-the-spot corrections to erroneous performance.
-than 90 days following completion. Followeo action is then delineated to upgrade areas where deficiencies are noted.
+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
-                                            .. /    . _. _ _ _ _ _ _ _ - _ - _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ - - _ _                          - _ - _ _ - - - _ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _
+.. /
 DERP Section 8 Issue 1
-                                                                                            #9' Public                   FORT ST. VRAIN NUCLEAR GENERATING STATION 0 SGTVIC9'                      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.,
+#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:
-fire, communications and notification, and medical emergency, are coordinated with
+(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.,
-* offsite participating agencies.
+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                              I instruction in the handling of fire and rescue apparatus. Additional instruction is provided in fire prevention, fire safety, pre-fire planning, fire fighting,.
+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
+fighting electrical fires, and the use of emergency breathing apparatus.
-,                                                  action. -All fire drilla are coordinated
+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.
+-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
+*#*8.5.3*#*
-                                                  -of emergency response facility communication links is accomplished
+Verification of personnel, emergency organization assignments, telephone numbers, and outside assistance contacts,.are performed quarterly.
-                                                  -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
+In addition to these annual drills, the hospital conducts regular in-house emergency drills on the treatment and l
-,                                                  emergency drills on the treatment and l                                                  care of injured and contaminated persons.
+care of injured and contaminated persons.
-I l
+I Drills involving Weld County Ambulance l
-Drills involving Weld County Ambulance
+-Service are conducted on a semi-annual r'
-                                                  -Service are conducted on a semi-annual r'                                               basis.                                                        -
+basis.
 l l
-l    FORMtD)772 22 3843
+l FORMtD)772 22 3843
-DERP Section 8 Issue 1 Pt;blic                                 FORT ST. VRAIN NUCLEAR GENERATING STATION "9'
+DERP Section 8 Issue 1 "9'
-$9fVIC9'                                            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.
+$9fVIC9' Pt;blic FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC ssRVICE COMPANY OF COLORADO O
-Health Physics Drills are conducted semi-annually, generally in connection
+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.
-* 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',.
+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                                                                                 ,
+b.
-An annual exercise of the DERP will be conducted to test the adequacy of implementing                                                                 !
+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.
-procedures and methods, test emergency equipment and communications networks, and ensure that emergency response personnel are g                                                                                    familiar with their duties.
+g 8.1.3 Emergency Planning Coordinator.
-.1.3 Emergency Planning Coordinator.
+The Nuclear Training and Support Manager has overall responsibility and authority for emergency f
-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.
+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.
-.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.
+The EPC coordinates plan revisions based on evaluations resulting from exercises / drills.
-OL                                                                                                                                                                                                  ;
+.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.
-FORM (D)372 22 3843 i
+OL FORM (D)372 22 3843 i
-           -              , -      - , _ . --         - _ . . . - . , , , - , - - . ,                 . . - . .- , - -                        r -                      .   ,- -
+r -
-                                                                                                                                                                                   , , . - ~
+,,. - ~
 I DERP Section b Issue 1
-                                                                                '9' Public                FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service
+'9' 0 Service
-* 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                     ,
+* 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.
-preparedness program are conducted annually. The results                      ,
+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.
-are considereo by PSC management in modifying aspects of the DERP. Audit documentation is maintained for at least five years.
+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.         .
+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.
-.3      MAINTENANCE AND INVENTORY Or EMERGENCY EQUIPMENT AND IUPPLIES Quarterly inspections of the operational readiness of                  '
+.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.
-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.
+Sufficient reserves of O
-.4        INDEPENDENT REVIEW OF THE EMERGENCY PREPAREDNESS PROGRAM
+instruments / equipment are maintained to replace those undergoing calibration or repair.
-                          *#*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.
+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.
+.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 FORT ST. VRAIN NUCLEAR GENERATING STATION 0Public Service
+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.
+* 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.
 .5.1 Section 8.1.1.d is in response to CAR 86-068.
-.5.2 Section 8.1.2, " drills and exercises", is in                                        I response to CAR 86-068.                                                       j 8.5.3 Section 8.1.2, " communication links and notification", is in response to CAR 86-066.
+.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.
 .5.4 Section 8.4 is in response to CAR 86-067.
-.5.5 Section 8.1.2, exercise / drill report time                                          l requirements are in response to QDR 87-077.                       '
+.5.5 Section 8.1.2, exercise / drill report time requirements are in response to QDR 87-077.
-O i     f*
+O i
-l FORM (Dl372 22 3043                                                                                                  r
+f*
-    ~.              _   _                        . - . . -   . , . . . . _ . ,   . -                     .
+l FORM (Dl372 22 3043 r
+~.
 DERP Section 9
-                                                                                                                                               'I Public             FORT ST. VRAIN fjuCLEAR GENERATING STATION y gf 7 O SerVICO'                   PUBUC SERVICE COMPANY OF COLORADO O            TITLE:    DEFUELING EMERGENCY RESPONSE PLAN: SECTION 9, RECOVERY "S'S" "sS/
+'I O SerVICO' Public FORT ST. VRAIN fjuCLEAR GENERATING STATION y gf 7 PUBUC SERVICE COMPANY OF COLORADO O
-UTHORIZED rwk ECME RSSw                            PORD9i i FEB 131991                                                                           fire DCCF NUMBER (S)          hh \2M
+TITLE:
-()                                                                                                                                                           .
+DEFUELING EMERGENCY RESPONSE PLAN: SECTION 9, RECOVERY "sS/
-                                                                                                                                      .g  e e
+"S'S" rwk UTHORIZED RSSw PORD9i i FEB 131991 fire ECME DCCF NUMBER (S) hh \\2M
-PT, ST. VRAIN                                                I NON CONTROLLED COPt i          w w y ssue stAnis WITH SITE DOCUML17 CONTROL CENTER PRIOR                                           4
+()
-(         --
+.g e
-                        'ID USE                                                I FORM (D)372 22 3642
+e PT, ST. VRAIN I
+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 FORT ST. VRAIN NUCLEAR GENERATING STATION                        Page 2 of 7 0Pubile  Service
+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                                                                                  ,
+* PUBUC SERVICE COMPANY OF COLORADO O
-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,                                                                                              ,
+.0 RECOVERY Recovery operations for FSV consist of those operhtions associated with the long term post-emergency efforts that follow a major incident.
-After termination of the emergency, (i.e., the plant is in a safe and stable condition) recovery actions are designed to:
+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
+(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.
- ,                                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.
-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.
+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.
+: Fire, flooding, or similar emergency conditions no longer constitute a hazard to the plant or station personnel.
-Overall plant is in a stable condition.                           .,-   .
+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                               -
+TSC Director has authorized transition from the Emergency Response Organization con figuration to the Recovery Organization and notifies personnel accordingly.
-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.
-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                                                                                                                                                       '
+O FORM (D)372 22 3M3
-FORM (D)372 22 3M3
-DERP Section 9 1ssue 1 Public             FORT ST. VRAIN NUCLEAR GENERATING STATION                              Page 3 of 7 0ServlC9'                  PUBUC SERVICE COMPANY OF COLORADO O               9.1  RECOVERY ORGANIZATION                            .
+DERP Section 9 1ssue 1 0ServlC9' Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 7 PUBUC SERVICE COMPANY OF COLORADO O
-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                                                !
+.1 RECOVERY ORGANIZATION Activation of an effective recovery operation will involve the transition of selected key technical personnel from emergency to recovery operations.
-assigned to direct and coordinate 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                                          *
+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.
-                ,      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.
-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:
+A general Recovery Organization is depicted in Attachment 9.2.
-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 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
-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.
+normal defueling/ decommissioning configuration and-is vested with the authority to commit corporate resources to accomplish the recovery.
-* The    Radeon/ Waste Manager     -
+The plant Operations Manager - (Manager, Nuclear
-(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, 1
+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 Quality Assurance Manager - (Manager, Quality Assurance Division) assures- that the overall conduct of recovery operations is performed in                                               I tccordance with corporate policy and rules and regulations governing activities which may affect public health and safety.                                                                    '
+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 Public                FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                        Page 4 of 7 l                                                        0 SerVlCO*PUBLIC SERVICE COMPANY OF COLORADO O                                                        +        The Recovery News Director                                                                                  -
+DERP Section 9 Issue 1 l
-(Director, Media Services) coordinates the flow df media information concerning                  recovery                                                     operations                and       acts as corporate spokesman concerning recovery activities.
+SerVlCO*
-An overview of topics which can be addressed during establishment of recovery operations                                                                                    is presented in Attachment 9.1.
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 7 PUBLIC SERVICE COMPANY OF COLORADO O
-.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.                                                                                                                                             .
+The Recovery News Director (Director, Media
-During recovery operations, actions will be preplanned to limit exposures.                      Access to affected areas will                                                                         be controlled and exposure                                                                       to                 personnel     documented.
++
+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.
+.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.
-.3     COMMITMENTS None e
+.3 COMMITMENTS None e
-k                                 .
+k FORM (D):r72 22 3643
-FORM (D):r72 22 3643
-DERP Section 9 Attachment 9.I FORT ST. VRAIN NUCLEAR GENERATING STATION                                          Issue I 0PublicSerVlCe*            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.
+DERP Section 9.I 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION Issue I SerVlCe*
-I.
+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. Initiating Events C. 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                                                                                     ,
+OF ACCIDENT A.
-III. SAFETY CONCERNS A. Re-Entry Requirements B. Maintaining Stable Plant Conditions IV. TENTATIVE REPAIR PLAN AND SCHEDULE
+Causes B.
-                .A . Major        Steps               Necessary                              to   Restore    to       a Defueling/ Decommissioning Phase t
+Initiating Events C.
-B. Evaluation of PSC Resources                                                                               ~
+Accident Chronology II.
-C. Licensing Considerations D. Quality Assurance Considerations E. Administrative Concerns F. Logi stic s/Schedulir.g FORM (01372 22 36*3                                                                                                                '
+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-Attachment 9.1 FORT ST. VRAIN NUCLEAR GENERATING STATION                            Issue 1 0Pubile                                  SerVlCG*                       PUBUC SERVICE COMPANY OF COLORADO                                   Page 6 of 7 O                                                                                                           '
+DERP Section 9-.1 0Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 1 SerVlCG*
-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                                                             .
+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
 FORM t0)372 22 3643
-DERP Section 9 Attachment 9.2 FORT ST. VRAIN NUCLEA' GENERATING STATION                              Issue 1 0Public Service
+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                                                                           -
+* 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                                                  -
+RECOVERY ORGANIZATION I
-l                   NUCLEAR     I l       OPERATIONS              l 1                                1 l
+RECOVERY l
+l DIRECTOR l
+I
+i VICE PRESIDENT, 1 l
+NUCLEAR I
+l OPERATIONS l
+1
+l l
+I l
+NEWS CENTER l
+l l
+ADVISORY I-1 MANAGER I
+l l
+SUPPORT l
+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    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 NT _ l IRXDCON/ WASTE ll QUALITY.l 10PERATIONS [
-l I
+t MANAGER I l~ ASSURANCE l l MANAGER l l SUPT, 0F
-l                NT _ l         IRXDCON/ WASTE l l QUALITY .l                            .
+-l l. MANAGER -1 IMGR,NUCLEARI l RA01ATION-1 IMGR, QUALITY l l PRODUCTION I l PROTECTION l l ASSURANCE.l,
-PERATIONS [                   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 ,   ,
+OIVISION/l 1
-    OIVISION/l                 1          AND   1   l   DIVISION l l STATION MGRI                   l CHEMISTRY l        1             l O
+AND 1
-  +
+l DIVISION l l STATION MGRI l CHEMISTRY l 1
+l O
++
 FORM (Of 372 22 3643
-DERP Section 10 Pubile            FORT ST. VRAIN NUCLEAR GENERATING STATION 1 of 15 0 Service
+DERP Section 10 0 Service
-* PURUC SERVICE COMPANY OF COLORADO TITLE:      DEFUELING EMERGENCY RESPONSE PLAN, SECTION 10 LETTERS OF AGREEMENT AND SUPPORTING PLANS agieo~sia's                             .g#
+* Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION 1 of 15 PURUC SERVICE COMPANY OF COLORADO TITLE:
-               ^rsoaizeo                            argg                                                                                      .
+DEFUELING EMERGENCY RESPONSE PLAN, SECTION 10 LETTERS OF AGREEMENT AND SUPPORTING PLANS agieo~sia's
-lSSEw                                          ocac 9 21 FEB 131991                              5' ATE"? b    Sl}-9l DCCF NUMBER (S)                           Ch. l 2 M 4
+.g#
-PT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR                                                                               -
+^rsoaizeo argg lSSEw ocac 9 21 FEB 131991 5' ATE"?b Sl}-9l DCCF NUMBER (S)
-                                                       TO USE FORM (D)372 22 3642
+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 Page 2 of 15 0 Publicservice
+DERP Section 10 FORT ST VRAIN NUCLEAR GENERATING STATION Issue 1 0 Public Page 2 of 15 service
 * PUBUC SERVICE COMPANY OF COLORADO O
-.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.
+.1 LETTERS OF AGREEMENT This section contains copies of Letters of Agreement with the various local agencies and contract :upport organizations.
-.2 Hydrology and seismic data can be obtained through the U.S.                                                                                                                                                        -
+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.
-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).
+.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                                  -                                        _ _ - _ - - _ - - _ _ _ _ - -      _ - - _ - - _ _ _ _ _ - - - _ _ - _ _ _ - - - _ _ . _ - - - - - - - _ - - - -                  - - - - - - _          - - - _ - - - -
+FORM (0)372 %3643 A
-OERP Section 10 FORT ST. VRAIN NUCLEAR GENERATING STATION              ssue f
+OERP Section 10 OPublic ssue FORT ST. VRAIN NUCLEAR GENERATING STATION f
-OPublic      Service
+Service
 * Pusuc senvice comeAmy or cotonApo O
-TABLE 10-1         .
+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)
-LIST OF INTERFACING PLANS                 -
+(State RERP)
-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)
-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.
-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
-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
-FEMA                                           Federal-Radiological Emergency Response Plan FORM (DIT12 22 3643
-DERP Section 10 Issue 1 Public           FORT ST. VRAIN NUCLEAR GENERATING STATION                      Page 4 of 15 0 SerVlCO*PUBUC SERVICE COMPANY OF COLORADO U(
+DERP Section 10 Issue 1 0 SerVlCO*
-PPS-88-0132                -
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 15 PUBUC SERVICE COMPANY OF COLORADO U(
-(                                                                                    "Unnersary Department of Radionor, and Radiaison Biology Foet Collins. Co6 credo 80523             .
+PPS-88-0132
-oon4m.5380 January 5,1988 Mr. Owen J. Clayton Emergency Planning Coordinator Fort St. Vrain 16805 WCR 19S Platteville, CO 80651
+(
+"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
+Colorado State University has conducted the radiation environmental V
-* entire Dreoperational phase as well as the current operational phase. This program has been on a contractual basis with the University.
+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                          -
+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--
-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.
-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 I
+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.
-radioactivity and the biological effects of ionizing radiation.                                              l 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.
+p J me E. Johhsg1. Ph.D.
-Q-    JEJ:nb P    essor FORMton372 22 3643
+Q-P essor JEJ:nb FORMton372 22 3643
-DERP Section 10 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                          Page 5 of 15 0 PubilC SerVICO*                               PUBLIC SERVICE COMPANY OF COLORADO
+DERP Section 10 Issue 1 0 PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 15 SerVICO*
-                                                                                                                 @ =r    a      E        PPS-88-0128 W hud.
+PUBLIC SERVICE COMPANY OF COLORADO
-Controls for Environmental Pollution, Inc.                                                                                                               -
+=r E
-Aosina e A C Bex 5351 e Santa Fe. New Mexico 67502 + ''etecnome SCS 982 9841 January 7,1988 Public Service Co. of Colorado                                                                                                                           -
+PPS-88-0128 a
-WCR 191/2 Platteville, CO 80651 Attn: Owen J. Clayton p
+W hud.
+Controls for Environmental Pollution, Inc.
+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.
-U        i would like to introduce to you and your staff our full analytical capabilities. We have
+Our laboratory provices complete environmental, bioassay and waste characterization programs for your type of industry.
-* 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.                                                                     _,
+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,                                   -
+Very truly yours, CONTROLS FOR ENVIRONMENTAL POLLUTION, INC.
-CONTROLS FOR ENVIRONMENTAL POLLUTION, INC.
+=.
-                                                                                                                                     =.
+James J. Mueller President JJM/jjs Enclosures FORM (o)372 22 3643
-James J. Mueller President JJM/jjs Enclosures                                                                                                                               .
-FORM (o)372 22 3643
-DERP Section 10 Issue 1 Public                                           FORT ST. VRAIN NUCLEAR GENERATING STATION                                               Page 6 of 15 0SerVlC9'                                                          PUBLIC SERVICE COMPANY OF COLORADO 9
+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 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                                                                     ,
+This assistance will be in the form of direct participation by CEP employees both off-site and on-site on an "as needed basis".
-Fort St. Vrain Nuclear Generating Station.
+Availability will be immediate for any assistance which can be performed at CEP's home office and within 8 hours for assistance requiring travel to Fort St. Vrain or other Public Service Company of Colorado f acilities.
-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 hours 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.
+Collecting and analyzing radiological environmental samples.
-: 3. Assistance with health physics monitoring. '
+.
-Providing monitoring assistance and radiological monitoring.
+Receiving and analyzing samples on an emergency basis.
-: 5. Analyzing urine and feces samples from Fort St. Vrain personnel.
+.
-()                                                              6. Post emergency write-up reports.                                                                               ,
+Assistance with health physics monitoring. '
+Providing monitoring assistance and radiological monitoring.
+.
+Analyzing urine and feces samples from Fort St. Vrain personnel.
+()
+.
+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.
+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:
-Very truly yours, CONTROLS FOR ENVIRONMENTAL POLLUTION, INC                                              .
+(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.
-                                                                                                     /V f                                                     -
+Very truly yours, CONTROLS FOR ENVIRONMENTAL POLLUTION, INC
-Ja es 3 Mueller                                                                  -
+/V f Ja es 3 Mueller
-President s )                                    33Mid!
+)
-FORM 101372 22 3643 1
+President 33Mid!
+s FORM 101372 22 3643 1
-DERP Section 10 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                       Page 7 of 15 0Public                                    $9fVIC9'     PUBLIC SERVICE COMPANY OF COLORADO R. S. Landauer, Jr. & Co.                                           PPS-88 0131 Tech Ops Om6aen of Tecntoos, incorporened 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                                                                                                                                   -
+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 hour, 7 days a week emergency processing.
 There ars various methods available to send the film to us.
@@ Line 2,599: / Line 3,319: @@
 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 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.
+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                                                                                                                        -
+l eannine MacDonald Mechnical Assistant Quality Assurance (v]
-Quality Assurance JMD/yls (v]
+JMD/yls FORM (0)372 22 3643
-FORM (0)372 22 3643
-DERP Section 10 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING-STATION                                                                    Page 8 of 15 0PubilCSerVlCe*                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                                                                               *
+DERP Section 10 Issue 1 0PubilC FORT ST. VRAIN NUCLEAR GENERATING-STATION Page 8 of 15 SerVlCe*
-                       ,   ,,,.                                                                                                                  ,w..-,...-
+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
-:::,',' ;,                                                                                                                         ..m...~.
+,w..-,...-
-              =,,,,,                                                                                                                                . m ... ...
+..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
+Mr. R. O. Williams January 7, 1988 Vice President. Nuclear Operations Public Service Company of Colorado J. O. No. 13569.XX
 ~
-West 26th Avenue                                                                                                  1,tr. No.        S-T-23 Suite 100D
+West 26th Avenue 1,tr. No.
-* 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)
+S-T-23 Suite 100D k
-Tort St. Vrain Nuclear Generating Statha, Stone and Webster Engineering
+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)
-* 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.                                                                                                                      . ,      .
+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.
+PSCC and SWEC have already established the appropriate terms and conditions applicable to services identified in Attachment - No.1.
-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                                                                                         ~
+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.
--690-8701).          Their office numbers are 303-741-7516 - and 303-741-7444 respectively t'
+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.
-J. J. M.        lante Vice President Enclosure JJMP:RSU DSM                                                                                                                   ,
+T.
-cc:      T. J. Novachek O. J. Clayton FORM (D)372 22 3043 am- - - - - - _ _ - - - . _ - , - _          -       - - -    -a ---_a-
+Ervin (home phone
+~
+-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 Public                                                       FORT ST. VRAIN NUCLEAR GENERATING STATION                                     Page 9 of 15               '
+DERP Section 10 Issue 1 0SerylCO*
-SerylCO*                                                             PUBUC SERVICE COMPANY OF CdLORADO ATTACMMENy NO. 1                                            .
+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
-e                                                         Emeraenev Support Available Trem S'm'EC Tor Fort St. Vrain. Under the Terms ano concitiens Of Existina Contreet (PSC) Document No.                           37754
+Tor Fort St. Vrain. Under the Terms ano concitiens Of Existina Contreet (PSC) Document No.
-: 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.
+1.
-: 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.
+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.
-: 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.
+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.
-: 4. Operations / Maintenance Suonert SWEC Personnel assist PSC Operations and Maintenance - personnel in rapid planning / procedure writing for emergency operations and maintenance
+.
-* activities.
+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.
-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.
+Operations / Maintenance Suonert SWEC Personnel assist PSC Operations and Maintenance - personnel in rapid planning / procedure writing for emergency operations and maintenance activities.
-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                                                                               .-
+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.
-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.
+Radiation Protection In addition to assisting in radiological dose assessments ites 1, - above.
-: 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.
+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.
-    . FORM (0)372 22 3643
+.
+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.
+.
+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 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                                             Page 10 of 15 0 Public Service
+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                                                                                                                   -
+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}
-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
-This Letter is to update the present agreement between Public service and the Platteville Fire District. We have reviewed the present a;;reement                                                                                                                 .
+DERP Section 10 Issue 1 0 SerVlCO*
-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.
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 15 PUBLIC SERVICE COMPANY OF COLORADO O
-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 Public              FORT ST. VRAIN NUCLEAR GENERATING STATION       Page 11 of 15 0 SerVlCO*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
+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 Fire Department           will as benotice    that to available      theassist Johnstown   Volunteer Fort St.
+This letter is to serve as notice that the Johnstown Volunteer Fire Department will be available to assist Fort St.
-Nuclear Generating Station either for routine operations               Vrain during an emergency. Please do not hesitate to notify us if or            we can be of service.
+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 t
+CW M
-James C. Young, Jr., Chie Johnstown Volunteer Fire Department O
+(/h James C.
-i FORM ID) 372.r .3643
+: Young, Jr., Chie t
+Johnstown Volunteer Fire Department O
+i FORM ID) 372.r.3643
-DERP Section 10 Issue 1 Public                                                            FORT ST. VRAIN NUCLEAR GENERATING STATION                                                      Page 12 of 15 0 Serv lC9' 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                                                                                                                                                                 .
+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
-OWen J. Clayton Emmeguncy Plamirst Ocordinator Public service Qagiany 16805 M3t 191/2 PlattsV111a, CD 80651 Dear Mr. Clayttnt                                                                                                                                                            .
+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.
-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.
-st. Anthony thspital systems' Flight Fur Life agrees to respond to the Ptet                                                                                                    -
+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.
-St. Vrain Facility in Plattaville, Cblerado, at the reganst of the Wald 03unty ocumminaticrus Osntar for amargency aertical assistance. Our Ozumanications M=,
+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.
-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.
+However, it is the W 47 Flight 18Jrse's h4=iM to dWYiate to another BMimi facility if thm =dimi omiition warrants.
-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
+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
-* cc: Baxtera Inckwced                                                             Arne Goehec Dr. mat +=m                                                  Cczmuunicatims Centar Dr. Drecen                                                   Operatiens Marsaal
+l ram ar.enreve.
-* Dr. Ctxmar                                                   Films FORMID)712 22 3N3 V
+FORMID)712 22 3N3
-ram ar.enreve .                                                                                          l
 (
-DERP Section 10 Public                             FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                                                Pa    13 of 15 0 $9fVlCO*                                PUBUC SERVICE COMPANY OF COLORADO O
+DERP Section 10 0 $9fVlCO*
+Public FORT ST. VRAIN NUCLEAR GENERATING STATION Pa 13 of 15 PUBUC SERVICE COMPANY OF COLORADO O
 V PPS-88-0243
-    ,YmM "lN:$?$*EN H.G. OLSON NUCLEAR ENGINEER k
+,YmM "lN:$?$*EN H.G. OLSON NUCLEAR ENGINEER k
 January 13, 1983 Hr. R. O. Williams, Jr.
-* 1 Vice President Nuclear Ooerations Fort St. Vrain Nuclear Generating Station Public Service Comoany of Colorado 16305 Weld County Road 19 1/2 Platteville C0 30651
+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
 (~h
 ,y
 ==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)and                                                                                            gh my myparticioation membershipinon       the Nuclear numerous HFSC audits. I have remained current on the operational status of the olant.
+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,                                                  ~
+Very truly yours,
-c i
+~
+i c
 H. G. Olson HGO:stw FORM (D)372 22 360
-DERP Section 10 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                                Page 14 of 15 0 Public Serv'CO'                     PUBUC SERVICE COMPANY OF COLORADO O
+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
+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                                                                                                                                                           .
+January 6, 1988 lit. Owen J. Clayton Emergency Planning Coordinator Public Service Company of Colorado 16805 WCR 19 1/2 Platteville, CO 80451
-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'
-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.
+.:, 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,
+incornly s,
-                                                                                                                                          ,        Janet A. J        on, PhD, CHP S
+Janet A. J on, PhD, CHP S
 O FORMIOn372 22 3643
-DERP Section 10 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION                                        Page 15 of 15 0 Public SerVlCO*                                           PUBUC SERVICE COMPANY OF COLORADO O
+DERP Section 10 Issue 1 0 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 15 SerVlCO*
-                                                                                                                                              '5TvE@c
+PUBUC SERVICE COMPANY OF COLORADO O
-                                                                                                                                                - -g g ESASCO        CONSTRUccamoa4*tsCTORS a we e e a44sce saavets '                                                                                INC.
+ESASCO CONSTRUccamoa4*tsCTORS INC.
-xco w wu s# santa ea cA sa gm es2-soss PPS-88-0550 Ac.::aert
+'5TvE@c
-          ,c    wa et E Pester
+- -g g a we e e a44sce saavets '
-                                                                                                                                                                        =
+xco w wu s# santa ea cA sa gm es2-soss Ac.::aert E Pester PPS-88-0550
-February 12, 1988 Public Sarvice Company of Colorado                                                                                                                     ,
+,c wa et
-WCR 13 1/2 Platteville, Colorado                                               80651 Attention:                                     Mr. Frank Novachek
+=
+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. 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.
-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                                                                                -
+Mr. Robert E. Pester 3000 W. MacArthur Blvd.
-W. MacArthur Blvd.
+Santa Ana, California 92704 (714) 662-4055 Sincerely, V J M, h S_ _ W 0
-Santa Ana, California                                     92704 (714) 662-4055 Sincerely, V
+cc: File R.
-J M, h S_ _ W cc: File R. Schwarz
+Schwarz O'
-* O'                 R. Craun O. J. Clayton FORM (D)372 22 3643
+R. Craun O. J. Clayton FORM (D)372 22 3643
-DERP 5ection 11 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING f,TATION            age 1 of 2 0Public                                             Service
+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                                              ,
+* PUBUC SERVICE COMPANY OF COLO8tADO TITLE:
-PONSIBLE i        B                                                                   ((                                                                       -
+DEFUELING EMERGENCY RESPONSE PLAN, SECTION 11 MAFS PONSIBLE
-PORC                                                                                                            EFFECTIVE REVIEW                                                               POIC 9 21 FEB 131991                       DATE       3 19 $ \
+((
-DCCF NUMBER (S)                                                 hC-l7%$
+i B
+PORC EFFECTIVE REVIEW POIC 9 21 FEB 131991 DATE 3 19 $ \\
+DCCF hC-l7%$
+NUMBER (S)
 A
-  ~
+~
-                                                                                                                              .o FT. ST. VRAIN NON-CONTROLLED ,
+.o FT. ST. VRAIN NON-CONTROLLED,
-COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT           >
+COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR TO USE FOfiM(D)372 22 3642
-CONTROL CENTER PRIOR
-* TO USE FOfiM(D)372 22 3642
-DERP Section 11 Issue 1 "9'          U Public                    FORT ST. VRAIN NUCLEAR GENERATING STATION                                                                                                                                               >
+DERP Section 11 Issue 1 "9'
-$9fVICO' PCBLIC SERVICE COMPANY OF COLORADO EMERGENCY Pl.ANNING ZONE s 'N                                                                          88 8 l l N                                                                                           ,                                                                                            ll
+U 0 $9fVICO' Public FORT ST. VRAIN NUCLEAR GENERATING STATION PCBLIC SERVICE COMPANY OF COLORADO EMERGENCY Pl.ANNING ZONE
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+'N 88 8 l l s
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 FORM (0)372 22 3643
-DERP Section 12 l                                                                                                                               Issue 1 age 1 of 4 FORT ST. VRAIN NUCLEAR GENERATING STATION 0Pubile   Service'                                    PUBUC SERVICE COMPANY OF COLORADO v            TITLE:        DEFUELING EMERGENCY RESPONSE PLAN, SECTION 12 PROCEDURES THAT IMPLEMENT OR SUPPLEMENT THE PLAN PONSIBLE N
+DERP Section 12 l
-adfL                                                                                                               .
+Issue 1 age 1 of 4 0Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION Service' PUBUC SERVICE COMPANY OF COLORADO v
-RESw                                                    POR09 21 FEB 131991                  '((TE' "'3.aA.qi DCCF NUMBER (S)              h&l2%
+TITLE:
-U(~ ~                                                                                                                                           .
+DEFUELING EMERGENCY RESPONSE PLAN, SECTION 12 PROCEDURES THAT IMPLEMENT OR SUPPLEMENT THE PLAN PONSIBLE N
-dr hw  .m FT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR                                                                                                               .
+adfL RESw POR09 21 FEB 131991
-   /N q)                    - - - - -
+'((TE' "'3.aA.qi DCCF NUMBER (S) h&l2%
-TO USE FOPM(D)372 22 3642
+U(~ ~
+dr hw
+.m FT. ST. VRAIN NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT CONTROL CENTER PRIOR
+/N TO USE q)
+FOPM(D)372 22 3642
-DERP Section 12 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 4 0Public  Service
+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 /
+* PUBUC SERVICE COMPANY OF COLORADO O
-Procedure Designation                                                                                                           Supplements RERP and Title                                                                                                                 Section No.
+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             -
+G-5 Personnel Emergency Response 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                                                                               .,
+G-7 FSV Project Personnel Training and Qualification Programs 8
-the Health Physics Procedures (HPPs).
+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 /
+* PUBUC SERVICE COMPANY OF COLORADO O
-Procedure Designation                                                                                   Supplements RERP and Title                                                                                          Section No.
+APPENDIX D Implements /
-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                                                         -
+Procedure Designation Supplements RERP and Title Section No.
-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               .,
+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 -
-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)
+,5,8 Outside Company SR-EP-6-Q DERP Phone List Verification -
-All Sections                                4,5,6 Abnormal Operating Procedures (AOPs)
+,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
-All Sections                                 4,5,6 Station DERP Implementing Procedures All Procedures                                All                  .
+Emergency Response Plan Emergency Operating Procedures (EOPs)
-O FORM (Dl372 22 3643 Y.   ..
+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.
-I DERP Section 12 Issue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 Public 0 $9fVIC9'                              PUBUC SERVICE COMPANY OF COLORADO APPENDIX D Implements /
+DERP Section 12 I
-Procedure Designation                                                                                      Supplements RERP and Title                                                                                               Section No.
+Issue 1 Public FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 0 $9fVIC9' PUBUC SERVICE COMPANY OF COLORADO APPENDIX D Implements /
-Medical Emergency Plan - FSV                                                                                  5,6,7 Technical / Administrative Services Manager's Administrative Procedures (TASMAPs)
+Procedure Designation Supplements RERP and Title Section No.
-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
+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
+~
 O FORM (D)372 22 3643
-DERP Section 13 Issue 1 age 1 of 7 Public              FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service
+DERP Section 13 Issue 1 age 1 of 7 0 Service
-* PusuC saRWCE COMPANY OF COLORADO O                  TITLE:        DEFUELING EMERGENCY RESPONSE PLAN, SECTION 13 O STINGS OF EMERGENCY KITS                        ,
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC saRWCE COMPANY OF COLORADO O
-       "5S[ "*''''                  8Adns(--
+TITLE:
-UTHORIZED e
+DEFUELING EMERGENCY RESPONSE PLAN, SECTION 13 O STINGS OF EMERGENCY KITS "5S[ "*''''
-nSjw                                    90Rc 9 21 FEB 131991                             lF"TE              3- M                                                 l occF                        c O -l2.S''l NUMBER IS)
+Adns(--
-O                                                                                                                                                          .
+UTHORIZED nSjw 90Rc 9 21 FEB 131991 lF" 3-M e
-FT. ST VRA!N NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT                                                                                                                        .
+TE occF c
-CONTROL CENTER PRIOR O-TO USE -
+-l2.S''l O
+NUMBER IS)
+O FT. ST VRA!N NON-CONTROLLED COPY VERIFY ISSUE STATUS WITH SITE DOCUMENT O-CONTROL CENTER PRIOR TO USE -
 FORM (01372 22 3M2 i
-   --   -- .-- ,,          ny,t,,   ,. v_..,   ,-                 -        , --
+ny,t,,
-                                                                                      --, - - . , _ . - - - ,         . - + . - .
+v_..,
-                                                                                                                                            . ~ , . , _ . - . , ,
+r
+. - +. -.
+. ~,., _. -.,,
-  -- ._-..   -..._..-..                                           .-.~.       - - -_            .     ..           -.-.    -       _ -..-                         -       .
+.-.~.
-                                                                                                                             . DERP Section 13 Issue 1
+DERP Section 13 Issue 1
-                                                                                                                                    '9' FORT ST. VRAIN NUCLEAR GENERATING STATION 0Public                    SerVlC9'                 PusuC SERVICE COMPANY OF COLORADO O                                                            LISTINGS OF EMERGENCY KITS, PROTECTIVE EQUIPMENT AND SUPPLIES STORED AND MAINTAINED FOR EMERGENCY PURPOSES
+'9' 0Public FORT ST. VRAIN NUCLEAR GENERATING STATION SerVlC9' PusuC SERVICE COMPANY OF COLORADO O
-* 1 TABLE OF CONTENTS l
+LISTINGS OF EMERGENCY KITS, PROTECTIVE EQUIPMENT AND SUPPLIES STORED AND MAINTAINED FOR EMERGENCY PURPOSES
-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
+* TABLE OF CONTENTS l
-Emergency Respiratory Protective Equipment                                     7 o
+Title Page Technical Support Center Emergency Kits 3
-l
+Drum Decon Supplies and Anti ''s 4
-* 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                                       -
+i Survey Truck 4
-Emergency Kits.
+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.
 a
-;O                                                        -
+; O fr FORM (D)T?2 22 3843
-fr FORM (D)T?2 22 3843
 DERP Section 13 Issue 1 9'
-PubilC               FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service
+Service
-* PusuC sERWCE COMPANY OF COLORADO
+* PubilC FORT ST. VRAIN NUCLEAR GENERATING STATION PusuC sERWCE COMPANY OF COLORADO TECHNICAL SUPPORT CENTER EMERGENCY KITS
-..                                                                TECHNICAL SUPPORT CENTER EMERGENCY KITS
+- Keys - Survey Vehicle
-                                                       - Keys - Survey Vehicle                                                                         *
+- Recording materials
-                                                       - Recording materials
+- Portable radio
-                                                       - Portable radio
+- Protective clothing
-                                                       - Protective clothing                                                                                                    *
+- Dosimetry
-                                                       - Dosimetry
+- Sample bottles and plastic bags
-                                                       - Sample bottles and plastic bags
+- Exposure Records
-                                                       - Exposure Records
+- Radiological Health Handbook f
-                                                       - Radiological Health Handbook                                                                                                       I f                                                                     -
+- Calculator with battery
-                                                       - Calculator with battery
+- Polyethylene sheets
-                                                       - Polyethylene sheets                                                                                                                ;
+- Survey equipment and supplies
-                                                       - Survey equipment and supplies
+- Tapes and ribbons, i.e., masking, radiation
-                                                       - Tapes and ribbons, i.e., masking, radiation
+- Signs, i.e., warning, road
-                                                       - Signs, i.e., warning, road
+- Respiratory equipment
-                                                       - Respiratory equipment
+- First aid kit
-                                                       - First aid kit
+- Yellow Rose
-                                                       - Yellow Rose
+- Film Badges
-                                                       - Film Badges
+- Flashlights /with batteries
-                                                       - Flashlights /with batteries
+- Miscellaneous Tools (screwdriver, allen wrench, wrenches)
-                                                       - Miscellaneous Tools (screwdriver, allen wrench, wrenches)
+- Masslin Cloth o
-                                                       - Masslin Cloth o
 FORM (D)772 22 3843
-                                                                            . . . - _   ,          . . - . , . . . - - . _ . . - , _ . ~ , - _ _ . . . . - - - -      , _ . ,         . . -
+.. -.,... - -. _.. -, _. ~, - _ _.... - - - -
 DERP Section 13 Issue 1 "9'
-                                     & Public                           FORT ST. VRAIN NUCLEAR GENERATING STATION
+& Public FORT ST. VRAIN NUCLEAR GENERATING STATION WQF Sorylce*
-!                                    WQF Sorylce*                       PusuC sERWCE COMPANY OF COLORADO O                                                                            DRUM DECON SUPPLIES AND ANTI-C'S
+PusuC sERWCE COMPANY OF COLORADO O
-                                                     - Protective clothing                                                                                   *
+DRUM DECON SUPPLIES AND ANTI-C'S
-                                                     - Decontamination supplies
+- Protective clothing
-                                                     - Sample bottles and plastic bags
+- Decontamination supplies
-                                                     - Tape, i.e., masking, radiation
+- Sample bottles and plastic bags
-                                                     - Wipo Envelopes
+- Tape, i.e., masking, radiation
-                                                                                                                                                       -                                         j SURVEY TRUCK                                                                                        !
+- Wipo Envelopes j
-l l
+SURVEY TRUCK
-                                                     - Survey equipment and supplies
+- Survey equipment and supplies
-                                                     - Recording material
+- Recording material
-                                                                                                                                                                                                 ]
+]
-                                                     - Calculator with battery
+- Calculator with battery
-                                                     - Stopwatch
+- Stopwatch
-                                                     - Radiation Boundary Tape
+- Radiation Boundary Tape
-                                                     - Flashlight with batteries 6
+- Flashlight with batteries 6
-                                                     - Maps 9          *
+- Maps 9
-                                                     - Copies of procedure DERP-FIELD
+- Copies of procedure DERP-FIELD
-                                                     - Compass CONTROL ROOM EMERGENCY SUPPLIES
+- Compass CONTROL ROOM EMERGENCY SUPPLIES
-                                                     - Dosimetry                                                                                                           -
+- Dosimetry
-                                                     - Respiratory equipment
+- Respiratory equipment
-                                                     - Implementing documents
+- Implementing documents
-                                                     - Controlled Distribution Set of station piping and instrument (P&I) drawings
+- Controlled Distribution Set of station piping and instrument (P&I) drawings
-                                                     - Controlled Distribution Set of station floor plan drawings
+- Controlled Distribution Set of station floor plan drawings
-                                                        -(located in the drawing file outside of the Control Room)
+-(located in the drawing file outside of the Control Room)
-                                                     - First aid kit                                                                                                             -
+- First aid kit FORM (D)372 4 22
-FORM (D)372 4 22
 * 3843
-_ _ . _ . _ _                   .__ _ _ _ _ _ _ . _ . _ = . _ _           _.              _        _ _ _ _ . _ _                                     _ _ _ _ . . _   _                 _ _.
+.__ _ _ _ _ _ _. _. _ =. _ _
-DERP Section 13
+DERP Section 13 Issue 1 0 $9fVlCO*
-:!                                                                                                                                                                     Issue 1 Public                         FORT ST. VRAIN NUCLEAR GENERATING GTATION 0 $9fVlCO* Pusuc sanvecs COMPANY OF COLORADO HEALTH PHYSICS AREA EMERGENCY SUPPLIES
+Public FORT ST. VRAIN NUCLEAR GENERATING GTATION Pusuc sanvecs COMPANY OF COLORADO HEALTH PHYSICS AREA EMERGENCY SUPPLIES
-                                               - Dosimetry                                                                                                               .
+- Dosimetry
-                                               - Respiratory equipment
+- Respiratory equipment
-                                               - Protective clothing
+- Protective clothing
-                                               - Survey equipment                                                                                                                                        .
+- Survey equipment
-                                               - Flashlights
+- Flashlights
-                                               - Batteries i'
+- Batteries i
-                                               - Flashlight bulbs                                                                                                                                              l 1
+- Flashlight bulbs 1
-l                                              - Poly bags, tape, survey r.heets, clipboard, pencils, chalk, radiation warning signs, barrier tape, and wipes preloaded in envelopes
+l
-                                               - Implementing documents                                                                                                                                        )
+- Poly bags, tape, survey r.heets, clipboard, pencils, chalk, radiation warning signs, barrier tape, and wipes preloaded in envelopes
-i                                                                                                                                                                                                             ;
+- Implementing documents
-DECON AREA EQUIPMENT LIST *
+)
-;                                              - Protective clothing l
+i DECON AREA EQUIPMENT LIST *
-                                               - Decontamination supplies                                                                                        ,,    ,
+- Protective clothing l
-l                                              - Sample bottles and plastic bags i
+- Decontamination supplies l
-i                                              - Exposure Records
+- Sample bottles and plastic bags i
-                                               - Tapes, i.e., masking, radiation i                                              - Bandages                                                                                                                                              .
+i
-j
+- Exposure Records
-                                               - Film Badges
+- Tapes, i.e., masking, radiation i
-                                               - First Aid Kit
+- Bandages j
-    .
+- Film Badges
+- First Aid Kit
 * NOTE: Located in Health Physics Area 4
-.t
+.t ).
-                ).                       -
 FORMIDl372 22 3043 I
 l
 DERP Section 13 Issue 1 O'
-Public                                                   FORT ST. VRAIN NUCLEAR GENERATING STATION 0 Service
+Service
-* PUBLIC SERVICE COMPANY OF COLORADO O                                                                    FIRST A10 ROOM EQUIPMENT LIST *
+* Public FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO O
-               - Instrument and first aid supply cabinet
+FIRST A10 ROOM EQUIPMENT LIST *
-               - Trauma kit (located in Shif t Supervisor's Of fice)
+- Instrument and first aid supply cabinet
-               - Canvas stretcher
+- Trauma kit (located in Shif t Supervisor's Of fice)
-               - Wire basket stretcher
+- Canvas stretcher
-               - Crutches d
+- Wire basket stretcher
-* NOTE:                                      Located on Level Five (5), adjacent to West Entrance.
+- Crutches d
+* NOTE:
+Located on Level Five (5), adjacent to West Entrance.
 Health Physics does not inventory this equipment.
 O r
@@ Line 2,957: / Line 3,737: @@
 DERP Section 13 l
-Issue 1 A Pubile                                                             FORT ST. VRAIN NUCLEAR GENERATING STATION    '9' M17 Service
+Issue 1 A Pubile FORT ST. VRAIN NUCLEAR GENERATING STATION
-* PUBUC SERVICE COMPANY OF COLORADO O                                                                                                                               EMERGENCY RESPIRATORY PROTECTIVE EQUIPMENT *
+'9' M17 Service
-* Health Physics                                              *
+* PUBUC SERVICE COMPANY OF COLORADO O
-                                                                                                                                          - Four Scott air packs
+EMERGENCY RESPIRATORY PROTECTIVE EQUIPMENT
-* Turbine Deck, El 4829, Fire Station                                        ,
+* Health Physics
-                                                                                                                                           - Six Scott air packs                                                          *
+- Four Scott air packs Turbine Deck, El 4829, Fire Station
-* Building 10. El 4839, Offices
+- Six Scott air packs Building 10. El 4839, Offices
-                                                                                                                                            - Five Scott air packs
+- Five Scott air packs Outside Auxiliary Electric Room
-* Outside Auxiliary Electric Room
+- Two Scott air packs El 4791, Fire Station
-                                                                                                                                             - Two Scott air packs
+- Six Scott air packs Central Alarm Station
-* El 4791, Fire Station
+- Two Scott air packs Search and Identification Building
-                                                                                                                                             - Six Scott air packs Central Alarm Station
+- Five Scott air packs a
-                                                                                                                                              - Two Scott air packs Search and Identification Building
+Technical Support Center
-                                                                                                                                               - Five Scott air packs a   .
+- Five Scott air packs NOTE: Scott air packs may be shown on individual center inventory lists also.
-* Technical Support Center
-                                                                                                                                                - Five Scott air packs NOTE: Scott air packs may be shown on individual center inventory lists also.
 k FORM (ol372 22 360
-_ _ _ _ _ . _ _ _ - - _ - _ _ _ _ _ - _ - _ - - _ . .                            . _ - - - _}}
+. _ - - - _}}