ML20098B458
| ML20098B458 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 09/07/1984 |
| From: | Gahm J PUBLIC SERVICE CO. OF COLORADO |
| To: | Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| P-84348, PROC-840907, NUDOCS 8409260108 | |
| Download: ML20098B458 (210) | |
Text
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, "B PUZLIC 8/21/84 c} 3,3 3,N 7-l Y RADIOLOGICAL ~ EMERGENCY RESPONSE PLAN - PLANT ISSUE EFFECTIVE NO. SUBJECT NUMBER DATE Table of Contents 3 10-08-82 Introduction 3 10-08-52 Section 1. Definitions ,
4 07-24-84 Section 2 Scope and Applicability 4 01-03-83 Section 3 Summary of the Radiological Emergency Response Plan 4 07-24-84 l Section 4 Emergency Conditions 5 08-21-84 l Section 5 Organizational Control of l Emergencies 6 08-21-84 l Section 6 Emergency Measures 7 08-21-84 C> i Sectioa 7 Emersencv Faciiities aad l Equipment 6 08-21-84 Section 8 Maintaining Emergency Preparedness 3 10-08-82 Section 9 Recovery 4 07-24-84 Section 10.A Agreement Letters and Summary of Referenced Interfacing Emergency Plans 7 07-02-84 Section 10.8 Sample Dose Calculations 4 04-02-84 Section 10.C Maps of Exclusion /,rea, Low Population Zone, Environmental Dosimetry, Population Densities 3 10-08-82 Section 10.0 Titles of Written Procedures that Implement or Supplement the Plan 6 07-24-84 Section'10.E Listings of Emergency Kits, Protective Equipment and Supplies Stored and Maintained for Emergency Purposes 5 11-28-83 O Section 10.F Cross Reference to NUREG-0654, Rev. 1 4 01-03-83 b ronu an.22 me 8409260108 840907 gDRADOCK05000g g7
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PUZLIC SERVICE COMPANY OF COLORADO RERP S:ction 4
; FORT ST. VRAIN NUCLEAR GENERATING STATION 1 of 22
-(~', FORT ST.VRAIN
- TITLE: RADIOLOGICAL EMERGENCY RESPONSE PLAN, SECTION 4 NON - ROLLED VERFYISSUE STATUS WITH DOCUMENTCENTER l lSSUANCE FORM 372-22 3567 AUTHORIZED BY //) $ ? af-#/V PORC R EVIEW
/ 58 2 M14 W EFFECTIVE DATE 8- Al- b 4.0 Emergency Conditions Emergencies are classified into four categories as provided by
" Emergency Action Level Guidelines For Nuclear Power Plants",
Appendix 1, USNRC NUREG-0654, Rev. 1. Each succeeding classification is more severe than its predecessor and results in a higher level of response. The classification system results in responses and procedures that are both timely and appropriate for a wide range of emergency conditions. 4.1 Classification The classifications described in the following sections (q) comprise the system. Each classification description includes appropriate levels of station and state / local government agency emergency response actions. The classifications given match those employed in the State RERP. 4.1.1 NOTIFICATION OF UNUSUAL EVENT This classification applies to situations where unusual events are in process (or have occurred) which indicate a potential for degradation of the level of safety of the plant. In these situations, time is available to take precautionary and constructive steps to prevent a more serious event and/or to mitigate any consequences that may 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 l event. No releases of radioactive material ( requiring offsite response or monitoring are j expected at this level. Table 4.1-1 outlines initiating events and response l O~ actions for the NOTIFICATION OF AN UNUSUAL EVENT class of incident. t i PORM 372 22 3642
RERP Section 4 PUBLIC SERVICE COMPANY OF COLORADO Issue 5 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Pag 2 2 of 22 .c
~ -O l - 4.1.2 ALERT This classification comprises events which are in process, or have occurred, that involve the potential for a substantial degradation of the level of safety of the plant. Any releases of radioactive materials are expected to represent small fractions of the EPA Protective Action Guide limits. The purpose of the ALERT category is to assure that emergency personnel are readily available if the situation degrades and to prmide offsite authorities with comprehensive status information. Operator modification of plant 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 followup notification to offsite authorities. If applicable, updated meteorological information, 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 p be terminated or an escalation to a more ~ severe - V emergency class is declared. Table 4.1-2 outlines initiating events and response actions for the ALERT class of incident. 4.1.3 SITE AREA EMERGENCY A SITE AREA EMERGENCY consists of events which are in process, or have occurred, that involve actual or likely major failures of plant protective functions. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary. The purpose of the SITE AREA EMERGENCY declaration is to assure that emergency response facilities are manned, that radiation monitoring teams are dispatched, that emergency forces are readily available, and to provide efficient exchange of status information between PSC and offsite authorities. Consideration of appropriate protective actions, based on actual or projected data, is warranted. Onsite and offsite emergency centers are activated. Onsite evacuation is initiated if indicated to be necessary by actual or projected doses. PSC radiological monitoring teams are deployed. The station provides status updates to offsite O'~ authorities, including meteorological information, offsite radiological monitoring data (prior to P i PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO $,$# 4 [ s FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 22 p
,/ - state monitoring team deployment), and projected doses (calculated on foreseeable plant conditions and projected long-term releases). State monitoring teams are dispatched to assess offsite consequences. If projected exposures approach those noted in the EPA PAGs, state / local authorities institute appropriate actions for public protection. A decision on termination, escalation, or recommended reduction in emergency class will be communicated to governmental authorities.
Table 4.1-3 outlines initiating events and response actions for the SITE AREA EMERGENCY class of incident. 4.1.4 GENERAL EMERGENCY A GENERAL EMERGENCY consists of events which are in process, or have occurred, that involve actual or imminent substantial core degradation, with the potential for loss of Prestressed Concrete Reactor Vessel (PCRV) integrity. Exposure levels beyond the site boundary may exceed EPA Protective Actinn q Guideline levels. There is prompt notification of Q appropriate state and local authorities of the GENERAL EMERGENCY status. The purpose of declaration of a GENERAL EMERGENCY is to rapidly initiate predetermined protective actions for the public. During a GENERAL EMERGENCY, resources and personnel are augmented by the activation of emergency centers. Radiological monitoring teams are dispatched. The station provides plant status updates, as well as data on radioactive releases, meteorological information, radiological field measurements, radiological dose projections, and affected downwind zones to offsite authorities. A decision on termination or reduction of the GENERAL EMERGENCY class will be communicated to governmental authorities after thorough review of the emergency situation. Table 4.1-4 outlines initiating events and response actions for the GENERAL EMERGENCY class of incident. 4.2 Offsite Accident Assessment
' ') The station has the responsibility to perform a preliminary assessment of the offsite consequences of an ?
a PORM 372 22 3643
ection 4
, PUBLIC SERVICE COMPANY OF COLCRADO , ~
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 22
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. incident. This preliminary assessment includes:
determination of the radiation exposure rate by precalculated analytical methods (see Section 6.2) and/or field surveys; estimation of projected total dose levels for different downwind sectors and distances; and, classification of incident consequences, per Tables 4.1-1 through 4.1-4. Based upon the results of these assessments, notification of state / local authorities of the appropriate incident classification is then made. After arrival at the Forward Command Post (FCP), the Colorado Department of Health (CDH) assumes responsibility for confirmatory (in-field) and continued offsite accident assessment, and FSV Field Monitoring Teams are recalled to the Personnel Control Center). This responsibility is carried out by dispatching COH field monitoring teams and by analysis of data provided by PSC. Long-term offsite assessments (secondary incident assessments) are the responsiblity of the CDH staff as noted in the State RERP. 4.3 Spectrum of Possible Accidents and Initiating Events The accidents which might occur at the Fort St. Vrain Nuclear Generating Station have been analyzed in Section 14 of the FSV FSAR for their severity of pJ consequence and probability of occurrence. These accidents reflect the design characteristics of a High Temperature Gas-cooled Reactor (HTGR) and are addressed in Tables 4.1-1 through 4.1-4 from the viewpoint of initiating events, alarm actuation and/or associated readings, and consequent incident classification.
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l t l 2 ( RERP Section 4 i Issue 5 Page 5 or 22 TABLE 4.1-1 EMERCEIICY ACTION l.EVELS (EALs) at CORRESPOIIDlIIC ACTIOIIS 100TIFICATl001 Or UleUSUAL EVENT FORT ST. VRAIN NUCLEAR GENERATIIIC STATIOsl EAL ( Ala rm, Instru-Initiatine Events ment Readine. etc.) PSC Actions State / tocol Actions ( Alarms on:
- 1. Any unplanned radio- 1. RT 7312 Inform State and Provide assistance if logical release CAM (s) local authorities requested ( ri re, to the Reactor RT 7324-1; RT 4801; or naturc or unusual security, medical, etc).
Bldg. or its vent- RT 7324-2; RT 4802; condition within 2 hours lation system. RT 7325-1; RT 4803; or occurrence, but in any RT 7325-2; RT 73437-1,2 event, within 15 minutes of declaration.
- 2. Any liquid weste release 2. a) RT 6212 or 6213 Augment on-shirt Continue orrsite resulting in orrsite alarm with inability resources notification as errIuent in excess of to prevent discharge Assess and respond. necessitated by Technical Specification orrsite. situation.
Limits. b) As determined by sta t ion pe rsonnel.
- 3. Indication or minor 3. a) 25% increase in Terminate with verbal summary to orrsite Standby until verbal fuel damege detected circulating act-in primary coolant ivity from pre- authorities followed by termination.
vious equilibrium written summary within conditions at the 24 hours. or same power level. or RT 9301 Escalate to a more Escalate to a more b) SR 5.2.11 results. severe class. severe class. NOTE 1: Assumption implicit throughout Tables 4.1 4.1-4 tha t a la rms a re confi rmed to be va l id by supporting observations or analysis as specirled by abnormal operating or annunciator response procedures. ItOTE 2: Due to instrument characteristics, alarm setpoints for radiation monitors listed in Tables 4.1 4.1-4 vary with time. Instruments and alarm setpoints are checked / calibrated quarterly. Consult leaster Setpoint List for actual settings. )
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RERP Section 4 issue 5 . Page 6 of 22 or 5 TABLE 4.1-1 EMERGENCY ACTION LEVELS ( EALs) & CORRESPONDING ACTIONS I
, NOTIFICATION OF UNUSUAL FVENT , ,
FORT ST. VRAIN NUCLEAR CENERATING STATION EAL ( Ala rm, Instru-
; initiatina Events ment Readino. etc.) PSC Actions State / Local Actions
- 4. Serious rire at the 4. a) any or various Note: Per agreement with the State t plant lasting more than a la rms on Fi re Con- or Colorado, PSC will notify
; 10 minutes, which could t ro l Ala rm Pane t ; the State prior to public i lead to substantial b) Fire Pump 1A Information releases concerning degradation of plant auto start; FSV. , safety systems, or c ) ve rba l repo rt s.
I which could result I in the release or .i radiological or i- . toxic materials. ,
- 5. Abno rma l coolant temp- 5. Violations or LCO 4.1.7 ,
or 4.1.9 for region ; l eratures or core ' y region temperature outlet mismatch, or region rises to the extent re- Delta-T respectively, , quiring shutdown in to the extent that shut- ? accordance with Tech- down per Station Tech-nical Spectrications I nical Specifications, is requi red ( SOP 12-04).
- 6. Natural phenomenon 6. a ) Se l smic Reco rde r that may be exper- Ope ra te; lenced or threatened b)-d) as visually
. that rep resent risks observed by, or 1 beyond normal levels: reported toi, station a) earthquake personnel, b) floods c) tornadoes d) extremely high winds 4 1 1 1 4
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RERP Section 4 Issue S Page 8 of 22 TABLE 4.1-1 EMERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS NOTIFICATION OF UNUSUAL EVENT FORT ST. VRAIN NUCLEAR CENERATING STATION i EAL ( Ala rm, instru- ! Initiatino Events ment Readino. etc.) PSC Actions State / Local Actions + l 9. Accidents within the 9. As occurring or i ' state that may involve reported by shipper. plant spent fuel ship-i ~ ments or plant radio-active waste shipments.
- 10. Loss of Engineered 10. Shutdown required in
. Safety Feature or accordance with applicable 1 Fi re Protection System LCOs: to the extent requiring a ) Eng inee red Sa regua rds shutdown in accordance 1) Plant Ventilation - with station Technical LCO 4.5.1 1 Specifications. 2) Steam /L.'a ter Dump System-LCO 4.3.3
- 3) PCRV penetration flow a restriction devices - !
. LCO 4.2.7 and i LCO 4.2.9 ! 4) PCRV penetration secnnda ry closures -
; LCO 4.2.7 and 4 LCO 4.2.9
- 5) PCRV Safety Valves -
1 LCO 4.2.8 SL 3.2 l LSSS 3.3.2.c i b) Fire Protection System - 4 LCO 4.2.6 and, LCO 4.10.1 - LCO 4.10.5 i a 4 4 4
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TABLE 4.1-1 I) EMERCENCY ACTION LEVELS (EALs).& CORRESPONOING ACTIONS NOTIFICATION.0F UNUSUAL EVENT
- l FORT ST. VRAIN NUCLEAR CENERATING STATION EAL ( Ala rm, instru-Initiatino Events ment Readina. etc.) 'PSC Actions $_ tate / Local Actions
- 11. Indication or alarms 11. Data Logger Ala rm/
on radiological effluent Alarm Summa ry indication , monitors not functional. or non-operational ! alarm or Indication on: a) RT-7324-1,2 and
. RT 4803; or
- , b) RT-7325-1 2, RT 4802, and RT 73b37-1; or c) Ri 73437-2 and RT 4801; or -
d) RT 6212 and RT 6213 I 2 li NOTE: Use ELCO 8.1.1 Technical ; i: Specification limits as basis. The initiating events for the NOTIFCATION OF UNUSUAL EVENT category are per Public Service Company. , separate written agreement with the State or Colorado. !1 , if , II
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RERP Section 4 Issue 5 Page 10 of 22 TABLE is.'1-2 ENERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS i ALERT FORT ST. VRAIN NUCLEAR CENERATING STATION i EAL ( Ala rm, Instru-l' initiatina Events ment Reading. etc.) PSC Actions State / Local Actions I 1. Rapid, severe fuel 1. Coolant inventory or Inform State and/or Provide assi stance, ir particle coating a ) grea ter than 2.4 local authorities or requested ( Fi re, j: failure. LG1)(Mev) Beta-Camma ALERT status /cause security, medical, etc.) Ib as decla red j' b. c i rcu la t ing 1-131 d
- ?
activity equivalent greater than 24Ci i
- c. plate out 1-131 greater than 1 x 10 Cl.
- d. SR 5.2.6 or
., SR 5.2.11 results.
- 2. Rapid, gross fall- 2. Loop 1 Hot Reheat Header ' Augment resources by Augment resources by ure or one steam (HRH) activity high . activating TSC, PCC, activating TCP and and FCP. State / local EOCs.
I generator reheat (5 mrem /hr); or, Loop 2 3! section with loss or HRH activity high (5 mrem /hr), accompanied o f fs i te powe r. by 230 KV OCB trips << and RAT undervoltage/
- ) loss of power ala re.
- ' Assess and respond.
it $$ 3. Prima ry coolant press- 3. PAL 9335 Place key emergency ure decay (to a PAL 9347 Dispatch onsite personnel (including
- ! value greater than PAL 9359 - monitoring teams with monitoring teams and l1 100 psi tess than and a rea monitor or i associated communica- associated communica-stack monitor ala rm.
tions, tions) on standby f( normal pressure, accom-status. a; panied by area and
- i stack radiation '
Provide periodic plant
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':4 orrsite authorities as
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, issue 5 Page 13 of 22 TABLE 4.1-2
'. EMERGENCY ACTION LEVELS (EALS) & CORRESPONDING ACTIONS ALERT TORT ST. VRAIN NUCLEAR GENERATING STATION EAL ( Ala rm, instru- - Initiatino Events ment Readino. etc.) PSC Actions State / Local Actions
- 11. Radiological ef- 11.RT 7324-1 indicating fluents exceed 10 a) greater than or equal times technical to 2.5 x 10 micro Ci/cc specification instan- mixed noble gas taneous limits, b) RT 7324-2 indicating greator than or equal to 2.5 x 10 micro Ci/cc mixed noble gas i c) RT 7325-1 Indicating a greater than or equal ,
.. to 7.0 x 10 mic ro Ci/cc 131 ; d) RT 7325-2 indicating greater than or equal a to 7.0 x 10 mic ro Ci/cc - l-131 e) RT 73437-1 indicating ..^! greater than or equal to 7.0 x 10 mic ro , Ci/cc 131 f) RT 4801 indicating greater than or equal 4 to 7.0 x 10 mic ro Ci/cc - l-131 [ 12. Ongoing security 12.a) As observed or comp romi se. repo rted. , T 4
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- . 1 j 'I l RrRP Section 4
' issue 5' i Page 14 of 22 i t
3 , j t 4 i , l 1 6 TABLE 4.1-2 ENERGENCY ACTION LEVELS (EALs)'& CORRESPONDING ACTIONS l ALERT 1 ; j TORT ST VRAIN NUCLEAR' GENERATING STATION ; n EAL ( Ala rm, Instru- , initiatina Events ment Readine. etc.) PSC Actions State / Local Actions
- 13. Severe natural 13.a) Seismic recorder De phenomenon being operate (greater experienced or than or equal to p rojected, such as: .05g); or b) As Reported a ) ea rthquake ex- ,
c) As Reported, ceeding Operating Basis Earthquake levels; b) flood near design level; or, c) tornado striking l racility. 4 14.0ther haza rds 14. As reported by, or
- being experienced or to, station
~ Or proJocted such as: persorrel. a ) a i rc ra rt c ra sh
- on facility; b) missile impact on racility; c) explosion damage .
, arrecting plant operation; or, h d) entry into facility
< environs or toxic l or flammable gas. (Some errect on ] racility experienced or anticipated. ) i d' 9 a
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RERP Section 4
. Issue 5 Page 15 of 22 i
i .. y TABLE 4.1-2 , f EMERGENCY ACTION LEVELS ( EALs) & CORRESPONDING ACTIONS ; ALERT FORT ST. VRAIN NUCLEAR CENERATING STATION EAL ( Ala rm, Instru-Initiatino Events ment Reading. etc.) PSC Actions State / Local Actions
- 15. Evacuation or con- 15. As deemed necessary trol room anti- by Shirt Supervisor cipated or requi red, i.
with control or shut-i, down systems estab- i lished f rom local stations. (Con-trol room integrity b reached. ) l
- 16. Control room !
- 16. All ala rms (annun-clators) lost for obse rva t ion. l more than 15 minutes ,
i ' and reactor is not . shutdown; or, plant transient experienced 2 . while all alarms lost. :l ' (Pa rameter indication ij j still functional.) j 17.other plant con- 17. As deemed necessa ry ditions warranting by Shirt Supervisor. 4 precautiona ry acti-F vation or the PCC, TSC, and FCP. E 4 4 t 4 l ) 4
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, TABLE 4.1-3 4 EMERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS SITE AREA EMERGENCY
'd FORT ST. VRAIN NUCLEAR CENERATING STATION EAL ( Ala rm, Instru-Initiatino Events ment Readino. etc.) PSC Actions State / Local Actions
- 1. Loss of prima ry 1. All 11 0 flow in- Inform state and/or Provide any assistance .
coolant forced dicators read zero, local authorities or requescod. ! t'i it ci rculation for over SITE AREA EMERGENCY 4 5 hr f rom 100% power. status /cause as de- l ( Lowe r powe r l eve l s c l a red . t preceeding LOFC ex- l 1 tends time available !
> before core damage i l Is incurred. See Augment resources by initiate immodlate 'j l LCO 4.2.18.) activating TSC, PCC, public notification .l i ;q
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( , Issue 5 Page 18 or 22 1 r
. TABLE 4.1-3,
- g. EMERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS I SITE AREA EMERGEMQY 4 FORT ST. VRAIN NUCLEAR CENERATING STATION ,
EAL ( Ala rm, instru-Initiatina Events ment Readina. etc.) PSC Actions State / Local Actions
- 7. Fire adversely 7. a) Fire pump 1A Provide release and Evaluate data and arrecting sarety s ta rt; dose projections initiate ingestion systems. b) Fire Control based on available pathway protective Ala rm Panel plant condition in- actions as aproppriate.
c) Va rious ala rms fo rma t ion and fo r-acco rd i ng to a r- seeable contingencies. - rected safety system d) Shift Supervisor determines fi re beyond capability or station starr.
- 8. a) Erriuent monitors 8. Stack monitor Terminate (or recom- Provide press brierings.
detect level s cor- a la rm wi t h co r- mend reduction of) i responding to greater responding stack emergency class verbally
, than 50 mree/hr W.B. concentra tion in- at FCP rollowed by I for 1/2 hr, or dications on: written summa ry within greater than 500 a) RT73437-1, RT4802, 8 hours, mrem /hr W.B. For two & RT7325-1,2 or minutes, at the site greater than or bounda ry under equal to 6.7 x 10 Escalate to CENERAL Maintain SITE EMERGENCY adverse meteorology micro Cl/cc l-131 EMERGENCY status until te rmi na t ion ! (or levels 5 times the above for thyrold b) RT 7324 -1,7 and RT 4803 - greater or reduction or emergency class.
{ I dose rate), than or equal to 6.6 x 10 j micro CI/cc mixed
- noble gases g b) These dose rates or are projected based
! on other plant para- Escalate to GENERAL meters cr are measured EMERGENCY. In the environs. I l . I , i
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.; e 'l 1 RERP Section 4 j issue 5 / Page 20 or 22 i. ; TABLE 4.1-3 EMERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS SITE AREA EMERGENCY FORT ST. VRAIN NUCLEAR GENERATING STATION 1 EAL ( Ala rm, Instru-PSC Actions 1 Initiatina Events ment Readina. etc.) State / Local Actions
- 11. Other hazards being 11. As observed by or i . .i experienced or pro- reported to, station i Jected with reactor personnel.
) not shutdodn, such as;
( '?, ! a ) a i rc ra f t c ra sh a rrec t ing ,, vital structures; j b) severe damage to safe
- j F
shutdown equipment; c) entry of toxic /rlammable i gas into vital a rea s. l 12. Reactor building 12. a) ouvers Open a la rm l fouvers open due to 3" water) i# bui ld ing be i ng ove r- b) Reactor building !! pressurized by pri- radiation ala rms. ma ry coolant. (DBA #2) 'lj 13. Evacuation or con-t ro l room accompanied
- 13. Remote shutdown instrumentation indi-by inability to cations (panel 1-49) l l
locally control shut-down systems with-in 15 minutes.
- 14. Other plant con- 14. As determined by ditions warranting Shif t Supervisor, activation of FCP/ ,
EOCs, monitoring teams, and precau-tionary public - notification. .j t O
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b ' ii 4i RERP Section 4 issue 5 Page 21 of 22 3
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t l TABLE 4.1-4 EMERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS GENERAL EMERGENCY
] FORT ST. VRAIN NUCLEAR CENERATING STA110N I ! EAL ( Ala rm, Instru-Initiating Events ment Reading. etc.) PSC Actions State / Local Actions-
- 1. a) Errivent monitors 1. Stack monitor Inform State and/or Provido assistance.
y detect levels cor- RT-732fs-1,2 a la rm, or local authorities or a responding to Irem/hr corresponding dose rates CENERAL EMERGENCY status /. -l W.B. (or 5 rem /hr determined with E-500 causo within 15 Initiate immediate public 8 thyroid) at the ex- or Cutie Pie detector min. of detection, notification of CENERAL 4 clusion area per procedure HPP-56 EMERGENCY status and bounda ry under and associated graphs. Augment resources by provide periodic public actual meteoro- activating ISC, PCC, updates, logical conditions. ECP, and FCP. j b) These dose rates Assess and respond. ,1 are projected based 3 on other plant pa ra- Consider / implement pro-
), esters or are measured Dispatch rad iolog ica l tective actions based j in the envi rons. monitoring teams with communications equipment, on current assessment.
j Augment resources by I. Provide a dedicated activating FCP and EOCs. Individual for plant ' j 2. Loss or physical 2. Situation evident. 1 control or the racility status updates to d (due to security orrsite authorities Dispatch key emergency
] breach) and periodic press b re i ring s.
pe rsonne l, including monitoring teams, with
- 3. Other plant con- 3. As determined by communications equipment.
ditions exist that Sh i f t Supe rv i so r. Make senior technical make release of l a rge and management starr amounts or radio- available for periodic Dispatch other emergency activity possible. consultation with NRC. pe rsonne l to duty stations within a 5-mile Provide meteorologica l radius and alert others data and dose esti- to standby status. mates (for actual re-lessos) to orrsite authorities via a dedicated individual. 0 4
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' RERP Section 4 Issue 5 Page 22 of 22 TABLE 4.1-4 EMERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS CENERAL EMERCENCY TORT ST. VRAIN NUCLEAR GENERATING STATION i
i EAL ( Ala rm, instru-j Initiatine Events ment Readino. etc.) PSC Actions State / Local Actions l Provide release and Provide orrsite monitoring i dose projections based resul ts to PSC and -
) upon information and fore- Jointly assess these. 1 A sceable contingencies.
4 j Terminate (or recommend Continuously assess i reduction of) emergency information f rom PSC
. class by briefing and orrsito monitoring ], authorities at the FCP, teams with regard to followed by written initiating or modifying summa ry within 8 hours, public protective actions.
Evaluato data and 1 initiato ingestion , I pathway protectivo j actions as appropriate. hj. Provide press brierings. j ' Maintain GENERAL i EMERGENCY status until j termination or reduction or emergency class. i i I f
I X 1 PUBLIC SERVICE COMPANY OF COLORADO RERP Section 5 S FORT ST. VRAIN NUCLEAR GENERATING STATION e U ~C FORT ST.VRAIN l TITLE: RADIOLOGICAL EMERGENCY RESPONSE PLAN, SECTION 5 NON - CONTROLLED COPY l VERWYlSSUE j
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STATUSWITH DOCUMENT CENTER ISSUANCE PfUOR TO USE AUTHORIZED b' FORM 372-2235U BY [ _8 PORC A EFFECTIVE REVIEW PORc 58 2 AWG141984 DATE 8- M- Sh 5.0 Organizational Control of Emergencies 5.1 The Normal Station Organization is shown, in chart form, on Figure 5.1-1 and is detailed in station Operating Technical Specifications. A shift of 8 operating and 9 security personnel, under the direction of a Shift Supervisor, is on duty at all times (Figure 5.1-2). Duties and responsibilities of operating personnel are set forth in station administrative procedures. 5.2 The Onsite Emergency Organization for the four categories of incident classification is depicted on Figures 5.2-1 o and 5.2-2. In the event of an emergency, the on-duty
's)
Shift Supervisor has the responsiblity to initiate immediate actions to limit the consequences of the emergency and to return the plant to a safe and stable condition. He is, further, assigned the authority for direction of site emergency operations (Emergency Coordinator) and retains this authority until relieved by the Control Room Director or Technical Support Center Director. In this interim capacity, he is responsible for: classification of the emergency event; initial notification of appropriate governmental emergency response agencies; and, initiation of protective actions l for station personnel. He may confer with FSV and PSC l management for advice or concurrence with initial accident l classification, if desired. (In the event the Shift Supervisor is unable to perform as Emergency Coordinator, the most senior Reactor Operator assumes that role.) The Emergency Coordinator is responsible for initially classifying the incident, recommending protective actions, initiating corresponding emergency actions, notifying offsite authorities of the incident, and establishing communications with the TSC. Responsibility for the decision for notification and protective action recommendation may not be delegated. Further responsibilities include: diag, nosing the accident , (s) condition and estimating radiological exposures based on radioactive material { releases and prevailing ! I k FORM 372 22 3642 w- , - - -
, PUBLIC SERVICE COMPANY OF COLORADO Secti n 5 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 27 1 O
!I meteorological conditions. To ensure this function 's covered at all times, the Shift Supervisor is an authorized Emergency Coordinator. The on-duty Shift Supervisor continues to functicn as the Emergency l Coordinator at least until the emergency organization is activated. The Fort St. Vrain Nuclear Generating Station emergency organization operates from three onsite emergency centers Control Room (CR), Technical Support Center (TSC), and Personnel Control Center (PCC). It is supported by three offsite emergency centers - Forward Command Post (FCP), State Emergency Operations Center (State EOC), and Executive Command Post (ECP). The station emergency organization will be manned and operational within 90 minutes after classification of an ALERT or higher level incident. Onsite and offsite emergency organization interrelationships are shown in schematic form in Figure 5.2-3. PSC's role in the offsite (local and state) emergency control centers is diagrammed in Figure 5.2-4 (FCP) and Figure 5.2-5 (State EOC). Augmentation in the form of headquarters support is shown in Figure 5.2-6 Tx (ECP) and is discussed in Section 5.3. The function, responsiblities, and staffing of the offsite emergency organization is also described in Section 5.3 and is shown in Figure 5.2-7. Post-emergency plant recovery plans and organization are described in Section 9.0. Emergency personnel assignments are shown by function. For clarity, normal job titles are also indicated. Qualification requirements (per the normal titles) are given 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 Figure 5.2-1 and discussed in Section 5.2. This responsiblity will remain with the Shift Supervisor until such time as the emergency organization for an ALERT or higher level accident is activated (Figure 5.2-2). During an ALERT, or higher level accident, overall command of PSC emergency operations will be exercised by the Corporate Emergency Director (Vice President of Production) at the FCP. He will provide direction to, and coordination for, the TSC Director (Manager, Nuclear Production) and the Manager, Nuclear Engineering (as. signed to the State p) c l EOC). He will coordinate additional headquarters support via the ECP. P FORM 372 - 22 3643 _ _ - . ~ ,.-.4 m, -~ . _ --- - . . _ - - , - - - 1
Section 5
, PUBLIC SERV!CE COMPANY OF COLORADO ,
1_ FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 27 i
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- a. The Corporate Emergency Director (CED) - (Vice President of Production) is in command of PSC emergency operations and is responsible for direction and coordination of:
- 1. PSC onsite and offsite emergency functions;
- 2. Interface between PSC and local / state / federal emergency response activities;
- 3. Transmission of plant status updates and radiological release data to FCP and State EOC emergency response and media center personnel;
- 4. Notification of state and local agencies concerning recommended protective actions;
- 5. Provision of administrative, technical, and logistic support to station emergency operations; and,
- 6. Continuity of emergency organization resources.
In the event the Vice President of Production is not available, the Vice President of Engineering and Planning will assume command of PSC emergency operations,
- b. The TSC Director -
(Manager, Nuclear Production) is in command of onsite emergency . operations. The TSC Director is authorized to initiate emergency actions, including declaring a particular class of emergency and , providing protective action recommendations to i offsite authorities. (The alternate TSC Director is the Station Manager). Duties and responsibilities of the TSC Director include direction and coordination of:
- 1. The TSC staff, which is responsible for collecting and analyzing the tecnnical information necessary for assessment of plant operational aspects, providing g-ss technical counsel 1.n support of the
(_) Control Room (CR), and assessment of radiological release consequences. o i FORM 372 - 22 3643 l
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PUBLIC SERVICE COMPANY OF COLORADO e FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 27 l
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- 2. The CR Director (Superintendent of Operations), who is responsible for control of plant operations, assessing I plant operational aspects, and implementing recommended corrective actions. (The alternate for the CR ;
I Director is the Shift Supervisor, ) l Training). l 3. The PCC Director (Scheduling / Stores l Coordinator), who is responsible for continued personnel accountability, assembling personnel for repair / damage control or radiological survey teams, search and rescue teams, reserve operating staff, and establishing radiological control areas as directed. (The alternate for the PCC Director is the Training Supervisor). 5.2.2 Plant Staff Emergency Assignments Three principal onsite groups comprise the station emergency organization. Each group operates under ( the supervision of a director ~at an emergency
\ centar (TSC, PCC, and CR) as discussed in Section 5.2.1. Each center Director is responsible for center communications and for assigning an individual to keep a record of important events, decisions, and actions. Plant staff emergency assignments and functions for these centers are summarized in the following paragraphs. Primary and alternate leads are shown for continuous 24-hour operation.
- a. Technical Support Center
- 1. Plant Condition Assessment Diagnose plant conditions, provide recommended corrective actions, and coordinate systems analysis and procedures. (Primary and Alternate:
Off-duty Shift Supervisors) 1
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FORM 372 3643
. - . - ~ . _
, PUBLIC SERVICE COMPANY OF COLORADO ,p m 5 l 1 ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 27 .p
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- 2. Engineering & Technical Analysis Direct core physics analysis, electrical and mechanical engineering, licensing, procedures development, and system anaiysis. Maintain liaison with offsite technical support such as NSSS, AE, EPRI.
(Primary: Technical Services Engineering Supervisor; Alternate: Senior Plant Engineer)
- 3. Health Physics / Radiological Monitoring Assess onsite radiological doses, direct radiological / radiochemical surveys and decontamination actions. (Primary:
Health Physics Supervisor; Alternate: Health Physicist)
- 4. Radiological Assessment Assess offsite radiological doses and consequences, determine potentially affected offsite areas, and confer with -
p si the Technical Support Center Director and the Radiological Assessment Coordinator
~ ~
at the FCP regarding plant status, offsite dose computations, and protective l actions (Primary: Senior Plant Engineer; l Alternate: Technical Services Engineer).
- 5. Emercency Maintenanc_e Determine and recommend repair / damage control and corrective actions for plant mechanical and electrical systems.
(Primary: Superintendent of Maintenance; l Alternate: Maintenance Supervisor -
- l. Electrical)
- 6. Emergency I&C Support Determine alternative I&C capabilities or configurations; repair / install / modify instrument and control equipment.
l (Primary: Superintendent of Nuclear l Betterment Engineering; Alternate: l Results Engineering Supervisor) t - FORM 372 22 3643
- n. . . . . - . . , .,.n.--.. .. ,.- . --.,..-...n._en_.-.n.
l , PUBLIC SERVICE COMPANY OF COLORADO ,lctin5 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 27 \.
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. 7. Administrative & Logistics Support Provide needed technical documents, communications and analytical equipment, clerical assistance, and food, transportation / housing support.
l (Primary: Nuclear Documents Supervisor; I Alternate: Nuclear Documents Specialist) 1
- 8. Computer Services Provide technical support in the areas of computer hardware and software development / modification. Provide I assistance to TSC Radiological Assessment l individual as needed. (Primary: Senior Analyst; Alternate: Senior Programmer)
- b. Personnel Control Center
- 1. Personnel Accountability Maintain continued personnel accountability, including personnel contamination surveys, control areas, and br3 exposure records. Handle search and rescue efforts, first aid, medical transportation, and personnel decontamination. (Health Physics Technicians, Scheduling /QC staff, and other personnel)
- 2. Operating Staff Support Relieve and support plant operations personnel as necessary in operating plant equipment, processing effluents, and performing emergency maneuvers. (Off-duty operations personnel)
- 3. Maintenance, Repair & Damage Control Perform mechanical and electrical repair / damage control, emergency maintenance, and temporary modifications.
(Maintenance staff and I&C Technicians, I augmented as necessary by PSC personnel l from offsite locations)
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l h t FORM 372 22 3643
etion 5 PUBLIC SERVICE COMPANY OF COLORADO e FORT ST. VRAIN NUCLEAR GENERATING STATION page 7 of 27 i _ j .C ~ Hazards Control - 4. Extinguish fires, purge hazardous gases, combat natural emergencies. (Fire Brigade personnel) During the day shift, the Fire Brigade receives initial direction from the CR Director and is subsequently assigned to the PCC.
- 5. Security
. Coordinate site access security with the Security Supervisor. The Lead Security Officer is the alternate for the Security Supervisor,
- c. Control Room
- 1. Plant Control Direct plant operation to terminate the incident, regain plant control, and minimize accident consequences. See Section 5.2 for further details. (Shift e Supervisor)
- 2. Plant Operation Assist the Shift Supervisor in implementing plant corrective actions.
(Reactor Operators)
- 3. Technical Assistance Provide technical analysis / advice and recommend corrective actions necessary to bring the plant to a safe and stable condition. (Technical Advisor)
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*ORM 372 3643
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Section 5
. PUBLIC SERVICE COMPANY OF COLORADO ,
[ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 27 b 5.3 Augmentation of Onsite Emergency Organization Onsite emergency operations are augmented by headquarters support (corporate resources) dispatched directly to the PCC or to an appropriate onsite location. Agreements have been executed with local and Denver-based service organizations to provide ambulance, firefighting, and medical aid services. Augmentation for detailed core physics analysis, thermal-hydraulic analyses, radiation monitoring, dose assessment, and decontamination / radioactive waste disposal will be provided on a contract basis. Headquarters and service agency augmentation and support are described in the following sections. 5.3.1 PSC Headquarters Support Provision for direct augmentation to the staffing of onsite emergency functions by non-station personnel may be quickly accomplished. These personnel may be utilized in support roles to supply additional manpower for repair / damage control teams, survey teams, access control, and logistical assistance. O Additionei headquarters menagement, admiaistrative. and technical support requested by the Corporate Emergency Director will be coordinated by the Executive Command Post Director. The ECP is manned by senior corporate personnel with the authority to activate corporate personnel, facilities, equipment, and financial resources in an emergency situation. The ECP supports PSC personnel stationed at onsite and offsite emergency centers. The ECP is located in Room 620, PSC Headquarters Building, Denver. In the event the ECP cannot utilize this location for any reason, an alternate facility located at the PSC Lookout Center in Golden, Colorado will be activated. The ECP contains up-to-date copies of station, state, and local government emergency plans, the corporate Emergency Plan, maps of the Fort St. Vrain area and its environs, regional maps, and 1 station layout drawings. Other equipment, facilities and services located within, or immediately adjacent and available to the ECP, l include stenographic assistance, reproduction ' equipment, simultaneous commercial television station monitoring equipment (al.1 VHF channels) and radio-television (-Q announcements. recording equipment for media FORM 372 22- 3643 ' ~
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Section 5 PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 27 l .
.V - The ECP will be operational within ninety (90) minutes after classification of an ALERT or higher t level accident. The ECP staff includes a Director i and four functional Managers. The roles and responsibilities of key members of the ECP staff are described in the following sections.
- a. The Director of the ECP - (President & CEO) will assume overall responsiblity for providing the Corporate Emergency Director with the counsel, expertise, and resources available within the PSC organization. He coordinates emergency assistance, provides reentry and recovery support, station and site modifications review by Nuclear Facilities Safety Committee, and supervises the following ECP emergency operations managers.
(Alternate: Executive VP & General Counsel)
- b. The Manager of Technical Support - (Nuclear Design Manager) will provide the Corporate Emergency Director and onsite emergency operations with technical advice in nuclear, mechanical, civil, and electrical engineering.
m He provides engineering support, technical C experts, and consultants as (Alternate: Nuclear Services Manager) requested.
- c. The Manager of Media Relations - (VP of Public Affairs) will coordinate communications between the ECP and the site, the FCP, the State EOC, and federal emergency operations not included in the site communications system. He assists the Director of the ECP and PSC media relations personnel in preparation of press releases, announcements, and interviews. (Alternate: Manager of Public Relations)
- d. The Manaaer of Resources - (VP of Accounting l and Corporate Secretary) will coordinate provision of manpower and equipment from within PSC, and from consultants / contractors, to support onsite emergency operations. He provides requested technical and craft manpower; personnel or consultants for engineering / design and construction reviews; temporary housing, office, transportation, and construction equipment; purchasing, financial, legal, and general office sepport; and, food deliveries and related logistics support to des'9"eted e=erse"cv operet'oas- (^ iter"ete:
-O VP of Finance & Treasurer) ?
FORM 372 22 3643
Section 5 PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 27
.g .U - e. The Manager of Security - (Manager of Claims, Safety, & Security) will coordinate PSC security operations with public law enforcement agencies. He acquires additional security manpower, hardware, and equipment, as requested. (Alternate: Security Coordinator) 5.3.2 Local Services Support In emergency situations, assistance from outside companies and services may be required. Assistance available from outside companies includes ambulance service to transport injured and/or contaminated 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 10, Appendix A. Table 5.3-1 lists these agencies by the type of service provided. The State RERP, to which participating agencies and PSC are signatory, is cited in lieu of letters of agreement for emergency assistance from (s) , other local service agencies. 5.3.3 Contract Support Specialized assistance from contractors may also be required in an emergency situation. Contract support may include nuclear steam supply system (NSSS), architect-engineer, construction, dosimetry and laboratory analysis, and decontamination and rad-waste disposal assistance. Provision has been made for selected contract support firms to provide this assistance, on request. Table 5.3-1 lists these contractors by type of service provided. (Section 10, Appendix A contains Letters of Agreement covering these contracted services). 5.4 Coordination with Participating Government Agencies The State of Colorado, through the Division of Disaster Emergency Services (D0 DES), has responsibility for control of offsite actions during a radiological emergency. 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. Since participating agencies and PSC are Plan signatories, the State RERP is cited in O sect 4aa 1o. ^aae"e4x ^ '" " eo of senerete 'etters or agreement. b FORM 372 22 3643
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Section 5 PUBLIC SERVICE COMPANY OF COLORADO , 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 27 O
- Governmental entities having jurisdiction within the 5 mile plume exposure EPZ are the State of Colorado; Weld County; and, the towns of Platteville, Johnstown, and Gilcrest.
A brief summary of the involvement and responsibilities of the major governmental agencies is shown in tabular form in Table 5.4.1. For a complete discussion of authority, assigned responsibilities, capabilities, and activation and communication arrangements, refer to the State RERP. 5.4.1 Station personnel coordinate onsite emergency operations with state / local government offsite emergency centers (Forward Command Post and State Emergency Operations Center). The role and function of PSC emergency personnel stationed at the FCP and the State EOC are described in the following sections.
- a. The Forward Command Post (FCP) functions as the control and coordination center for on-scene state / local / federal emergency response forces. The FCP communicates with the State EOC (the primary point through which the em Governor exercises overall control and U coordination of offsite emergency operations) and with the Weld County E0C (Weld County Communications Center) for effective coordination of county fcrces.
The FCP is located in the PSC Garage at Ft. I Lupton, approximately 12 miles south-southeast of the Station. Provision is made adjacent to the FCP for a facility to accomodate the needs of the media (State RERP, Annex S). A senior representative of D0 DES is responsible for control and coordination of FCF emergency response activities. Staffing of the FCP, as shown on Figure 5.2-4, consists of authorized representatives of: l
- 1. State Division of Disa' ster Emergency Sarvices
- 2. Weld County Sheriff's Office
- 3. Colorado State Patrol
- 4. Colorado Department of Health O
- " Radiological mon'itoring, and health units, as required.
9 FORM 372 22 3643
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, PUBLIC SERVICE COMPANY OF COLORADO $,Sectin5
[ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 27
\ 'v/ . Public information representative.
l
- 5. Public Service Company of Colorado l Vice President of Production Station Technical Liaison Radiological Assessment Coordinator Public Relations Representative i Nuclear Documents Staff
- 6. Others, as notified / required.
The Vice President of Production is in overall command of PSC emergency operations and is the main 1%k between the station and governmental authoritles. A PSC technical liaison representative (Primary: Technical / Administrative Services Manager; Alternate: Quality Assurance Manager) from the station, the Radiological Assessment Coordinator (Radiation Protection Manager), one public relations representative from PSC corporate headquarters, and members of the station clerical staff are also assigned to p v the FCP. Communications between the FCP, the site Technical Support Center, the State Emergency Operations Center, and the PSC Executive Command Post will be accomplished through commercial telephone service and/or radio. The responsibilities of PSC personnel assigned to the FCP include:
- Providing assistance and substantiated data on site emergency status and conditio.ns;
- Coordinating cowy mergancy response l actions with tfs" ., f 4te/ local / federal 1 agencies; !
- Coordinating radiological assessment activities between PSC' and those of state / local / federal agencies;
- Providing assistance to the FCP Public Information Coordination Team (PICT) in l the preparation of news and related media ;
releases, and control of rumours in I accordance with the PSC RERP Public h Information Plan; and, e
? . FORM 372 22 3643
Secti n 5 PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 of 27 p i " V
- = Maintaining communications flow between PSC personnel stationed at onsite and offsite emergency centers,
- b. The State Emergency Operations Center (State E0C) is the primary point through which the Governor, or his authorized designee, exercises overall control and coordination of emergency response operations through the Colorado Division of Disaster Emergency Services (D0 DES).
The State EOC is 'ocated in D0 DES headquarters at Camp Ge ge West in Golden, Colorado, approximately 40 miles southwest of the Fort St. Vrain Nuclear Generating Station. Provision is made at Camp George West for a facility to accomodate the needs of the media (State RERP, Annex S). Staffing of the State EOC, as shown on Figure 5.2-5, consists of authorized representatives of:
- 1. Office of the Governor J
- 2. Division of Disaster Emergency Services
- 3. Colorado Department of Health
- 4. Colorado State Patrol
- 5. Colorado National Guard
- 6. Federal Emergency Management Agency
- 7. Public Service Company of Colorado
- 8. Others, as notified / required PSC staffing at the State EOC includes the Vice President of Governmental Affairs or the l Manager of Nuclear Engineering, the Manager of l Corporate Communications or Media Relations l Director, technical assistance personnel, a radiation specialist, and supporting clerical personnel.
FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ,ftin5 S FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 27 ~(7 - %) - The responsbilities of PSC personnel assigned to the State E0C include: i
- Providing assistance and substantiated data regarding site emergency status and l conditions to local / state / federal emergency response agencies assigned to the State E0C;
- Coordinating company emergency response activities with those of state / local / federal agencies; and,
- Providing up-to-date site information to the Public Information Coordination Team (PICT) Chief (Governor's Office representative) and assisting the PICT in the preparation of mutually acceptable news releases, fact sheets, rumor control in accordance with the PSC RERP Public Information Plan, and background material media releases.
5.4.2 In addition to extensive coordination with state / local governmental technical () c entities, assistance from certain federal agencies in the area of communications, radiological monitoring and laboratory analysis, transportation, weather forecasts, and disaster relief may be required in an emergency situation. The State of Colorado, through D0 DES, will officially request federal assistance. PSC will, therefore, channel contacts with federal agencies (except NRC) through D0 DES. The following agencies will be notified / requested to provide assistance, as necessary:
- a. The Nuclear Regulatory Commission, Office of Inspection and Enforcement, Region IV, and the NRC Incident Response Center Bethesda, MD.
- b. The Department of Energy (DOE) - Radiological Assistance Teams (RAT), Idaho Falls, Idaho and Rocky Flats, Colorado; Aerial Monitoring System (AMS), Las Vegas, Nevada. DOE will activate the Interagency Radiological Assistance Plan (IRAP) as necessary.
- c. Federal Emergency Management Agency (~JiA),
Region VIII, Denver, Colorado. .O b u FORM 372- 22 3643
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FORT ST. VRAIN NUCLEAR GENERATING STATION page 16 of 27
.,m V i Figure 5.1-2 NORMAL SHIFT ORGANIZATION Fort St. Vrain Nuclear Generating Station l SHIFT SUPERVISOR l l TECHNICAL ADVISOR l l l (SRO) la*l l l (1) l [ (1)* 1 1 I I I -
l l l l I I I I l l l REACTOR OPERATOR l l LEAD SECURITY l ll HP TECHNICIAN la*] (SRO) l l OFFILCR l ll (1) l l (1)**l I (1) l I I I I I I I I I I I l REAC10R OPERATOR l l SECURITY GUARDS l N- l l (RO) l**l l
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[ EQUIPMENT OPERATORS l l l (1) l I I I I I I I I l AUXILIARY TENDERS l l l (1)**l - 1 I NOTES: SRO 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. l ** DURING HOT, COLD, CR REFUELING SHUTDOWN, ONLY ONE RO l IS REQUIRED TO BE CN DUTY. AN INDIVIDUAL WITH AN SRO l LICENSE OTHER THAN THE ON-DUTY SHIFT SUPERVISOR IS NOT O l REQUIRED, NOR IS AN AUXILIARY TENDER. d -------- LINE OF AUTHORITY l ******** COMMUNICATION P FORM 372 22 3643
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Section 5 PUBLIC SERVICE COMPANY - OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 17 of 27 m Figure 5.2-1 EMERGENCY ORGANIZATION (NOTIFICATION OF UNUSUAL EVENT) Fort St. Vrain Nuclear Generating Station l SHIFT SUPERVISOR
- l l TECHNICAL ADVISORI l l (SRO) l**l l l 1,2,3 l l 8 l l l l 1 l l l .........
l l [ l l l HP TECHNICIAN l l REACTOR OPERATOR l l LEAD SECURITY [ ll [**l (SRO) la*l OFFICER l l 4,6 l l l l 6,7 l 1 1 I I I I I I I I I I I I - l EQUIPMENT l l- REACTOR OPERATOR l l l O' ll l OPERATORS 5,6 l l__l l (RO) l**l SECURITY GUARDS l l l l l l l 1 I I I I I I I I l l EMERGENCY COORDINATOR l AUXILIARY TENDERS l ON CALL 24 HOURS A DAY, ONE HOUR l 5,6 l MAXIMUM RESPONSE TIME l _l 1 PLANT OPERATIONS AND CONTROL 2 0FFSITE NOTIFICATION 3 PLANT CONDITION ASSESSMENT 4 HEALTH PHYSICS & RADIOLOGICAL ASSESSMENT
- 5 REPAIR AND DAMAGE CONTROL 6 HAZARDS CONTROL 7 PERSONNEL ACCOUNTABILITY 8 TECHNICAL ASSISTANCE l .
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3 PUZLIC SERVICE COMPANY OF COLORADO ,[ction5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 24 of 27
; "' TABLE 5.3-1 LOCAL AGENCY AND CONTRACT SUPPORT SERVICES l
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 Facility Support Support Service Weld County Alternate Personnel Control Greeley, Colorado Cente; - Johnstown, Colorado n Contract Agency Support Service V, General Atomic Corporation NSSS, Reactor Physics, and San Diego, California Systems Modification Assistance l Other Support Agency Support Service Stone & Webster Engineering Corp. Engineering / Construction / Denver, Colorado System Modification Assistance Nuclear Power Consultants, Inc. Engineering / Quality Assurance Rockville, Maryland Assistance Proto-Power Management Corp. Technical Assistance - Groton, Connecticut Nuclear / Balance of Plant Systems
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.o TABLE 5.3-1(Continued) LOCAL AGENCY AND CONTRACT SUPPORT SERVICES Fort St. Vrain Nuclear Generating Station l Other Support Agency Support Service NUS Corporation Safety-Training Assistance Portland, Oregon Controls For Environmental Chemical-Radiochemical Pollution, Inc. Laboratory Analysis Santa Fe, New Mexico Colorado State University Environmental Monitoring Fort Collins, Colorado Assistance St. Luke's Hospital Medical Treatment /Decon-Denver, Colorado tamination Assistance - Dr. Hild.ng G. Olson Nuclear Engineering-O Fort Collins, Colorado Consultant Donald T. Klodt Metallurgical Consultant Denver, Colorado l R. 3. Landauer, Jr. & Co. Environmental Monitoring, 1 Glenwood, Illinois Dosimetry Processing l Western Radiation Consultants, Inc. Radiation Protection l Fort Collins, Colorado l EBASCO Services, Inc. Engineering, Construction, l Golden, Colorado Procurement Assistance l INPO Procurement, Industry l Atlanta, Georgia Support l l O FORM 372 22 3643
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Section 5 PUZLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 26 of 27 p
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TABLE 5.4-1
SUMMARY
OF STATE / LOCAL INVOLVEMENT AGENCY PRINCIPAL RESPONSIBLITIES LOCATION State of Colorado:
- 1) Division of a) emergency planning State EOC (Camp Disaster Emergency b) command & control George West, Services (DDDES) c) communications Golden, CD) &
d) coordination of Colorado FCP (Ft. Lupton, CD) National Guard & federal assistance
- 2) Colorado Department a) incident dose assessment FCP, CDH HQ of Health (CDH) b) recommendation of (Denver), State EOC, & deployed
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protective actions
.O c) co"ta='" t'oa coatroi' persoa"e' decontamination measures
- 3) Colorado Department ingestion pathway State EOC, FCP, of Agriculture (CDA) protective actions CDAHQ(Denver)
- 4) Colorado State a) traffic control State EOC, FCP, & '
Patrol (CSP) b) communication and deployed personnel transportation assistance
- 5) Office of the a) issue proclamations State EOC and l Governor for emergency Governor's office !
preparedness (Denver) b) utilize the National Guard c) issue evacuation orders d) handle media relations
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>ORM 372 22 3643
P Section 5 PUBLIC SERVICE COMPANY OF COLORADO u9
- FORT ST. VRAIN NUCLEAR GENERATING STATION Page 27 of 27 .- p)
TABLE 5.4-1 (Continued)
SUMMARY
OF STATE / LOCAL INVOLVEMENT AGENCY PRINCIPAL RESPONSIBLITIES LOCATION Weld County:
- 6) Weld County authorize and ensure County Bldg Commissioners appropriate county (Greeley,CO) emergency planning and response
- 7) Weld County a) handle county EOC & County Bldg Civil Defense communications (County E0C, b) coordinate local Greeley,CD) agency planning s c) handle emergency feeding fj and sheltering
- 8) Weld County a) traffic control FCP and Sheriff b) public notification deployed personnel c) conduct and confirm evacuation d) maintain law and order l
PORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO Secti n 6
- FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 30 FORT ST. VRAIN: ~
TITLE: RADIOLOGICAL EMERGENCY RESPONSE PLAN, SECTION 6 NON - CONTROLLED COPY VENFYISSUE , STATUS WITH , l DOCUMENTCENTER ISSUANCE PRIOR 70 USE AUTHORIZED p/ FORM 372 22-3567 , BY AA J -/.r-N PORC REVIEW [ g g g g g } 4 jgg4 EFFECTIVE DATE $~ M
- bN 6.0 Emergency Measures Station emergency measures will be initiated upon, and according to, incident classification. This section identifies segments of the station emergency 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 radioactivo material.
6.1 Activation of Emergency Organization
' The four classes of emergency defined in Section 4.1 require a varying degree and scope of emergency responses.
The emergency organization activated in each emergency classification is shown in Figures 5.2-1 and 5.2-2. The Shift Supervisor will immediately initiate action to limit the consequences of the event and to return the plant to a safe and stable conditicn. The emergency organization for a NOTIFICATION OF UNUSUAL EVENT consists of normal shift personnel (Figure 5.2-1). No augmentation is required. For ALERT events, onsite and offsite emergency centers will be manned and activated in situations where the Emergency Coordinator or Corporate Emergency Director deem it necessary. In SITE AREA EMERGENCY or GENERAL EMERGENCY level accidents, onsite and offsite emergency response facilities will, in 'all cases, be manned and activated. The Plant Emergency Alarms are sounded for ALERT and higher level accident classifications. The location and extent of the event is announced over the station Gai-tronics system or public adcress system. If the emergency occurs during a back shift period, the Shift Supervisor in the role of Emergency Coordinator, establishes the plant emergency organization per Section 5.2. l Upon incident assessment and classification of an UNUSUAL l EVENT, notification will be n:ade to the State (State EOC and Governor's Office) and to the Nuclear Regulatory '.]U l l Commission. Updates are made to keep these agencies FORM 372 22 3442 e 9 4 4 Jg. < - we . <e y t v o .p
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, PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION page 2 of 30
. q U ; l informed of event status, although activation of offsite l response centers is not expected unless the event l escalates to an ALERT or more severe category. The l initial emergency message for NOTIFICATION OF UNUSUAL l EVENT (Figure 6.1-2) is based upon an agreement between l the Governor of Colorado and PSC.
l Classification of an incident as an ALERT or higher event l requires notification consisting of three telephone contacts as indicated in Figure 6.1-1. The Nuclear Regulatory Commission (Region IV) is notified via " hot l line" (preferably) or commercial telephone service. The state and local emergency response organization is notified by a telephone call to the Weld County l Communications Center after notification is authenticated l by call-back. The PSC emergency organization is notified by a single call to the Public Service Company Operator at l corporate headquarters, who notifies the appropriate fanout list set forth in emergency plan notification procedures. The initial emergency message for ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY classes, together with followup messages for these accident levels are contained in Figures 6.1-3 and 6.1-4. Emergency center functions remain constant for ALERT, SITE (q/ AREA EMERGENCY, and GENERAL EMERGENCY classifications. Personnel / equipment augmentation may vary according to specific circumstances. The functions, as shown on Figure 5.2-2 include: Technical Support Center Command (Onsite) Plant Condition Assessment Recommendation of Corrective Actions Radiological Consequence (Dose Projections) Health' Physics Assessment Notification / Communications Onsite Protective Action Offsite Communications a nv s FORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO Secti n 6 FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 30
.g G ~. Control Room Assessment of Plant Operating Conditions Implementing Corrective Actions Fire Fighting Direction Personnel Accountability (Initial) personnel Control Center Personnel Accountability (Continued)
Emergency Repair / Damage Control Onsite/Inplant Surveys Radiation Protection (Personnel Monitoring / Dosimetry / Decontamination /Acc.ess/ Reentry Control) Search and Rescue /First Aid p Fire Brigade G Security Forward Command Post (PSC functions only) Command (PSC Overall) Government Notification / Communications Radiological Assessment Coordination
- Logistics Support l Media Relations ,
6.2 Assessment Actions The assessment of plant conditions, radiation levels, and offsite consequences is initially coordinated by the Shift Supervisor (Emergency Coordinator). Upon relief of the l Shift Supervisor by the Control Room Director (Primary: l Superintendent of Operations; Alternate: Shift Supervisor, l Training) and activation of the Technical Support Center (TSC) and the Personnel Control Center (PCC), these duties O~ wiii be ea er the e erse#cv orsamiz tioa described in
. Section 5.0. The different types of assessment actions FORM 372 22 3643 j
, PUZLIC SERVICE COMPANY OF COLORADO ,,jetin6 3
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 30 I are described in Table 6.2-1. Assessment will continue throughout the emergency period. Continued assessment may result in reclassification of the incident and consequent alteration in emergency response actions. Incidents involving potential or actual release of radioactive materials to the environment (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) require special methods of assessment to ensure that responses are appropriate for protection of the population-at-risk and station personnel. The Fort St. Vrain Nuclear Generating Station has installed capability for measuring radioactive Iodine concentration in the coolant. Post-accident sampling is described in appropriate Health Physics and Radiochemistry procedures. It also has an extensive system for monitoring radioactive materials released to the environment (e.g., gaseous, process liquid, reactor building ventilation exhaust, and steam jet air ejector vent). 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 G accident conditions. In any accident where releases are b not monitorable, emergency procedures provide " theoretical worst-case release rates corresponding to the Design Base Accidents outlined in Section 14 of the Fort St. Vrain Nuclear Generating Station FSAR." 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 Room. Additional readout capability is provided in the TSC via plant computer links. In the event that meteorological information in both 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 onsite to the North of . the plant. Guidance for the acquisition of meteorological l data from existing instrumentation and displays, as well as backup data from NOAA tower instrumentation, is provided in RERP implementing procedure RERP-MET, Meteorological Data Acquisition. The methodology and technique used to predict offsite concentrations of radioactive n:Lle gases and iodine is summarized as follows: O P PORM 372 22 3643 __ _--..v.. ~ .- ,-
Section 6 PUBLIC SERVICE COMPANY OF COLORADO , { FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 30
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Upon determination that an emergency, or potential emergency, could result in offsite dose consequences, the Radiation Protection Manager, or his designee in accordance with RERP implementing' procedure RERP-DOSE, "Offsite Dose Calculations"... l
- Notes present weather conditions (wind speed and direction, atmospheric stability, cloud cover, and precipitation) and calls the Stapleton Airport National Weather Service to obtain a forecast for the next 12 hours to anticipate changes in weather conditions that might affect dispersion and alter the zones affected.
- Determines radioactivity release rates by reading the Reactor Building Ventilation Exhaust Stack Monitors. If the monitors are inoperative, or if an anticipated release has not started, an estimate of the release rate is obtained from prepared tables. The basis for these tables is the actual circulating coolant activity and/or 10CFR100 accident siting criteria.
- Selects an atmospheric dispersion graph n (corresponding to the downwind distance (s) of V interest and the atmospheric stability class) and identifies the dispersion factor for the zone (s) of interest. The graphs consist of plots of dispersion factors (X/Q values) calculated from standard Gaussian plume equations for ground level sources as shown in Meteorology and Atomic Energy l (Reference 1) and based upon USNRC Regulatory Guide l 1.145 (Reference 2).
- Multiplies the iodine release rate by the dispersion factor to obtain an air concentration of radiciodines. He uses the expected plume duration in the zone (s) of interest as the exposure time and calculates the thyroid dose by multiplying the appropriate thyroid dose conversion factor for that post-shutdown time by the air concentration and then by the exposure time. He calculates doses by zone and compares the integrated doses to l Protective Action Guide (Reference 3) Criteria presented in Table 6.2-2.
i '9 FORM 372 22 3643
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. PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION f"
Page 6 of 30
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= Multiplies the noble gas release rate by the dispersion factor to obtain an air concentration of noble gases. He uses the expected plume duration in the zone (s) of interest as the exposure time and calculates whole body gamma dose by multiplying the appropriate whole body gamma dose conversion factor for that post-shutdown time by the air concentration and then by the exposure time. He calculates doses by zone and compares the integrated doses to Protective Action Guide Criteria presented in Table 6.2-2.
Air concentration levels are verified by field monitoring teams consisting of an HP technician and an assistant deployed in captive vehicles with portable emergency radiological instrumentation including air samplers with silver zeolite cartridges, radiation survey meters, and portable radios on the PSC frequency. These teams are deployed within 30 minutes of activation of the emergency organization, and have the capability to sample
~
radioiodine concentrations as low as 1 x 10 'pCi/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 RERP implementing procedure RERP-FIELD, Field Monitoring Procedure).
Unmonitored releases will be treated as unfiltered releases for the duration of the time that they went un-monitored, and will be assessed by utilization of data provided by the on-line noble gas monitor for circulating activity and reactor pressure instrumentation. These actions are described in detail in RERP implementing procedure RERP-DOSE, Offsite Dose Calculation. 6.3 Corrective Acti.ons l Station procedures contain steps for preventive and/or I corrective actions to avoid or mitigate serious j consequences of an incident. Instrumentation and control l system monitors provide indications / recordings and automatically control systems necessary for the safe and orderly operation of the station. These systems provide the operator with the information and controls needed to
- l start up, operate at power, shut down, and, if necessary, to cope with an abnormal operating condition or emergency, I should it occur. Control and display of information from these systems are centralized in the Control Room. The information provided by this instrumentation forms the l
,v p basis for declaration of emergency classes.
II le PoRM 372 22 3643 ee-- n - we =
Secti n 6
- PUZLIC SERVICE COMPANY OF COLORADO ,
6 FORT ST. VRAIN NUCLEAR GENERATING STATION page 7 of 30 .r~', b I Corrective actions will also involve response by the following onsite organizations:
- Fire Fighting Fire Brigades will respond to station fire calls.
If outside assistance is required, a call will be placed to the Platteville Volunteer Fire Department (VFD). The Platteville VFD will, upon arrival, be escorted to the firescene 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 requir d to assist in damage control, cleanup, and repair operations. Recovery from a GENERAL EMERGENCY will be handled with the assistance of agencies available for that purpose and the cooperative effcrt of industrial organizations such as AIF, EPRI, and EEI. The organization for post-emergency recovery is described-in Section 9.0. gs _. L -) 6.4 Protective Actions Protective actions will be taken to ensure that personnel, l onsite and offsite, are notified and actions initiated for their protection in the event radiation or airborne activity levels exceed predetermined values, or when other situations threaten personnel safety. Onsite actions to protect station personnel and visitors 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, Evacuation, and Personnel Accountability
- a. Onsite Protective actions for onsite personnel will be taken whenever a radiological emergency has occurred, or may occur, which will result in concentrations of airborne activity or radiation levels in excess of normal limits for a specified area or areas, that cannot be n
t/ s readily controlled. In addition, protective actions will be taken for onsite personnel in other emergency situations such as fires, P PORM 372 22 36C3
PUBLIC SERVICE COMPANY OF COLORADO [PSection6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 30 1 l V
- floods, and tornadoes where personnel safety is threatened. Notification of onsite I personnel will be by actuation of plant alarm systems, telephone calls, and Gai-tronics announcements as applicable. Notification i will be accomplished as soon as assessment l actions permit a determination of the 1 emergency class and corresponding actions.
Personnel will be notified of appropriate actions to be taken at their respective personnel accountability stations.
- 1. Personnel Accountability l FSV Visitors Center personnel will be notified within 15 minutes and advised of appropriate protective actions. Site visitors inside the owner-controlled area will be escorted by station personnel to the Security Building where they will be monitored for contamination and normally depart the site. Their escorts will then report to their predesignated personnel accountability stations. Contract personnel will exit via the security I building, where they will be monitored for contamination, and report to the Visitor's Center to await further instruction. Non-essential station personnel (i.e., personnel not specifically assigned to predesignated emergency functions) are required to I assemble at pre-assigned personnel l accountability stations where supervisors, or their designees will make accountability checks. Accountability status is reported to the Central Alarm Station (Security Desk in Lobby) which in turn reports to the Shift Supervisor.
l Initial accountability should be 1 completed within 30 minutes. Subsequently, the PCC Director has responsibility for maintaining personnel accountability. Refer to the Administrative Procedures Manual procedure G-5, " Personnel Emergency Response" for specific details of the personnel accountability process. e FORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO $,$ 6 ~ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 30
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, '~' 2. Security and Access Control The security program at the Fort St.
Vrain Nuclear Generating Station is designed to meet the access control requirements of 10 CFR 73.55. Support personnel reporting to the station during l an emergency may assemble first at the l Personnel Control Center, if the Center ' l is activated. The entry of required i l personnel will be coordinated through l normal security routine, either by the l PCC Director or the Shift Supervisor. Provisions to restrict access to areas of the site outside the fenced protected area have been made. The PCC Director will assign designated security personnel to control traffic access to the owner-contrelied area. Access control will be performed with the aid and cooperation of the Weld County Sheriff's Department.
- 3. Evacuation Od The PCC Director will assure survey of the designated PCC to determine habitability, establish a controlled area at the appropriate PCC location (either l the Training Center or the Engineering /QA l complex, dependening upon prevailing wind direction), and prepare to receive personnel, should plant evacuation be required.
In the event that radiation levels are greater than, or equal to, 2.5 mrem /hr outside the Reactor Building, or there is unidentified airborne contamination greater than, or equal to, 9 x 10 ' pCi/cc above backround outside of the Reactor Building (i.e., in the Turbine Building), or if conditions are such that the TSC Director deems it circumspect, such as during a SITE AREA or GENERAL EMERGENCY, non-essential personnel will be evacuated from the plant. If a plant evacuation was deemed l appropriate, there are two Personnel bs) Control Centers within the Owner Protected Area to evacuate to. These FORM 372 22 3643 __ = ,
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION (e Section 6 Page 10 of 30
.q L; , l PCCs are the Training Center and the l QA/ Engineering Complex Complete Emergency Kits, including radiological monitoring equipment and field radios are l stored at the Training Center and at the QA/ Engineering Complex.
The selection of a PCC is largely dependent upon the prevailing wind l condition and the accessibility of that i location. Personnel will be monitored for contamination, and accountability checks will be made by PCC staff as appropriate. Personnel onsite, but outside of the protected (fenced) area, will be notified of the emergency and directed to buildings in areas unaffected by the event. Should evacuation of the site become necessary, privately owned vehicles will be used. Tenants on PSC l property are notified by _ telephone or l personal contact of actions considered necessary to their protection (PCC procedure emergency call list).
~
O i In the event that the two onsite Personnel Control Center assembly areas l are uninhabitable (i.e., radiation levels are greater than, or equal to 2.5 mrem /hr, or there is unidentified airborne activity greater than, or equal
~
to, 9 x 10 ' pCi/cc above background), non-essential personnel will be directed to evacuate to one of three designated offsite PCC locations. The preferred offsite PCC area is the Johnstown County Shops. The alternate offsite PCCs are the PSC Longment Service Center and the Platteville Firehouse. The PCC Director is responsible for the transport of emergency equipment, including decontamination supplies, necessary to l establish the offsite PCC. Personnel in l the protected area will exit the security building where they will be monitored for l contamination and carded out of the plant.
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FORM 372 22 3643 I __ _ . . _ . _~
l PUBLIC SERVICE COMPANY OF COLORADO Secti n 6 FORT ST. VRAIN NUCLEAR GENERATING STATION page 11 of 30
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- 4. Rescue Operations The search and rescue function is handled by trained Fire Brigade or Health Physics personnel. When station personnel are unaccounted for in the initial or subsequent emergency accountability, the Shift Supervisor assigns a search and rescue team to locate and, if necessary, rescue. personnel, observing the emergency exposure limits outlined in Table 6.5-1.
- b. Offsite The Emergency Coordinator will recommend appropriate initial protective actions to offsite authorities, to include either evacuation or sheltering, as alternatives, based upon consideration of relative benefits of the alternatives. The action which affords the greatest amount of dose avoidance for accidents (where projected or measured offsite doses are expected.to exceed Protective Action Guides -
Table 6.2-2) will generally be preferred. However other factors such as pd release duration, mobilization time relative to plume arrival time, or adverse weather may be important considerations affecting the decision. 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 USEPA l Protective Action Guides (Reference 3) 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. Estimated sector evacuation times are shown in Appendix C, Figure 10.C-2. These evacuation times were formally published in detail in PSC report
" Evaluation Time Study of the 10-Mile Radius Area About the Fort St. Vrain Nuclear Generating Statica," as transmitted to the U.S. Nucle.* Regulatory Commission April 1, 1981 (P-81110). These estimates have
- been modified in RERP implementing procedure
! RERP-PAG, Protective Action Guideline l Recommendations, to account for use of the O toae 1ert e rix wara4as ^1ert (ew^) sxstem. FORM 372 a 22 3643 1
Section 6 PUBLIC SERVICE COMPANY CF COLORADD ,
.; FORT ST. VRAIN NUCLEAR GENERATING STATION page 12 of 30 U ~
Approximate initiation times for these protective actions are shown in Table 6.4-1. The means of public notification is the use of tone alert NOAA weather radios distributed to residents living within the plume exposure EPZ (5 mile radius). A brief prepared message is broadcast over the radio issuing general instructions regarding protective actions and informing the public to tune to a local Emergency Broadcast System (EBS) radio station for further information. Additional coverage is provided, if required, by personal notification by Weld County Sheriff's l Department personnel (with possible l augmentation by the Platteville Volunteer Fire l Department). Notification times are stated to approximate 15 minutes. Content of messages for the public and the decision to implement notification means is a State of Colorado responsibility (State RERP, Annex C). PSC emergency procedures provide for prompt notification of state, local, and federal agencies and keeping these agencies updated on C the overall status of the emergency. PSC will coordinate onsite actions with local, state, and federal agencies involved in offsite emergency response actions. Notification of offsite businessmen, property owners and tenants, school administrators, recreation facility operators, and the general public within the emergency planning zone will be accomplished by local tor.e alert radio or emergency forces, as noted in the State RERP. 6.4.2 Use of Onsite Protective Equipment and Supplies ; 1 A variety of protective equipment is available l onsite to minimize radiological exposures, I contamination problems, and fire fighting hazards. l The types of equipment, their criteria for I issuance, location, and means of distribution are noted in Table 6.4-2. Radiothyroid protective drugs in sufficient quantity to administer to 100 employees is stockpiled at FSV. Criteria for issuance and location is noted in Table 6.4-2. l l
. U) l FORM 372 22 3643 i
P Section 6
. PUBLIC SERVICE COMPANY OF COLORADO
{ FORT ST. VRAIN NUCLGAR GENERATING STATION Page 13 of 30 .s l N. I 6.4.3 Contamination Control Measures
- a. Plant Site Measures will be taken to prevent, or minimize, direct or subsequent ingestion of ;
radioactive materials deposited within the exclusion area. As necessary, affected areas will be isolated.. Details of contamination control measures for onsitr/ areas are contained in station procedures. The following is an outline of those procedural controls:
- 1. Radioactive Contamination of Personnel
- Controls have been established to insure that levels of removable contamination outside radiologically controlled areas will be maintained at less than allowable limits of 10dpm/100cm 2 alpha activity and 2
100dpm/100cm beta gamma activity. The environment of personnel working-('/ S s- within radiological control areas are supervised by Health Physics personnel. Radiation Work Permits (RWPs) may be required for personnel in such areas. Specific instructions, precautions, and limitations are listed on RWPs. Protective clothing is required for individuals entering contaminated areas. Individuals leaving radiological control areas are monitored for contamination upon departure.
- Quarterly integrated accumulations of radionuclides in the body will not exceed accumulation levels which would result from exposure to the maximum permissible 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 7- offsite sources.
(/ FORM 372 22 M4 1
PUZLIC SERVICE COMPANY OF COLORADO u6
, l FORT ST, VRAIN NUCLEAR GENERATING STATION Page 14 of 30 l
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- Exposure to airborne concentrations higher than the MPC will be prevented or avoided. If exposures are necessary, wearing appropriate, properly fitted respiratory protective equipment will be .
required, as determined by Health I Physics. Periodic air samples will be taken in selected operational and work areas to ensure that MPC levels are not exceeded.
- 2. Radioactive Contamination of Equipment
- 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.
- Equipment and tools will be o unconditionally released for use V outside the area only if removable contamination and radiation levels are less than allowable limits previously stated.
- Removal of material from radiological control areas with radiation and contamination levels in excess of specified limits must be approved for release by Health Physics personnel. Any contaminated material approved for release will be packaged, sealed, and labeled with a properly executed radioactive n.aterial tag and handled in accordance with approved procedures.
- b. Offsite For areas beyond the site boundary, Colorado l Department of Health (CDH) radiation
- monitoring teams will identify levels and l l control access. Until CDH teams arrive for l dispatch, Public Service Company EPZ teams may l be dispatched from the PCC to perform offsite l monitoring. For areas where public access
! hs normally occurs, criteria for offsite areas
. will be applied. Criteria and measures for FORM 372 - 22 3643 M""_~:__'^**~"Y ~'
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. . PUBLIC SERVICE COMPANY OF COLORADO ,jetion6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 30 O
, contamination control in offsite areas are detailed in the State RERP.
6.5 Aid to Affected Personnel 6.5.1 Emergency Personnel Exposure Criteria Exposure records are maintained for station personnel at each emergency center. This information will be utilized in determining emergency team assignments. Criteria used for limiting doses to emergency workers are based on l recommendations of the USEPA (Reference 3) and are shown in Table 6.5-1. Emergency workers will carry self-reading dosimeters in addition to film badges. Emergency dosimetry services will be provided , through contract with R.S. Landauer Corporation. { Emergency dosimetry service response is provided on I a 24-hour basis. Every effort will be made to minimize emergency worker doses through.the use of protective equipment and supplies. The PCC ! Director is responsible for emergency team assignments and may authorize emergency workers to o receive doses in excess of 10CFR20 limits. This V authorization to exceed occupational exposure I limits shall be performed in accordance with existing RERP implementing procedures (see RERP-EXP), and shall be given only after consultation with the senior Health Physics representative at the TSC, and under direction of the TSC Director. The PCC Director will be notified of accidental or emergency exposure in excess of occupational limits. Those individuals i l 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 (per USEPA recc mendation). The PCC 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. At the TSC, l the TSC Director is responsible for the issuance of l dosimeters as needed, and ensuring the ongoing accountability of each worker's dose. 6.5.2 Decontamination and First Aid Provisions have been made to assist personnel who O are injured, or who may have radiation doses. received There are personnel onsite who high FORM 372 22 3643
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Section 6 PUZLIC SERVICE COMPANY OF COLORADO ~ FORT ST, VRAIN NUCLEAR GENERATING STATION page 16 of 30 .g
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V are trained in first aid and decontamination procedures. In addition, onsite decontamination areas are equipped with decontamination facilities and other specialized equipment. Personnel found to be contaminated (any detectable activity above background) will undergo decontamination under the control of Health Physics procedures. Where l contamination of large or open wounds is involved, personnel will be immediately transported to designated medical facilities offsite where they will receive prompt medical attention in accordance withthe FSV Medical Emergency Plan. Each emergency team will include members trained in first aid. First aid kits are available at onsite locations in accordance with PSC policy specified in General Instructions, as well as in the onsite first aid facility. 6.5.3 Medical Transportation Injured / contaminated personnel who require medical attention will be transported to St. Luke's Hospital by the St. Anthony's Hospital Flight for p l Life, or by Weld County Ambulance Service. A (j personal vehicle may be utilized if the situation necessitates. Ambulance crews have been trained to handle contamination cases. PSC Health Physics personnel will accompa y contaminated patients to the hospital. 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. Hospital staff at St. Luke's are trained to treat contaminated patients (Section 10, Appendix A). Following decontamination, personnel suspected to have ingested radionuclides will undergo whole body counting at PSC or CDH facilities. Communications l between FSV and fixed medical facilities are via commercial telephone and are handled in accordance with the FSV Medical Emergency Plan. FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO Secti n 6
'h FORT ST. VRAIN NUCLEAR GENERATING STATION Page 17 of 30 U ; REFERENCES l
(1) Slade, D.H., ed., Meteorology and Atomic Energy - 1968, USAEC, July 1968. (2) USNRC, Regulatory Guide 1.145, Atmospheric Dispersion Models For Potential Accident Consequence Assess,ments at l Nuclear Power Plants, Revision 1, November 1982. (3) USEPA, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, June, 1980. (4) USEPA, Appendix D to the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, Technical Bases for Dose Projection Methods, January 1979. I l FORM 372 22 - 3643
i.-..,, . h O O O . l lr u k N t FIGURE 6.1-1 h i NOTIFICATION FANOUT .,, C l FORT ST. VRAIN NUCLEAR GENERATING STATION OO CONTROL aE ROOM 's s i ao Z m E I NRC PSCO , Ao REGION OPERATOR E EE WELD
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,lction6 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 19 of 30 .O Figure 6.1-2 INITIAL MESSAGE CONTENT (NOTIFICATION OF UNUSUAL EVENT)
Fort St. Vrain Nuclear Generating Station l A. The Emergency Coordinator and first management contact will l complete the following information jointly: l 1. Name and identity of caller l 2. Date of Event Time of Event l 3. General Category of Event l Unplanned Radiological Release to Reactor Building l Fuel Failure l Fire l Natural Phenomenon (circle one) l Earthquake Flood Tornado Winds 1 Unusual H4zards (circle one) l Aircraft Explosion Toxic Material l Other (Specify) l Spent Fuel Incident l 4. Description of Event l l 5. Actions Taken l l l l
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Section 6 PUBLIC SERVICE COMPANY OF COLORADO 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 20 of 30 (
- l 6. Status
l Under control by onsite staff, no offsite l assistance anticipated. l Under control by onsite staff. Will keep State and l NRC advised. l Offsite assistance may be required. Will advise. l (See Item 7.) l Offsite assistance required. (See Item 7.) l 7. If offsite assistance is anticipated or required, describe l assistance that has been or may be required: l l l l l 8. At the present time, the event does not involve offsite O l l release or the potential for offsite releases that would affect the general health and safety of the public. l B. The Emergency Coordinator will make notifications as follows: l l l Contact with State EOC (279-8855) and Governor's Office (866-2471)l ll or Mansion (837-8350) l ll l l 1. READ the following statement verbatim: l "THIS IS A NOTIFICATION OF AN UNUSUAL EVENT AT THE l FORT ST. VRAIN NUCLEAR GENERATING STATION. THIS l NOTIFICATION DOES NOT REQUIRE ACTIVATION OF l EMERGENCY RESPONSE CENTERS. THIS NOTIFICATION l REQUIRES VERIFICATION OF RECEIPT BY THE STATE. l VERIFY BY CALLING 571-7436 or 785-2223." l 2. READ all the information recorded in Step A (Page 1 of l this ATTACHMENT).
- FORM 372 3643
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Section 6 PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 21 of 30 V
; I 3. RECORD the following information:
l Name of State E0C contact Date/ Time l Name of Governor's Office / Mansion Contact l Date/ Time l Call back verification from State EOC, Date/ Time l Call back verification from Governor's Office / Mansion i Date/ Time I I I I I l l Contact with NRC Operations Center (Hot Line or 202-951-0550) l 1 l l l (Alternate means of notification are given in Attachment 1.) l 1. READ the following statement verbatim: O i l
TNIS IS NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION AT l PLATTEVILLJ, COLORADO. THIS NOTIFICATION APPEARS l TO BE REQUIRED PURSUANT TO 10CFR50.72, PARAGRAPH l (a)(3). THIS NOTIFICATION DOES NOT REQUIRE l ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE l ORGANIZATIONS." i l 2. READ the NRC Operations Center all of the information l recorded in Step A (Page 1 of this Attachement).
l 3. RECORD the following information: l Name of NRC Contact Date/ Time i l V l? F OR M 372 - 22 3643
.. _ ,_ _ ._ . .. . y _ _ . , .
RERP S:cticn 6 PUILIC SERVICE COMPANY OF COLORADO Issue 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 22 of 30 l Q-FIGURE 6.1-3 l NOTIFICATION OF EMERGENCY EVENT l (INITIAL MESSAGE CONTENT) l Fort St. Vrain Nuclear Generating Station l l l A. The Emergency Coordinator will complete Pages 1 and 2 of this l l attachment with the assistance of the first management l contact. : l 1. This is (Name) , Shift Supervisor at the Fort St. l Vrain Station. l 2. At (Time) we experienced an (ALERT, SITE AREA l EMERGENCY, GENERAL EMERGENCY) Class incident. l 3. a) There is NO, repeat NO, radioactive release taking l place, and no special protective actions are - I recommended at this time. I E l b) A small release M taking place, but at this t'i.me l @ protective actions are recommended and are not l anticipated to be. I @ l c) A radioactive release M, repeat M, taking place, l and we recommend that people in areas l remain indoors with l windows and doors closed. l M l d) A radioactive release M , repeat M , taking place, l and we recommend that evacuation of areas l be considered. l 4. Further information on incident conditions will be l provided in followup messages. l 5. Personnel Control Center to be located i O l 0Q m-M- M ,,
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RERP Section 6 l . s PUZLIC SERVICE COMPANY OF COLORADO Issue 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 23 of 30 4 FIGURE 6.1-4 l - l NOTIFICATION OF EMERGENCY EVENT Fort St. Vrain Nuclear Generating Station l I I i l l SUPPLEMENTAL INFORMATION l l l l l NOTE: This information is to be supplied to the NRC and the Colorado l Department of Health when requested. The radiological . I data can be determined as specified in RERP-DOSE. l 1. Date and Time of Incident l 2. Class of emergency (ALERT)(SITE AREA EMERGENCY) l (GENERAL EMERGENCY) 1 l 3. Type of release (airborne, waterborne, surface) l 4. Estimated duration of release (Hours) O l S. . Current release rate: _. l Noble Gas C1/sec; Iodine Ci/sec l 6. Estimated curies released: l Noble Gas Ci; Iodine C1 l 7. Wind Velocity MPH, from degrees. I to degrees, Air Temp 'F l 8. Stability Category . Form of Precip. l 9. Oose rate at EAB: WB rem /hr; Thyroid rem /hr l 2 Miles: WB rem /hr; Thyroid rem /hr l 5 Miles: WB rem /hr; Thyroid rem /hr l 10. Projected dose at EAB: WB rem; Thyroid rem
- l 2 Miles
- WB rem; Thyroid rem l l 5 Miles: WB rem; Thyroid rem i
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$e Page 24 of 30 g3 l ) i 12. Areas expected to be impacted by release i
I l 13. Estimate of an surface radioactive contamination l l 14. On-site response actions under way l l 15. Recommended Protective Action based on the projected dose at the l EAB (Read appropriate Protective Actions) l Projected Dose Recommended , l (rem) Protective Action ' l Whole Body <1 No planned protective actions. State l Thyroid <5 may issue advisory to seek shelter l and await instructions. Monitor l radiation levels. l Whole Body 1 to 5 Take shelter and consider selective ("/3 l Thyroid 5 to 25 evacuation. Monitor radiation l levels. Establish Controlled Area l and limit access. l Whole Body 5 and Conduct mandatory evacuation. l above Monitor radiation levels and adjust l Thyroid 25 and area for mandatory evacuation based l above on these levels Control Access. l 16. Prognosis for worsening of event l 17. Date and time of report FORM 372 22 3643
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lasue 7 Page 28 of 30 TABLE 6.4-1 initiation Times for Protective Actions for the General Public Approximate Initiation Time Exposure Pat v Action to be initiated 0 - 4 Hours inhalation of gases or Evacuation, shelter, access control, resp i ra to ry ! particulates protection, prophylaxis ( thyroid protection). Di rect radiation Evacuation, shelter, access control . ; I $} 1 4 - 48 Ilours Milk Take cows orr pasture, prevent cows f rom drinking surface water, quarantine contaminated milk, utilize stored feeds. l
! tia rvested fruits Wash all produce, or impound produce.
]y and vegetables Drinking water Cut orr contaminated supplies, substitute f rom other sources. Unha rvested produce Delay ha rvest until approved. l I t 2 - 14 Days lia rvested produce Substitute uncontaminated produce. { l Milk Discard or divert to stored products, such as cheese. l l Drinking water filter, demineralize, test. k I i 4 i t 6 i- ,
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's TABLE 6.5-1 Exposure Criteria for Emergency Workers' j Situation Whole Body Thy ro l d**
- 1. rmergency duties not related
- 5 Rem 25 Ree 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 control fires.
l 3. Lifesaving missions, e.g., sea rch 75 Rem Unlimited **** and rescue or injured people, j prevent conditions that would injure ' j numbers or people.
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- Admini stered in accordance with RERP Implementing procedure RERP-EXP, " Emergency Exposure Guidelines". I
** Respiratory protection will be provided as necessa ry.
*** Includes performing accident assessment, providing first aid, performing personnel decontamination,
,; previding ambulance service, and providing medical treatment services. ; 4 I ene* Although respirators and potassium Iodide blocks should be used where errective to control dose to emergency team workers, thyroid dose may not be a limiting factor for a lifesaving mission. I ! I i 4 !i ,i 1 - i *
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- PUBLIC SERVICE COMPANY OF COLORADO 'lERP Section 7
, Issue 6-FORT ST. VRAIN NUCLEAR GENERATING STATION yQh
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T -c3 mot.- @o$goLLO . I v ' l
- TITLE
- RADIOLOGICAL EMERGENCY RESPONSE PLAN, SECTION 7 NEMg l s#Sp#
ct o$# d # ! ISSUANCE 49 AUTHORIZED PORC / EFFECTIVE ! REVIEW PORc 5 8 2 AUG 141984 DATE $~ ll- $ 9 7.0 Emergency Facilities and Equipment This section describes: emergency control centers; onsite and offsite communication systems links; assessment equipment and facilities; protective facilities; first aid and medical l facilities; and damage control equipment and supplies. 7.1 Emergency Control Centers 7.1.1 Technical Support Center (TSC) Site emergency command activities will be centered o in the Technical Support Center (TSC) located U immediately adjacent to the Reactor Building and within short walking distance to the Control Roem. The TSC is equipped with intercoms, telephones, NRC hotline, dedicated Health Physics Network (HPN) telephone, telecopier, and radios for l communications with the CR, Personnel Control l Center (PCC), and Forward Command Post (FCP). The TSC is equipped with a CDC-1700 terminal for visualization of plant parameters and offsite dose calculations, essential drawings, specifications, and procedures. Radiation monitoring equipment, protective clothing, communic'ations equipment, 1 portable lighting, protective breathing apparatus, , and first-aid equipment are located in Emergency l Kits. The TSC meets habitability requirements i similar to those imposed upon the CR. 7.1.2 Forward Command Post (FCP) l The Forward Command Post is the focal point for the coordination of onsite and offsite emergency response activities. Management and technical personnel assigned to the FCP are responsible for protective action recommendations and liaison with offsite authorities and response facilities. The .VO FCP serves as the point from which the Corporate Emergency Director (CED), Vice President of FORM 372 22 3642
1 RERP Section 7
. PUBLIC SERVICE COMPANY OF COLORADO Issue 6
, )
1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 24 Y ,'
- Production, exercises overall control of the FSV Emergency Response Organization.
The FCP has work space allocated for PSC emergency personnel, state and local personnel, and the NRC. The FCP is adequately equipped with dedicated phone lines, PSC PBX phone lines, commercial phone lines, radio, and telecopy facilities to provide efficient communications with the TSC, ECP, State E0C, NRC, and the Weld County Communication Center. Onsite-offsite communcations are channelled through the TSC and FCP. The FCP is located at the PSC garage facility in Ft. Lupton, well out of the plume exposure EPZ. Generally, the FCP will be activated and manned for an ALERT or more severe . incident classification. (There are cases where, at the ALERT classification, activation of the FCP is not necessary. This is at the discretion of the Corporate Emergency Director, based upon his assessment of the situation.) There are plans to equip the the FCP with a CDC-1700 terminal to provide rapid access to plant () O parameters calculations. and to provide for offsite dose Briefings with the media are to take place at the Ft. Lupton Methodist Church, located in close proximity to the FCP. 7.1.3 Personnel Control Center (PCC) The primary and secondary locations for the Personnel Control Center (PCC) are the Training Center and the QA/ Engineering Office Complex, respectively. Emergency radiological monitoring equipment, first-aid and decontamination equipment, protective clothing, communications equipment, camera, portable lighting and protective breathing l apparatus are stored in emergency kits at both l onsite locations. There are three' designated offsite areas which may be utilized as the PCC if it becomes necessary to evacuate the onsite location (s). The preferred alternate offsite location is the Johnstown County Shops. The other alternate offsite PCC locations are the Longmont PSC Service Center and the Platteville Volunteer Fire Department. Routes to these locations are shown in RERP implementing procedure RERP-PCC, [] Personnel Control Center Procedure. l= l FORM 372 22 A43 m.v~.-,_ --
Section 7 PUBLIC SERVICE COMPANY OF COLORADO ,
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FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 24 U
- 7.1.4 Control Room (CR)
Emergency assessment and control is initially directed from the CR by the Shift Supervisor prior i to activation of the TSC. The CR, located adjacent I to the Reactor Building, is designed to be habitable during Design Basis Accidents. The CR contains full plant instrumentation, technical dr: wings, protective breathing apparatus, radio, telephone, and intercom systems. Emergency radiological monitoring equipment and protective clothing are located nearby. 7.2 Communications Systems The primary station-offsite link is between the TSC and the FCP. Communications between the station and the FCP consist of commercial telephone service backed by two way radins. From the FCP, messages are relayed to designated agencies via Weld County, Colorado Division of Disaster and Emergency Services (00 DES), and Colorado National Guard radio communication systems. Two-way radios will be used to maintain communications between the TSC and Emergency Monitoring Teams. Primary telephone and radio g communication links between the TSC and other emergency --- Q centers are shown on Figure 7.2-1. For a comprehensive discussion of overall emergency response communications, refer to Annex F of the State RERP. PSC, D0 DES, and Weld County Communcations facilities are manned on a 24-hour basis. These are the principle entities involved in the notification fanout. 7.3 Assessment Facilities Emergency measures described in Section 6 depend upon the availability of the monitoring instruments and laboratory facilities necessary for assessment of problems. This section describes onsite and offsite facilities and monitoring equipment used in intial and continuing assessment. 7.3.1 Onsite Systems and Equipment
- a. Geophysical data are grouped into meteorological and seismic categories. j
- 1. Meteorolooical Monitors Information is ot tained from installed instrumentation on the primary 60 meter meteorological tower with readout in the f) CR. The following information is l
.V obtained: wind direction, windspeed, FORM 372 22 3643
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RERP Section 7 PUBLIC SERVICE COMPANY OF COLORADO Issue 6
; FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 24
_ L.)
. standard deviation of wind direction (sigma theta), precipitation, dewpoint, temperature, 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 l onsite 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 directions. The system determines whether operating basis or safe shutdown maximum accelerations are exceeded in any of three directions.
- b. Area and process radiation monitoring systems are divided into seven basic groups.
() 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 be 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 l and local alarm. !
- 2. Equioment Monitors These monitors determine radiation levels in specific effluent streams. Redundant monitors are provided separate power l sources.
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j PUZLIC SERVICE COMPANY OF COLORADO RERP Section 7
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{ FORT ST. VRAIN NUCLEAR GENERATING STATION page 5 of 24 (~
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- 3. Liquid Monitors These devices are specifically designed to monitor liquid effluents. They utilize gamma scintillation detectors consisting of an NaI(Tl) crystal optically coupled 'to a photomultiplier tube.
- 4. Gas Monitors These monitors consist of a plastic Beta scintillator which is coupled to a 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
(,f--)c may be removed to be 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 loss of power to the normal operating stack monitors.
- 7. Reactor Building Ventilation Exhaust Stack Monitor This system monitors exhaust air from the reactor building for Beta particulates and Iodine-131 contaminants.
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PUZLIC SERVICE COMPANY OF COLORADO $,3*Cti"7 FORT ST. VRAIN NUCLEAR GENERATING STATION page 6 of 24
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. c. System Monitors These moniters detect and/or control problems within plant systems. These may be pressure detectors, heat detectors, flow elements, heat rise detectors, or similar devices designed to monitor plant parameters. Many of these detectors are capable of initiating control actions to prevent or mitigate damage or release of radioactive material.
- d. Fire Protection Systems There is an extensive Fire Protection System in operation at Fort St. Vrain. The Pyralarm Fire Detection System is designed to detect fires in the Three Room Control Complex (Control Room, Auxiliary Electric Room, and 480V Room), G-Wall Cable Area, J-Wall Cable Area, and the Reactor Building. These detectors are smoke detectors. In addition, there are Fixed Heat Detectors and Rate of Heat Rise Detectors serving other parts of the station. Fire extinguishing is by use of
- Halon System (Three: Room ~ Control Complex), or
-- - -- - ~
g-t,,_j sprinkler / deluge systems with either automatic or manual initiation. Specific information regarding Fire Detection / Suppression at FSV is contained in the System Abstracts (System 45), System Operating Procedures (SOPS), and in the Administrative Procedures (P-8).
- e. Radiation Analysis Radiochemical laboratory equipment, radiation monitoring stations, and fixed air sampling stations provide capability for detailed, isotopic analysis.
- f. portable Survey Instruments These instruments provide flexibility and backup capability for radiation measurements in areas not served by installed monitors or where installed monitors may be inoperative.
() F OR M 372 22 - N43
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P Section 7 PUBLIC SERVICE COMPANY OF COLORADO
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- FORT ST. VRAIN NUCLEAR GENERAT,NG STATION page 7 of 24
~, I" Specific equipment' and their locations for Fort St. Vrain onsite radiological assessment is summarized in Table 7.3-1. 7.3.2 Offsite Systems and Equipment The environmental radiological monitoring program for the Fort St. Vrain environs is provided under contract by Colorado State University (CSU). It consists of a comprehensive sampling system to monitor radioactivity in the ecosystems and atmosphere near the station. Biota samples are routinely collected and analyzed, as are air, water, soil, precipitation, vegetation, and milk samples. The agreement with CSU includes provision for environmental monitoring in the event of an emergency. In the event of an emergency, CSU can respond within four (4) hours. CSU also has facilities for radiochemistry and gamma spectrometry which would be accessible if required. Weather observations and forecasting may also be obtained through the National Weather Service (NWS) radio or from the Stapleton Airport National Weather Service Station. Offsite facilities are summarized in Table 7.3-2. V 7.4 Protective Facilities and Equipment Control Room shielding and ventilation are designed to allow personnel habitability during Design Basis Accident l conditions. The TSC is located 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, respiratory equipment, protective clothing, and portable lighting are available near the CR. Communications equipment is in the CR. 1 7.5 First Aid and Medical Facilities i Necessary treatment supplies are located at the First-Aid Station on level five of the Turbine Building immediately adjacent to the West Building entrance. In the event of l an emergency, an alternate first-aid area is provided in l the PCC. First-aid treatment of injured individuals will I be administered by trained personnel. Advanced medical ' care, if required, will be obtained by transporting the individuals to St. Luke's Hospital and/or North Colorado Medical Center. (Section 10, Appendix A contains - agreements with offsite medical facilities). . (vD P' FORM 372 3643
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RERP Section 7 PUBLIC SERVICE COMPANY OF COLORADO Issue 6 l FORT ST, VRAIN NUCLEAR GENERATING STATION page 8 of 24 ' r'r l _V 7.6 Damage Control Ecuipment and Supplies Fire hose stations, extinguishers, and hydrants are , strategically located throughout the station for use in the event of fire. Self-contained breathing apparatus (SCBA) is located strategically throughout the station to i be used as necessary for fire fighting, entry into airborne radioactivity areas, or entry into toxic gas areas. A chlorine container repair kit is available to seal the cover on a chlorine cylinder in the event of a valve leakage. Selected equipment spare parts are stored in the warehouse for equipment repair. O
. wJ FORM 372 22 3643 l
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PUBLIC SERVICE COMPANY OF COLORADO RERP Issue 6 Section 7 FORT ST. VRAIN NUCLEAR GENERATING STATION page 9 of 24
; FIGURE 7.2-1 PRIMARY AND SECONDARY COMMUNICATION LINKS ONSITE - OFFSITE EMERGENCY OPERATIONS Fort St. Vrain Nuclear Generating Station CONTROL ROOM _____
ooooooooooooooooooooooo oooc _ o -- - - CR Director -. .-.-.-.-.
- ll il 11 PERSONNEL CONTROL PSC 3l LF4TER PCC Director p
-[ ,, MONITORING TEAMS em Leader
*l g TECHNICAL .
$UPPORT LNTR l
I$l TSC Ol tecto r
-l l
, e' ONSITE NRC REGION IV ,o r0RMARD o' .0MMAND POS MELD COUNTT _ l
. o I Co rpo ra te I COMMUNICATIONS j neo* Emergency CENTER o..] NRC HEA000ARTERS
- Director Dispatcher P
STATE EMERRENCY EIECUTIVE OPERAliONS CENTER S COMMAND POST Nuclear Trojects ECP Director Manager
@ PRIMART
@ SECONDARY l
TELEPHONE (OPEN LINE) .- T BACKUP STATE RADIO $YSTEM
-- TELEPHONE
- STATE LOCAL GOVERNMENT
** ~ . ~ ~ PSC INTERCCM SYSTEM STATE PATROL
==== PSC cal-TRONICS SYSTEM N ONA 'A0
- PSC RA010 ooooooo NOT LINE
.O FORM 372 22 3643
RERP Section 7 PUBLIC SERVICE COMPANY OF COLORADO
- FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 24 I TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Description and Functional System Location Applicability _
- 1. Geophysical Monitors Meteorological Wind Speed Indicators Measures Wind Speed 0 located North of plant 58m above ground on 60m toyer North of level and 10 m the plant. above ground level.
Wind Speed Indicator Measures Wind Direction located North of plant 0 58m and 10m above on 60m tower-Same ground level Instrument as previous listing Delta Temperature Sensors Measures temperature located on 60m tower differential between north of plant 10m and 58m elevation U Rain Guage on 60m Measure precipitation tower Ten Meter Tower Windspeed, Wind direction Provide backun temperature, Solar Radiation, Meteorological para-etc. located North of meters (Operated by plant. NOAA)-available via data logger, modem dial-up (see RERP implementing proce-
, dures), or via remote readouts at tower.
Strong Motion 2 Detectors Below PCRV Record gound 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 Control Room. FORM 372 22 *e643 _ .- ..m.,___.- __. .
PUBLIC SERVICE COMPANY OF COLORADO (PSection7
- FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 24
~O I TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Seismoscopes 2 detectors 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. FORM 372 22 3643
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RERP Section 7 PUBLIC SERVICE COMPANY OF COLORADO Issue 6
- 1. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 24 p
TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Control Number Location Action Setpoint
- 2. Radiation Monitors Liquid Monitors
~
l RT6212 & Radioactive liquid 10 5 pCi/ml (also, if 750 cpm > BKG RT6213 effluent monitors. cooling tower blowdown 750 cpm > BKG l Reactor bldg.- drops to < 1100 gpm), Elev. 4771' closes HV-6212 & HV-62249, trips transfer pump P-6202 & 6202S, and trips reactor building sump pumps to prevent 1 X 10
-7 pCi/ml l
MPC value at site . ("'s perimeter from being
\> exceeded. (ELCO 8.1.2)
RT21251 Low pressure Bearing water removal 10,000 cpm separator drain pumps trip, water line monitor. diverted to liquid Reacter bldg.- waste sump. Elev. 4740' (Operator must go to recycle mode). RT2263 Reheat steam No control action 600 cpm RT2264* condensate monitor. 570 cpm Turbine bldg.- Elev. 4811' RT46211 Gas waste No control action 600 cpm RT46212 compressor cooling 600 cpm water monitor. Reactor b1dg. - Eley. 4740'
- NOTE: RT-2264 is normally lined up to monitor loop 2 steam generator penetration interspace for primary coolant in-leakage. Detection of activity in Steam Jet Air Ejector Discharge (RT31193) without correspondingly high indication on RT-2264 would suggest the need to switch RT-2264 to Reheat
~~ Steam Condensate, as directed by Emergency Procedure EP H-3.
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3*Cti " 7 PUBLIC SERVICE COMPANY OF COLORADO , 1 FORT ST. VRAIN NUCLEAR GENERATING STATION page 13 of 24 s _ o i ) TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Control Number Location Action Setpoint l Gas Monitors (Plastic Beta Scintillators) i RT7324-1 Reactor building Close block valve 35,000 cpm RT7324-2 ventilation exhaust FV-6351, divert ex- 1,300 cpm monitors. The haust from filters to monitors 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) C) RT7312 Building Radio- The primary action is to 1,000 cpm activity Monitor. terminate flow to panel Five point monitor- I-9325 by closing valves: samples: HV-6342
- 1) PCRV Bottom Head HV-6341
- 2) A & I Room HV-9316
- 3) Health Physics HV-93256 Access HV-2325
- 4) Control Room HV-2326
- 5) Turbine Deck HV-2357-1 Monitor is located HV-2357-2 on the Turbine Close all AI room Deck Elev. 4829'. sample valves. Normally samples a point for 7 minutes. All take suctio.
from an exhaust vent d zt. RT31193 Air Ejector Exhaust No control action. 500 cpm Monitor. Located (ELCO 8.8.1) on the mezzanine level of the Turbine Building, east of the main condenser, Elev. 4811'.
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FORM 372 3643
RERP Section 7 PUBLIC SERVICE COMPANY OF COLORADO Issue 6
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- FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 24 l
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im j _U i TABLE 7.3-1 ., ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Control Number Location Action Setpoint RT9301 Primary Coolant No automatic action. 4.6 X Monitor-0nline 10' cpm Beta scintillator to monitor the primary coolant. Located in the AI room, Elev. 4829'. RT9302 Kr-85 Monitor. No automatic action. 500 cpm Shielded monitor Operator will swap located on the purification trains. Turbine Deck - Elev. 4829'. RT6314-2 Gas Waste Exhaust High alarm diverts the 1.7 X O' Monitor. Operated flow to the gas waste 10' cpm 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 (NaI gamma scintillation detectors) RT6314-1 Monitor the gas Has the same control 7.0 X waste effluent action as RT6314-2. 10' cpm stream up stream (ELCO 8.8.1) of the gas monitor RT6314-2. Located i inside the gas waste l blower cubicle on Elev. 4781'. l l l l
. v} 'i FORM 372 22 3643
RERP Section 7 PUBLIC SERVICE COMPANY OF COLORADO Issue 6 1 FORT ST. VRAIN NUCLEAR GENERATING STATION page 15 of 24 1 o , 1 8 TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Control Number Location Action Setpoint i RT73437-1 Reactor Plant ELCO 8.8.1 -Close valve 10,000 cpm i Ventilation Exhaust FV6351, divert flow to l Iodine-131 gas waste vacuum tank. l Monitor Loc: Shutdown turbine building i Sampler / Detector: ventilation and place l El. 4916 the control room vent-l Turbine Side 11ation on recirculation. I Readout i El. 4829 l Control Room l This iodine monitor consists of two single channel l analyzers, one window being set for the photopeak l energy of interest (i.e. S'2I), and one being set for l an adjacent energy region. The adjacent region window (' l provides a background subtraction capability, thus l allowing the monitor to discriminate 2811 from noble l gas radioisotopes. A 2 inch by 2 inch NaI(TL) crystal l 1s utilized as the detector for this monitor. I RT73437-2 Reactor Plant Same automatic action 20,000 cpm l Ventilation as RT73437-1. l Exhaust Beta l Particulate Monitor l Loc: l Samples / Detector: l El. 4916 l Turbine Side l Readout l E1. 4829 l Control Room l This particulate monitor consists of an alpha detector l and a plastic beta scintillation detector viewing a l fixed filter for particulate radioactivity. The alpha l channel provides a live measurement of radon I concentration which is subtracted from the beta l measurement. ['J' ks FORM 372 22 3643
3*Cti " 7
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PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATIOfJ Page 16 of 24
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TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiction Transmitter Description and Alarm Number Location Setpoint Emergency Stack Monitors (PING - Particulates, Iodine, Noble Gases) Provided to Monitor Reactor Building Ventilation exhaust effluent during loss of power to the normal operating stack monitor. RT 4801 Reactor Plant Ver.tilation 10,000 cpm Exhaust Beta Particulate Monitor Loc: El. 4885, turbine side RT 4802 Reactor Plant Ventilation 19,000 cpm Exhaust Iodine Monitor Loc: El. 4885, turbine side RT 4803 Reactor Plant Ventilation 23,000 cpm Exhaust Noble Gas Monitor {} Loc: El. 4881, turbine side Reactor Building Ventilation Exhaust Stack Monitor l RT 7325-1 Reactor Plant Ventilation 1,600 cpm l Exhaust Iodine and Particulate Monitor Loc: l Samples / Detector: El. 4921 Turbine Side Readout El. 4829 Control Room l RT 7.325-2 Reactor Plant Ventilation 10 mr/hr l Exhaust G-M Detector Loc: l Sampler / Detector: El. 4921 Turbine Side Readout El. 4829 l Control Room I i O O FORM 372 22 3643 l w- w
3*Cti " 7 PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION page 17 of 24
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-V TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Alarm Number Location Setpoint TSC Ventilation Monitors RIT 7937 TSC Ventilation Inlet (P) 30,000 cpm Particulate, Iodine, Noble Gas (I) 3,000 cpm Loc: (G) 400 cpm Sampler / Detector: El. 4791 TSC Building Readout El. 4791 TSC Building RIT 7936 TSC Ambient Atmosphere (P) 30,000 cpm Particulate, Iodine, Noble Gas (I) 3,000 cpm LOC: (G) 400 cpm O V Sampler / Detector: El. 4811 TSC Readout EL. 4811 TSC FORM 372 - 22 3643
3*Cti " 7 PUBLIC SERVICE COMPANY OF COLORADO l -
- FORT ST. VRAIN NUCLEAR GEi4ERATING STATION Page 18 of 24
~ (') - C' TABLE 7.3-1 l 1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Alarm Transmitter Setpoint Number Location Elevation mrem /hr Reactor Building Area Radiation Monitors RT93250-1 Refueling Machine 4881 2.5 Control Room RT93252-1 Northeast Refueling Floor 4881 2.5 RT93250-2 East Walkway Outside HSF 4854 2.5 RT93252-2 South Stairwell 4864 2.6 RT93250-3 Hot Service Facility 4856 10.0 Platform RT93251-3 Hot Service Blower Section 4868 100 O V ' RT93250-4 Outside HSF Door 4839 2.5 RT93252-4 Instrument Room-Analytical 4829 2.5 Instrument Board RT93251-5 Gas Waste Filters 4781 2.5 RT93251-6 Truck Bay 4791 2.5 RT93252-6 Near South Stairwell 4791 2.5 RT93251-7 Core Support Filter 4781 2.5 RT93252-7 East Walkway 4781 2.5 , RT93250-8 North East Walkway 4771 2.5 RT93251-8 Decontamination Laundry 4771 2.5 RT93251-9 Buffer Helium Dryer Loop I 4740 2.5 RT93250-14 Refueling Floor / 4681 2500 East Wall o .O FORM 372 - 22 3643
s PUl'LIC SERVICE COMPANY OF COLORADO e$ction7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 19 of 24 { g TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Alarm Transmitter Setpoint Control Number Location Elevation mrem /hr Action Turbine Building Area Radiation Monitors RT93250-13 'Near Condensate Demin- 4791 2.5 eralizers RT93251-1 Reactor Plant Exhaust 4864 1000 Filter Room RT93251-4 General Office Area 4816 1.0 RT93250-5 Control Room 4829 1.0 Technical Support Center Area Radiation Monitor RIA-7951 Technical Support Center 4811 2.5 (G _J Equipment Radiation Monitors l RT93250-12 Steam / Water Dump Tank 4740 2.5 Alarm Monitor blocks opening HV-22156 vent valve to atmos-phere l RT93251-12 Steam / Water Dump Tank 4740 2.5 Alarm blocks opening HV-22156 vent valve to atmos- i phere ! l RT93250-10 Reheat Steam Hrader 4811 1 (alarm) l Monitor Loop
- 3 (trip) l RT93251-10 Reheat Steam header 4811 3 Monitor Loop 1 j 1
.O FORM 372 - 22 3643
' P 3*Cti " 7 PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIT4 NUCLEAR GET4ERATING STATION , Page 20 of 24
- '~ TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Alarm Transmitter Setpoint Control Number Location Elevation mrem /hr Action l RT93252-10 Reheat Steam Header 4811 1 (alarm) l Monitor Loop 1 3 (trip) l RT93250-11 Reheat Steam Header 4811 1 (alarm) l Monitor Loop 2 3 (trip) l RT93251-11 Reheat Steam Header 4811 1(alarm) l Monitor Loop 2 3 (trip) l RT93252-11 Reheat Steam Header 4811 1 (alarm) l Monitor Loop 2 3 (trip) l RT93252-12 PCRV Relief Valve 4885 2.5 Piping Monitor
/' 3. System Monitors O
Process Monitors affecting the Assessment of Radiological Accidents are shown in the EAL column of Tables 4.1 4.1-4.
- 4. Fire Detection Smoke Detectors Detect Products of Combustion Rate of Heat Rise Detects Quick Ri e of Detector . Temperature Fixed Heat Detector Detects a Set Temperature r
FORM 372 22 - 3643
1 e RERP Section 7 l PUBLIC SERVICE COMPANY OF COLORADO Issue 6 , - . FORT ST. VRAIN NUCLEAR GENERATING STATION Page 21 of 24 l ss' TABLE 7.3-1 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 State University) area.
._ 4 Fixed Air Sampling Sample particulates and n Stations-Just Outside radioiodines(operated V 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 Tritium Air Monitors Detect Airborne Tritium Alpha Survey Meters Detect Surface Contamination Neutron Detectors Determine Neutron Flux rate Ion Chambers Determine Gamma Dose rate O
v FORM 372 22 3643
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l RERP Section 7 l PUZLIC SERVICE COMPANY OF COLORADO Issue 6 FORT ST VRAIN NUCLEAR GENERATING STATION Page 22 of 24 () v TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Description and Functional System Location Applicability Beta-Gamma Geiger- Surface and Area Mueller Survey Meters Radiation Levels 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 Lo Vol Air Samplers Detect Airborne Iodine ~
~
. and Particulate Contamination
.O FORM 372 22 3643
., . .. . . . . _ - . . . , _ _ , .~..___ . ._. . . . _ _ _ _
RERP Section 7 PUBLIC SERVICE COMPANY OF COLORADO issue 6 .- , FORT ST. VR AIN NUCLEAR GENERATING STATH3N Page 23 of 24 =, . .k ) -- TABLE 7.3-2 OFFSITE ASSESSMENT EQUIPMENT AND FACILITIES Individual Functional Detector Applicability
- 1. Geophysical Monitoring Meteorological National Weather 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)
S between ten and fourteen (_/ miles from reactor) Fixed Air Sampling Stations Measure particulates and radiciodines (operated by contract with Colorado State University) Colorado State University Ge-Li Detector Gamma Spectrometry for Isotopic identification and Analysis NaI(TI) Detector Gamma Spectrometry for Isotopic identification and Analysis Radiochemistry Laboratory Chemical and radiological Analysis i ! .~/ : I I e ,onu m . 22. uu 1
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. . PUBLIC SERVICE COMPANY OF COLORADO RERP Section 7 Issue 6
, FORT ST. VRAIN NUCLEAR GENERATING STATION Page 24 of 24 TABLE 7.3-2 0FFSITE ASSESSMENT EQUIPMENT AND FACILITIES Individual Functional Detector Applicability Colorado State Department of Public Health Whole Body Counter Identification and quantification of inhaled or ingested radioisotopes.
Serves as backup to FSV System. O I
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'168V5WCR191/2,Platteville, Colorado 80651 September 7, 1984 Fort St. Vrain Unit ~No. 1 P-84348 Mr. Eric H. Johnson @ @ @ ONh U.S. Nuclear Regulatory Commission r
I ~ i ton ea bl y
Dear Mr. Johnson:
We are transmitting herein revisions to several emergency preparedness related documents. The changes affect the following document binders: Radiological Emergency Response Plan - Plant The following procedures are being transmitted for filing in the RERP
- Plant Procedures.
Section 4, Issue 5 Section 5, Issue 6 Section 6, Issue 7 Section 7, Issue 6 If there is confusion as to which issue is most recent whenever multiple copies are received in a short period of time, the highest issue number is always the most recent issue of a given procedure. If difficulties or questions arise in filing these procedures, please feel free to contact Ms. Sharilyn Johnson at (303) 785-2224, extension 275 for assistance. Very truly yours, J. W. Gahm Manager, Nuclear Production JWG/cjs
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r PUZLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAP GENER ATING STATION d .C k oh n sow
, 8/21/84 RADIOLOGICAL EMERGENCY RESPONSE PLAN - PLANT ISSUE EFFECTIVE NO. SUBJECT NUMBER DATE Table of Contents 3 10-08-82 Introduction 3 10-08-82 Section 1. Definitions ,
4 07-24-84 Section 2 Scope and Applicability 4 01-03-83 Section 3 Summary of the Radiological Emergency Response Plan 4 07-24-84 l Section 4 Emergency Conditions 5 08-21-84 l Section 5 Organizational Control of l Emergencies 6 08-21-84 l Section 6 Emergency Measures 7 08-21-84 l Section 7 Emergency Facilities and l Equipment 6 08-21-84 Section 8 Maintaining Emergency Preparedness 3 10-08-82 Section 9 Recovery. 4 07-24-84 Section 10.A Agreement Letters and Summary of Referenced Interfacing Emergency Plans 7 07-02-84 Section 10.B Sample Dose Calculations 4 04-02-84 Section 10.C Maps of Exclusion Area, Low Population Zone, Environmental I Dosimetry, Population Densities 3 10-08-82 Section 10.D Titles of Written Procedures l that Implement or Supplement the Plan 6 07-24-84 Section'10.E Listings of Emergency Kits, l Protective Equipment and Supplies Stored and Maintained for l Emergency Purposes 5 11-28-83 Section 10.F Cross Reference to NUREG-0654,
. Rev. 1 4 01-03-83 0,fe a .-.
4
- 1 PUBLIC SERVICE COMPANY OF COLORADO RERP Section 4 FORT ST. VRAIN NUCLEAR GENERATING STATION fy I
FORT ST. VRTJh'
- TITLE: RADIOLOGICAL EMERGENCY RESPONSE PLAN, SECTION 4 MN- ROLLED VEUY ISSUE STATUS ETH DOCUVENT CESTEA Pfacc TC USE Iu*Ts0R!zEo "n=
BY /d)$$ / H'/V PORC j b 14 EFFECTIVE R EVIEW DATE 8= Al- b 4.0 Emergency Conditions Emergencies are classified into four categories as provided by
" Emergency Action Level Guidelines For Nuclear Power Plants",
Appendix 1 USNRC NUREG-0654, Rev. 1. Each succeecing classification is more severe than its predecessor and results in a higher level of response. The classification system results in responses and procedures that are both timely and appropriate for a wide range of emergency conditions. 4.1 Classification The classifications described in the following. sections comprise the system. Each classification description includes appropriate levels of station and state / local government agency emergency response actions. The classifications given match those employed in the State RERP. 4.1.1 NOTIFICATION OF UNUSUAL EVENT This classification applies to situations where unusual events are in process (or have occurred) which indicate a potential for degradation of the level of safety of the plant. In +hese situations, time is available to take precautionary and constructive steps to prevent a more serious event and/or to mitigate any . consequences that may occur. This event status l 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. No releases of radioactive material requiring offsite response or monitoring are
- expected at this level.
Table 4.1-1 outlines initiating events and response actions for the NOTIFICATION OF AN UNUSUAL EVENT class of incident. t
; pt)mM 372 22 3442
r 1 5 "4 PUZLIC SERVICE COMPANY OF COLORADO ,lti l FORT ST. VRAIN NUCLEAR GENERATING STATION page 2 of 22 I 4.1.2 ALERT This classification comprises events which are in process, or have occurred, that involve the potential for a substantial degradation of the level of safety of the plant. Any releases of radioactive materials are expected to represent small fractions of the EPA Protective Action Guide limits. The purpose of the ALERT category is to assure that emergency personnel are readily available if the situation degrades and to provide offsite authorities with comprehensive status information. Operator modification of plant 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 followup notification to offsite authorities. If applicable, epdated meteorological information, verification of releases by surveys, and projected s 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 or an escalation to a more severe ~ emergency class is declared. Table 4.1-2 outlines initiating events and response actions for the ALERT class of incident. 4.1.3 SITE AREA EMERGENCY A SITE AREA EMERGENCY consists of events which are in process, or have occurred, that involve actual or likely major failures of plant protective furctions. Any releases are not expected to exceed EPA Protective Action Guideline exposure levels except near the site boundary. The purpose of the SITE AREA EMERGENCY declaration is to assure that emergency response facilities are manned, that radiation monitoring teams are dispatched, that emergency forces are readily available, and to provide efficient exchange of status information between PSC and offsite authorities. Consideration of appropriate protective actions, based on actual l or projected data, is warranted. Onsite and offsite emergency centers are activated. Onsite evacuation is initiated if indicated to be necessary by actual or projected doses. PSC radiological monitoring teams are. deployed. The station provides status updates to offsite authorities, including meteorological information, offsite radiological monitoring data (prior to t
. PORM 372 22 3643
1 3* "4 PU2LIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATR4G STeinCR4 Page 3 of 22 O
~
- state monitoring tean deployment), and projected doses (calculated on foreseeable plant conditions and projected long-term releases). State monitoring teams are dispatched to assess offsite consequences. If projected exposures approach those noted in the EPA PAGs, state / local authorities institute appropriate actions for public protection. A decision on termination, escalation, or recommended reduction in emergency class will be communicated to governmental authorities.
Table 4.1-3 outlines initiating events and response actions for the SITE AREA EMERGENCY class of incident. 4.1.4 GENERAL EMERGENCY A GENERAL EMERGENCY consists of events which are in process, or have occurred, that involve actual or imminent substantial core degradation, with the potential for loss of Prestressed Concrete Reactor Vessel (PCRV) integrity. Exposure levels beyond the site boundary may exceed EPA Protective Action Guideline levels. There is prompt notification of appropriate state and local authorities of the GENERAL EMERGENCY status. The purpose of declaration of a GENERAL EMERGENCY is to rapidly initiate predetermined protective actions for the public. During a GENERAL EMERGENCY, resources and personnel are augmented by the activation of emergency centers. Radiological monitoring teams are dispatched. The station provides plant status updates, as well as data on radioactive releases, meteorological information, radiological field measurements, radiological dose projections, and affected downwind zones to offsite authorities. l A decision on termination or reduction of the GENERAL EMERGENCY class will be communicated to l governmental authorities after thorough review of , the emergency situation. ! 1 Table 4.1-4 outlines initiating events and response l actions for the GENERAL EMERGENCY class of l incident. 4.2 Offsite Accident Assessment The station has the responsibility to perform a l preliminary assessment of the offsite consequences of an
?
i PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ,
~ '
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 22 I incident. This preliminary assessment includes: determination of the radiation exposure rate by precalculated analytical methods (see Section 6.2) and/or field surveys; estimation of projected total dose levels for different downwind sectors and distances; and, classification of incident consequences, per Tables 4.1-1 through 4.1-4. Based upon the results of these assessments, notification of state / local authorities of the appropriate incident classification is then made. After arrival at the Forward Command Post (FCP), the Colorado Department of Health (CDH) assumes responsibility for confirmatory (in-field) and continued offsite accident assessment, and FSV Field Monitoring Teams are recalled to the Personnel Control Center). This responsibility is carried out by disoatching CDH field monitoring teams and by analysis of data provided by PSC. Long-term offsite assessments (secondary incident assessments) are the responsiblity of the CDH staff as noted in the State RERP. 4.3 Spectru.n of Possible Accidents and Initiatino Events The accidents which might occur at the Fort St. Vrain Nuclear Generating Station have been analyzed in Section 14 of the FSV FSAR for their severity of consequence and probability of occurrence. These accidents reflect the design characteristics of a High Temperature Gas-cooled Reactor (HTGR) and are addressed in Tables 4.1-1 through 4.1-4 from the viewpoint of initiating events, alarm actuation and/or associated readings, and consequent incident classification. e
?
l . FORM 372 22 + 3643 l
t- -
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. i li R[RP Section 4 Issue 5 Page 5 or 22 i TABLE 4.1-1 EMERGENCY ACTION LEVELS (EALs) at CORRESPoel0ING ACil0NS j N0ffrICATION OF UNUSUAL EVENT FORT ST. VRAIN NUCLEAR GENERATING stall 04 EAL ( Ala rm, instru-l Initiatine Events ment Readine. etc.) PSC Actions State / Local Acklons Alarms on: , 1. Any unplanned redlo- 1. RT 7312 Inform State and Provide assistance ir l logical release CAM ( s) local authorftles requested [ ri re, i to the Reactor RT 7324-1; RT 480l; or nature or unusual security, medical, etc). j Sidg. or its vent- RT 7324-2; RT 4802; condition within 2 hours
- lation system. RT 7325-1; RT 4803; or occurrence, but in any j RT 7325-2; RT 73437-1,2 event, within 15 minutes
- or declaration.
I 1 2. Any liquid waste release 2. a) RT 6212 or 6213 Augment on-shirt Continue orrsite resulting In errsite alarm with inability resou rces notfrication as i; erripent in excess of to prevent discharge Assess and respond. necessitated by . Technical Specification orrsite. situation, f Limits, b) As determined by station personnel. ] 3. Indication or minor 3. a) 25% increase in Terminate with verbal ! ruel damage detected ci rculating act- summa ry to orrsite Standby until verbal in prima ry coolant Ivity from pre- authorities rollowed by te rm i na t ion.
- vlous equilibrium written summary within t
conditions at the 24 hours. or same power level, or RT 9301 Escalate to a more Escalate to a more b) SR 5.2.11 results, severe class. severe class. ' NOTE 1: Assumption implicit throughout Tables 4.1 4.1-4 tha t a la rms a re confi rmed to be va l id 1 by supporting observations or analysis as specirled by abnormal operating or annunciator j response procedures. { NOTE 2: Due to Instrument characteristics, alarm setpoints for radiation monitors listed in . Tables 4.1 4.1-4 very with time. Instruments and alarm setpoints are j checked / calibrated quarterly. Consult Master Setpoint List for actual settings. I i i 4 d
3.. .
- e. t_ .o ge .- e i
RERP Section 4' Issue 5 t Page 6 or 22 4 i
- TABLE 4.1-1 EMERCENCY ACT1011 LEVELS (EALs) & CORRESPOII0 LNG ACTIOllS i
NOTIFICATIOli 0F UllUSUAL EVENT , FORT ST. VRAIN NUCLEAR CENERATING STATION EAL ( Ala rm, Instru-Initiattne Events ment Readina. etc.) PSC Actions $1MeJ age _al..Aq Qong
- 4. Serious fire at the 4. a) any or various Note: Per agreement with the State plant lasting more than alarms on Fire Con- of Colorado, PSC will notify to minutes, which could t ro l Ala rm Pape l; the State prior to public lead to substantial b) fire Pump 1A Information releases concerning degradation or plant auto start; ISV.
safety systems, or c) verbal repo rt s. which could result
+ In the release or radiological or i, toxic materials.
- 5. Abnormal coolant temp- 5. Violations or LCO 4.1.7
. eratures or core or 4.1.9 for region region temperature outlet mismatch, or region rises to the extent re- Delta-T respectively, quiring shutdown in to the extent that shut-accordance with Tech- down per Station Tech-nical Specifications. nical Specifications is required (SOP 12-04).
- 6. statural phenomenon 6. a) Seismic Recorder that may be exper- Ope ra te; lenced or threatened b)-d) as visually that represent risks observed by, or beyond norsnel levels: reported to, station a) earthquake personnel, b) rioods c) tornadoes d) extremely high winds
.. . ..'g,, 'i:
9 RERP Section 4 issue 5 Page 7 or 22 TABLE Is.1-1 ' ~
- DIERCENCY A0TIO88 LEVELS (EAls) at CORRESP0000lIIG ACT10eIS 100TIIICATIOit of UleUSUAL EVLILT FORT ST. VRAIN leUCLEAR GENERATING STATl001 I EAL ( Alarm, Instru-i Initletine Events ment Readine. etc.) PSC Actions SJate/ Local _Aq Q9ttg
)
I 7. Unusual Haza rds 7. As visually observed by,
! l Experienced; or reported to, station a) Aircraf t crash personnel on s i te o r nea r the 4
site that is subject to public concern because or possible detrimental errect on i the plant; b) Onsite explosions or near onsite explosions that may be sutJect i to putsIIc concern , because or possible
- detrimental effect on j the plant; o r, g c) Onsite or near on-
< site plant related e
- accidents that could j result in the re-lease of toxic meterial or spills of flammable '
me te ri a l s.
- 8. Any serious redlo- 8. As occurring.
logical exposure of plant personnel or the transportation to orrsite recIltiles or 1 contaminated personnel wtoo may have been j Irdured. l I i
" *t *
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RERP Section 4 issue 5 Page 8 or 22 TABLE 4.1-1 EMERCENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS 1 IIOTIF1 CATION OF UNUSUAL EVENT FORT ST. VRAIN NUCLEAR CENERATIIIG STATION
. EAL ( Ala rm, ins t ru- =
Initiatine Events ment Readine. etc.) PSC Actiorts Stale / log _al Aq uons
- 9. Accidents within the 9. As occurring or state that may involve reported by shippet.
.. , plant spent fuel ship-ments or plant radio-active weste shipments.
- 10. Loss or Engineered 10. Shutdown required in j Safety Feature or accordance with applicable Fire Protection System LCOs:
to the extent requirlog - a ) Eng inee red Sa regua rds shutdown in accordance 1) Plant Ventilation - with station Technical LCO 4.5.1
! Specifications. 2) Steam / Water Dump 1
g System-LCO 4.3.3
; 3) PCRV penetration flow 1 restriction devices -
LCO 4.2.7 and LCO 4.2.9 4 ) PCRV penet ra t ion 4 seconda ry closures - 1 LCO 4.2.7 and i LCO 4.2.9 i 5) PCRV Sarety valves - j LCO 4.2.8 SL 3.2
; LSSS 3.3.2.c j b) Fire Protection System -
i LCO 4.2.6 and, LCO 4.10.1 - LCO 4.10.5 1 i i .1 1
' 'D ' * * ,o e .e g o. s
. 1 RtRI* Section 4 Issue 5 Page 9 of 22 TABLE 4.1-1 EMERGENCY ACTlost LEVELS (EALs) ar CORRESP0800!NC ACTIONS NOTIFiCAT5006 0F U80 USUAL EVEE FORT ST. VRAIN NUCLEAR CENERATIIGC STAT 1001 o
EAL ( Ata re, Instru-InItIaeIne_tvsnin ment ReadIne. etc2 r_SC Actions Staan/Logal Action 3 l
- 11. Indication or alarms 11. Data Logger Alare/
on radiological effluent Alarm Stemmary Indication monitors not fasoctiona 1. ol' non-ope ra t i ona l a la rm o r Ind ica t ion on: a) RT-7324-1,2 RDd
. RT 4803; or b) RT-7325-1 2, RT 4802, anst RT 73k37-1; or c) RI 73437-2 and RT 4801; or_
d) RT 6212 And RT 6213 8 l NOTE: Use ELCO 8.1.1 Technical l Specification limits as basis. The initistlog events for the le0TIFCAT1088 0F UfeUSUAL EVENT category are per Public Service Compan/ l f separate written agreement with the State of Colorado. 1 1
e 9
- ee e e ge. 'i'
, RIRP Section 4 issue 5 Page 10 or 22 1A8LE 4.1-2 3 EMERCENCY ACil04 LEVELS (EALs) & CORRESPONDING ACTIONS i ALERT FORT ST. YRAIN NUCLEAR CENERATING STATION EAL ( Ala rm, Instru-i Initletina Events ment Reading. etgj PSC Actions itajeftp_caMc1Lons ) 1. Rapid, severe fuel 1. Coolant inventory or Inform State and/or Provide assistance, if ] particle coating a) greater than 2.4 local authorities or requested (Fire, i ra l lure. ICillMovl Bets-Camma ALERT status /cause security, medical, etc.) Ib as decla red b ci rculating 1-131 activity equivalent greater than 24Cl j c. plate out 1-131 3 greater than 1 x 10 Cl.
- d. SR 5.2.6 or
. SR 5.2.11 results.
1 i 2. Rapid, gross fall- 2. toop 1 Hot Reheat Header Augment resources by Augment resources by ure or one steam (HRH) activity high activating 15C, PCC, activating TCP and generator reheat (5mree/hr); or, Loop 2 and FCP. State / local EOCs. section with loss of PRH activity high orrsi te power. ( 5mree/hr), accompanied 4 by 230 MV OC8 trips i
- ggd RAT undervoltage/
loss of powe r a la rm. I Assess and respond. , i ,
- 3. Prima ry coolant press- 3. PAL 9335 Place key emergency ure decay (to a PAL 934T Dispatch onsite personnel (including
] value greater than PAL 9359 monitoring teams with monitoring teams and 100 psi less than and area monitor or stack monitor alarm, associated communica- associated communica-i, no rma l p ressure, accom- tions. tions) on standby 1 , panied by area and status, i stack radiation , Provide periodic plant
- } moni to r a la rms). status agpdates to
! orrsite authorities as , } conditions warrant (at 3 j least every 15 minutes. )
l 0 -
.- . ~ . . .
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- RERP Section 4 Issue 5 Page II or 22 ,
,:. /
l' , . < t / #" TABLE 4.1-2 EMERCEIICY ACT 8088 LEVELS (EAls) at CORRESPONDING ACTIOllS/ ALERT FORT ST. VRAIN IIUCLEAR GENERATIIIG STATICII a 4 EAL (Alarm, instru-l InitiatirwLLyents ment Readine. etc.) PSC Actions Etateflocat Actions i
- 4. High radiation . levels 4. RT 7312 Provide meteorological Provide confirmatory or high ai rborne con- CAM (s) alarm assessments to orr- o rrs i to . rad ia t ion *
- tamination which in- RT 6212 site authorities and, monitoreng arul Ingest-
! dica tes severe degrad- RT 6213 I f re lea kes a re tion pathway dose ation in control or RT 93252-12 occurring, dose esti- projet.tlons i r acttsal radioactive materla t s. Area Ibnitors mates for actual relea3es siebstantially ,
- (Increase by factor releases, exceed technical specl-o f 1,000 ove r no rma l . ) Alarms with cor- rication limits.
'd.g., lifting PCRV responding meter Terminate by verbal reller valve or ab- readings on area summary to orrsite i normal release to or process monitors. authorities rollowed by j cooling tower blowdown. written summary within ; 8 hours.
i Maintain ALERT stattes amt l 1 ve rba l termina-or tion, i" i Escalate to a more severe class. or { l 5. Loss or errsite power 5. 230 MV OCs trips and Escalate to a more and vital onsite RAT undervoltage/ loss severe class. AC power for up to of power alarm accom-
]
i 30 minutes, panied by 4 Kv bus under-i voltage, 480V bus under-voltage, and Diesel Trouble alarias.
- 6. Loss or all vital DC 6. DC bus 1 less
! power for up to 30 than 10 volts, and . , minutes. DC bus 2 less j than 10 volts.
4 i i 0 8 i b __ - - _ - - - .A
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l RERP Section 4 i Issue $ Page 12.or 22 l TABLE Is.1-2 DIERGE10CY ACTIOsl LEVEL.S (EALs) k CORRESP0000llIG ACil0ftS AI.Elli FORT ST. VRA198 ItUCLEAR GL50ERATIIIC STATION [AL ( Ala rm. Instru-Initiatine Events Laen_t_f_cading, etgj PSC Agf lon_g itate/Jocal Actions
- 7. Loss or primary 7. All He flow indicators coolant forced circ- read zero, usation for between
! 2 and 5 hours.*
- 8. Loss or secondary 8. All secondary coolant coolant ruvictions flow indicators
, needed for removing read zero. ( resideaal heat.
- 9. Loss or normal 9. a ) Indication or in-ability to place the sufficient rods reactor f ra a sub- inserted; or, c ri t ica l cond i t inn by b) netetron count scram of time contrul ra te no t dec res s lrig.
rtMis. 10.Seriotes rire which 10.a) any or various cot Id lead to sub- stares on Fire Control stantial degradation Alarm Panet; of plant saroty b) fire Pump 1 A auto start; or, systems, c) verbal reports. l
- These times are Frena LOf C at 100% power. Times may be correspondingly longer for lower power levels (LCO 4.2.18).
- i. ,
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9
~
r *D ' ' ,e e: . g,.- . RERP Section 4 Issue 5 Pags 13 or 22 H TABLE 9.1-2 EMERCENCY ACTION LEVELS (EAls) ar CORRESPONOING ACTIONS elLBI FORT ST. VRAIN N'ICLEAR CENERATING STATION EAL ( Ala rm, Instru- . Initletine Events ment Readine. etc.) PSC Actions State / Local Actions 11.Radlological er- 11.RT 7324-1-Indicating riuents exceed 10 a) greater than or equal times technical to 2.5 x 10 micro C1/cc speclrication inston- mixed noble gas teneous Ilmits, b) RT 7324-2 indicating greeter than or equal to 2.5 x 10 micro Cl/cc mixed noble gas c) RT 7325-1 I nd ica t ing greater than or equal to 7.0 x 10 micro Cl/cc - l-131 d) RT 7325-2 indicating greater than or equal
, to 7.0 x 10 mic ro Cl/cc - I-131 e) RT 73437-1 Indicating
, greater than or equal to 7.0 x 10 mic ro Cl/cc 131 f) RT 4801 Indicating greater than or equal to 7.0 x 10 mic ro C1/:c 131 4 12.pngoing security 12.a) As observed or comp romi se, reported. , E
m.-- - - - r 'tr = -
- ge e e g e. s-
?
e RERP Section 4 issue 5
, t Page 14 or 22 TABLE 4.1-2 ENERCENCY ACil0N LEVELS (EALs) & CORRESPONDING ACTIONS ALERT TORT ST. YRAIN NUCLEAR CENERATING STATION EAL ( Ala rm, Instru-Initiatina Evenis ment Readine. etc.) PSC Actions flate/ Local Acilo_n3
- 13. Severe natural 13.a) Selsmic recorder phenomenon being operate (greater experienced or titen or equal to p rojec ted, such as: .05g); or b) As Reported a ) ea rthquake ex- ,
c) As Reported. ceeding Operating Basis Earthquake levels; b) rioed near design level; or, c) tornado striking I racility. 14.0ther haza rds 14. As reported by, or being experienced or to, station or proJocted such as: personnel, a ) a i rc ra r t c ra sh on racility; b) missile impact on racility; c) explosion damage
, arrecting plant
- Operation; or, d) entry into facility envi rons or toxic or riammable gas.
(Some errect on racility experienced or anticipated. )
- .p . . .
,, ', e ge- e' RERP Section fa issue 5 Page 15 or 22 TABLE 4.1-2 EMERCENCY ACTION LEVELS (Eats) er CORRESPONDING ACil0NS ALERT FORT St. VRAIN NUCLEAR CENERATING SIAilON
[AL ( Ala rm, Instru-Initiatina Evenig ment Readine. etc.) PSC Actions j S ajef_Logel Actiong
- 15. Evacuation or con- 15. As deemed necessa ry trol room anti- by Shirt Supervisor cipated or required, with control or shut-down systems estab-l1shed from 1ocai stations. (Con-trol room integrity breached. ) i
' I
- 16. All a la rms (annun- 16. Control room I clators) lost for obse rva t ion. p more than 15 minutos EDd reactor is not shutdown; or, plant I
transient experienced while all alarms lost. (Parameter Indication , still functional.) 17.0ther plant con- 17.As deemed necessary ditions warranting 'oy Shl rt Supe rvi so r. precautionary acts-vation of the PCC, TSC, and FCP.
)
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RERP Section is
, Issue 5 Page 16 of 22 TABLE 4.1-3 EMERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS SITE AREA [MERGENCY .
l
. FORT ST. VRAIN NUCLEAR CENERATING STATION EAL ( Ala rm, Instru- !
initiatino Events ment Readino. etc.) , PSC Actions EtateLL_ocal Actiorys -1
- 1. Loss or primary 1. All lie flow In- Inform state and/or Provido any assistance coolant fo rced dicators read zero, local authorities or reqtms ted.
circulation for over SITE AREA EMERGENCY t 5 hr f rom 100% power. status /cause as de-( Lowe r powe r leve l s clared. preceeding LOFC ex-tends time available before core damage -- 1 is incurred. See Augment resources by initinte immediate j LCO 4.2.18.) activating TSC, PCC, public notirication ECP, and FCP. or St1E AREA EMERGENCY l
' 2. Non-Isolable primary 2. Loop 1 or 2 flRll activity .
status; provide coolant leakage alarm-high with Assess and respond. periodic public updates, through a steam gen- Shirt Supervisor erator rehea t section, determination that leakage is non-Isoiable. , Dispatch radiological monitoring teams with Augment resources by communications equip- activating FCP and LOCs. ment, e I s I I
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RERP Section 4 Issue 5
] ,
Page 18 or 22 1
?
1 TABLE 4.1-3 EMERCENCY ACTION LEVELS (EALs) & CDRRESPONDING ACilDNS SITE AREA EMERCLfg;Y FORT ST. VRAIN NUCLEAR CENERATING STATION EAL (Alarm, Instro- , initiatine Events ment Reading. etc.) PSC Actions $1 ale /Logal Actions
- 7. Fire adversely 7. a) Fire pump 1A Provide release and Evaluate data and arrecting safety start; dose projections initiato ingestion systems, b) Fire Control based on available pathway protect ive Ala rm Pane l plant condition In- actions as aproppriate.
c) Various alarms forma tion and for-according to ar- seeable contingencies. - rected safety system d) Shlrt Supervisor determines rire beyond capability or station starr.
- 8. a) Erriuent monitors 8. Stack monitor Terminate (or recom- Provido press briefings.
detect levels cor- alarm with cor- mend reduction or) responding to greater responding stack emergency class verbally than 50 arem/hr W.B. concentration In- at FCP rollowed by i
; for 1/2 hr, or dications on: written summa ry within greater than 500 m ) RI T3813 7-1, RT4802, 8 hours, mres/hr W.B. ror two & RT7325-1,2 or minutes. at the site greater than or bounda ry under equal to 6.7 x 10 Escalate to CENERAL Maintain SITE EMERCINCY o E meteolglogy pdyof micro Cl/cc l-131 EMERGENCY status untl1 termination (or level _s 5 times b) RT 7324 -1,2 and or reduction or ! the above for thyrold RT 4803 - greater emergency class, t dose rate), than or equal to 6.6 x 10 g micro Cl/cc mixed noble gases , b) These dose rates or are projected based on other plant para- Escalate to CENERAL ; meters or are measured EMERGENCY.
j in the envi rons. , i l ' e i 1 4
y i
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4 RERP Section 4 1ssue 5 Page 19 nr 22 i TABLE 4.1-3 EMERGENCY ACTION LEVELS (EAls) & CORRESPONDING Acil0NS SITE AREA EMERGE _NM FORT ST. VRAIN NUCLEAR CENERATING STATION g EAL ( Alarm, Instru-j init'atino Events ment Readine. etc.) PSC Actions S_t3.te/ Local Acilogs i
- 9. Imminent loss or 9. Situation evident.
l" physical control or
'. the plant due to f security breach.
(Response detailed in station secuirty plan ) ,
- 10. Severe natural 10.
rhenomenon being ex-perienced or projected (with plant f.ot in cold shutdown), sucts as: i a) earthquake greater a) Selsmic Recorder than Safe Shutdown Operate alarm with Earthquake indication or ground motion greater than 0.109 horizontal or greater than 0.067g i vertical, b) riood greater than b) As reported or design levels, observed. c) winds in excess c) average wind volo-city greater tisan 90 or design levels mph or 10 second gusts exceeding 99 mph. d) tornado in excess d) horizontal wind
- 4 or design lovels velocity greater
, than 202 mph.
N
a e - e e i s n i o t 4 c 2 A n 2 o l i r a_ t o c c o e50 L S 2 / e e
' Pue t Rsg a Esa t R1P S_
S N O . I T C A N O G I N T A ID T N S O P G S N E I R Y T s R Q A n O N R o C E E i 3 G N t
- & R E c 1 E G A
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(e. ~ e . g ea RERP Section 4. Issue 5 Page 21 of 22 e I TABLE 4.1-4
'i j [MERGENCY ACTION LEVELS (EALs) & CORRESPONDING ACTIONS CENERAL EMERGENCY
.: FORT ST. VRAIN NUCLEAR CENERATING STATION 1
EAL ( Ala rm, ins t ru- . Initiatinq_Even(3 ment Readine. etc.) PSC Actions 11stellocal Agljona
- 1. a) Errluent monitors 1. Stack moni tor Inform State and/or Provido assistance.
detect levels cor- RT-7324-1,2 a l s rm, o r local authoritics or responding to t rem /hr correspondig dose rates CENERAL EMERGENCY status / l W.B. ' determined with E-500 cause within 15 Initiato immediate public 1 thyro}or 5 ree/hrd ) a t t he ex- or Cutie Pie detector min. or detection, notification or CENERAL clusion area por procedure liPP-56 EMERGENCY sta tus and boundary under and associated graphs. Augment resources by provido periodic public sqiunt meteoro- activating TSC, PCC, updates, logical conditions. ECP, and TCP.
, b) These dose rates Assess and respond.
-t are projected based
.1 on other plant para- Considor/ implement pro-J meters or are measured Dispatch radiological tective actions based.
j in the envi rons, moni toring teams with on current assessment, g communications equipment.
, Augment resources by Provido a dedicated activating ICP and LOCs.
, 2. Loss or physical 2. Situation evident. Individual for plant control or the racility status updates to i (due to security orrsite authorities Dispatch key enorgency 2, breach) and periodic press personnel, including brefrings, monitoring teams, with 3 Other plant con- 3. As determined by communications equipment.
ditions exist that Sh l rt Supe rvi sor. Make senior technical make release or la rge and management starr amounts of radio- available for periodic Dispatch other emergency activity possible, consultation with MRC. personnel to duty stations within a 5-mile Provide meteorological radius and alert others data and dose esti- to standby status, mates I ror actual re-lessos I to ortsite author ties via a dedicated Individual.
c :- -,: 7
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i .: RERP Section 4-Issue 5 Page 22 of 22 TABLE 4.1-4 EMERCENCY ACTION LEVELS (EALs) er CC$RRESPONDING ACTIONS CENERAL EMERCENCY FORT ST. VRAIN NUCLEAR CENERATING STATIOsl EAL ( Ala rm, instru-Initiatino Events ment Readine. etc.) EEC. Actions 11 ale / Local Actiong
': Provide release and Provido orrsite monitoring dose projections based results to PSC and upon Information and fore- Jointly assess theso, seeable contingencies.
Terminate (or recommend Continuously assess reduction of) emergency information f rom PSC Olass by brlering and orrsite monitoring authorities at the FCP, temas with rega rd to rollowed by written Initiating or modifylng summa ry within 8 hours, public protective actions.
. Evaluate data and initiate ingestion
{ pathway protective actions as appropriato. Provide press brlerings. Maintain CENERAL
; EMERGENCY status until termination or
); reduction or emergency y
class, i i i
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y, PUBLIC SERVICE COMPANY OF COLORADO RERP Section 5 FORT ST. VRAIN NUCLEAR GENERATING STATIOM e f 27
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- TITLE: RADIOLOGICAL EMERGENCY RESPONSE PLAN, SECTION 5 NON - CONTROLLED COPY VER!FYlSSUE STATUS WTH COCUMENT CENTER ISSUANCE PR:On TO USE AUTHORIZED b" - - . - ..
BY M_ ff" PORC A EFFECTIVE REVIEW PORc 58 2 ABG141984 DATE 8- Sd- Sk 5.0 Organizational Control of Emeroencies 5.1 The Normal Station Organization is shown, in chart form, on Figure 5.1-1 and is detailed in station Operating Technical Specifications. A shift of 8 operating and 9 security personnel, under the direction of a Shift Supervisor, is on duty at all times (Figure 5.1-2). Duties and responsibilities of operating personnel are set forth in station acministrative procedures. 5.2 The Onsite Emergency Oroanization for the four categories of incident classification is depicted on Figures 5.2-1 and 5.2-2. In the event of an emergency, the on-duty Shift Supervisor has the responsiblity to initiate
. immediate actions to limit the consequences of the emergency and to return the plant to a safe and stable condition. He is, further, assigned the authority for direction of site emergency operations (Emergency Coordinator) and retains this authority until relieved by the Control Room Director or Technical Support Center Director. In this interim caoacity, he is responsible for: classification of the emergency event; initial notification of appropriate governmental emergency response agencies; and, initiation of protective actions l for station personnel. He may confer with FSV and PSC l management for advice or concurrence with initial accident l classification, if desired. (In the event the Shift Supervisor is unable to perform as Emergency Coordinator, the most senior Reactor Operator assumes that role.)
The Emergency Coordinator is responsible for initially classifying the incident, recommending protective actions, initiating corresponding emergency actions, notifying offsite authorities of the incident, and establishing communications with the TSC. Responsibility for the decision for notification and protective action recommendation may not be delegated. 1 Further responsibilities include: diagnosing the accident I concition and estimating radiological exposures based on l - radioactive material releases and prevailing t FORM 372 - 22 3642
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PUBLIC SERVICE COMPANY OF COLORADO ,jetin5 S FORT ST. VRAIN NUCLEAR GENERATING STATION page 2 of 27
- meteorological conditions. To ensure this function is covered at all times, the Shift Supervisor is an authorized Emergency Coordinator. The on-duty Shift Supervisor continues to function as the Emergency l Coordinator at least until the emergency organization is activated.
The Fort St. Vrain Nuclear Generating Station emergency organization operates from three onsite emergency centers Control Room (CR), Technical Support Center (TSC), and Personnel Control Center (PCC). It is supported by three offsite emergency centers - Forward Command Post (FCP), State Emergency Operations Center (State EOC), and Executive Command Post (ECP). The station emergency organization will be manned and operational within 90 minutes after classification of an ALERT or higher level incident. Onsite and offsite emergency organization interrelationships are shown in schematic form in Figure 5.2-3. PSC's role in the offsite (local and state) emergency control centers is diagrammed in Figure 5.2-4 (FCP) and Figure 5.2-5 (State EOC). Augmentation in the form of headquarters support is shown in Figure 5.2-6 (ECP) and is discussed in Section 5.3. The function, responsiblities, and staffing of the offsite emergency organization is also described in Section 5.3 and is shown in Figure 5.2-7. Post-emergency plant recovery plans and organization are described in Section 9.0. Emergency personnel assignments are shown by function. For clarity, normal ' job titles are also indica'2d. Qualification requirements (per the normal titir,) are given in corporate job descrir : ens. 5.2.1 Direction and Coordinatio,: Initial direction and coordination of onsite emergency operations will be the responsibility of the Shift Supervisor, as shown in Figure 5.2-1 and discussed in Section 5.2. This responsiblity will ! remain with the Shift Supervisor until such time as I the emergency organization for en ALERT or higher I level accident is activated (Figure 5.2-2). During an ALERT, or higher level accident, overall l command of PSC emergency operations will be exercised by the Corporate Emergency Director (Vice President of Production) at the FCP. He will provide direction to, and coordination for, the TSC Director (Manager, Nuclear Production) and the l Manager, Nuclear Engineering (as. signed to the State
. EOC). He will coordinate additional headquarters support via the ECP.
F OR M 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO u5
, FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 27 ~
- a. The Corporate Emeroency Director (CED) - (Vice President of Production) is in command of PSC emergency operations and is responsible for direction and coordination of: -
- 1. PSC onsite and offsite emergency functions;
- 2. Interface between PSC and local / state / federal emergency response j activities;
- 3. Transmission of plant status updates and radiological release data to FCP and State EOC emergency response and media l center personnel;
- 4. Notification of state and local agencies concerning recommended protective actions;
- 5. Provision of administrative, technical, and logistic support to station emergency operations; and,
- 6. Continuity of emergency organization I resources.
In the event the Vice President of Production is not available, the Vice President of Engineering and Planning will assume command of PSC emergency operations.
- b. The TSC Director -
(Manager, Nuclear Production) is in command of onsite emergency operations. The TSC Director is authorized to initiate emergency actions, including declaring a particular class of emergency and providing protective action recommendations to offsite authorities. (The alternate TSC Director is the Station Manager). Duties and responsibilities of the ' 'C Director include direction and coordination of:
- 1. The TSC staff, which is responsible for collecting and analyzing the technical information necessary for assessment of plant operational aspects, providing technical counsel 1,n support of the Control Room (CR), and assessment of radiological -elease consequences.
PORM 372 22 3NQ
1 PUBLIC SERVICE COMPANY OF COLORADO FORT ST VRAIN NUCLEAR GENERATING STATION S ftin5 l Page 4 of 27 l I 2. The CR Director (Superintendent of Operations), who is responsible for control of plant operations, assessing j plant operational aspects, and implementing recommended corrective actions. (The alternate for the CR l Director is the Shift Supervisor, ; 1 Training). l 3. The PCC Director (Scheduling / Stores l Coordinator), who is responsible for continued personnel accountability, assembling personnel' for repair / damage control or radiological survey teams, search and rescue teams, reserve operating staff, and establishing radiological control areas as directed. (The alternate for the PCC Director is the Training Supervisor). 5.2.2 Plant Staff Emeroency Assignments Three principal onsite groups comprise the station emergency organization. Each group operates under the supervision of a director' at an emergency center (TSC, PCC, and CR) as discussed in Section 5.2.1. Each center Director is responsible for center communications and for assigning an individual to keep a record of important events, decisions, and actions. Plant staff emergency assignments and functions fcr these centers are summarized in the following paragraphs. Primary and alternate leads are shown for continuous 24-hour operation.
- a. Technical Suoport Center
- 1. Plant Condition Assessment Diagnose plaht conditions, provide recommended corrective actions, and I coordinate systems analysis and procedures. (Primary and Alternate:
Off-duty Shift Supervisors) PORM 372 22 3643
s etion 5 PUBLIC SERVICE COMPANY OF COLORADO ue _ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 27 I 2. Encineerino & Technical Analysis Direct core physics analysis, electrical and mechanical engineering, licensing, procedures development, and system analysis. Maintain liaison with offsite technical support such as NSSS, AE, EPRI. (Primary: Technical Services Engineering Supervisor; Alternate: Senior Plant Engineer)
- 3. Health Physics / Radiological Monitoring Assess ~onsite radiological doses, direct radiological / radiochemical surveys and decontamination actions. (Primary:
Health Physics Supervisor; Alternate: Health Physicist)
- 4. Radiological Assessment Assess offsite radiological doses and consequences, determine potentially affected offsite areas, and confer with -
the Technical Support Center Director and - the Radiological Assessment Coordinator at the FCP regarding plant status, offsite dose computations, and protective l actions (Primary: Senior Plant Engineer; l Alternate: Technical Services Engineer)
- 5. Emeroency Maintenance Determine and recommend repair / damage control and corrective actions for plant mechanical and electrical systems.
(Primary: Superintendent of Maintenance; l Alternate: Maintenance Supervisor - l Electrical)
- 6. Emeroency I&C Supoort ,
Determine alternative I&C capabilities or configurations; repair / install / modify instrument and control equipment. l (Primary: Superintendent of Nuclear l Betterment Engineering; Alternate: l Results Engineering Supervisor) FORM 372 22 3643
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Secti n 5
. PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST, VRAIN NUCLEAR GENERATING STATION Page 6 of 27
! 7. Acministrative & Locistics Succort Provide needed technical documents, communications and analytical equipment, clerical assistance, and food, transportation / housing support.
l (Primary: Nuclear Documents Supervisor; 1 Alternate: Nuclear Documents Specialist)
- 8. Comouter Services Provide technical support in the areas of computer hardware and software development / modification. Provide l assistance to TSC Radiological Assessment i individual as needed. (Primary: Senior Analyst; Alternate: Senior Programmer)
- b. Personnel Control Center
- 1. personnel Accountability Maintain continued personnel accountability, including personnel contamination surveys, control areas, and exposure records. Handle search and rescue efforts, first aid, medical transportation, and personnel decontamination. (Health Physics Technicians, Scheduling /QC staff, and other personnel)
- 2. Operating Staff Support Relieve and support plant operations personnel as necessary in operating plant equipment, processing effluents, and performing emergency maneuvers. (Off-duty operations personnel)
- 3. Maintenance, Repair & Damage Control l Perform mechanical and electrical i
repair / damage control, emergency maintenance, and temporary modifications. (Maintenance staff and I&C Technicians, augmented as necessary by PSC personnel from offsite locations) FORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO hfue $
, FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 27 ~
4 Hazards Control Extinguish fires, purge hazardous gases, combat natural emergencies. (Fire Brigade personnel) During the day shift, the Fire Brigade receives initial direction from the CR Director and is subsequently assigned to the PCC.
- 5. Security
. Coordinate site access security with the Security Supervisor. The Lead Security Officer is the alternate for the Security Supervisor.
- c. Control Room
- 1. Plant Control Direct plant operation to terminate the incident, regain plant control, and minimize accident consequences. See Section.5.2 for further details. (Shift Supervisor)
- 2. Plant Operation Assist the Shift Supervisor in implementing plant corrective actions.
(Reactor Operators)
- 3. Technical Assistance Provide technical analysis / advice and recommend corrective actions necessary to bring the plant to a safe and stable condition. (Technical Advisor) l I
l l h PORM 372 22 3643
~ l PUBLIC SERVICE COMPANY OF COLORADO Secti n 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 27
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5.3 Auomentation of Onsite Emeroency Orcanization Onsite emergency operations are augmented by headquarters support (corporate resources) dispatched directly to the PCC or to an appropriate onsite location. Agreements have been executed with local and Denver-based service organizations to provide ambulance, firefighting, and medical aid services. Augmentation for detailed core physics analysis, thermal-hydraulic analyses, radiation monitoring, dose assessment, and decontamination / radioactive waste disposal will be provided on a contract basis. Headquarters and service agency augmentation and support are described in the following sections. 5.3.1 PSC Headouarters Support Provision for direct augmentation to the staffing of onsite emergency functions by non-station personnel may be quickly accomplished. These personnel may be utilized in support roles to supply additional manpower for repair / damage control teams, survey teams, access control, and logistical assistance. Additional headquarters management, administrative, and technical support requested by the Corporate Emergency Director will be coordinated by tha Executive Command Post Director. The ECP is manned by senior corporate personnel with the authority to activate corporate personnel, facilities, equipment, and financial resources in an emergency situation. The ECP supports PSC personnel stationed at onsite and offsite emergency centers. The ECP is located in Room 620, PSC Headquarters Building, Denver. In the event the ECP cannot utilize this location for any reason, an alternate- facility located at the PSC Lookout Center in Golden, Colorado will be activated. The ECP contains up-to-date copies of station, state, and local government emergency plans, the corporate Emergency Plan, maps of the Fort St. Vrain area and its environs, regional maps, and station layout drawings. Other equipment, facilities and services located within, or immediately adjacent and available to the ECP, include stenographic assistance, reproduction equipment, simultaneous commercial television station monitoring equipment (al.1 VHF channels) and radio-television recording equipment for media announcements. b FORM 372 22 3643
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Secti n 5 PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 9 of 27
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l
- The ECP will be operational within ninety (90) I minutes after classificacion of an ALERT or higher level accident. The ECP staff includes a Director and four functional Managers. The roles and responsibilities of key members of the ECP staff are described in the following sections.
- a. The Director of the ECP - (President & CEO) ,
will assume overall responsiblity for i providing the Corporate Emergency Director with the counsel, expertise, and resources available within the PSC organization. He coordinates emergency assistance, provides reentry and recovery support, station and site modifications review by Nuclear Facilities Safety Committee, and supervises the following ECP emergency operations managers. (Alternate: Executive VP & General Counsel)
- b. The Manager of Technical Support - (Nuclear Design Manager) will provide the Corporate Emergency Director and onsite emergency operations with technical advice in nuclear, mechanical, civil, and electrical engineering.
He provides engineering support, technical experts, and consultants as requested. (Alternate: Nuclear Services Manager)
- c. The Manager of Media Relations - (VP of Public Affairs) will coordinate communications between the ECP and the site, the FCP, the State EOC, and federal emergency operations not included in the site communications system. He assists the Director of the ECP and PSC media relations personnel in preparation of press releases, announcements, and interviews. (Alternate: Manager of Public Relations)
- d. The Manager of Resources - (VP of Accounting l and Corporate Secretr.ry) will coordinate provision of manpower and equipment from within PSC, and from consultants / contractors, to support onsite emergency operations. He provides requested technical and craft manpower; personnel or consultants for engineering / design and construction reviews; temporary housing, office, transportation, and construction equipment; purchasing, financial, legal, and general office support; and, food deliveries and related logistics support to
- designated emergency operations. (Alternate
l VP of Finance & Treasurer) P ' FORM 372 22 3643
PUBLIC SER*.lCE COMPANY OF COLORADO ,[x 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 27
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- e. The Manager of Security - (Manager of Claims, Safety, & Security) will coordinate PSC security operations with public law enforcement agencies. He acquires additional security manpower, hardware, and equipment, as requested. (Alternate: Security Coordinator) 5.3.2 Local Services Sucoort In emergency situations, assistance from outside companies and services may be required. Assistance available from outside companies includes ambulance service to transport injured and/or contaminated 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 10, Appendix A. Table 5.3-1 lists these agencies by the type of service provided. The State RERP, to which participating agencies and PSC are signatory, is cited in lieu of letters of agreement for emergency assistance from other local service agencies. 5.3.3 Contract Suocort Specialized assistance from contractors may also be required in an emergency situation. Contract support may include nuclear steam supply system (NSSS), architect-engineer, construction, dosimetry and laboratory analysis, and decontamination and rad-waste disposal assistance. Provision has been made for selected contract support firms to provide this assistance, on request. Table 5.3-1 lists these contractors by type of service provided. l (Section 10, Appendix A contains Letters of : Agreement covering these contracted services). l 5.4 Coordination with Participating Government Acencies , The State of Colorado, through the Division of Disaster l l Emergency Services (D0 DES), has responsibility for control I i of offsite actions during a radiological emergency. The l concept of operations for discharging this resppnsibility, together with a discussion of action responsibilities assigned to various state / local governmental agencies is contained in the State RERP. Since participating agencies i and PSC are Plan signatories, the State RERP is cited in Section 10, Appendix A in lieu of separate letters of agreement.
- I t
PORM 372 22 3643
, PUBLIC SERVICE COMPANY OF COLORADO a5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 27 ~
Governmental entities having jurisdiction within the 5 mile plume exposure EPZ are the State of Colorado; Weld ; County; and, the towns of Platteville, Johnstown, and i Gilcrest. A brief summary of the involvement and responsibilities of the major governmental agencies is shown in tabular form in Table 5.4.1. For a complete discussion of authority, assigned responsibilities, capabilities, and activation and communication arrangements, refer to the State RERP. 5.4.1 Station personnel coordinate onsite emergency operations with state / local government offsite emergency centers (Forward Command Post and State Emergency Operations Center). The role and ' function of PSC emergency personnel stationed at the FCP and the State EOC are described in the following sections. I
- a. The Forward Command Post (FCP) functions as thc control and coordination center for on-scene state / local / federal emergency response forces. The FCP communicates with the State EOC (the primary point through which the
. Governor exercises overall control and coordination of offsite emergency operations) and with the Weld County EOC (Weld County '
Communications Center) for effective coordination of county forces. The FCP is located in the PSC Garage at Ft. Lupton, approximately 12 miles south-southeast of the Station. Provision is made adjacent to the FCP for a facility to accomodate the needs of the media (State RERP, Annex S). A senior representative of D0 DES is responsible for control and coordination of FCP emergency response activities. 1 Staffing of the FCP, as shown on Figure 5.2-4, consists of authorized representatives of:
- 1. State Division of Disaster Emergency Services
- 2. Weld County Sheriff's Office
- 3. Colorado State Patrol
- 4. Colorado Department of Health
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Radiological monitoring, and health units, as required. FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO n5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 27
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Public information representative.
- 5. Public Service Company of Colorado Vice President of Production Station Technical Liaison Radiological Assessment Coordinator Public Relations Representative l Nuclear Documents Staff
- 6. Others, as notified / required.
The Vice President of Production is in overall command of PSC emergency operations and is the main link between the station and governmental authorities. A PSC technical liaison representative (Primary: Technical / Administrative Services Manager; Alternate: Quality Assurance Manager) from the station, the Radiological Assessment Coordinator (Radiation Protection Manager), one public relations representative from PSC corporate headquarters, and members of the station clerical staff are also assigned to the FCP. Communications between the FCP, the site Technical Support Center, the State Emergency Operations Center, and the PSC Executive Command Post will be accomplished through commercial telephone service and/or radio. The responsibilities of PSC personnel assigned to the FCP include: Providing assistance and substantiated data on site emergency status and conditio.ns; Coordinating company emergency response actions with those of state / local / federal agencies; ' i a Coordinating radiological assessment ! activities between PSC and those of state / local / federal agencies; Providing assistance to the FCP Public Information Coordination Team (PICT) in i the preparation of news and related media releases, and control of rumours in accordance with the PSC RERP Public Information Plan; and, l 1 b FomM 372 22 3643 l
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- Maintaining communications flow between PSC personnel stationed at onsite and offsite emergency centers.
- b. The State Emeroency Doerations Center (State EOC) is the primary point through which the Governor, or his authorized designee, exercises overall control and coordination of emergency response operations through the i Colorado Division of Disaster Emergency :
Services (D0 DES). The State EOC is located in D0 DES headquarters at Camp George West in Golden, Colorado, approximately 40 miles southwest of the Fort St. Vrain Nuclear Generating Station. Provision is made at Camp George West for a facility to accomodate the needs of the media (State RERP, Annex S). Staffing of the State EOC, as shown on Figure 5.2-5, consists of authorized representatives of:
- 1. Office of the Governor
- 2. Division of Disaster Emergency Services
- 3. Colorado Department of Health
- 4. Colorado State Patrol
- 5. Colorado National Guard
- 6. Federal Emergency Management Agency
- 7. Public Service Company of Colorado
- 8. Others, as notified / required PSC staffing at the State EOC includes the Vice President of Governmental Affairs or the l Manager of Nuclear Engineering, the Manager of l Corporate Communications or Media Relations l Director, technical assistance personnel, a radiation specialist, and supporting clerical I personnel.
F OR M 372 22 - 3643
n5 PUBLIC SERVICE COMPANY OF COLORADO ,lc 3 l_ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 27 The responsbilities of PSC personnel assigned te the State E0C include:
- Providing assistance and substantiated data regarding site emergency status and conditions to local / state / federal emergency response agencies assigned to the State EOC; Coordinating company emergency response activities with those of
. state / local / federal agencies; and,
- Providing up-to-date site information to the Public Information Coordination Team (PICT) Chief (Governor's Office representative) and assisting the PICT in the preparation of mutually acceptable news releases, fact sheets, rumor control in accordance with the PSC RERP Public Information Plan, and background material media releases.
5.4.2 In addition to extensive coordination with state / local governmental entities, technical assistance from certain federal agencies in the area of communications, radiological monitoring and laboratory analysis, transportation, weather forecasts, and disaster relief may be required in an emergency situation. The State of Colorado, through D0 DES, will officially request federal assistance. PSC will, therefore, channel contacts with federal agencies (except NRC) through D0 DES. The following agencies will be notified / requested to provide assistance, as necessary:
- a. The Nuclear Regulatory Commission, Office of Inspection and Enforcement, Region IV, and the NRC Incident Response Center Bethesda, MD.
- b. The Department of Energy (DOE) - Radiological Assistance Teams (RAT), Idaho Falls, Idaho and Rocky Flats, Colorado; Aerial Monitoring System (AMS), Las Vegas, Nevada. DOE will activate the Interagency Radiological Assistance Plan (IRAP) as necessary.
- c. Federal Emergency Management Agency ( C A),
Region VIII, Denver, Colorado. t FOmM 372 22 3643
.. ..i. .
8 E . "' o 05 ig FIGURE 5.1-1 T t C NORMAL STATION ORGANIZATION p FORT ST. VRAIN NUCLEAR GENERATING STATION g3 MNAGER vs E NuttEAR gm PRODUCTION 2 55 ao l I z m STATION MNAGER RADIATION PROTECTION m MAGER TECitNICAL/ ADMIN
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' mlNT TR41NING
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_ SUPVRS ENGR y gg$ $ sUPVRs (2) sUPVR suPVR surVR SUPVR SUPVR
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_ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 16 of 27
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Figure 5.1-2 NORMAL SHIFT ORGANIZATION Fort St. Vrain Nuclear Generating Station l SHIFT SUPERVISOR l l TECHNICAL ADVISOR l l l (SRO) l**l l l (1) l l (1)* I I I I i - l
- l l l I
- l I
- l I I l REACTOR OPERATOR l l LEAD SECURITY l l l HP TECHNICIAN l**l (SRO) i I 0FFICER I II (1) I I (1)"I I (1) l I I l l I I I i 1 l l l l REACTOR OPERATOR l l SECURITY GUARDS l l l (RO) l*=l l l l (2)"l l (8) l l 1 I I I I I I I I lE0VIPMENT OPERATORS l 1 I (1) i I I I I I I I I I AUXILIARY TENDERS l l l (1)**l
- I I NOTES:
SRO 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. l ** DURING HOT, COLD, OR REFUELING SHUTDOWN, ONLY ONE RO I IS REQUIRED TO BE ON DUTY. AN INDIV;bdAL WITH AN SRO I LICENSE OTHER THAN THE ON-DUTY SHIFT SUPERVISOR IS NOT l REQUIRED, NOR IS AN AUXILIARY TENDER. LINE OF AUTHORITY l ******** COMMUNICATION P FORM 372 22 3643
x RERP Section 5 PUBLIC SERVICE COMPANY OF COLORADO _ FORT ST VR AIN NUCLEAR GENERATING STATION 1 of 27
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-. Figure 5.2-1 l
' EMERGENCY ORGANIZATION
, (NOTIFICATION OF UNUSUAL EVENT)
Fort St. Vrain Nuclear Generating Station i SHIFT SUPERVISCR" l lTECHhlCAL ADVISOR l l 'l (SRO) l**l ** l l 1,2,3 l l 8 I I I l i 1 - 1 l l ......... I
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- l HP TECHNICIAN l l REACTOR OPERATOR l l LEAD SECURITY l ll [**l (SRO) l*el 0FFICER [
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'4 HEALTH PHYSICS & RADIOLOGICAL ASSESSMENT -
5 REPAIR AND DAMAGE CONTROL 6 HAZARDS CONTROL 7 PERSONNEL ACCOUNTABILITY 8 TECHNICAL ASSISTANCE 1 1 I e FORM 372 22 3643
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__ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 19 of 27 I . Figure 5.2-3 ONSITE-OFFSITE EMERGENCY ORGANIZATION Fort St. Vrain Nuclear Generating Station l TECHNICAL SUPPORT CENTER ) l l
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. FORT ST, VRAIN NUCLEAR GENERATING STATION Page 20 of 27
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, , PUBLIC SERVICE COMPANY OF COLORADO e FORT ST. VR AIN NUCLEAR GENERATING STATION Page 24 of 27 l
- TABLE 5.3-1 LOCAL AGENCY AND CONTRACT SUPPORT SERVICES Fort St. Vrain Nuclear Generating Station Local Acency Suocort Service Volunteer Fire Department Onsite Fire Protection Platteville, Colorado Assistance / Ambulance Service Volunteer Fire Departments Mutual Aid Fire Protection Milliken, Johnstown, Gilcrest, Assistance Colorado Facility Support Support Service Weld County Alternate Personnel Control Greeley, Colorado Center - Johnstown, Colorado Contract Agency Support Service General Atomic Corporation NSSS, Reactor Physics, and San Diego, California Systems Modification Assistance l Other Support Acency Support Service Stone & Webster Engineering Corp. Engineering / Construction /
Denver, Colorado System Modification Assistance Nuclear Power Consultants, Inc. Engineering / Quality Assurance Rockville, Maryland Assistance Proto-Power Management Corp. Technical Assistance - Groton, Connecticut Nuclear / Balance of Plant Systems 1 l I FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ue _ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 25 of 27 TABLE 5.3-1 (Continued) LOCAL AGENCY AND CONTRACT SUPPORT SERVICES Fort St. Vrain Nuclear Generating Station l Other Succort Agency Support Service NUS Corporation Safety-Training Assistance Portland, Oregon Controls For Environmental Chemical-Radiochemical Pollution, Inc. Laboratory Analysis Santa Fe, New Mexico Colorado State University Environmental Monitoring Fort Collins, Colorado Assistance St. Luke's Hospital Medical Treatment /Decon-Denver, Colorado tamination Assistance Dr. Hilding G. Olson Nuclear Engineering Fort Collins, Colorado Consultant Donald T. Klodt Metallurgical Consultant Denver, Colorado l R. S. Landauer, Jr. & Co. Environmental Monitoring, l Glenwood, Illinois Dosimetry Processing l Western Radiation Consultants, Inc. Radiation Protection l Fort Collins, Colorado l EBASCO Services, Inc. Engineering, Construction,
} Golden, Colorado Procurement Assistance l INPO Procurement, Industry l Atlanta, Georgia Support PORM 372 - 22 3643
,. . PUBLIC SERVICE COMPANY OF COLORADO , fd n 5 S
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 26 of 27 TABLE 5.4-1
SUMMARY
OF STATE / LOCAL INVOLVEMENT AGENCY PRINCIPAL RESPONSIBLITIES LOCATION State of Colorado:
- 1) Division of a) emergency planning State EOC (Camp Disaster Emergency b) command & control George West, Services (D0 DES) c) communications Golden, CO) &
d) coordination of Colorado FCP (Ft. Lupton, CD) National Guard & federal assistance
- 2) Colorado Department a) incident dose assessment FCP, CDH HQ of Health (CDH) b) recommendation of (Denver), State protective actions -~ EOC, & deployed c) contaminatien control / personnel decontamination measures
- 3) Colorado Department ingestion pathway State EOC, FCP, of Agriculture (CDA) protective actions CDA HQ (Denver)
- 4) Colorado State a) traffic control State EOC, FCP, &
Patrol (CSP) b) communication and deployed personnel transportation assistance
- 5) Office of the a) issue proclamations State EOC and Governor for emergency Governor's office preparedness (Denver) b) utilize the National Guard -
c) issu evacuation orders d) handi. media relations ? F omu 372 - 22 3643 _ . . . . _ . . _ _ _ _=
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, PUBLIC SERVICE COMPANY OF COLORADO Secti n 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 27 of 27 TABLE 5.4-1 (Continued)
SUMMARY
OF STATE / LOCAL INVOLVEMENT AGENCY PRINCIPAL RESPONSIBLITIES LOCATION Weld County:
- 6) Weld County authorize and ensure County Bldg Commissioners appropriate county (Greeley,CO) emergency planning and response
- 7) Weld County a) handle county EOC & County Bldg Civil Defense communications (County EOC, b) coordinate local Greeley,CO) agency planning c) handle emergency feeding and sheltering
- 8) Weld County a) traffic control FCP and Sheriff b) public notification deployed personnel c) conduct and confirm evacuation d) maintain law and order e
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. _ ._ _7 _ _ _ _. _ _ . . _ _ . . . _ ..___
, ., PUBLIC SERVICE COMPANY OF COLORADO [PSection6
. X FORT Sl. VRAIN NUCLEAR GENERATING STATION Page 1 of 30 FORT ST. VCAIN
- TITLE
- RADIOLOGICAL EMERGENCY RESPONSE PLAN, SECTION 6 NON - CONTROLLED L8f VERIFYISSUE STATUS WITH DOCUVENT CENTER ISSUANCE FR:0F TO USE AUTHORIZED FORY r;.'52567 BY .
p/ / -//-N PORC REVIEW
/ PORC 5 8 2 AUG 141984 EFFECTIVE DATE b- Al* bN 6.0 Emeroency Measures Station emergency measures will be initiated upon, and according to, incident classification. This section identifies segments of the station emergency 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 Emeroency Orcanization The four classes of emergency defined in Section 4.1 require a varying degree and scope of emergency responses. The emergency organization activated in each emergency classification is shown in Figures 5.2-1 and 5.2-2. 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 orguization for a NOTIFICATION OF UNUSUAL EVENT consists of normal shift personnel (Figure 5.2-1). No augmentation is required. For ALERT events, onsite and offsite emergency centers will be manned and activated in situations where the Emergency Coordinator or Corporate Emergency Director deem it necessary. In SITE AREA EMERGENCY or GENERAL EMERGENCY level accidents, onsite and offsite emergency response facilities will, in all cases, be manned and activated. The Plant Emergency Alarms are sounded for ALERT and higher level accident classifications. 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 organization per Section 5.2. l l Upon incident assessment and classification of an UNUSUAL l EVENT, notification will be made to the State (State EOC ! [ and Governor's Office) and to the Nuclear Regulatory 1
, l Commission. Updates are made to keep these agencies E FORM 372 22 3442
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- l PUBLIC SERVICE COMPANY OF COLORADO (PSjetion6 ue
{ FORT ST. VR AIN NUCLEAR GENERATING ETATh0N page 2 of 30
- 1 informed of event status, although activation of offsite i response centers is not expected unless the event i escalates to an ALERT or more severe category. The l initial emergency message for NOTIFICATION OF UNUSUAL l EVENT (Figure 6.1-2) is based upon an agreement between I the Governor of Colorado and PSC.
l Classification of an incident as an ALERT or higher event l requires notification consisting of three telephone contacts as indicated in Figure 6.1-1. The Nuclear Regulatory Commission (Region IV) is notified via " hot l line" (preferably) or commercial telephone service. The state and local emergency response organization is notified by a telephone call to the Weld County l Communications Center after notification is authenticated I by call-back. The PSC emergency organization is notified by a single call to the Public Service Company Operator at I corporate headquarters, who notifies the appropriate fanout list set forth in emergency plan notification procedures. The initial emergency message for ALERT, SITE AREA EMERGENCY, and GENERAL EMERGENCY classes, together with followup messages for these accident levels are contained in Figures 6.1-3 and 6.1-4. Emergency center functions remain constant for ALERT SITE AREA EMERGENCY, and GENERAL EMERGENCY classifications. Personnel / equipment augmentation may vary according to specific circumstances. The functions, as shown on Figure 5.2-2 include: Technical Supoort Center Command (Onsite) Plant Condition Assessment Recommendation of Corrective Actions Radiological Consequence (Dese Projections) Health Physics Assessment Notification / Communications Onsite Protective Action Offsite Communications o PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO (,Sectin6 FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 30 I
- Control Room l
l Assessment of Plant Operating Conditions Implementing Corrective Actions Fire Fighting Direction Personnel Accountability (Initial) Personnel Control Center Personnel Accountability (Continued) Emergency Repair / Damage Control Onsite/Inplant Surveys Radiation Protection (Personnel Monitoring / Dosimetry / Decontamination / Access / Reentry Control) Search and Rescue /First Aid Fire Brigade Security Forward Command Post (PSC functions only) Command (PSC Overall) Government Notification / Communications Radiological Assessment Coordination Logistics Support Media Relations . 6.2 Assessment Actions The ass.ssment of plant conditions, radiation levels, and offsite consequences is initially coordinated by the Shift Supervisor (Emergency Coordinator). Upon relief of the l S'11ft Supervisor by the Control Room Director (Primary: l Superintendent. of Operations; Alternate: Shift Supervisor, l Training) and activation of the Technical Support Center (TSC) and the Personnel Control Center (PCC), these duties will be assumed by the emergency organization described in . Section 5.0. The different types of assessment actions PORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO ,
, FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 30
! are described in Table 6.2-1. Assessment will continue throughout the emergency period. Continued assessment may result in reclassification of the incident and consequent alteration in emergency response actions.
Incidents involving potential or actual release of radioactive materials to the environment (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) require special methods of assessment to ensure that responses are appropriate for protection of the population-at-risk and station personnel. The Fort St. Vrain Nuclear Generating Station has installed capability for measuring radioactive Iodine concentration in the coolant. Post-accident sampling is described in appropriate Health Physics and Radiochemistry procedures. It also has an extensive system for monitoring radioactive materials released to the environment (e.g., gaseous, process liquid, reactor building ventilation exhaust, and steam jet air ejector vent). 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 releases are not monitorable, emergency procedures provide " theoretical worst-case release rates corresponding to the Design Base Accidents outlined in Section 14 of the Fort St. Vrain Nuclear Generating Station FSAR." 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 Room. Additional readout capability is provided in the TSC via plant computer links. In the event that meteorological information in both 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 onsite to the North of . the plant. Guidance for the acquisition of meteorological l data from existing instrumentation and displays, as well as backup data from NOAA tower instrumentation, is provided in RERP implementing procedure RERP-MET, Meteorological Data Acquisition. The methodology and technique used to predict offsite concentrations of radioactive n:M e gases and iodine is summarized as follows: 1 FORM 372 22 3643
.l
PUBLIC SERVICE COMPANY OF COLORADO $ t " ue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 30 I Upon determination that an emergency, or potential emergency, could result in offsite dose consequences, the Radiation Protection Manager, or his designee in accordance with RERP implementing ' procedure RERP-DOSE, "Offsite Dose Calculations"...
- Notes present weather conditions (wind speed and direction, atmospheric stability, cloud cover, and precipitation) and calls the Stapleton Airport National Weather Service to obtain a forecast for the next 12 hours to anticipate changes in weather
. conditions that might affect dispersion and alter the zones affected.
Determines radioactivity release rates by reading the Reactor Building Ventilation Exhaust Stack Monitors. If the monitors are inoperative, or if an anticipated release has not started, an estimate of the release rate is obtained from prepared tables. The basis for these tables is the actual circulating coolant activity and/or 10CFR100 accident siting criteria.
- Selects an atmospheric dispersion graph (corresponding to the downwind distance (s) of interest and the atmospheric stability class) and identifies the dispersion factor for the zone (s) of interest. The graphs consist of plots of dispersion factors (X/Q values) calculated from standard Gaussian plume equations for ground level sources as shown in Meteorology and Atonic Energy l (Reference 1) and based upon USNRC Regulatory Guice l 1.145 (Reference 2).
- Multiplies the iodine release rate by the dispersion factor to obtain an air concentration of radiciodines. He uses the expected plume duration in the zone (s) of interest as the exposure time and calculates the thyroid dose by multiplying the appropriate thyroid dose conversion factor for that i
post-shutdown time by the air concentration and then by the exposure time. He calculates doses by zone and compares the integrated doses to l l Protective Action Guide (Reference 3) Criteria presented in Table 6.2-2. l P vonu an x2.sva
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PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 30 I
- Multiplies the noble gas release rate by the dispersion factor to obtain an air concentration of noble gases. He uses the expected plume duration in the zone (s) of interest as the exposure time and calculates whole body gamma dose by multiplying the appropriate whole body gamma dose conversion factor for that post-shutdown time by the air concentration and then by the exposure time. He calculates doses by zone and compares the integrated doses to Protective Action Guide Criteria presented in Table 6.2-2.
Air concentration levels are verified by field monitoring teams consisting of an HP technician and an assistant deployed in captive vehicles with portable emergency radiological instrumentation including air samplers with silver zeolite cartridges, radiation survey meters, and portable radios on the PSC frequency. These teams are deployed within 30 minutes of activation of the emergency organization, and have the capability to sample radiciodine concentrations as low as 1 x 10 %Ci/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 RERP implementing procedure RERP-FIELD, Field Monitoring Procedure). Unmonitored releases will be *reated as unfiltered releases for the duration of the time that they went un-monitored, and will be assessed by utilization of data provided by the on-line noble gas monitor for circulating activity and reactor pressure instrumentation. These actions are described in detail in RERP implementing procedure RERP-DOSE, Offsite Dose Calculation. 6.3 Corrective Acti.ons l Station procedures contain steps for preventive and/or corrective actions to avoid or mitigate serious consequences of an incident. Instrumentation and control l system monitors provide indications / recordings and automatically control systems necessary for the safe and orderly operation of the station. These systems provide the operator with the information and controls needed to l start up, operate at power, shut cown, and, if necessary, to cope with an abnormal operating condition or emergency, should it occur. Control and display of information from these systems are centralized in the Control Room. The information provided by this instrumentation forms the basis for declaration of emergency classes. I o PORM 372 22 3643
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Secti n6 PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 30 I Corrective actions will also involve response by .ne following onsite organizations:
- Fire Fiohtino Fire Brigades will respond to station fire calls.
If outside assistance is required, a call will be placed to' the Platteville Volunteer Fire Department (VFD). The Platteville VFD will, upon arrival, be escorted to the firescene by security personnel.
- Damace 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. Recovery from a GENERAL EMERGENCY will be handled with the assistance of agencies available for that purpose and the cooperative effort of industrial organizations such as AIF, EPRI, and EEI. The organization for post-emergency recovery is described in Section 9.0.
6.4 Protective Actions Protective actions will be taken to ensure that personnel, l onsite and offsite, are notified and actions initiated for their protection in the event radiation or airborne activity levels exceed predetermined values, or when other situations threaten personnel safety. Onsite actions to protect station personnel and visitors 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, Evacuation, and Personnel Accountability
- a. Onsite Protective actions for onsite personnel will be taken whenever a radiological emergency has occurred, or may occur, which will result 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 onsite personnel in other emergency situations such as fires, 9
POMM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO $,Sectin6
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FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 30 j I floods, and tornadoes where personnel safety is threatened. Notification of onsite personnel will be by actuation of plant alarm systems, telephone calls, and Gai-tronics announcements as applicable. Notification will be accomplished as soon as assessment actions permit a determination of the emergency class and corresponding actions. Personnel will be notified of appropriate actions to be taken at their respective personnel accountability stations.
- 1. personnel Accountability l FSV Visitors Center personnel will be notified within 15 minutes and advised of appropriate protective actions. Site visitors inside the owner-controlled area will be escorted by station personnel to the Security Building where they will be monitored for contamination and normally depart the site. Their escorts will then report to their predesignated personnel accountability stations. Contract personnel will exit via the security building, where they will be monitored for contamination, and report to the Visitor's Centei- to await further instruction. Non-essential station personnel (i.e., personnel not specifically assigned to predesignated emergency functions) are required to l assemble at pre-assigned personnel l accountebility stations where supervisors, or their designees will make accountability checks. Accountability status is reported to the Central Alarm Station (Security Desk in Lobby) which in turn reports to the Shift Supervisor.
l Initial accountability should b'e l completed within 30 minutes. Subsequently, the PCC Director has responsibility for maintaining personnel accountability. Refer to the Administrative Procedures Manual procedure G-5, " Personnel Emergency Response" for specific details of the personnel accountability process. 6 FORM 372 22 3643
u6 PUBLIC SERVICE COMPANY OF COLORADO $, FORT ST VRAIN NUCLEAR GENERATING STATION Page 9 of 30
; 2. Security and Access Control The security program at the Fort St.
Vrain Nuclear Generating Station 1; designed to meet the access control requirements of 10 CFR 73.55. Support personnel reporting to the station during l an emergency may assemble first at the l Personnel Con.rol Center, if the Center i is activated. The entry of required i personnel will be coordinated through l normal security routine, either by the l PCC Director or the Shift Supervisor. Provisions to restrict access to areas of the site cutside the fenced protected area have been made. The PCC Director will assign designated security personnel to control traffic access to the owner-controlled area. Access control will be performed with the aid and cooperation of the Weld County Sheriff's Department.
- 3. Evacuation The PCC Director will assure survey of the designated PCC to determine habitability, establish a controlled area at the appropriate PCC location (either l the Training Center or the Engineering /QA l complex, dependening upon prevailing wind direction), and prepare to receive personnel, should plant evacuation be required.
In the event that radiation levels are greater than, or equal to, 2.5 mrem /hr outside the Reactor Building, or there is unidentified airborne contamination greater than, or equal
~
to, 9 x 10 ' uC1/cc above backround outside of the Reactor Building (i.e., in the Turbine Building), or if conditions are such that the TSC Director deems it circumspect, such as during a SITE AREA or GENERAL EMERGENCY, non-essential personnel will be evacuated from the l plant. I If a plant evacuation was deemed l appropriate, there are two Personnel Control Centers within the Owner l Protected Area to evacuate to. These l FORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO n6 FORT ST VRAIN NUOLEAR GENERATING STATION page 10 of 30
- l PCCs are the Training Center and the i OA/ Engineering Complex. Complete Emergency Kits, including radiological monitoring equipment and field radios are l stored at the Training Center and at the QA/ Engineering Complex.
The selection of a PCC is largely dependent upon the prevailing wind condition and the accessibility of that location. Personnel will be monitored for contamination, and accountability checks will be made by PCC staff as appropriate. Personnel onsite, but outside of the protected (fenced) area, will be notified of the emergency and directed to buildings in areas unaffected by the event. Should evacuation of the site become necessary, privately owned vehicles will be used. Tenants on PSC l property are notified by telephone or l personal contact of actions considered necessary to their protection (PCC procedure emergency call list). l In the event that the two onsite Personnel Control Center assembly areas l are uninhabitable (i.e., radiation levels are greater than, or equal to 2.5 mrem /hr, or there is unidentified airborne activity greater than, or equal to, 9 x 10 pCi/cc above background), non-essential personnel will be directed to evacuate to one of three designated offsite PCC locations. The preferred offsite PCC area is the Johnstown County Shops. The alternate offsite PCCs are the PSC Longment Service Center and the Platteville Firehouse. The PCC Director is responsible for the transport of emergency equipment, including decontamination supplies, necessary to l establish the offsite PCC. Personnel in l the protected area will exit the security building where they will be monitored for l contamination and carded out of the plant. I FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO Secti n 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 30 I 4. Rescue Operations The search and rescue function is handled by trained Fire Brigade or Health Physics personnel. When station personnel are unaccounted for in the initial or subsequent emergency accountability, the Shift Supervisor assigns a search and rescue team to locate and, if necessary, I rescue. personnel, observing the emergency I exposure limits outlined in Table 6.5-1.
- b. Offsite The Emergency Coordinator will recommend
- appropriate initial protective actions to offsite authorities, to include either evacuation or sheltering, as alternatives, based upon consideration of relative benefits of the alternatives. The action which affords the greatest amount of dose avoidance for accidents (where projected or measured offsite doses are expected to exceed Protective Action Geides -
Table 6.2-2) will generally be preferred. However other factors such as release duration, mobilization time relative to plume arrival time, or adverse weather may be important considerations affecting the decision. 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 USEPA l Protective Action Guides (Reference 3) 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. Estimated sector evacuation times are shown in Appendix C, Figure 10.C-2. These evacuation times were formally published in detail in PSC report
" Evaluation Time Study of the 10-Mile Radius Area About the Fort St. Vrain Nuclear Generating Station," as transmitted to the U.S. Nuclear Regulatory Commission April 1, 1981 (P-81110). These estimates have been modified in RERP implementing procedure RERP-PAG, Protective Action Guideline l Recommendations, to account for use of the tone alert Early Warning Alert (EWA) System.
F ORM 372 22. M43
, . PUBLIC SERVICE COMPANY OF COLORADO (,5fd n 6 1
, ORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 30 h
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. Approximate initiation times for these protective actions are shown in Table 6.4-1.
The means of public notification is the use of tone alert NCAA weather radios distributed to residents living within the plume exposure EPZ (5 mile radius). A brief prepared message is broadcast over the radio issuing general instructians regarding protective actions and informing the public to tune to a local Emergency Broadcast System (EBS) radio station for further information. Additional coverage is provided, if required, by personal . notification by Weld County Sheriff's ' l Department personnel (with possible l augmentation by the Platteville Volunteer Fire l Department). Notification times are stated to approximate 15 minutas. Content of messages for the public and the decision to implement notification means is a State of Colorado responsibility (State RERP, Annex C). PSC emergency procedures provide for prompt notification of state, local, and federal agencies and keeping these agencies tipdated on the overall status of the emergency. PSC will coordinate onsite actions with local, state, and federal agencies involved in offsite emergency response actions. Notification of offsite businessmen, property owners and tenants, school administrators, recreation facility operators, and the general public within the emergency planning zone will be accomplished by local tone alert radio or emergency forces, as noted in the State RERP. 6.4.2 Use of Cmsite Protective Ecuipment and Suoplies 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 Table 6.4-2. Radiothyroid protective drugs in sufficient quantity to administer to 100 employees is stockpiled at FSV. Criteria for issuance and location is noted in Table 6.4-2. l l s ronu 372 22. as43 l l
PUBLIC SERVICE COMPANY OF COLORADO Secti n6
; FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 of 30 l
1 6.4.3 Contamination Control Measures l
- a. plant Site Measures will be taken to prevent, or j minimize, direct or subsequent ingestion of '
radioactive materials deposited within the exclusion area. As necessary, affected areas will be isolated. Details of contamination control measures for onsite areas are contained in station prc:edures. The following is an outline of those procedural controls:
- 1. Radioactive Contamination of Personnel Controls have been established to insure that levels of removable ,
contamination outside radiologically l controlled areas will be maintained ' at less than allowable limits of 10dpm/200cm2 alpha activity and 100dpm/100cm2 beta gamma activity. The environment of personnel working within radiological control areas are supervised by Health Physics personnel. Radiation Work Permits (RWPs) may be required for personnel in such areas. Specific instructions, precautions, and limitations are listed on RWPs. Protective clothing is required for individuals entering contaminated areas. Individuals leaving radiological control areas are monitored for contamination upon departure. Quarterly integrated accumulations of radionuclides in the body will not exceed accumulation levels which would result from exposure to the maximum permissible 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. l l . PORM 372 22
- 3643
PUBLIC SERVICE COMPANY OF COLORADO a6 { FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 30
- Exposure to airborne concentrations higher than the MPC will be prevented or avoided. If exposures are necessary, wearing appropriate, properly fitted re spiratory protective equipment will be required, as determined by Health Physics. Periodic air samples will be taken in selected operational and work areas to ensure that MPC levels are not exceeded.
- 2. Radioactive Contamination of Eouipment
- 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.
- Equipment and tools will be unconditionally released for use outside the area only if removable contamination and radiation levels are less than allowable limits previously stated.
- Removal of material from radiological control areas with radiation and contamination levels in excess of specified limits must be approved for release by Health Physics 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.
- b. Offsite For areas beyond the site boundary, Colorado l Department of Health (CDH) radiation monitoring teams will identify levels and l control access. Until CDH teams arrive for i l dispatch, Public Service Corr.pany EPZ teams may l l be dispatched from the PCC to perform offsite l monitoring. For areas where public access normally occurs, criteria for offsite arcas
, will be applied. Criteria and measures for E conu an 22. as4s l
PUBLIC SERVICE COMPANY OF COLORADO Secti n 6 g FORT ST. VRAIN NUCLEAR GENERATING STATION Page 15 of 30
~
contamination control in offsite areas are detailed in the State RERP. 6.5 Aid to Affected Personnel 6.5.1 Emeroency personnel Exoosure Criteria Exposure records are maintained for station personnel at each emergency center. This information will be utilized in determining emergency team assignments. Criteria used for limiting doses to emergency workers are based on I recommendations of the USEPA (Reference 3) and are shown in Table 6.5-1. Emergency workers will carry self-reading dosimeters in addition to film badges. Emergency dosimetry services will be provided through contract with R.S. Landauer Corporation. 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 PCC 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 existing RERP implementing procedures (see RERP-EXP), and shall be given only after consultation with the senior Health Physics representative at the TSC, and under direction of the TSC Director. The PCC 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 (per USEPA recomniendation). The PCC 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. At the TSC, l the TSC Director is responsible for the issuance of l dosimeters as needed, and ensuring the ongoing accountability of each worker's dose. 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 personnel onsite who FORM 372 22 3643 s
Secti n6 PUZLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION page 16 of 30
. l I are trained in first aid and decontamination procedures. In addition, onsite decontamination areas are equipped with decontamination facilities and other specialized equipment. Personnel found to be contaminated (any detectable activity above background) will undergo decontamination under the control of Health Physics procedures. Where l contamination of large or open wounds is involved, personnel will be immediately transported to designated medical facilities offsite where they will receive prompt medical attention in accordance withthe FSV Medical Emergency Plan.
Each emergency team will include members trained in first aid. First aid kits are available at onsite locations in accordance with PSC policy specified in General Instructions, as well as in the onsite first aid facility. 6.5.3 Medical Transoortation Injured / contaminated personnel who require medical attention will be transported to St. Luke's Hospital by the St. Anthony's Hospital Flight for l Life, or by Weld County Ambulance Service. A personal vehicle may be utilized if the situation necessitates. Ambulance crews have been trained to , handle contamination cases. PSC Health Physics personnel will accompany contaminated patients to the hospital. 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 Canver. 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. Hospital staff at St. Luke's are trained to treat contaminated patients (Section 10, Appendix A).
~o llowing decontamination, personnel suspected to have ingested radionuclides will undergo whole body counting at PSC or COH facilities. Communications l between FSV and fixed medical facilities are via commercial telephone and are handled in accordance with the FSV Medical Emergency Plan.
PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO Secti n 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 17 of 30 '
- REFERENCES (1) Slade, D.H., ed., Meteorology and Atomic Energy - 1968, USAEC, July 1968.
(2) USNRC, Regulatory Guide 1.145, Atmospheric Dispersion Models For Potential Accident Consequence Assessments at l Nuclear Power Plants, Revision 1, November 1982. (3) USEPA, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, June,1980. (4) USEPA, Appendix D to the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, Technical Bases for Dose Projection Methods, January 1979. n ? PORM 372 22 3643
c. e-- -
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- FIGURE 8.1-1 h NOTIFICATION FANOUT ,C
! FORT ST. VRAIN NUCLEAR GENERATING STATION O CONTROL -aE x l ROOM a
ss eo I t . I *9' z
- NRC PSCO ,, 8o I REGION OPERATOR E EE
) ly WELD COUNTY PSCo I [ l3 E$ 9 l COMM FACILITY ~ CENTER DIRECTORS j? i OR ao i STATE LEAD G8 RERP REPS E@ FANOUT i >
- ALTERNATES 8 i i l STAFF JE]
, CD C D k H m .f o f. a O , 8
- l i
= PUBLIC SERVICE COMPANY OF COLORADO $PSetion6ue . FORT ST. VR AIN NUCLEAR GENERATING STATION Page 19 of 30 ~ 1 Figure 6.1-2 INITIAL MESSAGE CONTENT (NOTIFICATION OF UNUSUAL EVENT) Fort St. Vrain Nuclear Generating Station l A. The Emergency coordinator and first management contact will I complete the following information jointly: l 1. Name and identity of caller l 2. Date of Event Time of Event l 3. General Category of Event l Unplanned Radiological Release to Reactor Building l Fuel Failure l Fire l Natural Phenomenon (circle one) l Earthquake Flood Tornado Winds l Unusual Hazards (circle one) l Aircraft Explosion Toxic Material l Other (Specify) l Spent Fuel Incident i 4. Description of Event I l 5. Actions Taken I l 9 9 romu sta 22. as43 a emg. p 4L y
- me *- w *** se et are au.*,+y m t -+ *e ; e % * **s**
- s. 9e eg: 4 -we*= . . , - - .e . < e . se + = .m e- ..m. e.,.e p . .,
= PUBLIC SERVICE COMPANY OF COLORADO ,y m 6 ; FORT ST. VRAIN NUCLEAR GENERATING STATH3N Page 20 of 30 1 ; 6. Status: '
l I l Under control by onsite staff, no offsite l l assistance anticipated. l Under control by onsite staff. Will keep State and l NRC advised. l Offsite assistance may be required. Will advise. l (See Item 7.) l Offsite assistance required. (See Item 7.) l 7. If offsite assistance is anticipated or required, describe l assistance that has been or may be required: l l l l l l l 8. At the present time, the event does not involve offsite
! release or the potential for offsite releases that would l affect the general health and safety of the public.
l B. The Emerger.cy Coordinator will make notifications as follows: l l l Contact with State E00 (279-8855) and Governor's Office (866-2471)[ ll or Mansion (837-8350) l ll l l 1. READ the following statement vernatim: l "THIS IS A NOTIFICATION OF AN UNUSUAL EVENT AT THE l FORT ST. VRAIN NUCLEAR GENERATING STATION. THIS l NOTIFICATION DOES NOT REQUIRE ACTIVATION OF l EMERGENCY RESPONSE CENTERS. THIS NOTIFICATION l REQUIRES VERIFICATION OF RECEIPT BY THE STATE. l VERIFY BY CALLING 571-7436 or 785-2223." l 2. READ all the information recorded in Step A (Page 1 of l this ATTACHMENT) l i l b FORM 372 22 3H3
. . . . . . ~ . . . . .
g r,, , _ .-
PUBLIC SERVICE COMPANY OF COLORADO Secti n 6 FORT ST. VR AIN NUCLEAR GENERATING STATION Page 21 of 30 l 3. RECORD the following information: l Name of State EOC contact Date/ Time l Name of Governor's Office / Mansion Contact l Date/ Time l Call back verification from State ECC, Date/ Time ' l Call back verification from Governor's Office / Mansion l Date/ Time l I 1 I I l l Contact with NRC Operations Center (Hot Line or 202-951-0550) l I I I l (Alternate means of notification are given in Attachment 1.) l l 1. READ the following statement verbatim: l "THIS IS NOTIFICATION OF AN UNUSUAL EVENT AT THE l FORT ST. VRAIN NUCLEAR GENERATING STATION AT l PLATTEVILLE, COLORADO. THIS NOTIFICATION APPEARS l TO BE REQUIRED PURSUANT TO 10CFR50.72, PARAGRAPH l (a)(3). THIS NOTIFICATION DOES NOT REQUIRE l ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE l ORGANIZATIONS." l 2. READ the NRC Operations Center all of the information l recorded in Step A (Page 1 of this Attachement). f l 3. RECORD the following information:
} Name of NRC Contact Date/ Time
RERP S:ction 6
. PUBLIC SERVICE COMPANY OF COLORADO Issue 7 ~
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 22 of 30
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.l FIGURE 6.1-3 l NOTIFICATION OF EMERGENCY EVENT l (INITIALMESSAGECONTENT) l Fort St. Vrain Nuclear Generating Station l A. The Emergency Coordinator will complete P2ges 1 and 2 of this l attachment with the assistance af the first management l contact. ,
l 1. This is (Nime) , Shift Supervisor at the Fort St. l Vrain Station. l 2. At (Time) we experienced an (ALERT, SITE AREA l EMERGENCY, GENERAL EMERGENCY) Class in:icent. l 3. aj There is NO, repeat NO, radioactive release taking l place, and no speciaTprotective actions are - l reccamended at this time. I E l b) A small release H taking place, but at this tip l N_0 protective actions are recommended and are not I anticipated to be. I E l c) A radioactive release H, repeat H, taking place, l and we reccamend that people in areas l remain indoors with l windows and doors closed. I E l d) A radioactive release H, repeat M, taking place, l and we recommend that evacuation of areas l be considered. l 4. Further information on incident conditions will be l provided in followup messages. l 5. Personnel Control Center to be located I A FORh4 372 22 3843
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- - - - , ww w ' '
RERP Section 6 PUZLIC SERVICE COMPANY OF COLORADO Issue 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 23 of 30 l FIGURE 6.1-4 - l NOTIFICATION OF EMERGENCY EVENT Fort St. Vrain Nuclea.r Generating Station 1 l l l l l l I SUPPLEMENTAL INFORMATION l , I I I l l NOTE: This information is to be supplied to the NRC and the Colorado i l Department of Health when requested. The radiological . ! l data can be determined as specified in RERP-DOSE.
]
l 1. Date and Time of Incident l 2. Class of emergency (ALERT)(SITE AREA EMERGENCY) l (GENERAL EMERGENCY) l l 3. Type of release (airborne, waterborne, surfcce) l 4. Estimated duration of release (Hours) l, 5. . Current release rate: . I Noble Gas C1/sec; Iodine C1/see 1 6. Estimated curies released: l Noble Gas Ci; Iodine Ci
~
l 7. Wind Velocity _ MPH, from degrees. l to degrees, Air Temp 'F ) l 8. ' Stability Category . Form of Precio. l l 9. Oose rate at EAB: WB rem /hr; Thyroid rem /hr l 2 Miles: WB rem /hr; Thyroid rem /hr l 5 Miles: WB rem /hr; Thyroid rem /hr l 10. Projected dose at EAB: WB rem; Thyroid rem l 2 Miles: WB rem; Thyroid rem l 5 Miles: WB rem; Thyroid rem 1 l h i 1 POMM 372 22 3M3
. ~ . _ _ _ . . . _ . , _ . _ .,..
u6 PUILIC SERVICE COMPANY OF COLORADO , FORT ST. VR A1N NUCLEAR GENERATING STATION Page 24 of 30 l 12. Areas expected to be impacted by release l l l 13. Estimate of any surface radioactive contamination I l 14. On-site response actions under way l l 15. Recommended Protective Action based on the projected dose at the i EAB (Read appropriate Protective Actions) l Projected Dose Recommended l (rem) Protective Action l Whole Body <1 No planned protective actions. State l Thyroid <5 may issue advisory to seek shelter l and await instructions. Monitor l radiation levels. l Whole Body 1 to 5 Take shelter and consider selective Thyroid 5 to 25 l l evacuation. Monitor radiation l l levels. Establish Controlled Area ' l and limit access. I Whole Body 5 and Conduct mandatory evacuation. l above Monitor radiation levels and adjust l l Thyroid 25 and area for mandatory evacuation based i I above on these levels Control Access. l ( l 16. Prognosis for worsening of event l 17. Date and time of report ! I 1
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Issue F Page 28 or 30 1 TABLE 6.4-1 initiation Times for Protective Actions for the General Public l Approximate flyltlation Time Exoosure Pathway eq11g_n to be Initialed 0 - 4 Ilours inhalation or gases or Evacuation, shelter, access control, resp i ra to ry particulates protection, prophylaxis ( thyroid protection). Di rect radiation Evacuation, shelter, access control. 1 4.- 48 Ilours Milk Take cows 000 pasture, provent cows f rom drinking surface water, quarantino contaminated milk, l utilize stored reeds. l ' { liarvested fruits Wash all produce, or impound produce. and vegetables
' Drinking water Cat off contaminated suppIles, substitute l
From other sources. Unharvested produce Delay harvest until approved. 2 - 14 Days Itarvested produce Substitute uncontaminated producn. 4 . Milk Discard or divert to stored products, + such as cheese. 2 Drinking wate.- ri t ter, demineralize, test. 1 J I e e
p- . te a e- "g e ,: t: REstP Section 6 issue 7 Page 29 or 30 TABLE 6.88-2 Use of Protective Equipment and Supplies Criteria for Lau lpme_n_t lesuance Loga t f ort Mqa,ns of DA tr_lbutigg 4
. I 1) rull race Canister As neerled by onsite al Selected Frergency a) Issued at Personnel ! Resp i ra tor Emergency Teams in areas Monitoring Kits Control Center ' or high alrborne radio- b) Respiratory issue h) Picked up at nearest activity Lockers-Turbine Deck, station as di rected , by Health Physics l Pe rsonne l .
- 2) Scir-Contained a) Inhalation hazard during a) Control Room a) Used as needed by Breathing Apparatus fire righting b) Various Areas in ope ra to rs.
. b) Airborne radioactivity in Station b) Issued as needed by J excess or administratively llentlh Physics l set levels Personnel. ! c) Toxic gas hazard 4
j 3) Protective Clothing As needed in areas or a) Various Areas of a) Isst*ed as needed by j (Cove ra l l s, Hoods, known contamination ties station. Ilenith Physics { Boots, Cloves) b) Emergency Kits Personnel, b) Issued at Personnel , Control Center. 1
- 4) Alr-red Respirator Airborne radioactivity a) C e trol Room a) Used as required by
; in excess or administratively b) Respiratory lasue ope ra to rs.
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- 5) TilYRO-I? LOCK Airborne radiolodine a) . Respi ratory issue issued only by floalth (Potassium lodide) concentrations elevated Lockers-Turbine Deck Physics Personnel tablets. (130 mg) to the extent that b) Emergency hits at under direction nr l an Individual properly Training Center and the Radiatinn Protection fitted with respiratory QA/ Engineering complex Manager with consent or l protection may De raCllities ( PCCS). the PSC Medical Department, expected to receive a thyroid Inhalation dose in excess of 10 rem (Refer '
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l PUBLIC SERVICE COMPANY OF COLORADO RERP Section 7 FORT ST. VRAIN NUCLEAR GENERATING STATION
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; TITLE: RADIOLOGICAL EMERGENCY RESPONSE plan, SECTION 7 G"
%e qgeWS ISSUANCE hhf, f.//.ff PORC '
EFFECTIVE REVIEW PORc 5 8 2 AUG 141984 DATE $- 2.I - $ 9 7.0 Emercency Facilities and Eouiement This section describes: emergency control centers; onsite and offsite communication systems links; assessment equipment and facilities; protective facilities; first aid and medical l facilities; and da age control equipment and supplies. 7.1 Emeroency Control Centers 7.1.1 Technical Support Center (TSC) Site emergency command activities will be centered in the Technical Support Center (TSC) located immediately aojacent to the Reactor Building and within short walking distance to the Control Room. The TSC is equipped with intercoms, telephones, NRC hotline, dedicated Health Physics Network (HPN) telephone, telecopier, and radios for l communications with the CR, Personnel Control I Center (PCC), and Forward Command Post (FCP). The TSC is equipped with a CDC-1700 terminal for visualization of plant parameters and offsite dose calculations, essential drawings, specifications, and procedures. Radiation monitoring equipment, protective clothing, communic ~ations equipment, portable lighting, protective breathing apparatus, , and first-aid equipment are located in Emergency l Kits. The TSC meets habitability requirements similar to those imposed upon the CR. l 7.1.2 Forward Command Post (FCP) The Forward Command Post is the focal point for the coordination of onsite and offsite emergency response Management and technical activities. l personnel assigned to the FCP are responsible for protective action recommendations end liaison with offsite authorities and response facilities. The FCP serves as the point from which the Corporate . Emergency Director (CED), Vice President of FORM 372 22 3642 .e- -
PUBLIC SERVICE COMPANY OF COLORADO RERP 3'Cti "7 Issue 6 { FORT ST. VRAIN NUCLEAH GENERATING ETATION page 2 of 24
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Production, exercises overall control of the FSV Emergency Response Organization. l The FCP has work space allocated for PSC emergency personnel, state and local personnel, and the NRC. The FCP is adequately equipped with dedicated phone lines, PSC PBX phone lines, commercial phone lines, radio, and telecopy facilities to provide efficient communications with the TSC, ECP, State EOC, NRC, and the Weld County Communication Center. Onsite-offsite communcations are channelled through the TSC and FCP. The FCP is located at the PSC garage facility in Ft. Lupton, well out of the plume exposure EPZ. : Generally, the FCP will be activated and manned for l an ALERT or more severe incident classification. (There are cases where, at the ALERT , classification, activation of the FCP is not I neces sa ry. This is at the discretion of the Corporate Emergency Director, based upon his assessment of the situation.) There are plans to equip the the FCP with a CDC-1700 terminal to provide rapid access to plant parameters and to provide for offsite dose calculations. Briefings with the media are to take place at the Ft. Lupton Methodist Church, located in close proximity to the FCP. 7.1.3 Personnel Control Center (PCC) The primary and secondary locations for the Personnel Control Center (PCC) are the Training Center and the QA/ Engineering Office Complex, respectively. Emergency radiological monitoring equipment, first-aid and decontamination equipment, protective clothing, communications equipment, camera, portable lighting and protective breathing l apparatus are stored in emergency kits at both l onsite locations. There are three' desicnated offsite areas which may be utilized as the PCC if it becomes necessary to evacuate the onsite locatien(s). The preferred alternate offsite location is the Johnstown County Shops. The other alternate offsite PCC locations are the Longmont PSC Service Center and the Platteville Volunteer Fire Department. Routes to these locations are shown in RERP implementing procedura RERP-PCC, Personnel Control Center Procedure. 4 FORM 372 22 MW3
3 PUBLIC SERVICE COMPANY OF COLORADO ,f*i"7 { .' FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 24 7.1.4 Control Room (CR) Emergency assessment and control is initially directed from the CR by the Shift Supervisor prior i to activation of the TSC. The CR, located adjacent I to the Reactor Building, is designed to be habitable curing Design Basis Accidents. The CR contains full plant instrumentation, technical drawings, protective breathing apparatus, radio, telephone, and intercom systems. Emergency radiological monitoring equipment and protective clothing are located nearby. 7.2 Communications Systems : The primary station-offsite link is between the TSC and the FCP. Communications between the station and the FCP consist of commercial telephone service backed by two-way radios. From the FCP, messages are relayed to designated l agencies via Weld County, Colorado Division of Disaster and Emergency Services (D0 DES), and Colorado National Guard radio communication systems. Two way radios will be used to maintain communications between the TSC and Emergency Monitoring Teams. Primary telephone and radio communication links between the TSC and other emergency -- centers are shown on Figure 7.2-1. For a comprehensive discussion of overall emergency response communications, refer te Annex F of the State RERP. PSC, D0 DES, and Weld County Communcations facilities are manned on a 24-hour basis. These are the principle entities involved in the notification fanout. 7.3 Assessment Facilities Emergency measures described in Section 6 depend upon the availability of the monitoring instruments and laboratory facilities necessary for assessment of problems. This section describes onsite and offsite facilities and { monitoring equipment used in intial and continuing assessment. j I 7.3.1 Onsite Systems and Eouioment
- a. Geophysical data are grouped into meteorological and seismic categories, t
- 1. Meteorolocical Monitors l
l Information is obtained from installed instrumentation on the primary 60 meter meteorological tower with readout in the CR. The fol owing information is l obtained: wind direction, windspeed, i i FORM 372 22 3643
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5
, , PUBLIC SERVICE COMPANY OF COLORADO ,lCSI"7 1
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 24 I standard deviation of wind direction (sigma theta), precipitation, dewpoint, temperature, and temparature differential witn 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 l onsite 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 directions. The system determines whether operating basis or safe shutdown maximum accelerations are exceeded in any of three directions.
- b. Area and process radiation :nonitoring systems are divided into seven basic groups.
- 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-Mue)ler tube as a detector and has a self-contained check source. The area monitors share two common annunciators, one which may be 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.
- 2. Equiement Monitors These monitors determine radiation levels in specific effluent streams. Rsdundant monitors are provided separate power sources.
FORM 372 22 3M3
PUBLIC SERVICE COMPANY OF COLORADO RERP Section 7
. Issue o FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 24 l
I 3. Licuid Monitors These devices are specifically designed to monitor liquid effluents. They utilize gamma scintillation detectors consisting of an NaI(Tl) crystal optically coupled 'to a photomultiplier tube.
- 4. Gas Monitors These monitors consist of a plastic Beta scintillator which is coupled to a photomultiplier tube to monitor effluents in the gaseous phase.
- 5. Particulate and Iodine Monitors These monitors continuously draw a portion of the airborne affluent 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 be counted and isotopically analyzed on a multichannel analyzer.
- 6. Emeroency 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 loss of power to the normal operating stack monitors.
- 7. Reactor Buildino Ventilation Exhaust Stack Monitor This system monitors exhaust air from the )
reactor building for Beta particulates and Iodine-131 contaminants. t FORM 372 22 ;M43
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3
. . PUBLIC SERVICE COMPANY OF COLORADO ,jti"7 )
[ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 24 D I c. System Monitors These monitors detect and/or control problems within plant systems. These may be pressure detectors, heat detectors, flow elements, heat rise detectors, or similar devices designed to monitor plant parameters. Many of these detectors are capable of initiating control actions to prevent or mitigate damage or release of radioactive material.
- d. Fire protection Systems There is an extensive Fire Protec+. ion System in operation at Fort St. Vrain. The Pyralarm .
Fire Detection System is designed to detect fires in the Three Room Control Complex (Control Room, Auxiliary Electric Room, and 480V Room), G-Wall Cable Area, J-Wall Cable Area, and the Reactor Building. These detectors are smoke detectors. In addition, s there are Fixed Heat Detectors and Rate of Heat Rise Detectors serving other parts of the station. Fire extinguishing is by use of Halon System (Three-Room Control Complex), or sprinkler / deluge systems with either automatic or manual initiation. Specific information regarding Fire Detection / Suppression at FSV is contained in the System Abstracts (System 45), System Operating Procedures (SCPs), and in the Administrative Procedures (P-8).
- e. Radiation i.nalysis Radiochemical laboratory equipment, radiation monitoring stations, and fixed air sampling stations provide capability for detailed, isotopic analysis.
- f. Portable Survey Instruments These instruments provide flexibility and backup capability for radiation measurements in areas not served by installed monitors or where installed monitors may be inoperative.
FORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO Section 7
',' FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 24 I Specific equipment ^ and their locations for Fort St. Vrain onsite radiological assessment is summarized in Table 7.3-1.
7.3.2 Offsite Systems and Ecuipment The environmental radiological monitoring program for the Fort St. Vrain environs is provided under contract by Colorado State University (CSU). It consists of a comprehensive sampling system to monitor radioactivity in the ecosystems and atmosphere near the station. Biota samples are routinely collected and analyzed, as are air, water, soil, precipitation, vegetation, and milk samples. The agreement with CSU includes provision for environmental monitoring in the event of an emergency. In the event of an emergency, CSU can respond within four (4) hours. CSU also has facilities for radiochemistry and gamma spectrometry which would be accessible if required. Weather observations and forecasting may also be obtained through the National Weather Service (NWS) radio or from the Stapleton Airport National Weather Service Station. Offsite factlities are summarized in Table 7.3e2; - - 7.4 Protective Facilities and Equipment Control Room shielding and ventilation are designed to allow personnel habitability during Design Basis Accident [ conditions. The TSC is located 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, respiratory equipment, protective clothing, and portable lighting are available near the CR. Communications equipment is in the CR. 7.5 First Aid and Medical Facilities 1 Necessary treatment supplies are located at the First-Aid Station on level five of the Turbine Building immediately adjacent to the West Building entrance. In the event of l an emergency, an alternate first-aid a ea is provided in l the PCC. First-aid treatment of injured individuals will be administered by trained personnel. Advanced medical care, if required, will be obtained by transporting the individuals to St. Luke's Hospital and/or North Colorado Medical Center. (Section 10, Appendix A contains agreements with offsite medical facilities). a pomu 372 - 22 >>u
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RERP Section 7 PUBLIC SERVICE COMPANY OF COLORADO Issue 6 FORT ST. VR AIN NUCLEAR GENERATING STATION Page 8 of 24
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7.6 Damace Control Eouipment and Sucolies Fire hose stations, extinguishers, and hydrants are strategically located throughout the station for use in the event of fire. Self-contained breathing apparatus (SCBA) 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. A chlorine container repair kit is available to seal the cover on a chlorine cylinder in the event of a valve leakage. Selected equipment spare parts are stored in the warehouse for equipment repair. G i FORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO RERP Issue 6 Se d on 7 z FORT ST. VRAIN NUOLEAR GENERATING STATION page 9 Cf 24 FIGURE 7.2-1 l PRIMARY AND SECONDARY COMMUNICATION LINKS ONSITE - OFFSITE EMERGENCY OPERATIONS Fort St. Vrain Nuclear Generating Station CONTROL RDOM ooooooooooooooooooooooo p oooe , _____ o ----a - CR Director p. s.-.
- ll :: Il PERSONNEL CONTROL p PSC
- CENTER *l s NONITORING TEAMS *l l PCC Director TECHNICAL .
tacer d SUPPORT CNTR Il E TSC Oltector l
-l l
- DNSITE
_ p
= NRC REG 10N IV o
{ ,o , (,g[g pgg IELD COUNTT l
. o I Corporate l COMMUNICATIONS "" j ooo, NRC HEA000ARTERS p e, o
- Emergency CENTER Dirtetor Dispatcher P
STATE EMERGENCY EIECUTIVE OPERATlONS CENTER 3 COMMAND POST huclearProjects ECP Director 1 Manager
@ PRIMART
@ SECONDARY TELEPHONE (OPEN LINE) "T EACKUP STATE R1010 SYSTEM
-- TELEPHONE STATE LOCAL EDVERNMENT
...... - PSC INTERCon SYSTEg STATE PATROL PSC cal.TRONICS SYSTEM y gfgg
- PSC RADIO ooooooo NOT LINE FORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO RERP Section 7
# Issue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION page 10 of 24 ~
TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Description and Functional System Location Acolicability _
- 1. Geoohysical Monitors l Meteorological Wind Speed Indicators Measures Wind Speed 0 l located North of plant 58m above ground i on 60m toyer North of level and 10 m '
the plant. above ground level. Wind Speed Indicator Measures Wind Direction located North of plant @ 58m and 10m above on 60m tower-Same ground level i Instrument as previous l I listing Delta Temperature Sensors Measures temperature I located on 60m tower differential between north of plant 10m and 58m elevation i Rain Guage on 60m Measure precipitation tower ) i Ten Meter Tower Windspeed, Wind direction Provide backup I temperature, Solar Radiation, Meteorological para-l etc. located North of meters (Operated by plant. NOAA)-available via 1 data logger, modem dial up (see RERP implementing proce-dures), or via remote readouts at tower. Strong Motion 2 Detectors Below PCRV Record gound Accelegraphs 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 Control Room. 9 7Omu 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO Section 7
. FORT ST, VRAIN NUOLEAR GENERATING STATION Page 11 of 24
- TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Seismoscopes 2 detectors below PCRV Smoked glass supported I detector on top of PCRV on a Penoulum. As relative motion occurs, a stylus scribes a record on the glass.
s d I ? FORM 372 22 3643
1 1 PUBLIC SERVICE COMPANY OF COLORADO REU Sgetion 7
- - 4 Issue o
- FORT ST. VR AIN NUCLEAR GENERATING STATION Page 12 of 24
~ TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Control Number Location Action Setooint
- 2. Radiation Monitors Liquid Monitors
~
l RT6212 & Radioactive liquid 10 5 pC1/ml (also, if 750 cpm > BKG RT6213 effluent monitors. cooling tower blowdown 750 cpm > BKG l Reactor b1dg.- drops to < 1100 gpm), Elev. 4771' closes HV-6212 & HV-62249, trips transfer pump P-6202 & 62025, and trips reactor building sump pumps l to prevent 1 X 10- pCi/mi MPC value at site perimeter from being exceeded. (ELCO 8.1.2) RT21251 Low pressure Bearing water removal 10,000 cpm separator drain pumps trip, water line monitor. diverted to liquid Reactor b1dg.- - waste sump. Elev. 4740' (Operator must go to recycle mode). RT2263 Reheat steam No control action 600 cpm RT2264* condensate monitor. 570 cpm Turbine bldg.- Elev. 4811' RT46211 Gas waste No control action 600 cpm i RT46212 compressor cooling 600 cpm water monitor. Reactor b1dg. - Elev. 4740'
' NOTE: RT-2264 is normally lined up to monitor loop 2 steam generator penetration interspace for primary coolant in- i leakage. Detection of activity in Steam Jet Air Ejector Discharge (RT31193) without correspondingly high indication I on RT-2264 would suggest the need to switch RT-2264 to Reheat Steam Condensate, as directed by Emergency Procedure EP H-3.
FORM 372 22 3613
5
; PUBLIC SERVICE COMPANY OF COLORADO ,lction7 1 FORT ST. VRAM NUCLEAR GENERATING STATIOM Page 13 of 24 TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Control Number Location Action Setooint Gas Monitors (Plastic Beta Scint'llators)
RT7324-1 Reactor building Close block valve 35,000 cpm RT7324-2 ventilation exhaust FV-6351, divert ex- 1,300 cpm monitors. The haust from filters to monitors 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. l inlet dampers. l (ELCO 8.8.1) RT7312 Building Radio- The primary action is to 1,000 cpm activity Monitor. terminate flow to panel Five point monitor- I-9325 by closing valves: samples: HV-6342
- 1) PCRV Bottom Head HV-6341 j 2) A & I Room HV-9316 l
' 1
- 3) Health Physics HV-93256 Access HV-2325
- 4) Control Room HV-2326
- 5) Turbine Deck HV-2357-I Monitor is located HV-2357-2 on the Turbine Close all AI room Deck Elev. 4829'. sample valves. Normally i
samples a point for 7 i l minutes. All take suction ! ( from an exhaust vent duct. 1 RT31193 Air Ejector Exhaust No control action. 500 cpm Monitor. Located (ELCO 8.8.1) on the mezzanine level of the Turbine Building, east of the main condenser, Elev. 4811'. e FORM 372 22 3643
, PUBLIC SERVICE COMPANY OF COLORADO 380ti " 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 of 24
$ TABLE 7.3-1 I ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Control Number Location Action Setooint RT9301 Primary Coolant No automatic action. 4.6 X Monitor-Online 10' cpm Beta scintillator to monitor the primary coolant. Located in the AI room, Elev. 4829' . RT9302 Kr-85 Monitor. No automatic action. 500 cpm Shielded monitor Operator will swap located on the purification trains. 6 Turbine Deck - Elev. 4829'. RT6314-2 3as Waste Exhaust High alarm diverts the 1.7 X Monitor. Operated flow to the gas waste 10' cpm 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 7.0 X waste effluent action as RT6314-2. 10' cpm stream up stream (ELCO 8.8.1) of the gas monitor RT6314-2. Located inside the gas waste blower cubicle on Elev. 4781'. ? FORM 373 - 33 3%3
. i PUBLIC SERVICE COMPANY OF COLORADO 58 04 " 7 FORT ST. VR AIN WUCLEAR GENERATING STATION Fage 15 of 24 ; TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Control Number Location Action Setecint l RT73437-1 Reactor Plant ELCO 8.8.1 -Close valve 10,000 cpm l Ventilation Exhaust FV6351, divert flow to l l Iodi.1e-131 gas waste vacuum tank. l l Monitor Loc: Shutdown turb.ine building l Sampler / Detector: ventilation and place
[ El. 4916 the control room vent-l Turbine Side 11ation on recirculation. l Readout l El. 4829 l Control Room l This iodine monitor consists of two single channel l analyzers, one window being set for the photopeak l energy of interest (i.e. 282I), and one being set for l an adjacent energy region. The adjacent region window l provides a background subtraction capability, thus
! allowing the monitor to discriminate 282I from noble l gas radioisotopes. A 2 inch by 2 inch NaI(TL) crystal l 1s utilized as the detector for this monitor.
l RT73437-2 Reactor Plant Same automatic action 20,000 cpm l Ventilation as RT73437-1. l Exhaust Beta l Particulate Monitor l Loc: l Samples / Detector: 1 El 4916 l Turbine Side l Readout [ El. 4829 l Control Room l This particulate monitor consists of an alpha detector l and a plastic beta scintillation detecte viewing a l fixed filter for particulate radioactivity. The alpha l channel provides a live measurement of radon l concentration which is subtracted from the beta l measurement. A FOptM 372 22 3643
"7
, , PUBLIC SERVICE COMPANY OF COLORADO ,'0ti 5
.' . ORT ST. VRAIN NUCLEAR GENERATING STATION
, Page 16 of 24 O
TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Alarm Number Location Setooint l Emergency Stack Monitors (PING - Particulates, Iodine, Noble Gases) Provided to Monitor Reactor Building Ventilation exhaust effluent during i loss of power to the normal operating stack monitor. l RT 4801 Reactor Plant Ventilation 10,000 cpm Exhaust Beta Particulate Monitor Loc: El. 4885, turbine side RT 4802 Reactor Plant Ventilation 19,000 cpm Exhaust Iodine Monitor Loc: El. 4885, turbine side RT 4803 $ Reactor Plant Ventilation 23,000 cpm Exhaust Noble Gas Monitor Loc: El. 4881, turbine side Reactor Building Ventilation Exhaust Stack Monitor l RT 7325-1 Reactor Plant. Ventilation 1,600 cpm l Exhaust Iodine and Particulate Monitor Loc: l Samples / Detector: El. 4921 Turbine Side Readout El. 4829 Control Room l RT 7325-2 Reactor Plant Ventilation 10 mr/hr l Exhaust G-M Detector
'oc:
l Sampler / Detector: El. 4921 Turbine Side Readout El. 4829 { Control Room i l l l PORM 372 22 3643 l .. )
. l PUBLIC SERVICE COMPANY OF COLORADO , ' *i " 7 S
FORT ST. VR AIN NUCLEAR GERERATING STATION page 17 of 24 l
~
1 l l
- l TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Transmitter Description and Alarm Number Location Setooint l l
l TSC Ventilation Monitors ' RIT 7937 TSC Ventilation Inlet (P) 30,000 cpm Particulate, Iodine, Noble Gas (I) 3,000 cpm Loc: (G) 400 cpm l Sampler /0etector: El. 4791 , TSC Building l Readout El. 4791 TSC Building RIT 7936 TSC Ambient Atmosphere (P) 30,000 cpm Particulate, Iodine, Noble Gas (I) 3,000 cpm L LOC: (G) 400 cpm Sampler / Detector: El. 4811 TSC Readout EL. 4811 TSC 1 l
~
PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ue FORT ST. VR AIM NUCLEAR GENERATING STATION Page 18 of 24 O TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Alarm Transmitter Setpoint Number Location Elevation mrem /hr Reactor Building Area Radiation Monitors 1 l RT93250-1 Refueling Machine 4881 2.5 , Control Room l RT93252-1 Northeast Refueling Floor 4881 2.5 Rt93250-2 East Walkway Outside HSF 4854 2.5 RT93252-2 South Stairwell 4864 2.5 RT93250-3 Hot Service Facility 4856 10.0 Platform RT93251-3 Hot Service Bicwer Section 4868 100 RT93250-4 Outside HSF Door 4839 2.5 RT93252-4 Instrument Room-Analytical 4829 2.5 Instrument Board RT93251-5 Gas Waste Filters 4781 2.5 ' RT93251-6 Truck Bay 4791 2.5 RT93252-6 Near South Stairwell 4791 2.5 RT93251-7 Core Support Filter 4781 2.5 RT93252-) East Walkway 4781 2.5 . RT93250-8 North East Walkway 4771 2.5 RT93251-8 Decontamination Laundry 4771 2.5 RT93251-9 Buffer Helium Dryer Loop I 4740 2.5 l RT93250-14 Refueling Floor / 4531 2500 East Wall ( 1 FOR 372 22- 3643 ( {'
PUBLIC SERVICE COMPANY OF COLORADO f ue FORT ST. VRAIN NUCLEAR GENERATING STATION Page 19 of 24
; TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Alarm Transmitter Setpoint Control Number Location Elevation mrem /hr Action Turcine Building Area Radiation Monitors RT93250-13 'Near Condensate Demin- 4791 2.5 eralizers RT93251-1 Reactor Plant Exhaust 4864 1000 l' Filter Room RT93251-4 General Office Area 4816 1.0 )
RT93250-5 Control Room 4829 1.0 Technical Support Center Area Radiation Monitor l RIA-7951 Technical Support Center 4811 2.5 Equipment Ra,diation Monitors l RT93250-12 Steam / Water Dump Tank 4740 2.5 Alarm Monitor blocks opening HV-22156 l vent valve j to atmos-phere
. I RT93251-12 Steam / Water Dump Tank 4740 2.5 Alarm blocks opening HV-22156 vent valve to atmos- ,
phere l l RT93250-10 Reheat Steam Header 4811 1 (alarm) l Monitor Loop 1 3 (trip) l RT93251-10 Reheat Steam Header 4811 3 Monitor Loop 1 i l FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO 50 1"7 -
- FORT ST. VRAIN NUCLEAR GENER ATING STATION Page 20 of 24 TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Channel and Radiation Alarm Transmitter Setpoint Control Number Location Elevation mrem /hr Action l RT93252-10 Reheat Steam HeLoer 4811 1 (alarm) l Monitor Loop 1 ,
3 (trip) l RT93250-11 Reheat Steam Header 4811 1 (alarm) l Monitor Loop 2 3 (trip) l RT93251-11 Reheat Steam Header 4811 1 (alarm) l Monitor Loop 2 3 (trip) l RT93252-11 Reheat Steam Header 4811 1 (alarm) l Monitor Loop 2 3 (trip) l RT932af .2 PCRV Relief Valve 4885 2.5 Piping Monitor
- 3. System Monitors Process Monitors affecting the Assessment of Radiological Accidents are shown in the EAL column of Tables 4.1 4.1-4.
- 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 O PORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO $,Slction7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 21 of 24
- ' TABLE 7.3-1 ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Desc-iption and Functional System Location Applicability
- 5. Facilities Whole Body Counter Detect, identify, and quantify internal deposition of radio-activity Radiochemistry Equipped for Radiological Laboratory Anal) sis Radiation TLD Measure radiation dose Monitoring Stations rates (operated by Outside Security Fence, contract with Colorado inside owner controlled State University) area.
._ 4 Fixed Air Sampling larple particulates and Stations-Just Outside radiciodines (operated Security Fence by contract with Colorade State j 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 Tritium Air Monitors Detect Airborne Tritium Alpha Survey Meters Detect Surface Contamination Neutron Detectors Determine Neutron Flux rate Ion Chambers Determine Gamma Dose rate
- Fonu 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO EEE 2ssue 6 38 tic" 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 22 of 24 e TABLE 7.3-I ONSITE ASSESSMENT EQUIPMENT AND FACILITIES Instrument Description and Functional System Location Aeolicability Beta-Gamma Geiger- Surface and Area Mueller Survey Meters Radiation Levels SAH-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 l Proportional Counter l l Determine Alpha-Beta- I j Gamma Contamination g Hi and Lo Vol Air Samplers Detect Airborne Iodine ~
- and Particulate !
Contamination I l ( t FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO Section 7 FORT ST. VRAIN NUCLEAR GENERATING STATION page 23 of 24 l l TABLE 7.3-2 DFFSITE ASSESSMENT EQUIPMENT AND FACILITIES Individual Functional Detector Aeolicability
- 1. Geoohysical Monitoring Meteorological National Weather Service Denver Weather Forecasting Stapleton Airport
- 2. Rac~1olooical 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 radiciodines (operated by contract with Colorado State University) Colorado State University Ge-Li Detector Gamma Spectrometry for Isotopic identification and Analysis NaI(Tl) Detector Gamma Spectrometry for Isotopic identification and Analysis Radiochemistry Laboratory Chemical and radiological Analysis ; 1 l ? FORM 372 - 22 3643
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- REP.P Section 7 PUBLIC SERVICE COMPANY OF COLORADO Issue 6 FORT ST. VRAIN NUOLEAP GENERATING S4 TION page 24 of 24 1
. TABLE 7.3-2 0:FSITE ASSESSMENT EQUIPMENT A'D FACILITIES Individual Functional Deteeto- Acolicability Colorado State Department of Public Health Whole Body Counter Identification and quantification of inhaled or ingested radioisotopes. Serves as backup to FSV System.
- a. FORM 372 22 3643 me, m. - ._
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v . cf Oc!!cado 16805 WCR 19 1/2, I'latteville, Colorado 80651 September 7, 1984 Fort St. Vrain Unit No. 1 P-84348 h Mr. Eric H. Johnson 7; '
~ T Q7 %~~ k
! U.S. Nuclear Regulatory Commission l' 611 Ryan Plaza Drive, Suite 1000 t SEP I a1984 Arlington, Texas 76011 g
Dear Mr. Johnson:
4 We are transmitting herein revisions to several emergency preparedness related documents. The changes affect tne following 1 ! document binders: Radiological Emergency Response Plan - Plant l l The following procedures are being transmitted for filing in the RERP l
- Plant Procedures. I Section 4, Issue 5 Section 5, Issue 6 Section 6, Issue 7 .
Section 7, Issue 6 If there is confusion as to which issue is most recent whenever multiple copies are received in a short period of time, the highest issue number is always the most recent issue of a given procedure. If difficulties or questions arise in filing these procedures, please feel free to ' contact Ms. Shai11yn Johnson at (303) 785-2224, extension 275 for assistance. Very truly yours,
/
J. W. Gahm Manager, Nuclear Production JWG/cjs
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