ML20070T842
| ML20070T842 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/03/1983 |
| From: | Mcbride M, Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20070T835 | List: |
| References | |
| PROC-830103-01, NUDOCS 8302090543 | |
| Download: ML20070T842 (569) | |
Text
{{#Wiki_filter:_ _ _ NRC PUBLIC SERVICE COMPANY OF CCLORADO
. FORT ST. VRAIN NUCLEAR GENERATING STATION BOOK 1 hk 1/3/83 NON-CONTROLLED COP'/
RADIOLOGICAL EMERGEN;y RESPONSE PLAN - STATION ISSUE EFFECTIVE NO. SUBJECT NUM3ER DATE l RERP CR-ALERT Control Room Alert, Site Emergency, i General Emergency Procedure 16 01-03-83 RERP-DOSE Offsite Dose Calculations Methodology 2 10-08-82 O I l l O O 8302090543 830203 PDR ADOCK 05000267 N
PUBLIC SERVICE COMPANY OF CCLORADO CR ALERi FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 1 of 11 3 (G TITLE: CONTROL ROGY, ALERT. SITE EMERGENCY. GENERAL EMERGENCY PROCEDURE ISS^)ANCE AUTHORIZED g,, % a g . BY @M77/.4M L t EFFECTIVE PORC REVIEW EORc 4 9 7 DEC 2 71982 DATE I~ b b TABLE OF CONTENTS i Section Description Pace 1.0 Criteria for Implemyntation........... ... ...... ..... .. 3 2.0 Procedure... ....... .... . ............................. 3 3.0 Responsibilities ... .......... . ...... ......... .. . ..... 10 l 4.0 References ..... ... . ...... .. .......... ............... 11 A (v 6 5.0 -Referenced or Supportino Procedures......... .... ........... 11 Figurt 1 Response Center Manning Requirements ...... ........... 1 Figure 2 Visitor's Center Evacuation Routes ...... .. .......... 1 Figure 3 Site Sector Map...... ... ... ........... ......... . 1 Table 1 NOTIFICATION OF UNUSUAL EVENT. . . . . . . . . . . . . . . . . . . . . . . . . 1 Table 2 ALERT... . .. .... . .. .. .. ............. ..... 1 Table 3 SITE AREA EMERGENCY............... ...... ......... .. 1 Table 4 GENERAL EMERGENCY...... ...... ...... . ......... .... 1 l l s l Table 5 Fort St. Vrain Atmospheric Stability Categories......... I l Table 6 Dose Conversion Factors (DCFs) .... .............. ... 1 Attachment 1 Notification to Activate State Emergency Response Centers.. . . . ............... ....... 1
- Attachment 2 Local Determination of Stack Concentration... I ; n Attachment 3 Dispersion Factors..... ........ ... .. . 1 i
t U Datalogger Monitored Release... l Datasheet 1 ........ .. 1 FORM 372 22 3842
)
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16
. Page 2 of 11 Datasheet 2 Datalogger Unmonitored Release........ .. .. . 1 Datasheet 3 Preliminary Assessment of Plant Conditions. . .. 1 Checklist 1 Emergency Coordinator / Control Room Director Checklist... . . ...... . ....... . 1 Checklist 2 Datalogger Monitored Release..... ............ . 1 Worksheet 1 Monitored Release Calculations (Manual) ... .. 1 Worksheet 2 Monitored Release Calculations (TI-59). . . . . . . . . 1 Worksheet 3 Unmonitored Release Cal.;ulations (Manual) . ... 1 Worksheet 4 Unmonitored Release Calculations (TI-59)........ 1 Work /Datasheet/Checkli st Cantrol Li st . . . . . . . . ..... ...... ..... 1 Forms Use Reporting Sheet *. ...................... . .... .... 2 ,
- ANYTIME A WORKSHEET, DATASHEE1, OR CHECKLIST HAS BEEN WRITTEN ON, CGMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED
($ WORKSHEET SECTION AND FORWARD IT TO THE TECHNICAL CLERK AND
\) RECORDER, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
l l NJ F O R M 37: - 22 3643 l
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 3 of 11 n v 1.0 Criteria for Imolementation This procedure is to be utilized by Control Room personnel in the event of an occurrence which is classified as an ALERT, or higher, FSV Radiolog ical Emergency Response Plan (RERP) event, as defined in Tables 1 through 4 of this procedure. Guidance to assist in the accident classification process can be found in Emergency Procedure EP CLASS. Initial accident classification is the responsibility of the Shift Supervisor, in the role of Emergency Coordinator. 2.0 Procedure E.1 General Responses 2.1.1 Under any emergency condition, the Shift Supervisor ind onsite pert c.nnel will immediately initiate those actions required to limit the consequences of the event and return the plant to a safe and stable condition. 2.1.2 Implementation of the FSV Radiological Emergency Response Plan (RERP) is required whenever any of the Initiating Events of Tables 1 through 4 of ('l te ! procedure occurs. Additional guidance on ' accident classification is containe.d in Emergency Procedure EP-Class, as well as in each individual Emergency Procedure. Initial accident i classification is the responsibility of the Shift Supervisor. I 2.1.3 Checklist 1 is for use oy the CR Director and/or the Emergency Coordinator. This check list is a brief summary of actions, and is to be used for guidance purposes to assist in verifying execution of required responses. 2.1.4 During non-working hours, PSC personnel required to man the response centers (Figure 1) are notified by telephone. It is the responsiblity of the individual response center Alternate Directors (or the first individual contacted by the Director) to ensure that these notifications are made (see RERP-HOME). Refer to the RERP PHONE LIST for instructions and personnel names and telepnene numbers. *. O FORM 372 22 - 3543
. PUBLIC SERVICE COMPANY OF COLORADO CR ALEPT FORT ST. VRAIN NUCLEAR GENERATING STATION Issu6 16 Page 4 of 11 2.2 Initial Required Responses for ALERT, SITE EMERGENCY, GENERAL EMERGENCY In the event of an occurrence believed to be defined by any of the events listed in Table 4.1-2 through 4.1-4 of the RERE (included as Tables 2 through 4 of this procedure), the following actions shall be taken: (If event is an escalation of : NOTIFICATION OF UNUSUAL EVENT, begin with Step 2.2.7) 2.2.1 On-Shift Control Room Personnel 2.2.1.1 Implement Emergency Procedure actions required to limit the consequences of the event and return the plant to a safe and stable condition.
2.2.1.2 If a rediological release is involved, make a preliminary assessmen of the release. Actions to perform offsite dose calculations are described in implementing procedure RERP-DOSE. PERP-DOSE should be utilized as a reference in any cases where questions as (",) to the specifics of dose calculation I procedures arise. Worksheets, dose Datasheets, and Checklists for calculations are contained herein, a's summarized below: Worksheet 1 Monitored Release - Manual; l Worksheet 2 Monitored Release - TI-59; Worksheet 3 Unmonitored Release - Manual; Worksheet 4 Unmonitored Releace - TI-59; Datasheet 1 Monitored Datalogger; Datasheet 2 Unmonitored Datalogger; and Checklist 2 Monitored Datalogger. Datalogger calculation is the most rapid means of assessing offsite consequences, provided the user is familiar with the programs proper utilization. It is the Shift supervisor's responsbility to assure that the offsite consequence
. assessments are performed as required.
T..i s activity will become the responsibility of the Technical Support Center after full facility activation. 2.2.1.3 As soon as possible, inform the Emergency O Coordinator of the results of the C/ preliminary radiological assessment. FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
. ( FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16
- i. .
Page 5 of 11 ' 2.2.2 Shift Supervisor (CR Director Checklist - Checklist 1) 2.2.2.1 Assume the position of the Emergency Coordinator until relieved by the Control Room Director (Primary: Station Manager; Alternate: Superintendent of Operations), or the TSC Director. 2.2.2.2 As Emergency Coordinator, direct onsite emergency responses and initiate any required corrective actions. 2.2.2.3 Notify the on-duty Technical Advisor. Page Plant Home Phone Ext. Phone l J. Eggebroten 1 J. Sills
. l F. Novachek 2.2.2.4 If a radiological release or potential l ~
radiological release is involved delegate the preliminary assessment of the release to a Reactor Operator and obtain preliminary assessment results. This calculation should be performed at an average rate of approximately once every 15 minutes until relieved of this responsibility by the TSC or until offsite release is terminated. 2.2.2.5 Initiate radiolooical protective actions for station personnel. l s FORM 372,22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT k-FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 g ,' - Page 6 of 11 2.2.2.6 Centact one member of plant management listed below in order of preference: Page Plant Home Phone Ext. Phor;e Supt. of Operations i Station Mangar ', Admin./ Tech. Serv. Manage- 'I. Mgr. Nuclear '.od. { Rad. Protection j Manager i Vice Pres., Prod. ! 2.2.2.7 Based on preliminary plant and radic'ogical assessments, the Shift Supervisor (Emergency Coordinator) shall confirm the classification of the emergency (Radiological ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) with the first management contact. 2.2.2.8 Radiological ALERT, SITE EMERGENCY, GENERAL EMERGENCY If the emergency is determined to be a Radiological ALERT, SITE AREA EMERGENCY, l or GENERAL EMERGENCY: l a) Sound the Plant Emergency Alarr and
, announce the nature of the emergency
, (NOTE: this step need not be
- repeated if it was performed as part ,
of the applicable Emergency Procedure). b) All onsite personnel will first report to their Emergency Stations (refer to Administrative Procedure G-5, Personnel Emergency Response) r for initial personnal accountability. Personnel assigned to Emergency Response Centers will report to their Emergency Response
. Center when directed to do so.
FORM 372 22 36C3
g PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 16 5 Page 7 of 11 c) In cooperation with the first management contact, the Shift Supervisor (Emergency Coordinator) will complete the " Notification to Activate State Emergency Response Centers" from (Attachment 1).
, d) Thr Shift Supervisor (Emergency Coordinator) will then make the following notifications (these numbers are on the aute-dialer telephone i t, both the Control Room and Shift Supervisor's office):
(1) PSC Company Operator (2) Weld County Communications Center (Using Greeley Line)
*(3) NRC Operations Center " Hot Line" or s l
~
*Back-up Emergency Numbers for NRC Notification:
J or on HPN system (located in Control Room and the TSC). (4) Duty Technical Advisor (see Step 2.2.2.3 for telephone
- numbers).
The i nfo r.nati on on the
" Notification to Activate State Emergency Response Centers" Form (Attachment 1) will be read to ti.e , above contacts, except the TA, who will be directed to report to the plant site.
.O FORM 372 22 36E3
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 8 of 11 O e) The management contact will contact his Emergency Response Center alternate. The Response Center altctnate (or the first individual contacted for each response facility) is responsible for notifying the remaining people for that response center. f) Inform Visitor's Center (VC) to instruct visitors at the VC to depart to the Fort Lupton Fire Station and, depending on the wind direction, specify the departure route (see Figure 2). Wind from North Route #3 Wind from ;outh Route #1 Wind from East Route #1 Wind from West Route #2 g) Notify Security of the impending arrival of emergency personnel and provide acequate clearance for O erotecteo ^ree eccess. require:. 8ere 2.2.2.9 After the TSC is activated, establish l communications. 2.2.2.10 Receive initial personnel accountability report from Security. Utilize the Fire Brigade to locate and/or rescue any unaccounted-for personnel if required. l Plant rosters are provided at emergency assembly areas to assist in rapid evaluation of departmental accountability. 2.2.3 Technical Advisor l 2.2.3.1 When the Plant Emergency Alarm sounds or I whenever directed by the Shift . Supervisor (Emergency Coordinator), I immediately report to the Control Room. 2.2.3.2 Make initial assessment of plant status by completing " Preliminary Assessment of
. Plant Conoitions" for (Datasheet 3).
m F OR M 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16
- 4) Page 9 of 11
/ .
2.3 Follow-up Responses 2.3.1 CR Director 2.3.1.1 Direct the control of plant operations. 2.3.1.2 Request supplemental Operations personnel from the TSC Director, as required, to control the emergency. (The TSC Director will relay the request to the PCC Director and thus maintain re-entry control). 2.3.1.3 Initiate corrective actions recommended by the TSC Director to minimize the consequences of the emergency. 2.3.2 Control Room Personnel 2.3.2.1 Maintain the plant in a safe and stable condition. 2.3.2.2 implement corrective actions as directed by the CR Director. 2.3.3 Technical Advisor Provide tec"nical analysis and advise as requested by the Control Room Director or TSC Director. Wherever possible, assist TSC personnel in collection and assessment of plant status data. 2.4 Recovery The CR Director is responsible for recommending a termination of the emergency status, from a plant operational viewpoint, to the TSC Director. This recommendation shall be based upon the CR Director's determination that:
- Radiation levels are stable or decreasing with time.
- Releases of radioactive materials to the environment have ceased, or are controlled within Technical
, Specification Limits.
- Fires, flooding, or similar hazards no longer pose a threat to plant environment or personnel.
- Measures have been successfully instituted to repair 73 or compensate for malfunctioning plant equipment.
\~-]
l FORM 372 - 22 3543
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 10 of 11 3.0 Resconsibilities 3.1 Emergency Coordinator The Emergency Coordinator is the on-duty Shift Supervisor. The title of Emergency Coordinator is retained by the duty Shift Supervisor until he is relieved by either the Control Room Director or the Technical Support Center Director, upon activation of the FSV Emergency Organization (see Figure 1). The Emergency Coordina:or is responsible for: -
- Initial accideat classification;
- Recommending protective actions (NOTE: This responsibility may not be delegated);
- Initiating emergency actSns to mitigate the accident;
- Notifying offsite authorities (NOTE: The responsibility for making the decision to notify offsite authorities may not be delegated);
- Diagnosing accident conditions;
- Estimating radiological exposures; and
'
- Establishing communications with the TSC.
l Responsibility for the decision for offsite notification l and protective action recommendation may not be delegated. 3.2 Control Room Director The Control Room (CR) Director is responsible for control of plant operations, assessing plant cperational aspects, and for implementir.g any recommended corrective actions. l In addition, the CR Director may request any additicnal i operations personnel necessary through the TSC Director. 3.3 Technical Advisor l The Technical Advisor is responsible to provide technical analysis and advice as requested, and to provide recommendations of corrective actions necessary to restore the plant to a safe and stable condition. l O l FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COL OR ADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 11 of 11 ( 3.4 Control Room Personnel Plant Control and Plant Operations responsibilities are handled by personnel already on-shift and assigned those responsibilities. 4.0 References 4.1 FSV Radiological Emergency Response Plan 4.2 State Radiological Emergency Response Plan 5.0 Referenced or Supoorting Procedures 5.1 RERP-TSC, Technical Support Center Procedure 5.2 CR-UE, Control Room Unusual Event Procedure 5.3 EP-CLASS, Event and Emergency Classification Overview 5.4 RERP-DOSE, Offsite Dose Calculation Methodology 5.5 RERP-PAG, Protective Action Guideline Recommendations () 5.6 RERP-PCC, Personnel Control Center Procedure 5.7 RERP-HOME, Home Packet for Off-Shift Notifications 5.8 HPP-56, Manual Release Rate Determination 5.9 Station Security Plan and Procedures 5.10 RERP Phone Lists t O FCRM 372 22 360
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PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Figure 2 Issue 16 Page 1 of 1 O VISITOR'S CENTER EVACUATION ROUTES Colorado Hvv. 60 Johnstown : M1111k' n i 0 3 E u Visitor's >m Fort St. Center ~j; _ Vrain bS o Colorado Hvv. 66 , Platteville N N 3 i 3 Colorado Hwv. 52
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l 6 (616 4th St.) m I i l l FORM 372 22 3643
, PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STAT!ON Figure 3 Issue 16 Page 1 of 1 O
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PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Iable 1 Issue 16 Page 1 of 4 s TABLE 1 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 1. Any unplanned radio- 1. Alarms on:
logical release to RT 7312 the Reactor Building CAM (s) or its ventilation RT 7324-1 system. RT 7324-2 RT 7325-1 RT 7325-2 RT 4801 RT 4802 RT 4803 RT 73437-1, 2
- 2. Any liquid waste re- 2. a) RT 6212 or 6213 alarm lease resulting in with inability to prevent offsite effluent in discharge offsite.
excess of Technical Specification limits. b) As determined by () station personnel.
- 3. Indication of minor 3. a) 25% increase in fuel damage detected circulating activity in primary coolant. from previous equilibrium cond-itions at the same power level.
RT 9301 (RR 93256). l l b) SR 5.2.11 results.
- 4. Serious fire at the 4. a) any of various alarms plant lasting more on Fire Control Alarm than 10 minutes Pan'el ;
which could lead to substantial b) Fire Pump .A auto degradation of plant start; safety systems, or which could result c) verbal reports. in the release of radiologial or toxic materials. n%/ FORM 372 22 - 364
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
?
FORT ST. VRAIN NUCLEAR' GENERATING STATION Iable 1 Issue 16 Page 2 of 4 f, b TABLE 1 NOTIFICATIO_N OF UNUSUAL EVENT Event Indication
- 5. Abnormal coolant temp- 5. Violations of eratures or core egion LCO 4.1.7 or LCO 4.1.9 temperature rises for region outlet to the extent mismatch, or region requiring shutdown in AT, respectively, accordance with to the extent that Technical Speci- shutdown per Station fications. Technical Speci-fications is required (SOP 12-04).
- 6. Natural phenomenon that 6. a) Seismic Recorder may be experienced Doerate; or threatened that represent risks beyond b)-d) as visually observed normal levels: by, or reported to, a) earthquake station personnel.
l ' f) b) floods c) tornadoes d) extremely high winds
- 7. Unusual Hazards 7. As visually observed by, Experienced: or reported to, station personnel, a) Aircraft crash on site or near the site that is subject to public concern because of possible detrimental effect on the plant; b) Onsite explosions or near site explosions that may be subject to public concern because of possible detrimental effect on the plant; or, v
t FORM 372 - 22 3L0 l l
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Iable 1 Issue 16 Page 3 of 4 O V IABLE 1
@TIFICATION OF JNUSUAL EVENT Event Indication
- 7. c) Onsite or near site plant related accidents that could result in the release of toxic material or spills of flammable materials.
- 8. Any serious radio- 8. As occurring.
iogical exposure of plant personnel or the transportation ! to offsite facilities of contaminated personnel ! who may . ave been 1 l O '"3"ree-(Probably cannot be determined within two hours- call to be made in a timely fashion.)
- 9. accidents within the 9. As occurring or state that may reported by shipper.
involve plant spent fuel shipments or plant radio-l active waste shipments.
- 10. Loss of Engineered 10. Shutdcwn required in Safety Feature or Fire accordance with applicable Protection System to LCOs:
the extent requiring Shutdown a) Engineered Safeguards in accordance with station Technical Specifications. 1) Plant ventilation-
. LCO 4.5.1
- 2) Steam / Water Dump O Svstem - LCO 4.2.3 FORM 372 - 22 3643
- PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN fiUCLEAR GENERATING STATION Table 1 Issue 16 Page 4 of 4 O
TABLE I NOTIFICATION OF UNUSUAL EVENT Event Indication
- 10. (Cont). 3) PCRV penetrction flow restriction devices - LC0 4.2.7 and LCO 4.2.9
- 4) PCRV penetration secondary closures -
LCO 4 2.7 and LCO 4.2.9
- 5) PCRV Safety Valves -
LCO 4.2.8 SL 3.2 LSSS 3.3.2.c b) Fire Protection System - LCO 4.2.6, LCO 4.10.1-LCO 4.10.5 I'/T s_
~
- 11. Indication or alarms 11. Data Logger Alarm / Alarm on radiological effluent Summary indication of non-monitors not functional. operational alarm or indication on:
a) RT 7324-1, 2 and RT 4803; or b) RT 7325-1, 2, RT 4802, and RT 73437-1; or c) RT 73437-2 and RT 4801; or d) RT 6212 and RT 6213. NOTE: Use LCO 4.8.1 Technical Specification Limits as basis. FORM 372 22 3643
4 PUBLIC SERVICE COMPANY OF COLORADG CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Table 2 Issue 16 Page 1 of 4 g 3
\
wJ TABLE 2 ALERT Event Indication
- 1. Rapid, severe fuel 1. Coolant Inventory of particle coating a) >2.4 (CI) (Mev) Beta-Gamma failure. Ib b) circulating I-131 activity equivalent >24Ci c) plate out I-131 >1x10' Ci d) SR 5.2.6 or SR 5.2.11 results.
- 2. Rapid, gross failure of 2. Loop 1 Hot Reheat header (HRH) one steam generator reheat activity high (5 mrem /hr);
section with loss of or, Loop 2 HRH activity offsite power. high (5 mrem /hr) accompanied by 230 Kv OCB. trips O- "o a^T ##dervo>'eoe' oss of power alan. -
- 3. Primary coolant pressure 3. PAL 9335 decay (to a value greater PAL 9347 than 100 psi less than PAL 9359 normal pressure, n a_nd area monitor accompanied by area and or stack monitor alarm l stack radiation monitor alarms).
( 4. High radiation levels or 4. RT 7312 high airborne contamination CAM (s) alarm which ind' cates severe RT 6212 degradation in control of RT 6213 radioactive materials. RT 93252-12 (Increase by factor Area Monitors of 1,000 over normal.) e.g. lifting PCRV relief valve or abnormal release to cooling tower blowdown. Alarms with corresponding meter readings on area or process monitors. O FORM 372 - 22 JC43
t PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Table 2 f Issue 16 Page 2 of 4 f) v 4 TABLE 2 ALERT Event Indication
- 5. Loss of offsite power and 5. 230 KV OCB trips and RAT vital onsite AC power undervoltage/ loss of power alarm for up to 30 minutes. accompanied by 4 KV bus undervcitage 480V bus under-voltage, and Diesel Trouble alarms.
- 6. Loss of all vital 6. DC bus 1 < 10 volts and DC power for up to DC bus 2 < 10 volts 30 minutes.
- 7. Loss of crimary coolant 7. All He flow indicators read forced circulation for zero.
between 2 and 5 hours.*
- 8. Loss of secondary coolant 8. All. secondary coolant flow functions needed for indicators read zero.
() removing residual heat.
~
- 9. Loss of normal ability 9. a) Indication of insufficient to place the reactor in rods inserted; or, a subcritical condition by scram of the control b) neutron rods. count rate not decreasing.
- 10. Serious fire which could 10. a) any of various alarms on lead to substantial Fire Control Alarm Panel j
degradatio, of plant safety systems. b) Fire Pump 1A auto start c) verbal reports These times are LOFC from 100% power. Times may be correspondingly longer fo" lowe* power levels (CMG-4). e O O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Table 2 issue 16 Page 3 of 4 O U TABLE 2 ALERT Event Indication
- 11. Radiological effluents 11. a) RT 7324-1 indicating exceed 10 times technical 22.5 x 10 2 pCi/cc specifications instan-tenous limits. b) RT 7324-2 indicating 22.5 x 10 2 pCi/cc c) RT 7325-1 indicating 27.0 x 10 ' pCi/cc
' d) RT 7325-2 indiccting 27.0 x 10 8 pCi/cc e) RT 73437-1 indicating 27.0 x 10
- pC1/cc I-131.
<> at 48o2 4rd'c t4"9 -O 2 7.0 x 10
- pCi/cc I-131.
g) RT 4803 indicating 2 2.5 x 10 2 pCi/cc Utilize reading from above instruments and calculate dose i rate per procedures
- 12. Ongoing security 12. a) As observed or reported; compromise.
b) Guard Station Trouble alarm; or, c) Guard Station Actnowledge alarm.
- 13. Severe natural phenom- 13. a) Seismic recorder operate I
enon beins experienced or (2.05 g) or projected, such as: a) earthquake exceeding c) As Reported Operating Basi: Earthquake level.;; c) As Reported b) flood near desi . m level; c , U c) tornodo striking facility. FORM 372 22 3643
( PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Table 2 Issue 16 Pe.ge 4 of 4 TABLE 2 ALERT Event Indi:ation
- 14. Other hazards being 14. As reported by, or to, experienced or projected station personnel, sucn as:
a) aircraft crash on facility; b) missile impact on facility; c) explosion damage affecting plant operation; or,
, d) entry into facility environs of toxic or flammable gas.
(Some effect on facility ex-perienced or anticipated) (~N 15. Evacuation of control 15. As deemed necessary by A-) room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations. (Control room inte:rity . breached).
- 16. All alarms 16. Control room observation.
(annunciators) lost for more than 15 minutes and reactor is not shutdown; or, plant transient experienced while all alarms lost. (Parameter indicatics still functional.)
- 17. Other plant conditions 17. As deemed necessary by warranting precautionary Shift Supervisor.
. activation of the PCC, TSC, and FCP.
e FORM V2 + 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Table 3 Issue 16 Page 1 of 4 O TABLE 3 SITE AREA EMERGENCY Event Indication
- 1. Loss of primary coolant 1. All He flow indicators read forced circulation for zero.
over 5 hr. from 100% power. (Lower power levels preceeding LOFC extends time available before core damage is incurred. See CMG-4.)
- 2. Non-isolable primary 2. Loop 1 or 2 HRH activity coolant leakage through a alarm-high with Shift steam generator reheat Supervisor determination section, that leakage is non-isolable.
- 3. PCRV relief valve remains 3. RT 93252-12 alarm and rapidly gS open. decreasing Reactor pressure.
U
- 4. Determination of inability 4. 230 KV OCB trips and RAT to restore onsite AC undervoltage/ loss of power
, power. alarm accompanied by 4Ky l bus undervoltage, 480v bus undervoltage, and Diesel Trouble alarms. Standby Diesel Fail to Start.
- 5. Loss of functions needed 5. Inability to insert for plant hot shutdown. sufficient control rods accompanied by failure of emergency reserve shutdown system - resulting in inability to maintain .0 lap at 220 F.
l
- 6. Major damage to spent 6. a) Visual observation.
fuel due to severe cask i
, damage resulting in release b) area radiation monitor of radioactivity to plant alarms.
environs. V FORM 372 22 364
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAJN NUCLEAR GENERATING STATION Table 3 Issue 16 Page 2 of 4 d ' TABLE 3 SITE AREA EMERGENCY Event Indication
- 7. Fire adversely affecting 7. a) Fire pump 1A start; safety systems.
b) Fire Control Alarm Panel c) Various alarms according to affected safety system. d) Shift Supervisor determines fire beyond capability of station staff.
- 8. a) Effluent monitors 8. Stack monitor alarm with detect levels corresponding stack corresponding to concentration indications p/
q_ 3 greater than 50 mrem / on: hr,or greater i than 500 mrem /hr a) RT 73437-1, RT 4802, l whole body for two and RT 7325-1, 2
~
l minutes at the 26.7 x 10 ' pCi/cc site boundary under I-131; or, adverse meteorology (or levels 5 times b) RT 7324-1, 2, l the above for thyroid and RT 4803 dose rate). >6.6 x 10 2 uCi/cc l b) These dose rates are mixed noble gasses. projected based on other plant parameters or are measured in the environs.
- 9. Imminent loss of physical 9. Situation evident.
control of the plant due l to security breach. '. (Response detailed in Station Security Plan.) FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VN,1N NUCLEAR GENERATING STATION Table 3 Issue 16 Page 3 of 4 0v TABLE 3 SITE AREA EMERGENCY Event Indication
- 10. Severe natural phenomenon 10.
being experienced or projected (with plant not in cold shutdown), such as; a) earthquake greater a) Seismic Recorder Operate than Safe Shutdown alarm with indication of Earthquake ground motion greater than 0.10g horizontal or greater than 0.067g vertical. b) flood greater than b) As reported or observed. design levels r-~s c) winds in excess of c) average wind velocity (_) design levels greater than 90 mph or 10 second gusts exceeding 99 mph. d) tornado in excess of d) horizontal wind design levels velocity greater than 202 mph.
- 11. Other hazards being 11. As observed by or experienced or projected reported to, station with reactor not shutdown, personnel.
such as; a) aircraft crash affecting vital structures; b) severe damage to safe shutdown equipment; . c) entry of toxic / flammable gas into vital areas.
- 12. Reactor building louvers 12. a) Louvers Open Alarm
. open due to building (3 inches water) being overpressurized by primary coolant. b) Reactor building (~') (DBA #2) radiation alarms. v FORM 372 22 - 3443
4 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT ' FORT ST. VRAIN NUCLEAR GENERATING STATION Table 3 Issue 16 Page 4 of 4 0 . TABLE 3 SITE AREA EMERGENCY Event Indication
- 13. Evacuation of control 13. Remote shutdown l room accompanied by instrumentation indications inability to locally (panel I-49).
control shutdown systems within 15 minutes.
- 14. Other plant conditions 14. As determined by warranting activation of Shift Supervisor.
FCP/EOCs, monitoring teams, and precautionary public noti'ication. O I l l 4 O FORM 372 - 22 360
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FOftT ST. VRAIN NUCLEAR GENdRATING STATION Iable 4 Issue 16 Page 1 of 1 O TRLE 4 GENERAL EMERGENCY Event Indication
- 1. a) Effluent monitors 1. Stack monitor RT-7324-1, 2 detect levels alarm, or corresponding to Corresponding dose 1 rem /hr. whole rates determined with body (or 5 rem /hr E-500 or cutie pie thyroid) at the detector per exclusion area procedure HPP-56 and boundary under associated graphs.
actual meteoro-logical conditions. b) These dose rates are projected based on other plant para-meters or are in the environs.
- 2. Loss of physical control 2. Situation evident.
of the facility. (due to security breach).
- 3. Other plant conditions 3. As determined by exist that make release Shift Supervisor.
of large amounts of radioactivity possiole. O F ORM 372 3643
PUBLI6 SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Table 5 Issue 16 Page 1 of 1 O TABLE 5 FORT ST. VRAIN ATMOSDHERIC STABILITY CATEGORIES" at ('F) af ('F) f rom from Reactor Pasquill Stability o8** 60m tower Building Categories Classification (Deceees) s-1.7 s-1.5 A Extremely Unstable 222.5
>-1.7 to s-1.5 >-1.5 to s-1.3 B Moderately Unstable <22.5 to 217.5
>-1.5 to s-1.3 >-1.3 to s-1.2 C Slightly Unstable <17.5 to 212.5
>-1.3 to s-0.4 >-1.2 to s-0.4 D teutral <12.5 to 27.5
>-0.4 to s+1.3 >-0.4 to s+1.2 E Slightly 5 table <7.5 to 23.8
>+1.3 to 5+3.5 >+1.2 te s+3.1 F Moderately 5 table <3.8 to 22.1 i >+3.5 >+3.1 G Extremely 5 table <l 1 l
l 1 n ! U t - per Proposed Revision 1 to Regulatory Guide 1.23, September i 1980. For utilizing other than Reactor Building Instruments l (AT) utilize NRC Regulatory Guide 1.23, Proposed Revision 1 as a i referente for stability classification. Standard deviation of horizontal wind direction fluctuation (plume meander) over a period of 15 minutes to I hour. O f ! ( '%) FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VR AIN NUCLEAR GENERATING STATION Table 6 Issue IL Page 1 of 1 ( ' TABLE 6 DOSE CONVERSION FACTORS (DCF'S) Radionuclide rem /hr 3 DCF(Ci/m )* Kr-83m 2.7E-1 Kr-85m 1.3E+2 Kr-S5 1.7E+0 Kr-87 6.5E+2 Kr-88 1.7E+3 Kr-89 1.5E+3 Kr-90 1.0E+3 Xe-131m 9.9E+0 Xe-133m 2.7E+1 Xe-133 3.3E+1 Xe-135m 3.5E+2 Xe-135 2.0E+2 Xe-137 1.5E+2 Xe-138 6.8E+2 l l NoDie gas weighted average total boay DCF 7.5E+2 l l l (based on 879 Mw(t) design inventory) l
/~T l I l
%J I-131 1.2E+6 I-132 1.7E+4 I-133 2.3E+5 I-134 5.6E+3 I I-135 5.7E+4 l
l Radiciodine weighted average thyroid DCF 5.3E+4 l l (based on 879 Mw(t) design inventory) I I - __ I
*DCF's for noble gases from "The EXREM III Computer Code for Estimating External Radiation Doses to Populations from Environmental Releases," ORN L-TM-4332, with the exception of DCF's for Kr-89 and Kr-90, which are from " Final Environmental Statement, Light Water Breeder Reactor Program," Volume 3 of 5,
" Commercial Application of LWBR Technology," ERDA-1541.
[N FORM 372 22 3643 i 9
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATit:G STATION Attach. 1 Is ue 16 Page 1 of 4 r ( NOTIFICATION TO ACTIVATE STATE EMERGENCY RESPONSE CENTERS A. The Emergency Coordinator will complete Pages 1 and 2 of .nis attachment with the assistance of the first management contact. I l l Required Information i I l
- 1. This is (Name)_ , Shift Supervisor at the Fort St.
Vrain Station.
- 2. At (Time) we experienced an (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident.
- 3. a) There is NO, repeat NO, radioactive release taking place, and no special protective actions are recommended at this time.
E b) A radioactive release IS, repeat IS, taking place, and we recommend that people in areas remain indoors with windows and doors closed. c) A radioactive release I_S, repeat IS, taking place, ar.d we reccmmend that avacuation of areas ! be considered.
- 4. Further information on incident conditions will be provided in followup messages.
i l l. 4 Y FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. 1 Issue If ' Page 2 e' 4
-s
(& I SUFPLEMENTAL INFORMATION , NOTE: This information is to be supplied to the NRC and the Colorado Department of Health when requested. The radiological data can be determined as specified in Section 2.2.1.2 of this procedure.
- 1. Date and Time of Incident
- 2. Class of emergency (ALERT)(SITE AREA EMERGENCY)
(GENERAL EMERGENCY)
- 3. Type of release (airborne, waterborns, surface)
- 4. Current release rate:
Noble Gas Ci/see Iodine Ci/sec
- 5. Estimated curies released Noble Gas Ci Iodine Ci 6 Wind Velocity MPH, from degrees. Air Temp.
- F.
O(_/ 7. Stability Category , Form of Precip.
- 8. Dose rate at EAB - WB rem /hr Thyroid rem /hr
- 9. Projected dose at EAB - WB rem Thyroid rem
- 10. Estimated accumulated dose at EAB-WB rem Thyroid rem
- 11. Estimate of any surface radioactive contamination
- 12. On-site response actions under way i
l l O l _ FORM 372 22 - 36<c
, , PUBLIC SERVICE COMPANY OF COLORADO CR ALERT b FOR: ST. VRAIN NUCLEAR GENERATING STATION Attach. I t -
~
Issue 16 Page 3 of 4
- 13. Recommended Protective Action based on the projected dose at the EAB (NOTE: Refer to RERP-PAG):
Circle Appropriate Protective Actions and Read Aloud . Projected Dose Recommended (ren) Protective Action Whole Body <1 No planned protective' actions. State Thyroid <5 may issue advisory to seek shelter and await instructions. Monitor radiation levels. Whole Body 1 to 5 Take shelter and consider selective Thyroid 5 to 25 evacuation. Monitor radiation 1:vels. Establish Controlled Area and limit access. Whole Body 5 and above Conduct mandatory evacuation. Monitor Thyroid 25 and above radiation leveis and adjust area for mandatery evacuation based on these levels Control Access.
- 14. Prognosis for worsening of event
- 15. Date and time of repcrt __
B. The Emergency Coordinator will make ' notifications in sequence as follows: I I l PSC Company Operator i I or I I i
- 1) INSTRUCT the Operator to initiate the " Fort St.
Vrain Radiological Emergency Call List."
- 2) READ verbatim the information recorded in Part A (Page 1 of this attachment).
- t. 3) RECCRD the following information:
Time PSC Operator Notified
. 7'me Operator Callback Received FORM 372 22 36CB
JUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRA.'d N'JCLEAR GENERATING STATION Attach. 1 Issue 16 Page 4 of 4 I l l Weld County Jsing Greeley Line) l I i
- 1) READ verbatim the information recorded in Part A (Page 1 of this attachment).
- 2) RECORD the following information:
Time Weld County Notified Time Weld County Callback Received i ! l NRC OPERATIONS CENTER (HOT LINE OR i l I (Use HP Network Line if NRC Hot Line and Land Line are inoperable.)
- 1) READ Items 1) through 4) from Part A.
- 2) READ the following sentences verbatim. "THIS EVENT IS BEING REPORTED PURSUANT TO 10-CFR50.72, ITEM NUMBER 1. WE ARE PRESENTLY ACTIVATING STATE AND LOCAL EMERGENCY RESPONSE CENTERS."
- 3) READ the supplemental faformation (Page 2 of this attachment).
- 4) RECORD the following information:
NAME of NRC Contact TIME of NRC Contact / 1 l l l l { FORM 3rg.gg,3g43
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. 2 Issue 16 Page 1 of 1 0 - LOCAL DFTERM~ NATION OF STACK CONCENTRATION I This procedure should be performed by a person familiar with the instrumentation used to make a local determination of the stack concentration. I I l Dosimeter will be worn when performing this procedure. Exposure l l time will be kept to a minimum. [ l l
- 1. Proceed to the survey area at the exhaust stack on level 10, Turbine Building.
- 2. Insert instrument probe in shielded box at the exhaust stack and note reading (mR/hr). ,
- 3. Leave area immediately. Report the instrument used and reading (mR/hr) to the Control Room via the Gai-tronics.
!- 4. Return to Control Room and verify proper instrument reading (mR/hr) conversion to concentration (vCi/cc) via conversion graph posted in Control Room (refer to HPP-56, as required). NOTE: Utilize HPP-56, " Manual Release Rate Determination" as a reference, if required. l l l l 1 - A V FORM 372 22 - 3343 1
9 O O O Cf At t l1T A L t.a cle . 3 issue 16 ra9e 1orfra TABLE 1A 3 X/4 VA1,UES (XI(s sec/m ) AT illE EXCLOSION Alt [A DOUNOAlW (590m) TOR AN ANIH0HEllit LOCAf f 0 AT A llLIGilf Of 10 MLIERS ACCORDING TO IllE EQUA110NS OF HRC RFC CUIDi. 1.185 1 WINDSPEED AT 10 HE1[RS (p1Pil) S tals i l i t.y Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 1J.0 20.0 30.0 50.0 A 3. fa 69 1. ? b 1.156 0. 697: 0.8968 0.386 0.289 0.231 0 . 1 788 0.116 0.069 15 II.f90 i 5 . 1816 3.1530 2.298 1. 68:2 1.277 0.95ft 0.766 0.57'.s 0.383 0.230 C 23.250 11.630 7.751 8.650 8 3.22 2. 5 884 1.938 1.550 1.163 0.715 0.t 65 0 36.56 18.28 12.19 7.88 4fs 6.928 5,988 88 . 8:91 3.593 2.695 1.796 1.0 78
- i. 8 8.f 6 8 4 2fs . 2 3 16.15 10.83 10.83 9.8469 8 7.089 5.670 18.252 2.835 1.101 0 88.18 2 8 sis . 21 29. fi / 20.35 18 . 534 1 14 . 8 2 10. P,1 8.650 6 . 8411 8 fa.325 2. 59')
G 17:0.20 70.11 86 6 . 186 33.62 Iso.06 31.16 23.37 18.70 188.02 9 . 38 8 's.609
CR ALERT i tN Attach. 3
^
e2 f 14 - i FIGURE *.A. F
- DISPERSION FACTOR (X/Q) vs. WINDSPEED FOR THE EXCLUSION.
AREA BOUNDARY (590 METERS), ACCORDING TO THE EQUATIONS
" OF NRC REG. GUIDE 1.145. WIND 5PEEDS SHOWN ARE THE INDICATION-FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS.
i 1 _ s' f -. -x-y;-=- szu.w y,_.. " -.w.---. - _ , ~ _ - a= - - . . ~ -,_, .
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_ _ . .- _ _ .- - . - =. .. - ~ _- _. . . t O O O Cit All.RT Attacts. 3 issue 16 Page 3 of 13 4 i TABLE 2A 4 X/Q VALUr.S (X10-6 sec/m3) AT A DOWNWlNO DlSIANCE Of 2 itiLIS , FOR AN ANLHOMETLit L OCATID Ai A KtICit! 0F 10 HETERS ACCORDING 10 Tile EQUATIONS Of NRC RLG GUIDF 1. 18s5 WINOSPLEO AT 10 HETERS (HPil) Stats i i i ty class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 i 1 i A 0.12fs 0.062 0. 07 1 0.025 0.018 0 . 0 18: 0.010 0.008 0.006 0. 00fs 0.002 0 1.751 0.876 0 .5881 0.350 0.250 0.195 0 . 1846 0.117 0.088 0.058 0.035 C 12.97 6.8838 is.322 2.593 1.852 1.fo rs t 1.s18 1 0.865 0. 688 8 0 fs32 0.259 0 38.13 19.07 12.71 7.859 6.1084 5.019 3.972 3.177 2.383 1.589 0.953 E 68.89 8 32. f t's 21.63 1 3 . 77: 11. fs6 9.821 7.961 6.369 re .116 3. 1 88: 1.911 r 30.fi 65.18 1:3.858 28.33 25.27 22.53 17.91 138. 3 3 1 0 . 77: 7.163 3.298 1 C 250.1 125.0 83.35 56.60 56.184 51.12 38.79 31. f13 23.28 15.52 9.310 i 4 5 m
CR ALERT : Attach. 3 I
!ssue 16 Page 4 of 14
- h. .
)
to 2 l 5
- n FIGURE :.A.
,p
- DISPERSION FACTOR (X/Q) vs.WINDSPEED FOR A DOWNWIND DISTANCE OF 2 MILES, ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS 5 FOR AN ANEMOMETER LOCATED AT -A HEIGHT OF 10. METERS.
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. e a i 1 O Cft J.I IRT A t. ta c h . 3 issde 16 + l' age 5 or 18 TABLE 3A l X/Q VAtUIS (X1ti-6 sec/m 3) Ai A DOWNWIND D8 STANCE Of is MILES 00R AN ANI.H0HElfit 10CAllD AT A IIEICill 0F 10 HLititS ACCORDIf4G 10 illE IQUATIONS OF NRC RLC GUIDE 1.18s5 WlhDSI'[ED AT 10 HETERS (H1'll) Stability Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 A 0.069 0.038 0.023 0 . 0 18: 0.010 0. or18 0.006 0.005 0.003 0.002 0.001 0 0.155 0.078 0.092 0.031 0.022 0.011 0.013 0.010 0.078 0.005 0.003 C 3.963 1.982 1.321 0.793 0.566 0.880 4 0.330 0 . 2 68: 0.198 0.132 0.079 D 17.87 8 7.f 3f: is 956 3.028 2.271 1.823 1.f 11 1.132 0.8'49 0.566 0. 3 fs0 E 29.17 'Is . 59 9. 725 6.053 88.757 3.918 3.095 2.8676 1.857 1.?38 0. lfs 3 I ! I 65. fs6 32.73 21.82 13.85 11. fs0 9.626 7.585 6.068 ft . 551 3.03fe 1. 82tl G 132.81 66.82 1 fi ls .28 29.081 25.85 22.67 19.37 13.90 10.86 2 6.98:8 8.169 1 l l t k
..ve
., CR A1,ERT Attaen. 3 Issue 16 ,
-O ee9e 6 or 14 .
Str2 5 6 j ' i ! j
- 4
. l 1e 3 FIGURE 3.A.
DISPERSION FACTOR D:lQ) vs.WINDSPEED FOR A DOWSWIND s DISTANCE OF 4 Ml' ". ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.14Sl WINDSPEEDS SHOWN ARE THE INDICATIONS *
- i FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS.
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t O O O Cil Al iItI At tacle. 3
- Issue 16 Payrt 7 or Ils i
l TABL E isA + X/Q VALUES (X10 sec/m ) Al A 00WNWIND DISTANCE OT 5 Mit ES l IOR AN ANtHOMLillt LOCA TFil AT A 1801G111 Of 10 METERS ACCORDING 10 Tile EQUAFiONS Of HRC REG GUIDE 1.1Is5 l WINDSI'EED AT to HETERS (HPil) i StabiIity Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 ?O.0 30.0 50.0 i A 0.057 0.028 0.019 0.011 0.008 0.006 0.005 0.00's 0.003 0.002 0.00I i l D C.172 0.036 0. 0Pfs 0 . 0 18s 0.010 0.008 0.006 0.005 0.00's 0.002 0.001 C 2.7088 1.352 0.902 0. 5's 1 0.386 0.301 0.225 0.180 0.135 0.090 0.05's i 13 10.96 5.8 18 3.652 2. 228e 1.655 1.322 1.017 0.816 0.612 0.8 08 0 . 2'i 5 i E 32. fs 3 11.21 7. fs l6 is.630 3.586 2.927 2.29's 1.837 3.377 0.918 0. % 1 l r 52.07 26.03 17.36 10.93 8.819 7. 3fs 7 5.759 8.608 8 3. 8:56 2.30's 1.382 i G 107.7 53.86 35.91 23.30 20.188 17.388 13. 3 ts 10.67 8.005 5.336 3.202 4 Y Y f t a
- CR ALERT Attach. 2
' Issue 16 Page 8 of 14 i _
io 2 - .- 5- : PIGURE 4.A. ' htSPERSION FACTOR (X/Q) vs. WINDSPEED FOR A DOWNWl'ID DISTANCE OF 5 MILES. ACCDRDING TO THE EQUATIONS OF 74RC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS i FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS. i I 1P3-5 j . i ! I i . 1 i i . ! j l j
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. A t. t.a c h . 3 I ssive 16 Page 9 or Ile 1
TABLE 5A X/Q VAlotS (X10 " sec/m3) AT A 00WNWINO DISIANCE OI 6 MllfS FOR AN ANIMOMEitit LOCAIFO AT A IIElCHI 0F 10 M01ERS ACCORDING 10 illE EQUATIONS Of NRC REG Gul0E 1.1f65 WINDSPEED AT 10 METERS (MPil) r
'U 12.0 15.0 20.0 30.0 50.0 7.0 9.0
$') 1.0 2.0 3.0 5.0 l
0.032 0. 0 27: 0.016 0.010 0.8 85 0.283 0.162 0.097 0.069 0.05ft 0. 08 0 l A 4 9.068 0.051 0. 08:1 0.031 0.028 0.072 8 0 616 0.308 0.206 0.123 0.088 I 2.817 2.191 1. 68 3 1.315 0.986 0.651 0. 39fs C 19.72 9.859 6.513 3 . 9 84 7s i l 17.35 12.88 10.21 7.830 6.288 8.713 1 3 . 18 2 l . 88'; 8's.61 t f2.81 2 8 .581 j u I 22.96 17.88 18.33 10.75 7.166 is.299 1 119.6 89.81 'i9.81 36.93 28.31 8 ) E I ! 11.66 59.15 8:6.17 36.93 21.70 18.l:7 11.08 r 131.9 8 215.9 18488 . 0 90.18 181 0.fi 108.1 86.l:5 688. 881 743.23 2 5 .98 909.7 Il5fl .9 303.2 195.3 165.2 G i j i i _. -r - -
CR ALERT - Attach. 3 Issue 16
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to 2 Page 10 of 14 1: s s FIGURE 5.A. DISPERSION FACTOR (X/0) vs. WINDSPEED FOR A DOWNWIND DISTANCE OF 6 MILES. ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEED5 SHOWh ARE THE INDICATIONS f'OR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS tes 5 , 'g 4
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I - P O O O : i cli At ilti AI, ta c ts . 3 lsstso 1(, Page i t or 18: T Allt.E 6A 3'
- X/Q VAIMS (X10 sec/m , A1 A DOWNWINO DlSIANCL of a HlLES IOlt AN ANIMOHEIEH 10CATT D AT A 11010118 Of 10 HE1 Fits ACCORDeNG 10 1HE EQUATIONS OF NRC RtG CUIDE 1. 18s5 WINDSI'f ED AT 10 HEIERS (HPil) ,
i i i StabiIity Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 a A 0.379 0.190 0.126 0.016 0. 05fs 0. 0fs2 0.032 0.025 0.019 0.013 0.008 I 11 0 .3s88: 0. 2's 2 0.161 0.097 0.069 0 . 0 58: 0. 07:0 0.032 0 . 0 28s 0.016 0.010 C 12.66 6.329 ls.219 2.531 1.808 1.806 1.055 0.88 Is 0.633 0.l 22 0.253 D 5 7. 988 28.9/ 19.31 11.11 8.599 6.808 5.195 84.169 3.126 2. 08ts 1.251 i E 126.3 63.15 is2.10 25.8's 1 9 . 584 15.71 1 2 . 18s 9.735 7.301 is . 8(17 2.920 r 322.7 161. fs 101.6 66.87 52.07 is2.f 7 32.93 26.35 19.76 13.11 ( . 90's G 698. is 37s9. 2 232.8 188.2 4 121.7 101.6 78.19 62.55 8:6.91 31.28 13.71 e l j
CR ALERT Attach. 3 Issue 16 Page 12 of 14 O te2 -
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4
. * * ' i i ,
a I l' FIGURE 6.A. . . I DISPER$10N FACTOR (X/Q) vs.WINDSPEED FOR A DOWNWIND
,p DISTANCE OF 8 MILES. ACCORDING TO THE EQUATIONS OF 1 NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS 8 g FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS.
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e - 9 O cit Al I Iti A t. t.a cle . 3 issue 16 i l'a ge 13 o f Ils a TAH1E 7A X/Q VAlCfS (X10~7 sec/m3 ) A i A DOWft4t NH DISI Af4CE of IU Hil.[S i TOR AN Af4EMOHE1 Eft LOCA1ID AT A flEIGill Of 10 HElinS ACCullDlHG 10 life IQUAll0NS OF NitC RIG GUIDE 1.18 85 l WINDSI' RED Al 10 METERS (Hf'll) i Stahi1ity Class 1.0 2.0 3.0 5.0 7.0 9.o 12.0 , 15.0 20.0 .30.o So.n 1 A 0.313 0.156 0 . 1016 0.063 0.084 5 0. 0 3'> 0.026 0.021 0.016 0.01u n.006
!! U. 02 0.?O1 0.1388 0.080 0.057 U.Ofl 5 0.033 0.077 H.HPH 0.013 0.006 G 8.833 81.8816 2.97 is 1.167 1.262 0.981 0.736 0.589 0.f isr2 0.29's 0.111 D f3.02 l 23.51 184 . 3f: 8.678 6 . 3885 5.008 3.810 3.057 2.29?. 5 . 'iP8 p.917 l E 99.81 89.90 8 33.?? 20.35 15.26 IP.20 9 . 3 88: 7.527 '.s . 68:5 3.763 P.258 i
r 2%.9 I?8,5 8 5 . 68: $2.96 i lo.71 32.95 25.8844 20.35 15.?6 10.18 6.105 I G 568.7 28ls.3 189.6 119.8 96.80 1 79.62 61.16 is8.93 36.10 Pls. ls6 18s. 6 8 f y i i j e h
* " CR ALERT Attach. 3 -
Issue 16
~
Page 14 of 14 k 4 tt ~ s FIGURE 7.A.
,g D15PER$10N FATTOR (X/Q) vs.WINDSPEED FOR A DOWNWIND DISTANCE OF 10 Mlf *% ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN AR7.THE INDICATIONS--
3 i FOR AN ANEMOMETER LOCATED- AT A HEIGHT OF 10 METERS.
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PUBLIC SERVICE CCMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Issue 16 Pege 1 of 2
~
/')
V Datasheet 1 - Data Logger (or IBM) Monitored Release A. Projection - Option 2
, 1. Current and release start date and time:
l a) / / l l b) : l
- 2. Projected end of release date and l time:
l a) / / l b) :
- 3. Radiation Monitor Values, Noble Gas a) RT-7324, 1 cpm
.- b) RT-7324. 2 cpm i
If one of the above is offscale or inoperative: a) E-500 or Cutie Pie? b) Instrument Reading mR/hr
- 4. Exhaust Stack Flow Rate efm S. Radiciodine Monitor Values; RT-73437, 1 l
l a) Initial Reading from chart cpm l l b) Intermediate Reading from chart cpm l c) Peak or Current Reading from chart cpm d) Time between a and b minutes l e) Time betw9en b and c minutes
- 6. Wind Direction (preferred sampling point is 10 meter instrument on 60
. meter meteorological tower) l FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING E ATION Datasheet 1 Issue 16 Page 2 of 2
- 7. Wind Speed (f referred sampling point is 10 meter instrument on 60 meter mateorological tower) mph
- 8. Distance between upper and lower l temperature instruments l meters
! 9. Delta Temperature between temperature instruments i op
- 10. Standard Deviation (Sigma Theta) of Wind Direction - 15 min. average l
B. Puff - Cption 2 0 1. c#rremt emo reieese stert o*te emo time: a) / / b) l l 2. End of Puff date and time (not to exceed 15 minutes after B.1) a) / / b) .
.C . Total for All Puffs - Option 3 Change option and execute DF 41-0-0.
l l-FORM 372 3043
, PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 2 Issue 16 Page 1 of 2 Datasheet 2 - Data Logger (or IBM) Unmonitored Release)
- 1. Date and Ti;ne of beginning of release a) / /
b)
- 2. Time of Louvers closed
- 3. Maximum CPM, RIS-9301 cpm
- 4. a) Primary coolant I-151 equivalent circulating inventory Ci b) Primary coolant I-131 equivalent
- s. plateout inventory ,
Ci
- 5. Primary Coolant Vclume sec
- 6. a) PCRV Pressure Before Release psig b) PCRV Pressure After Release psig
- 7. Wind Direction (prefererd sampling point is 10 meter instrumentation on 60 meter meteorological tower) o
- 8. Wind speed (preferred sampling point is 10 meter instrumenation on 60 meter meteorological tower) mph FOR .1 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 2 Issue 16 Page 2 of 2
- 9. Distance between upper and lower temperature ir,struments meters
- 10. Delta Temperature between temperature ,
instruments F
- 11. Standard Deviation (Sigma Theta) of wind Direction - 15 min. average ,
1 l l O l l 1 O O FORM 372 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
/ FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 3 Issue 16 Page 1 of 2 (v,)
PRELIMINARY ASSESSMENT OF P!)sNT CONDITIONS TECHNICAL ADVISOR
- 1. Brief description of event
- 2. Date/ Time et event
- 3. Date/ Time of assessment
- 4. If the data logger is operating, obtain the Demand Function Printout (or printe the specified displays):
NOTE: All screens and demana functions are accessible from Display 900. DF 69-0-0 _ l l () DF 76-0-0 DF 77-1-0 Post Trip Review Helium Inventory i PRIMARY SYSTEM
- 5. Current Reactor Power 1
l 6. Rod Runback Occur (Y/N) If yes, record positions 2B 4A l \ 7. If shutdown, are all rods fully inserted (Y/N)
- 8. Circulators Operating A B C D MODE:
Steam /Feedwater/Cond./ Firewater
- j. 9. Purification Train A B To: Storage, PCRV, or Ventilation p
G
- 10. Is heat removal capability adequate at this time (Y/N)
FORM 372 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FOPT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 3 ' Issue 16 Page 2 of 2 SECONDARY SYSTEM
- 11. Loops Operating I II
- 12. Feed to S/G's: Norm FW Emer. FW Emer. Cond.
Fi rewater
- 13. Status of Aux. Boilers Remarks .
Time Description O l l l l' l 1-l l O FORM 372 22 - 3643
PUBLIC SERVICE COM7ANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1 Issue 16 Page 1 of 2 O I EMERGENCY COORDINATOR /CR DIRECTOR CHECKLIST
- 1. Initiate Emergency Procedure actions.
1
- 2. Technical Advisor notified.
- 3. Obtain preliminary assessment of release.
- 4. Obtain meteorological data.
l
- 5. Initiate protective actions for l station personnel.
- 6. Contact plant management and confirm accident classification.
- 7. Complete Notifications Form.
ALERT or Higher - Attachment 1
- 8. Sound Plant Emergency Alarm if ALERT or higher and announce nature of the emergency.
- 9. Receive initial personnel accountability report.
O FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATlhG STATION Checklist 1 Issue 16 Page 2 of 2. (
\a]
- 10. Notify Visitor's Center if Alert or higher; specify departure route 1, 2, or 3 (see Figure 2).
- 11. Make notifications.
(ALERT or Higher) PSC Operator Weld County Communications Center NRC Operations Center
- 12. Select the PCC location based upon consideratior of the dominant wind direction and accessability to emergency respondants from offsite.
I O The 14st belo- s-mer4zes the available alternative locations. 1 * ! a. Inside Protected A-ea.
*1) Warehouse
- 2) Craft-Shops i
l b. Outside Protected Area.
*1) Mod-City
- 2) GA Field Office l
l 13. Confirm communications with TSC and notify of PCC location. l l,
- Preferred locations for the FCC are either the warehouse or Mod-City, l
based upon equipment storage. O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 2 Issue 16 Page 1 of 2 Checklist 2 - Data Logger Monitored Release NOTE: Initialize the summing screen by entering option 4 and running DF 41-0-0. This should be done for the first calculation only.
- 1. " DEMAND FUNCTICN OVERVIEh"' key, located cursor on DF 41-0-0 and "XMIT CURSOR."
l 2. Step 1 trings up display 941. Follow i steps on this display. They lead the user frem ,creen to screen through the basic program steps. Always utilize program "0PTION 2" when performing calculations for record keeping or dose reporting purposes. This "0PTION" reverts to a "1" after the Demand Function is run and must O be reset to a "2" each time. l .
- l
- 3. Perform a " duration of release" calculation utilizing the projected or estimated end of release time. Utilize 2 hours from current as a default value I whenever this value isn't known.
- 4. Print displays from this calculation.
- 5. Display results and print l
l " NOTE: Be certain to reset option to "2" after performance of a calculation. l FORM 372 22 3643
1 PUBLIC SERVICE COMPANY OF COLORADO CR-ALERT
;, FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 2 Issue 16 Page 2 of 2
- 6. Perform a " puff" calculation utilizing a projected ending time 15 minutes from the
- current time shown on step 3 of this checklist. Release start time should be the same as current time.
- 7. Print displays from step 6.
- 8. Display results and print l
- 9. Set "0PTION" to "3" ard rerun DF 41-0-0 l 10. Print Display 951 which tabul ter tSo results i -
O '
SUMMARY
OF DISPLAYS TO PRINT Step No. Displays Verification
- 4. 944, 942, 948, 951 _ _ _ .
- 5. 945, 947
- 7. 944, 942
- 8. 945, 947
- 10. 949 l
[ ( FCnPA 372 22 3643 l
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT e FORT ST VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 1 of 9 WORKSHEET 1 ASSESSMENT OF RELEASE-MONITORED RELEASE This attachment i> to be used only if the TI-59 calculator program is not used. If the TI-59 is used, Worksheet 2 is to be used. This attachment is used to determine the following: a) Estimated noble gas and iodine release and release rate; b) The estimated whole body and thyroid gamma dose and dose rate at the EAB; c) Classification of the release; d) Projected whole booy and thyroic gamma dose at the EAB; and e) Recommended protective action for the general population.
,,s 1. Date/ Time of beginning of release. ___
i ) , 2. Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation.
- 3. Hours between 1. and 2.
- 4. Collect the following data:
a) Maximum CPM, RIS-7324-1: ( RR-935 3'3, red pen) cpm b) Sensitivity, RIS-7324-1: (I-14, 403-P7) pC1/cc/ cpm c) Maxiraum CPM,'RIS-7324-2: l (RR-93539, blue pen) cpm d) Sensitivity, RIS-7324-2: (I-14,203-P7) pCi/cc/ cpm e) Maximum CPM / Min, R:S-73437-1: cpm / min NOTE: Maximum CPM / Min must be calcuii ed as: (Maximum CPM - Initiei or Intermediate CPM) ('") ( Elapsed Time (min) ) V from strip chart. FORM 372 22 3643
PUBUC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION !!orksheet 1 Issue 16 Page 2 of 9 b) v f) Sensitivity, RIS-73437-1: uCi/cc/ cpm / min g) Site Area Emergency Limit (as posted):
- 1) 6.6E-2 pCi/cc noble gas
- 2) 6.7E-5 uCi/cc '2I 2
h) Ten Times Technical Specification Limits ( s posted):
- 1) 2.5E-2 uC1/cc noble gas
- 2) 7.0E-8 uCi/cc '2I 2
i) Exhaust Stack Flow (cfr.): (1-15, FI-7320) cfm j) Exhaust Stack Flow (cc/sec): (Step 41 x 4.72E + 2) cc/sec l k) Average Wind Speed at 10 meters: mph
- 1) Wind Direction
- Os at 10 meters: From Degrees NOTE: North = 0 increasing degrees - c.w.
m) Differential Temperature: F Circle appropriate instrument 60m tower Reactor Building
- 5. Determine sectors affected using Site Sector Map.
(Figure 3) Sector (s)
- 6. Determine Stability Category using Table 5, Step 4k), and 4m).
Stability Category
- l. NOTE: Use proper column based on whether 60m tower or reactor building l
uT instruments used. i e v FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 3 of 9 O I I l Noble Gas Concentration l l l
- 7. Calculate the exhaust stack noble gas concentration.
a) RIS-7324-1 concentration = (step da) x (step 4b)
=( )x( )
= pCi/cc b) RIS-7324-2 concentration = (step 4c) x (step 4d)
=( )x( )
= pCi/cc l
l c) If either RIS-732^-1 or RIS-7324-2 is off-scale high, record the stack concentratien as obtair.ed by local, portable instrument (refer to HPP-56 or Attachment 3 for instructions). Local Indicated Concentration = pCi/cc i l d) Enter the highest of 7a), 7b), or 7c) pCi/cc l l , l Noble Gas Release Rate l l 1
- 8. Calculate the Source Term, Q (i.e., Noble Gas Release Rate).
/
l Q = (step 7d) x (step 4j) x (1 E -6 Ci/pci)
=( )x( ) x (1 E -6)
= Ci/sec 9
O O FORM 372 22 3643
PUBLIC SERVICE COMPANY CF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 page 4 of 9
/ 'N L)
I i i Classification of Event i I i
- 9. Determine weighted noble gas dose conversion factor from Table 2. 7.5E+2 Rem / hour Ci/m 3
- 10. Determine the EAB dilution factor from Attach-ment 1 using the Stability Category (Step 6) and wind speed (Step 4k).
Dilution Factor = sec/m 2 General Emeroency Determination
- 11. Determine whole body dose rate at the EAB.
Dese Rate = (step 8) x (step 9) x (step 10)
=( )x( )x( )
= Rem / hour O)
(_ If the resulting dose rate at the EAB is 2 1 Rem / hour, the l classification of the event is GENERAL EMERGENCY. Inform the i Shift Supervisor of the General Emergency condition. Then go l directly to Step 14 of this attachment. Site Area Emeroency Determination i
- 12. Criteria for Site Emergency: If Step 7d) is greater than or l equal to 6.6E-2 pCi/cc, the classification of the event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Emergency Condition. Then go directly to Step 14 of this attachment.
Radiological Alert Determination l
- 13. Criteria for Radiological Alert: If Step 7d) is greater than or equal to ten times the Technical Specification limit 2.5E-2 uCi/cc*, the classification of the event is RADIOLOGICAL ALERT.
Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 14.
- NOTE: Technical specification limit = 2.5E-3pCi/cc 10x Technical Specification limit = 2.5E-2 uCi/ce, as stated above.
O v FORM 372 22 3443
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 5 of 9 O I I l Curies of Noble Gas Released l l l
- 14. Calculate the curies of noble gas released to present time.
Curies released = (step 8) x (step 3) x (3.6 E +3 s/hr)
=( )x( ) x (3.6 E +3)
= Curies i I
[ Acca:rulated Whole Boc'y Gamma Dose at EAB l I _ _ l l 15. Calculatt the dose receivsd at the EAB. Dese n (ttep 11) x (steo 3) O =< >x< > l = Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release. l l 1 l l projections l l 1
- 16. If the release is continuing, consult with the Shift Supervisor i and estimate the total number of hours the release will cortinue (i.e., from beginning to end). If the release has terminated, enter value from step 3.
l, Preliminary estimate of release hours hours. l l e a FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 6 of 9 O
- 17. Project'the totaal whole body gamma dose at the EAB.
Projected dose at EAB = (step 11) x (step 16)
=( )x( )
= Rem i I l 131 I Concentration i l i
- 18. Calculate the exhaust stack 182I concentration.
RIS-73437-1 concentration = (steo 4e) x (step 4f)
=( )x( )
= uC1/cc l l 1 1311 and Total Radioiodine Release Rate l
~ (s) l _
l I l
- 19. Calculate the source term Q (2 2I release rate).
Q = (ster 18) x (step 4j) x (1 E -6)
=( )x( ) x (1 E -6)
= Ci/sec l
- 20. Calculate QT f r total radioiodine release.
O T
= (step 19) x (1.05 E + 2)*
l l
=( ) x (1.05 E + 2)*
= Ci/sec
- Ratio of total radiciodines to 2'11 in design inventory.
l O O FORM 372 22 300
l l PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION t!orksheet 1 Issue 16 Page 7 of 9 O l l l Classification of Event l l l
- 21. Determine weighted radioiodine dose conversion factor from Attachment 8. 5.3E+4 Rem / hour C1/m2 General Emergency Determination
- 22. Determine the thyrutd dose rate at the EAB.
Dose Rate = (step 20) x (step 21) x (step 10)
=( )x( )x( )
= P,em/ hour If the resulting dose rate at the EA3 is 2 5 Rem / hour, the l classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency Condition. Then go directly to Step 25 of this attachment.
- (G / Site Area Emergency Determination l 23. Criteria for Site Area Emergency: If Step 18 is great than or l equal to 6.7E-5 uCi/cc, the classification of the event is SITE
! Inform the Shift Supervisor of the Site Emergency EMERGEf4CY. Condition. Then go directly to Step 25 of this attachment. Radiological Alert Determination l 24. Criteria for Radiological Alert: If Step 18 is greater than or l equal to ten times the Technical Specification limit 7.0E-8 uCi/cc*, the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 25. NOTE: Technical Specification Limit = 7.0E-9pC1/cc 10x Technical Specification Limit = ME-8uci/cc, as stated above. . l l~ r. F OR M 372 22 - 3643 l I l
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 8 of 9 I I l Curies of Radiciodine Released l I I
- 25. Calculate the curies of radiciodine released to present time.
Curies Released = (step 20) x (step 3) x (3.6 E +3) l =( )x( ) x (3.6 E +3) ( = curies
! l l \ccumulated Tt.yroid Dose at EAB l l l
- 26. Calculate tne dose received at the EAB.
Dose = (step 22) x (step 3)
=( )x( )
= Rem f;0TE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
l 1 l l Projections l l l l
-2 7 . If the release 'is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hours.
- 28. Project the total thyroid dose at the EAB.
1 l Projected Dose at EAB = (step 22) x (step 27) ! =( )x( )
= Rem O
FOftM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 9 of 9 r~s U
- 29. Determine the recommended protective action for the general population based on the results of steps 17 and 28, refer to RERP-PAG.
- 30. The whole body gamma dose rate at the EAB is (step 11): Rem / hour
- 31. The classification of the event based on noble gases is (step 11 or step 12 or step 13):
- 32. The noble gas release rate is (step 8): Ci/sec
- 33. The accumulated whole oody gamma dose at the FAB is (step 15): Rem
- 34. The tetai number of curies of noble gas release to the present time is (step 14): Curies
- 35. The projected whole body gamma dose at the EAB is (stepT77: Rem Baseo on orojected release duration of (step 16): _ hours
- 36. The thyroid dose rate at the EAB is (step 22): Rem / hour
, -O 37. T8e cless4f4cet4on of 18e event eesed oe redio-iodines is (step 22 g step 23 g step 24): l
- 38. The radioicdine release rate is (step 20): C1/sec
- 39. The accumulated thyroid dose at the EAB is (step 26): Rem t
- 40. The total number of curies of radioiodine released to the present time is (step 25): Curies
- 41. The projected thyroid dose at the EAB is (step 28): Rem Based on projected release duration of (step 27): hours
, *If this classification differs from the classification in step l
31, the higher (i.e., more severe) classification is to be used to determine recommended protective action. l I FORM 372 3643 l l
I PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Werksheet 2 l Issue 16 I Page 1 of 7 l l O uJ WORKSHEET 2 ASSESSMENT OF RELEASE USING TI-59 CALCULATOR PROGRAM-MONITORED RELEASE This attachment is only to be used if the TI-59 calculator program is used. If the program is M used, use Worksheet 1. This attachment is used to determine the following: a) Estimated noble gas and radiciodine release and release , rate; b) Estimated whole body and thyroid gamma dose and dose rate at the EAB; c) Classificaticn of the release; d) Frojected whole body and thyroid gamma dose at the EAB; and e) Reccomended protective action for the general population.
- 1. Collect the following data:
(3 U a) Date/ Time of beginning of release: b) Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation: l c) Hours between la) and Ib): hours (ST0 11) l l d) Maximum CPM, RIS-7324-1: cpm (RR-93539, red pen) (STO 03) e) Sensitivity RIS-7324-1: pCi/cc/ cpm (I-14,403-P7) (STO 04) f) Maximum CPM, RIS-7324-2: cpm (RR-93539, blue pen) (ST0 05) g) Sensitivity, RIS-7324-2: pCi/cc/ cpm (I-14, 203-P7) (STO 06) O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT l FORT ST. VRAIN NUCLEAR GEN; RATING STATION !!0rksheet 2 Issue 16 Page 2 of 7 O
*h) Maximum mR/hr, Cutie Pie-25?O Probe: mR/hr (ST0 01)
*i) Maximum mR/hr, E-500-GM Probe mR/hr (STO 02) j) Maximum CPM / MIN, RIS-73437-1: cpm / min (STO 07)
NOTE: Maximum CPM / Min must be calculated as: (Maximum CPM - Initial or Intermediate CPM) ( Elapsed Time (min) ) from strip cnart. k) Sensitivity, RIS-7343'/-1: _uCi/cc/ cpm /mir (STO 03)
- 1) Site Emergency Limit (as posted): 1) 6.6E-2 pCi/cc noble gas
- 2) 6.7E-5 uC*/cc 281I m) Ten Times Technical Specification Limits (as posted): 1) 2.5E-2 pCi/cc noble gas
- 2) 7.0E-8 uCi/cc 1'11 n) Exhaust Stack Flow (cfm):
(I-15, FI-7320) cfm (STO 09) o) Average Wind Speed at 10 meters: mph p) Wind Direction at 10 meters: NOTE: North = 0 increasing degrees-c.w. From Degrees
. q) Differential Temperature F Circle appropriate instrument 60m Tower Reactor Building
- Steps lh) and 11) used only if RIS-7324-1 or RIS-7324-2 off-scale high.
O v FORM 372 22 3643 m .
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT,ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 3 of 7 O
- 2. Determine sectors affected using Site Sector Map (Figure 3):
Sector (s)
- 3. Determine Stability Category using Table 5 and Steps lo) ar.d Iq).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
- 4. Determine the EAB dilution factor from -
Attachment I using the Stability Category (Step 3) and wind speed (Step lo). Dilution Factor sec/m2 (STO 10)
- 5. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has ter.ai-nated, enter value fron step Ic).
Preliminary estimate of release hours hours. (ST0 12) 4 O FORM 372 22 + 3643
PUBLIC SERVICE COMt ANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 4 of 7 [- v
- 6. Prepare the TI-59 for data entry.
a) Place TI-59 in printer / security cradle. b) Plug in printer / security cradle. c) Turn on printer / security cradle and TI-59. d) Depress " TRACE" button on printer. e) Obtain the magnetic card labeled "FSV Off-Site Dose Calculation (RERP) - Monitored Release." f) Read magnetic card into TI-59.
- 1) Depress l1l , IINVl , [2ndl , l WRITE l keys.
- 2) Insert magnetic card into r1ght side of TI-59.
Card should oe right side up with the "1" in the upper left-hand corner.
- 3) "1" will be displayed if the card was read properly -cortinue with Step 7. If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card
-( with the same title and repeat Step 6f).
l [ . i I l (~)J u-t ( FORM 372 22 3643 1
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 5 of 7 O
- 7. Input the necessary data into the indicated TI-59 storage registers.
a) Step 1c) = l@l 11 , b) Step Id) = l@l 03 c) Step le) = l@l 04 d) Step If) = l@l 05 e) Step 19) = l@l 06 f) Step lb) = l@l 01 g) Step li) = l@l 02 h) Step lj) - l@l 07 i) Step Ik) = l@l 08 j) Step in) = l@l 09 k) Step 4) = l@l 10
- 1) Step 5) =
lB1 12 l 8. Run Dose Assessment Program l a) Depress l@l key.
. b) Wait until a number is displayed. A flashing number indicates improper execution of the program. Depress l@landl@l l keys and repeat Steps 7 and 8.
O FORM 372 22 3643
l PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATifJG STATION Worksheet 2 - Issue 16 Page 6 of 7 O l
SUMMARY
l
- 9. a) The whole body gamma dose rate at the EAB is(RCL 19): Rem / hour b) The classification of the event based on noble gases is:
- 1) If Step 10.a) 2 1 Rem / hour, l GENERAL EMERGENCY.
- 2) If RCL 17 2 6.6E-2 uti/cc (Step 1.1)1),
SITE AREA EMERGENCY.
- 3) If RCL 17 2 2.5E-2 uCi/cc (Step 1.m)1) and s 6.6E-2 pCi/ce, RADIOLOGICAL ALERT.
c) The noble gas release rate is (RCL 18): Ci/sec d) The accumulated whole body gamma dose at the EAB is (RCL 21): Rem e) The total number of curies of noble
~ O_f s gas released to the present time is (RCL 20): Ci f) The projected whole body gamma dose at tne EAB is (RCL 22): Rem g) The thyroid dose rate at the EAB is (RCL 27): Rem / hour 9
O O FORM 372 22 4 364J
l PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 1ssue 16 Paga 7 of 7 (JD "h) The classification of the event based on radiciodines is:
- 1) If Step 10.g) 2 5 Rem / hour, GENERAL EMERGENCY.
- 2) If RCL 23 2 6.7E-5 pCi/cc (Step 1.1)2),
SITE AREA EMERGENCY.
- 3) If RCL 23 2 7.0E-8 pCi/cc (Step 1.m)2) and
< 6.7E-5 pC1/cc, RADIOLOGICAL ALERT.
- 1) The radiciodine release rate is (RCL 26): C1/sec j) The accumulated thyroid dose at the EAB is (RCL 29): Rem k) The total number of curies of radiciodine released to the present time is (RCL 28): Ci
- () 1) The projected thyroid dose at the EAB is (RCL 30): Rem i
Based on projected rele:se duration ! of (RCL 12): _ hours
- 10. Determine the recommended protective action for the general population based on RERP-PAG.
- If this classification differs from the classification in Step l
10b), the higher (i.e., more severe) classification is to be used to determine recommended protective actions. l t O O FORM 372 - 22 36G l
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FOPT ST. VRAIN NUCLEAR CENERATING STATION !!orksheet 3 Issue 16 Page 1 of 10 Og . WORKSHEET 3 ASSESSMENT OF RELEASE-UNMONITORED RELEASE This attachment is to be used only if the TI-59 calculator program is no_t used. If the TI-59 program is used, Works:.eet 4 is to be used. This attachment is used to determine the following due to an unmonitored release via the Reactor Building Louvers or the PCRV Relief Valves: a) Estimated whole body and thyroid gamma dose and dose rate at the EAB; b) Classification of the release; c) Projected whole body and thyroid gamma dose at the EAB; and d) Recommended protective action for the general population.
- 1. Date/ Time of beginning of release
- 2. Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the
- vp/ calculation.
- 3. Hours between 1. and 2. hours
- 4. Collect the following data:
1 a) Maximum CPM, RIS-9301: (RR-93256, Pt. 10) _ cpm b) Sensitivity RIS-9301: pCi/cc/ cpm i l c) Dr' mary coolant 182I equivalent l circulating inventory: Ci I l d) Primary coolant 2'2I equivalent ) l plateout inventory: Ci ! l l e) Primary Coolant Volume: sec l. f) Site Emergency Limit (as posted): 1) 6.6E-2 pC1/cc noble l l gas l .
- 2) 6.7E-5 pCi/cc2821 g) Ten times Technical Specification Limits 1 (as posted): 1) 2.5E-2 pCi/cc noble I gas I F ORM 372 3643 j l
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksneet 3 Issue 16 Page 2 of 10 0
- 2) 7.0E-8 _uCi/cc 2'2I i h) Average Wind Speed at 10 meters: mph i) Wind Direction at 10 meters: From _
Degrees NOTE: North = 0 increasing degrees - c.w. j) Differential Temperature F l Circle instrument used: 60m tower Reactor Building
- 5. Determine sectors affected using Site Sectcr Map (Figure 3):
Sector (s) 1 l
- 6. Determine Stability Category using Table 5, Step 41 and Step 4j:
l 1 Stability Category NOTE: Use proper column based on whether
~ ()
(3 60m tower or reactor building AT instruments used. i l 7. Calcula e the release noble gas concentration: RIS-9301 conce:.tration = (sten 4a) > (step 4b)
=( )x( )
l
= yC1/cc l
- 8. Calculate the source term, Q ng (n ble gas rslease rate):
a) Reactor Building Louvers Q = (step 7) x (5.8 E +7)* x (1 E -6 Ci/pci) ng
=(
~
) x (5.8 E +7)* x (1 E -6)
= C1/sec
- Release rate (cc/sec) from louvers (FSAR, Section 14.11.2.6).
l - O FORM 372 3643 i 1
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 3 of 10 m G b) PCRV Safety Valves Q ng = (step 7) x (1.9 E +7)** x (1 E -6)
=( ) x (1.9 E +7)** x (1 E -6)
= Ci/sec
** Release rate (cc/sec) from both PCRV safeties (FSAR, Section 6 .8).
I I l Classification of Event i I I l 9. Determine weighted n'oble gas dose ! conversion factor from Table 2: 7.5E+2 Rem / hour C1/m 3 i i 10. Determine the EAB atmospheric dilution factor I from Attachment 1 using Steps 6 and 4h: 1 Dilution Factor sec/m2 General Emeroency Determination
- 11. Determine the whole body dose rate at the EAB:
a) Reactor Building Louvers Dose Rate = (step 8a) x (step 9) x (step 10)
=( )x( )x( )
l
- = Rem / hour l
l b) PCRV Safety Valves l l Dose Rate = (step 8b) (step 9) x (step 10) l
=( )x( )x( )
= Rem / hour
- 12. If the resulting dose rate at the EAB is 2 1 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency Condition. Tnen go directly to Step 15.
FC' M 372 22 - lso43
l PUBLIC SERVICE COMPANY OF COLORADO CR ALERT l FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 ) Issue 16 1 Page 4 of 10 O<.y Site Area Emergency Determination
- 13. If Step 8a. or 8b. is greater than or equal to 9.6E-1 C1/sec, the classification of event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Area Emergency Condition. Then go directly to Step 15.
Radiological Alert Determination
- 14. If Step 8a. or 8b. is greater than or equal to ten times the Technical Specification limit 3.7E-1 Ci/sec, the classification ,
of the event is RADIOLOGICAL ALERT. Inform the Shift Sunervisor i of the Radiological Alert Condition. Then proceed with 5tep 15. - NOTE: Technical Specification Limit = 3.7E-2 Ci/sec. 10x Technical Specification Limit = 3.7E-1 Ci/cc, as stated above l I l Curies of Noble Gas Released l l 1 O v
- 15. Calculate the curies of ioble gas released to present time.
a) Reactor Building Louvers i Curies Released = (step 8a) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E C )
= Curies b) PCRV Safety Valves Curies Released = (step 8b) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= Curies l'
1 O a FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 5 of 10 0 1 I l Accumulated Whole Body Gamma Dose at EAB l l l
- 16. Calculate the dose received at the EAB.
a) Reactor Building Louvers Dose = (step Ila) x (step 3)
=( )x( )
= Rem j b) PCRV Safety Valves Dose = (step lib) x (step 3)
=( )x( )
l ' = Rem l NOTE: This calculation assumes the recipient was at the j ~ t EAB for the entire duration of the release. I l ' l Projections l I I
- 17. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue l (i.e., from beginning to end). If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hour ( s) . i ! 18. Project the total whole body gamma dose at the EAB. a) Reactor Building Louvers l Projected Dose at EAB = (step 11a) x (step 17)
=( )x( )
= Rem l
O FOFtM 372 - 22 3643 I
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet'3 Issue 16 Page 6 of 10 b) PCRV Safety Valves Projected Dose at EAB = (step lib) x (step 17)
=( )x( )
= Rem
- 19. Calculate the release 2'2I equivalent concentration (Reactor Building Louvers or PCRV Safety Valves).
2'2I Equivalent Concentration = (step 4c) + (step 4d) x (5.7 E -3) + (step 4e)
=( )+ ( ) x (5.7 E -3) +( )
= Ci/cc
*** Amount of plateout 2'11 equivalent released (FSAR, Section 14.11.2.7.1).
- 20. Calculate the source term, Q (2'2I equivalent release rate).
, (~) 1) Reactor Building Louvers
. U ( Q = (step 19) x (5.8 E +7)
=( ) x (5.8 E +7)
= Ci/sec b) PCRV Safety Valves Q = (step 19) y (1.9 E + 7)
=( ) x (1.9 E +7)
= Ci/sec I I l Classification of Event I l l
- 21. Determine 2'2I dose conversion factor from Attachment 8. 1.2E+6 Rem / hour C1/m3
\
FORM 372 22 - 3643
PUZLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION b!orksheet 3 Issue 16 Page 7 of 10 (m
- 22. Determine the thyroid dose rate at the EAB.
a) Reactor Building Louvers Dose Rate = (step 20a) x (step 21) x (step 10)
=( )x( )x( )
= Rem / hour b) PCRV Safety Valves Dose Rate = (step 20b) x (step 21) x (step 10)
=( )x( )x( )
= Rem / hour General Emeroency Determination
- 23. If the resulting dose rate at the EAB is 2 5 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency Condition. Then go directly to Step 26 of this attachment.
Site Area Emergency Determination l l
- 24. If Step 20a. or 20b. is greater than or equal to 9.8E-4 Ci/sec, the classification of the event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Area Emergency Condition. Then go directly to Step 26 of this t.ttachment.
Radiological Alert Determination
-2 5. If Step 19 is greater than or equal to ten times the Technical Specification limit 1.0E-7 Ci/sec, the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiclogical Alert Condition. Then proceed with Step 26.
NOTE: Technical Specification Limit = 1.0E-8 Ci/cc ,. 10x Technical Specification Limit = 1.0E-7 C1/cc, as stated above. l ! O O FORM 372 22 3643 l l
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 8 of 10 1 -- l l Curies of 182I Equivalent Released l I I
- 26. Calculate the curies of 181I equivalent released to present time.
a) Reactor Building Louvers Curies Released = (step 20a) x (step 3) x (3.6 E +3 s/hr)
=( )x( ) x (3.6 E +3)
= Curies b) PCRV Safety Valves Curies Released = (step 20b) .x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= Curies
-0 I I l Accumulated Thyroid Dose at EAB 1 I i
- 27. Calculate the dose received at the EAB.
a) Reactor Building Louvers Dose =
= (step 22a) x (step 3)
= Rem l
b) PCRV Safety Valves Dose = (step 22b) x (step 3) l
)x(
=( ) l l
= Rem I NOTE: This calculation assumes the recipient was at the EAS for the entire duration of the release.
O l F0F4M 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRA!N NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 9 of 10 O I I r l Projections l I I
- 28. If the release is continuing, consult with the Shift Supervisor l and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has terminated, enter value from step 3.
[ 1 Preliminary estimate of release hours hour (s).
- 29. Project the total thyroid dose at the EAB.
a) Reactor Building Louvers l Projected Dose at EAB = (step 22a) x (step 28)
=( )x( )
,= Rem b) PCRV Safety Valves Projected Dose at EAB = (step 22b) x (step 28)
=( )x( )
= Rem I
l 30. Determine the recommended protective action for the general l population based on the results of Steps 18 and 29. Refer to RERP-PAG. l l I I l Summary l 1 1
- 31. The whole body gamma dose rate at the EAB is (Step lla or lib): Rem /hr
- 32. The classification of the event based on noble gases is (Step 12 or Step 13 or Step 14):
. 33. The noble gas release rate is (Step 8a or 8b): Ci/sec 1
l FORM 372 22 3643 l
1 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT I FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 l Page 10 of 10 O
- 34. The accumulated whole body gamma dose at the EAB is (Step 16a or 16b): Rem
- 35. The total number of curies of noble gas released to the present time is (Step 15a or 15b): Curies
- 36. The projected whole body gamma dose at the EAB is (Step 18a or 18b): Rem
- 37. Based on projected release duration of (Step 17):
hours
- 38. The thyroid dose rate at the EAB is (Step 22a or 22b): Rem / hour
- 39. *The classification of the event based on 1'11 equivalent is (Step 23 or Step 24 or Step 25):
- 40. The l'21 equivalent release rate is (Step 20a or 20b): Ci/sec
~ vp' 41. The accumulated thyroid dose at the EAB is (Step 27a or 27b): Rem
- 42. The total number of curies of 2'2I equivalent released to the present time is (Step 26a or 26b): Curies 1
- 43. The projected thyroid dose at the EAB is (Step 29a or 29b): Rem Based on projected release duration of ,
(Step 28): hours ! l 1
*If this classification differs from the classification in Step 31, the higher (i.e., more severe) classification is to be used to determine recommended protective action.
I l 1 O FORM 372 22 - 3643
~
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Pagt 1 of 6 O WORKSHEET 4 ASSESSMENT OF RELEASE USING TI-59 CALCULATOR PROGRAM-UNMONITORED RELEASE This attachment is only to be used if the TI-69 calculator program is used. If the program is ny used, use Worksheet 3. This attachment is used to determine the following due to an unmor.itored release via the Reactor Building Louvers or the PCRV Relief Valves: a) Estimated whole body and thyroid gamma dose and dose rates at the EAB; b) Classification of the release; c) Projected whole body and thyroid gamma dose at the EAB; and d) Recommended protective action for the general population.
- 1. Collect the following data:
a) Date/ Time of beginning of release: b) Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation: c) Hours between la) and Ib): hours (ST0 07) d) Maximum CPM, RIS-9301: cpm (RR-93256,Pt. 10) (STO 01) e) Sensitivity RIS-9301: pCi/cc/ cpm (STO 02) f) Primary Coolant 222I equivalent Ci circulating inventory: (posted) (STO 03) . g) Primary Coolant 222 equivalent Ci plateout inventory: (posted) (ST0 04) h) Primary Coolant Volume: (posted) cc - (ST0 05) O v FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Page 2 of 6 O
- 1) Site Emergency Limit: { posted)1) 6.6E-2 pCi/cc noble gas
- 2) 6.7E-5 pCi/cc 2'2I j) Ten Times Technical Specification Limits (posted):
1,1].5E-2 pC1/cc noble gas
- 2) 7.0E-8 pCi/cc 2'2I k) Average Wind Speed at 10 meters: mph
- 1) Wind Direction at 10 meters:
NOTE: North = 0 increasing uegrees-c.w. From Degrees m) Differential Temperature F Circle instrument used 60m Tower Reactor Building m
~
- 2. Deteratine sectors affected using Site Sector Map (Figure 3):
Sector (s)
- 3. Determine Stability Category using Table 5 and Steps 1.1) and 1.m).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building 4T instruments used.
- 4. Determine the EAB dilution factor from Attachment 1 using the Stability Category (Step 3) and wind speed (Step Ik).
Dilution Factor sec/m' (ST0 06) O FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Paga 3 of 6 O
- 5. If the release is continuing, consult with the Shift Supervisor and estimate the total number
- of hours the release will continue (i.e., from beginning to end). If the release has te- -
nated, enter value from step 1.c). Preliminary estimate of release hours hours.(STO 08)
- 6. Prepare the TI-59 for data entry.
l a) Place TI-59 in printee/ security c adle. l I b) Plug in print ar/ security cr adle. l c) Turn on printer / security cradle a_nd TI-59. d) Depress " TRACE" button on printer. e) Obtain the magnetic card labeled "FSV Off-Site Dose Calculation (RERP) - Unmonitored Release." f) Read magnetic card into TI-59. , 1) Depress lIl,lMl ,l@l , l WRITE l keys. !~p 1 U 2) Insert magnetic card into right side of TI-59. Card should be right side up with the "1" in the upper left-hand corner.
- 3) "1" will be displayed if the ccrd was read properly - continue with Step 6f)4). If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card witt, the same title and repeat Step 6f).
- 4) Depress 12l , II!LVI ,12Ml , l WRITE l keys.
- 5) In>ert card into right side of TI-59.
Card should be upside aown with the "2" in the lower left-hand corner.
- 6) "2" will be displayed if the card was read properly - continue with Step 7. If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card with the same tit el and repeat Step 6f).
V FORM 372 22 + 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Page 4 of 6 O
- 7. Input the necessary data into the indicated TI-59 storage registers.
a) Step Ic) = l@l 07 b) Step Id) = l@l 01 c) Step le) = l@l 02 d) Step If) = l@l 03 e) Step ig) = l@l 04 f) Step lb) = l@l 05 g) Step 4 = j@l 06 h) Step 5 = l@l 08
- 8. Run Dose Assessment Program. l a) Depress l@l key.
b) Wait until a number is displayed. A flashing number indicates improper execution of the pro yam. Depressl@ land l@l keys and repeat Steps 7 and 8. l 1 1 l O 1 FOR M 372 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Page 5 of 6 l
SUMMARY
l
- 9. a) The release path is: )
- 1) Reactor Building Louvers j
- 2) PCRV Reliefs 1 b) The whole body gamma dose at the EAB is (RCL 12 for louver,,
RCL 13 for reliefs). rem / hour c) The classification of the event based on noble gases is:
- 1) If Step 10b) 2 1 Rem / hour, GENERAL EMERGENCY.
- 2) If Step 10c) 2 9.6E-1 Ci/sec SITE AREA EMERGENCY.
- 3) If Step 10c) 2 3.7E-1 Ci/sec and s 9.6E-1 Ci/sec, N RADIOLOGICAL ALERT.
~ {d If RCL 11 2 9.6E-1 Ci/sec, 4)
SITE AREA EMERGENCY.
- 5) If RCL 11 > 3.7E-1 Ci/sec and < 9.6E-1 Ci/sec, RADIOLOGICAL ALERT.
e) The accumulated whole body gamma dose at the EAB is (RCL 16 for louvers, Nem RCL 17 for reliefs): f) The total number of curies of noble gas released to the present time is (RCL 14 for louvers, RCL 15 Ci for reliefs): g) The projected whole body gamma dose at the EAB is (RCL 18 for louvers, Rem RCL 19 for relief s): Based on a projected release duration hours - of (RCL 08)- O FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION klorksheet 4 l Issue 16 Page 6 of 6 f h) The thyroid dose rate at the EAB is (RCL 24 for louvers, RCL 25 i for reliefs): Rem / hour
- 1) The 132 equivalent release rate is (RCL 22 for louvers, RCL 23 for reliefs): Ci/sec
*j) The classification of the event based on 222I equivalent is:
- 1) If Step 10h) 2 5 Rem / hour, I GENERAL EMERGENCY.
l 2) If Step 101) 2 9.8E-4C Ci/sec l SITE AREA EMERGENCY l 3) If Step 101) 2 1.0E-7 Ci/sec and + 9.8E-4 Ci/sec RADIOLOGICAL ALERT. l k) The accumulated thyroid dose at the EAB is (RCL 28 for louvers, RCL 29 for reliefs): Rem r The total number of curies of 2'1I
~
1) equivalent released to the present time is (RCL 26 for louvers, RCL 27 for reliefs): Ci m) The projected thyroid do'se at the EAB l is (RCL 30 for louvers, RCL 31 i for reliefs): Rem
]
l Based on projected release duration l of (RCL 08): hours l 1
-10 . Determine the recommended protective action for the general l population. Refer te RERP-PAG.
*If this classification differs from the classification in Step 10b),
the higher (i .e. , more severe) classification is to be used to determine recommended protective actions. S
. l l
i (> F OR M 372 22 - 3643 l l l
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 16 Page 1 of 3 O Work /Datasheet/ Checklist Control List Worksheet No. Title Number Cooies 1 Monitored Release Calculations (Manual) 2 2 Monitored Release Calculations (TI-59) 2 3 Unmonitored Release Calculations (Manual) 2 4 Unmonitored Release Calculations (TI-59) 2 Datasheet No. 1 Datalogger Monitored Release 5 2 Datalogger Unmonitored Release 2 3 Preliminary Assessment of Plant Conditions 2
-O Checklist No.
1 Emergency Coordinator / Control Room 2 Director Checklist Attachment No. I Notification to Activate State Emergency 2 Response Centers e O FORM 372 - 22 3443
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 16 Page 2 of 3 O V FORMS USE REPORTING SHEET Technical Clerk and Recorder: This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at
. The following forms have been utilized from this copy:
Worksheet Numbers Copies Used em
- k s)
- Datasheet Numbers Copies Used l
l l Checklist Numbers Copies Used 1 i
- The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book.
([]) F ORM 372 36G
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 16 Page 3 of 3 FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: Technical Clerk and Recorder Date Received Date Replaced l Technical Clerk and Recorder will transmit this form to the originating individual / department upon completion of this form to rotify users that the procedure has been updated and that all l - [^g v worksheets, checklists, and datasheets are present in the required number of copies. l l l l O FORM 372 22 3643
I PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue I6 Page 1 of 9 O WORKSHEET 1 ASSESSMENT OF RELEASE-MONITORED RELEASE This attachment is to be used only if the TI-59 calculator program is not used. If the TI-59 is used, Worksheet 2 is to be used. . This attachment is used to determine the following: a) Estimated noble gas and iodine release and release rate; b) The estimated whole body and thyroid gamma dose and dose rate at the EAB; c) Classification of the release; d) Projected whole body and thyroid gamma dose at the EAB; and e) Recommended protective action for the general population.
- 1. Date/ Time of beginning of release.
- 2. Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation.
(
- 3. Hours between 1. and 2.
- 4. Collect the following data:
a) Maximum CPM, RIS-7324-1: (RR-93539, red pen) cpm b) Sensitivity, RIS-7324-1: (I-14, 403-P7) pCi/cc/ cpm c) Maximum CPM,'RIS-7324-2: (RR-93539, blue pen) cpm d) Sensitivity, RIS-7324-2: (I-14,203-P7) pCi/cc/ cpm e) Maximum CPM / Min, RIS-73437-1: cpm / min NOTE: Maximum CPM / Min must be calculated as: (Maximum CPM - Initial or Intermediate CPM) ( Elapsed Time (min) ) from strip chart. FORM 372 - 22 36CB
i. PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST VRAIN NUCLEAR GENERATING STATION Worksheet 1 f Issue 16 Page 2 of 9 O f) Sensitivity, RIS-73437-1: vC1/cc/ cpm / min g) Site Area Emergency Limit (as posted):
- 1) 6.6E-2 uC1/cc noble gas
- 2) 6.7E-5 uti/cc '2I i
h) Ten Times Technical Specification Limits (as posted):
- 1) 2.5E-2 uCi/cc noble gas
- 2) 7.0E-8 vC1/cc2 '2I i) Exhaust Stack Flow (cfm):
(I-15, FI-7320) cfm j) Exhaust Stack Flow (cc/sec): i (Step 41 x 4.72E + 2) cc/sec l k) Average Wind Speed , at 10 meters: mph
- 1) Wind Direction at 10 meters: Degrees
-Q From NOTE: North = 0* increasing degrees - c.w.
m) Differential Temperature: *F Circle appropriate instrument [ 60m tower Reactor Building
- 5. Determine sectors affected using Site Sector Map.
(Figure 3) Sector (s)
- 6. Determine Stability Category using Table 5, Step _4k), and 4m).
Stability Category
. NOTE: Use proper column based on l
whether 60m tower or reactor building l AT instruments used. O FORM 372 22 3643 l
I ', r FUBlic SERVICE COMPANY OF COLORADO CR ALERT
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l F'RT ST. VRAIN NUCLEAR CENERATING STATION Worksheet I
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Issue 16 Page 3 of 9 O I I l Noble Gas Concentration l l l
- 7. Calculate the exhaust stack noble gas concentration.
a) RIS-7324-1 concentration = (step 4a) x (step 4b)
=( )x( )
= pCi/cc b) RIS-7324-2 concentration = (step 4c) x (step 4d)
=( )x( )
= pCi/cc c) If either RIS-7324-1 or RIS-7324-2 is off-scale high, record the stack concentration as obtained by local, portable instrument (refer to HPP-56 or Attachment 3 for instructions).
~O 'ece, 1#aic tee co#ceatretio# = uc4/cc d) Enter the highest of 7a), 7b), or 7c) pC1/cc I I Noble Gas Release Rate l l l l l
- 8. Calculate the Source Term, Q (i.e., Noble Gas Release Rate).
/
Q = (step 7d) x (step 4j) x (1 E -6 Ci/pci)
=( )x( ) x (1 E -6)
= C1/sec l
G O FORM 372- 22 3643 1
I - PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 4 of 9 l I l Classification of Event l I I
- 9. Determine weighted noble gas dose conversion factor from Table 2. 7.5E+2 Rem / hour 3
C1/m
- 10. Determine the EAB dilution factor from Attach-ment I using the Stability Category (Step 6) and wind speed (Step 4k).
Dilution Factor = sec/m' General Emeroency Determination
- 11. Determine whole body dose rate at the EAB.
Dose Rate = (step 8) x (step 9) x (step 10)
=( )x( )x( )
1
= Rem / hour
-O if the reso, ting dose rate at the EAB is 2 1 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the i
Shift Supervisor of the General Emergency condition. Then go directly to Step 14 of this attachment. l Site Area Emergency Determination
- 12. Criteria for Site Emergency: If Step 7d) is greater than or equal to 6.6E-2 pCi/cc, the classification of the event is SITE AREA EMERGENCY. Inform the Sbift Supervisor of the Site Emergency Condition. Then go directly to Step 14 of this attachment.
Radiological Alert Determination
- 13. Criteria for Radiological Alert: If Step 7d) is greater than or equal to ten times the Technical Specificatio.: limit 2.5E-2 pCi/cc*, the classification of the event is RADIOLOGICAL ALERT.
Inform the Shift Sunervisor of the Radiological Alert Condition. Then proceed with Step 14. '~
- NOTE: Technical specification limit = 2.5E-3pci/cc 10x Technical Specification limit = 2.5E-2 vCi/ce, as stated above.
G O FORM 372 22 3643
I- PUBLIC SERVICE COMPANY OF COLORADO CR ALER1
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 l' Issue 16 Page 5 of 9 O I l l Curies of Noble Gas Released i I i
- 14. Calculate the curies of noble gas released to present time.
Curies released = (step 8) x (step 3) x (3.6 E +3 s/hr)
=( )x( ) x (3.6 E +3)
= Curies l I I Accumulated Whole Body Gamma Dose at EAB l l l I 15. Calculate the dose received at the EAB.
Dose = (step 11) x (step 3)
~O =c )xc >
= Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release. .
I I l Projections l I i
- 16. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has terminated, enter value from step 3.
- Preliminary estimate of release hours hours.
lC O FORM 372 22 3643 l
I g.' . PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 6 of 9 O 17. Projr_::t'the totoal whole body gamma dose at the EAB. Projected dose at EAB = (step 11) x (step 16)
=( )x( )
= Rem 1 .I l 131 I Concentration l l 1
- 18. Calculate the exhaust stack 2'2I concentration.
RIS-73437-1 concentration = (step 4e) x (step 4f)
=( )x( )
= pC1/cc I I l 1311 and Total Radiciodine Release Rate l
~O i i
- 19. Calculate the source term Q (2'2I release rate).
Q = (step 18) x (step 4j) x (1 E -6)
=( )x( ) x (1 E -6)
= C1/sec
- 20. Calculate Q T f r total radiciodine release.
Q T = (step 19) x (1.05 E + 2)* I
=( ) x (1.05 E + 2)*
= Ci/sec l'
1
- Ratio of total radiciodines to 2821 in design inventory.
I G O FORM 372 - 22 3643 2
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- FORT ST. VRAIN NUCLEAR GENERATING STATION Worksh:et 1 Issue 16 Page 7 of 9 O
l l l Classification of Event i l i
- 21. Determine weighted radioiodine dose conversion factor from Attachment 8. 5.3E+4 Rem / hour C1/m 3 General Emeroency Determination
- 22. Determine the thyroid dose rate at the EAB.
Dose Rate = (step 20) x (step 21) x (step 10)
=( )x( )x( )
= Rem / hour If the resulting dose rate at the EAB is 2 5 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency Condition. Then go directly to Step 25 of this attachment.
~ () Site Area Emergency Determination
- 23. Criteria for Site Area Emergency: If Step 18 is great than or equal to 6.7E-5 pCi/ce, the classification of the event is SITE
! EMERGENCY. Inform the Shift Supervisor of the Site Emergency ! Condition. Then go directly to Step 25 of this attachment. Radiolooical Alert Determination l 24. Criteria for Radiological Alert: If Step 18 is greater than or equal to ten times the Technical Specification limit 7.0E-8 pCi/cc*, the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 25. i NOTE: Technical Specification Limit = 7.0E-9uC1/cc 10x Technical Specification Limit = 7.0E-8pC1/ce, as stated above. V Q FORM 372 22 3643
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I PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 8 of 9 O l l 1 Curies of Radiciodine Released i I I
- 25. Calculate the curies of radiciodine released to present time.
Curies Released = (step 20) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= curies
! l l Accumulated Thyroid Dose at EAB l l l
- 26. Calculate the dose received at the EAB.
Dose = (step 22) x (step 3)
. =( )x( )
= Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
I I l Projections i I I l 27. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has terminated, enter value from step 3. Preliminary estimate of release hours hours.
- 28. Project the total thyroid dose at the EAB.
Projected Dose at EAB = (ste; ?2) x (step 27)
=( )x( )
= Rem O
Q' F OR M 372 - 22 3643
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1 lt , y PUBLIC SERVICE COMPANY OF COLORADO CR ALEr.T FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet I
~{d v Issue 16 o Page 9 of 9 i
/
O 29. Determine the recommended protective action fo: the general population based on the results of steps 17 and 28, refer to l RERP-PAG.
- 30. The whole body gamma dose rate at the EAB is (step 11): Rem / hour
- 31. The classification of the event based on noble gases is (step 11 or step 12 or step 13):
- 32. The noble gas release rate is (step 8): Ci/sec
- 33. The accumulated whole body gamma dose at the EAB is (step 15): Rem
- 34. The total number of curies of noble gas release to the present time is (step 14): Curies
- 35. The projected whole body psmma dose at the EAB is (step 17): Rem Based on projected release duration of (step 16): hours
- 36. The thyroid dose rate at the EAB is (step 22): Rem / hour
-O 37. The ciassification of the event besed on radio-iodines is (step 22 g step 23 o_r step 24):
- 38. The radioiodine release rate is (step 20): Ci/sec
- 39. The accumulated thyroid dose at the EAB is (step 26): Rem
- 40. Th2 total nuri.ber of curies of radiciodine released to the present time is (step 25): _ Curies
- 41. The projected thyroid dose at the EAB is (step 28): Rem Based on projected release duration of (step 27): hours
,. *If this classification differs from the classification in step 31, the higher (i.e. , more severe) classification is to be used to determine recommended protective action.
O FORM 372 3643 e--
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,7 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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. FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 1 of 9 O
WORKSHEET 1 ASSESSMENT OF .iELEASE-MONITORED RELEASE This attachment is to be used only if the TI-59 calculator program is ng used. If the TI-59 is used, Worksheet 2 is to be used. This attachment is used to determine the following: a) Estimated noble gas and iodine release and release rate; b) The estimated whele body and thyroid gamma dose and dose rate at the EAB; c) Classification of the release; d) Projected whole body and thyroid gamma dose at the EAB; and e) Recommended protective action for the general population.
- 1. Date/ Time of beginning of release.
s 2. Date/ Time of endi , of release. If release is still occurring, enter the Date/ Time of the calculation. _
- 3. Hours between 1. and 2.
- 4. Collect the following data:
a) Maximum CPM, RIS-7324-1: (RR-93539, red pen) cpm b) Sensitivity, RIS-7324-1: (I-14,403-P7) yCi/cc/ cpm c) Maximum CPM,'RIS-7324-2: l (RR 93539, blue pen) cpm d) Sensitivity, RIS-7324-2: (I-14,203-P7) pCi/cc/ cpm e) Maximum CPM / Min, RIS-73437-1: _ cpm / min NOTE: Maximum CPM / Min must be calculated as: l * (Maximum CPM - Initial or Intermediate CPM) ( Elspsed Time (min) ) from strip chart. FORM 372 22 - 3643
-)
'1 - PUBl.lC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 g Issue 16 Page 2 of 9 O Sensitivity, RIS-73437-1: pCi/cc/ cpm / min f) g) Site Area Emergency Limit (as posted):
- 1) 6.6E-2 uC1/cc noble gas
- 2) 6.7E-5 pC1/cc2 '2I h) Ten Times Technical Specification Limits (as posted):
- 1) 2.5E-2 uCi/cc noble gas
- 2) 7.0E-8 uti/cc '2I 2
i) Exhaust Stack Flow (cfm): (I-15, FI-7320) cfm j) Exhaust Stack Flow (cc/sec): (Step 41 x 4.72E + 2) cc/sec k) Average Wind Speed at 10 meters: mph
- 1) Wind Direction
-O at 20 meters: From oeerees NOTE: North = 0* increasing degrees - c.w.
m) Differential Temperature. __' F Circle appropriate instrument 60m tower Reactor Building
- 5. Determine sectors affected using Site Sector Map.
(Figure 3) Sector (s)
- 6. Determine Stability Category using Table 5, Step 4k), and 4m).
Stability Category
. NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
o O FORM 372 22 - 3643
E PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 3 of 9 O I I l Noble Gas Concentration l I I
- 7. Calculate the exhaust stack noble gas concentration.
a) RIS-7324-1 concentration = (step 4a) x (step 4b)
=( )x( )
= uCi/cc b) RIS-7324-2 concentration = (step 4c) x (step 4d)
=( )x( )
= pC1/cc c) If either RIS-7324-1 or RIS-7324-2 is off-scale high, record the stack concentration as obtained by local, portable instrument (refer to HPP-56 or Attachment 3 for instructions).
-O tocai Indicatea Concentratioa = .C1/cc d) Enter the highest of 7a), 7b), or 7c) pCi/cc I i l Noble Gas Release Rate l 1 I
- 8. Calculate the Source Term, Q (i.e., Noble Gas Release Rate).
Q = (step 7d) x (step 4j) x (1 E -6 Ci/pci) t l (
=( )x( ) x (1 E -6)
= Ci/sec l .
O FORM 372 22 3643 i
l5 ' PUBLIC SERVICE COMPANY OF COLORADO CR ALERT Worksheet'l FORT 5T. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 4 of 9 O I I l Classification of Event i I I
- 9. Determine weighted noble gas dose conversion ,
factor from Table 2. 7.5E+2 Rem / hour Ci/m'
- 10. Determine the EAB dilution factor from Attach-ment I using the Stability Category (Step 6) and wind speed (Step 4k).
Dilution Factor = sec/m' General Emeraency Determination
- 11. Determine whole body dose rate at the EAB.
Dose Rate = (step 8) x (step 9) x (step 10)
=( )x( )x( )
l
= Rem / hour
-O If the resulting dose rate at the EAB is 2: 1 Rem / hour, the V
classification of the event is GENERAL EMERGENCY. Inform tne Shift Supervisor of the General Emergency condition. Then go directly to Step 14 of this attachment. Site Area Emeroency Determination
- 12. Criteria for Site Emergency: If Step 7d) is greater than or equal to 6.6E-2 pCi/cc, the classification of the event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Emergency Condition. Then go directly to Step 14 of this attachment.
Radiological Alert Determination 1
- 13. Criteria for Radiological Alert: If Step 7d) is greater than or equal to ten times the Technical Specification limit 2.5E-2 pCi/cc*, the classification of the event is RADIOLOGICAL ALERT.
Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 14. l
- NOTE: Technical specification limit = 2.5E-3pCi/cc 10x Technical Specification limit = 2.5E-2 pCi/ce, I as stated above.
l O F OR M 372 3643 l
f PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 Page 5 of 9 0 l l l Curies of Noble Gas Released l l l
- 14. Calculate the curies of noble gas released to present time.
Curies released = (step 8) x (step 3) x (3.6 E +3 s/hr)
=( )x( ) x (3.6 E +3)
= Curies i I I Accumulated Whole Body Gamma Dose at EAB l l l
- 15. Calculate the dose received at the EAB.
l ! Dose = (step 11) x (step 3)
)x(
~
=( )
= Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
l l l l Projections l l l
- 16. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue l
(i.e., from beginning to end). If the release has terminated, enter value from step 3. Preliminary estimate of release hours hours. O FORM 372 22 3643 l
i _ PUBLIC SERVICE COMPANY OF COLORADO CR ALERT 5' FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 1 Issue 16 , Page 6 of 9 O
- 17. Project'the totoal whole body gamma dose at the EAB.
i Projected dose at EAB = (step 11) x (step 16)
=( )x( )
= Rem l 131 I Concentration l l l l l 18. Calculate the exhaust stack 2'11 concentration.
RIS-73437-1 concentration = (step 4e) x (step 4f)
=( )x( )
= pC1/cc l
l l 1 _ l 131I and Total Radioiodine Release Rate
- 19. Calculate the source term Q (2'2I release rate).
< Q = (step 18) x (step 4j) x (1 E -6)
=( )x( ) x (1 E -6)
= Ci/sec
- 20. Calculate Q T f r total radiciodine release.
Q T = (step 19) x (1.05 E + 2)*
=( ) x (1.05 E + 2)*
= Ci/sec
- Ratio of total radioiodines to 22 2I in design inventory.
O FORM 372 22 3643
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4 - PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATH)N t!orksheet 1 Issue 16 Page 7 of 9 I i l Classification of Event l l l
- 21. Determine weighted radioiodine dese conversion factor from Attachment 8. 5.3E+4 Rem / hour C1/m' General Emergency Determination
- 22. Determine the thyroid dose rate at the EAB.
Dose Rate = (step 20) x (step 21) x (step 10)
=( )x( )x( )
= Rem / hour If the resulting dose rate at the EAB is 2 5 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emercancy Condition. Then go directly to Step 25 of this attachment.
~() Site Area Emergency Determination
- 23. Criteria for Site Area Emergency: If Step 18 is great than or equal to 6.7E-5 pCi/cc, the classification of the event is SITE EMERGENCY. Inform the Shift Supervisor of the Site Emergency Condition. Then go directly to Step 25 of this attachment.
Radiolooical Alert Determination f 24. Criteria for Radiological Alert: If Step 18 is greater than or equal to ten times the Technical Specification limit 7.0E-8 pCi/cc*, the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 25. NOTE: Technical Specification Limit = 7.0E-9pC1/cc 10x Technical Specification Limit = 7.0E-8uCi/ce, as stated above. O F OR M 372 22 - 36G
4 - PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VR AIN NUCLEAR GENERATING STATION Morksheet 1 Issue 16 Page 8 of 9 (j) l l l Curies of Radiciodine Released I I I
- 25. Calculate the curies of radiciodine released to present time.
Curies Released = (step 20) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= curies i I l Accumulated Thyroid Dose at EAB l l 1
- 26. Calculate the dose received at the EAB.
Dose = (step 22) x (step 3) _ %/ (3 =( )x( )
= Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
I I I Projections l I 1 1
- 27. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hours.
- 28. Project the total thyroid dose at the EAB.
Projected Dose at EAB = (step 22) x (step 27)
=( )x( )
= Rem O
FORM 372 22 364
i g' ' PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION !*!orksheet I h Issue 16 Page 9 of 9 O 29. Determine the .ecommended protective action for the general population based on the results of steps 17 and 28, refer to RERP-PAG.
- 30. The whole body gamma dose rate at the EAB is (step 11): Rem / hour
- 31. The classification of the event based on noble gases is (step 11 or step 12 or step 13):
- 32. The noble gas release rate is (step 8): Ci/sec -
- 33. The accumulated whole body gamma dose at the EAB is (step 15): Rem
- 34. The total number of curies of noble gas release to the present time is (step 14): Curies
- 35. The projected whole body gamma dose at the EAB is (step 17): . Rem Based on projected release duration of (step 16): hours
- 36. The thyroid dose rate at the EAB is (step 22): Rem / hour l -O
- 37. *The classification of the event based on radio-iodines is (step 22 or step 23 or step 24):
- 38. The radioiodine release rate is (step 20): C1/sec
- 39. The accumulated thyroid dose at the EAB is (step 26): Rem
- 40. The total number of curies of radioiodine i
released to the present time is (step 25): Curies
- 41. The projected thyroid dose at the EAB is (step 28): Rem -
Based on projected release duration of (step 27): hours
*If this classification differs from the classification in step l
l 31, the higher (i.e., more severe) classification is to be used to determine recommended protective action. I. 8 O j FORM 372 22 3643
i PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 1 of 7 O WORKSHEET 2 , ASSESSMENT OF RELEASE USING TI-59 CALCULATOR PROGRAM-MONITORED RELEASE This attachment is only to be used if the TI-59 calculator program is used. If the program is not used, use Worksheet 1. This attachment is used to determine the following: a) Estimated noble gas and radiciodine release and release rate;
, b) Estimated whole body and thyroid gamma dose and dose rate at the EAB; c) Classification of the release; d) Projected whole body and thyroid gamma dose at the EAB; and e) Recommended protective action for the general population.
- 1. Collect the following data:
~ () a) Date/ Time of beginning of release:
b) Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation: I c) Hours between la) and Ib): hours (ST0 11) Maximum CPM, RIS-7324-1: cpm d) (RR-93539, red pen) (STO 03) e) Sensitivity RIS-7324-1: pCi/cc/ cpm (I-14,403-P7) (STO 04) f) Maximum CPM, RIS-7324-2: cpm (RR-93539, blue pen) (STO 05) g) Sensitivity, RIS-7324-2: pCi/cc/ cpm (I-14,203-P7) (STO 06) O ls FORM 372 - 22 3643 l
i , PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 2 of 7 O
*h) Maximum mR/hr, Cutie Pie-2520 Probe: mR/hr (STO 01)
*i) Maximum mR/hr, E-500-GM Probe mR/hr (STO 02) j) Maximum CPM / MIN, RIS-73437-1: cpm / min (STO 07)
NOTE: Maximum CPM / Min must be calculated as: (Maximum CPM - Initial or Intermediate CPM) ( Elapsed Time (min) ) from strip chart. k) Sensitivity, RIS-73437-1: uCi/cc/ cpm /mir (STO 08)
- 1) Site Emergency Limit (as posted): 1) 6.6E-2 pCi/cc noble gas
- 2) 6.7E-5 pC1/cc 182I
-O m) Ten Times Techeice, Specification Limits (as posted): 1) 2.5E-2 pCi/cc noble gas
- 2) 7.0E-8 vCi/cc l'2I n) Exhaust Stack Flow (cfm):
(I-15,CI-7320) cfm (STO 09) o) Average Wind Speed at 10 meters: mph p) Wind Direction at 10 meters: NOTE: North = 0 increasing degrees-c.w. From Degrees q) Differential Temperature *F Circle appropriate instrument 60m Tower Reactor Building
- Steps lh) and li) used only if RIS-7324-1 or RIS-7324-2 off-scale high.
O 4 FORM 372 22 3643
i PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 h Issue 16 Page 3 of 7 O
- 2. Determine sectors affected using Site Sector Map (Figure 3):
Sector (s)
- 3. Determine Stability Category using Table 5 and Steps lo) and Iq).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
- 4. Determine the EAB dilution factor from Attachment I using the Str.bility Category (Step 3) and wind speed (Step lo).
Dilution Factor sec/m' (ST0 10)
- 5. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has termi-nated, enter value from step Ic).
~
Preliminary estimate of release hours hours. (ST0 12) l l l l O 5 FORTA 372 22 3643
1 ~ ~ PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 4 of 7 O 6. Prepare the TI-59 for data entry. a) Place TI-59 in printer / security cradle. b) Plug in printer / security cradle, c) Turn on printer / security cradle and TI-59. d) Depress " TRACE" button on printer. e) Obtain the magnetic card labeled "FSV Off-Site Dose Calculation (RERP) - Monitored Release." f) Read magnetic card into TI-59.
- 1) Depress lI] ,lINVl , l2ndl , l WRITE l keys.
- 2) Insert magnetic card into rig'.t side of TI-59.
Card should be right side up with the "1" in the upper left-hand corner.
- 3) "1" will be displayed if the card was read properly -continue with Step 7. If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card
_O with the same title and repeat Step 6f). t l 4 O FORM 372 22 3643 l - - - - -
1 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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g' _. Worksheet 2 FORT ST. VRAIN NUCLEAR GENERATING STATION h' Issue 16 Page 5 of 7
- 7. Input the necessary data into the indicated TI-59 storage registers.
a) Step ic) = lST0[ 11 b) Step Id) = lSTOl 03 c) Step le) = lSTOl 04 d) Step If) = l3Tdl 05 . e) Step ig) = l@,l 06 l f) Step 1h) = lSTOl 01 g) Step li) = lSTOl 02 l _ h) Step lj) = lSTOl 07 i) Step Ik) = l5TDl 08 i j) Step in) = l5761 09 k) Step 4) = IST0[ 10 l) Step 5) = lSTol 12
- 8. Run Dose Assessment Program a) Depress l@l key.
b) Wait until a number is displayed. A flashing number indicates improper execution of the program. Depress l@landlIi57l keys and repeat Steps 7 and 8. lg FORM 372 22 3643
1 ~ PUSLIO SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION k!orksheet 2 Issue 16 Page 6 of 7 O l
SUMMARY
l
- 9. a) The whole body gamma dose rate at the EAB is(RCL 19): Rem / hour b) The classification of the event based on noble gases is:
- 1) If Step 10.a) 2 1 Rem / hour, GENERAL EMERGENCY.
- 2) If RCL 17 2 6.6E-2 pCi/cc (Step 1.1)1),
SITE AREA EMERGENCY.
- 3) If RCL 17 2 2.5E-2 pCi/cc (Step 1.m)1) and s 6.6E-2 pCi/cc, RADIOLOGICAL ALERT. ;
c) The noble gas release rate is (RCL 18): Ci/sec d) The accumulated whole body gamma dose at the EAB is (RCL 21): Rem e) The total number of curies of noble O gas released to the present time is (RCL 20): Ci f) The projected whole body gamma dose at the EAB is (RCL 22): Rem g) The thyroid dose rate at i.he EAB is (RCL 27): Rem / hour 4 4 O ! FORM 372 - 22 3643
? -
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 h' ' Issue 16 Page 7 of 7 l O The classification of the event
*h) based on radiciodines is:
- 1) If Step 10.g) 2 5 Rem / hour, GENERAL EMERGENCY.
- 2) If RCL 23 2 6.7E-5 pCi/cc (Step 1.1)2),
SITE AREA EMERGENCY.
- 3) If RCL 23 2 7.0E-8 pCi/cc (Step 1.c)2) and
< 6.7E-5 uCi/cc, RADIOLOGICAL ALERT.
- 1) The radiciodine release rate is (RCL 26): Ci/sec j) The accumulated thyroid dose at the EAB is (RCL 29): Rem k) The total number of curies of radiciodine released to the present time is (RCL 28): Ci 1 ~O 1) The presectea 18vroid dose at the EAB is (RCL 30): Rem l
Based on projected release duration of (RCL 12): hours
- 10. Determine the recommended protective action for the general population based on RERP-PAG.
- If this classification differs from the classification in Step 10b), the higher (i .e. , more severe) classification is to be used to determine recommended protective actions.
l l e 4 O FORM 372 22 - 3643
1 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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g(,+ FORT ST. VF.AIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 1 of 7 O WORKSHEET 2 ASSESSMENT OF RELEASE USING TI-59 CALCULATOR PROGRAM-MONITORED RELEASE This attachment is only to be used if the TI-59 calculator program is used. If the program is not used, use Worksheet 1. This attachment is used to determine the following: a) Estimated noble gas and radioiodine release and release rate; b) Estimated whole body and thyroid gamma dose and dose rate at the EAB; c) Classification of the release; d) Projected whole body and thyroid gamma dose at the EAB; and e) Recommended protective action for the general population.
- 1. Collect the following data:
~O a) o teetime or be91 nnin9 or reie se:
b) Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation: c) Hours between Ia) and Ib): hours (STO 11) Maximum CPM, RIS-7324-1: cpm d) (RR-93539, red pen) (STO 03) e) Sensitivity RIS-7324-1: pC1/cc/ cpm (I-14,403-P7) (STO 04) flaximum CPM, RIS-7324-2: cpm l f) (RR-93539, blue pen) (STO 05) g) Sensitivity, RIS-7324-2: pCi/cc/ cpm (I-14,203-P7) (STO 06) i f i O F OR M 372 - 22 3643
? PUBLIC SERVICE COMPANY OF COLORADO CR ALERT g\
- FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 2 of 7 O Maximum mR/hr, Cutie Pie-2520 Probe: mR/hr "h)
(STO 01)
*i) Maximum mR/hr, E-500-GM Probe mR/hr (STO 02) j) Maximum CPM / MIN, RIS-73437-1: cpm / min (STO 07)
NOTE: Maximum CPM / Min must be calculated as: (Maximum CPM - Initial or Intermediate CPM) ( Elapsed Time (min) ) from strip chart. k) Sensitivity, RIS-73437-1: uC1/cc/ cpm /mir (STO 08)
- 1) Site Emergency Limit (as posted): 1) 6.6E-2 uCi/cc noble gas
- 2) 6.7E-5 pC1/cc 222I
~O m) Ten Times Technical Specification Limits (as posted): 1) 2.5E-2 uCi/cc noble gas
- 2) 7.0E-8 uCi/cc 2'2I n) Exhaust Stack Flow (cfm):
(I-15, FI-7320) cfm (ST0 09) o) Average Wind Speed at 10 meters: mph p) Wind Direction at 10 meters: NOTE: North = 0 increasing degrees-c.w. From Degrees q) Differential Temperature F Circle appropriate instrument 60m Tower Reactor Building
- Steps lh) and li) used only if RIS-7324-1 or RIS-7324-2 off-scale high.
4 O F OR M 372 - 22 3643 l
1 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 3 of 7 O Determine sectors affected using Site 2. Sector Map (Figure 3): Sector (s)
- 3. Determine Stability Category using Table 5 and Steps lo) and Iq).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
- 4. Determine the EAB dilution factor from Attachment 1 using the Stability Category (Step 3) and wind speed (Step lo).
Dilution Factor sec/m' (ST0 10)
- 5. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has termi--
nated, enter value from step Ic).
~() Preliminary estimate of release hours hours. (ST0 12) 14 O
FORM 372 22 36C3
? g. - PUBLIC SERVICE COMPANY OF COLORADO' CR ALERT '
FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 4 of 7 O 6. Prepare the TI-59 for data entry. a) Place TI-59 in printer / security cradle. b) Plug in printer / security cradle. c) Turn on printer / security cradle and TI-59. d) Depress " TRACE" button on printer. e) Obtain the magnetic card labeled "FSV Off-Site Dose Calculation (RERP) - Monitored Release." f) Read magnetic card into TI-59.
- 1) Depress ill , lINVl ,l@l , l WRITE l keys.
- 2) Insert magnetic card into right side o- TI-59.
Card should be right side up with the "." in the upper left-hand corner. I
- 3) "1" will be displayed if the card was read properly -continue with Step 7. If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card 4th the sa e title a#e repeat sten er).
_O i e a O FORM 372 22 3643 l
i PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 5 of 7 O 7. Input the necessary data into the indicated TI-59 storage registers. a) Step Ic) = l@l 11 b) Step Id) = l@l 03 c) Step le) = l@l 04 d) Step If) = l@l 05 e) Step ig) = l@l 06 f) Step 1h) = l@l 01 g) Step li) = lSTOl 02 _ h) Step lj) = ]@l 07 i) Step Ik) = l@l 08 j) Step in) = l@l 09 k) Step 4) = l5fDl 10 l
- 1) Step 5) =
l@l 12
- 8. Run Dose Assessment Program a) Depress l@l key.
b) Wait until a number is displayed. A flashing number indi cates improper execution of the program. Depress l@l and lii57] keys and repeat Steps 7 and 8. 5 4 O FORM 372 - 22 3643
! - o PUBLIC SERVICE COMPANY OF COLORADO CR ALERT ~
FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 16 Page 6 of 7 (1) l
SUMMARY
l
- 9. a) The whole body gamma dose rate at the .
EAB is(RCL 19): Rem / hour b) The classification of the event based on noble gases is:
- 1) If Step 10.a) 2 1 Rem / hour, GENERAL EMERGENCY.
- 2) If RCL 17 2 6.6E-2 pCi/cc (Step 1.1)1),
SITE AREA EMERGENCY.
- 3) If RCL 17 2 2.5E-2 pCi/cc (Step 1.m)1) and s 6.6E-2 pCi/ce, RADIOLOGICAL ALERT.
, c) The noble gas release rate is (RCL 18): Ci/sec d) The accumulated whole body gamma dose at the EAB is (RCL 21-): Rem e) The total number of curies of noble
~() gas released to the present time is (RCL 20): Ci f) The projected whole body gamma dose at the EAB is (RCL 22): Rem g) The thyroid dose rate at the EAB -
is (RCL 27): Rem / hour l 4 O FORM 372 22. M43 w -. _ - - .
g, PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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Worksheet 2 d' FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 T Page 7 of 7 O
*h) The classification of the event l based on radioiodines is: j
- 1) If Step 10.g) 2 5 Rem / hour, i GENERAL EMERGENCY. !
- 2) If RCL 23 2 6.7E-5 pCi/cc i (Step 1.1)2),
SITE AREA EMERGENCY.
- 3) If RCL 23 2 7.0E-8 pC1/cc (Step 1.m)2) and
< 6.7E-5 pC1/cc, RADIOLOGICAL ALERT.
- 1) The radiciodine release rate is (RCL 26): C1/sec j) The accumulated thyroid dose at the EAB is (RCL 29): Rem k) The total number of curies of radioiodine released to the present time is (RCL 28): Ci
~O 1) The projected thyroid dose at the EAB is (RCL 30): Rem Based on projected release duration of (RCL 12): hours
- 10. Determine the recommended protective action for the general ppulation based on RERP-PAG.
- If this classification differs from the classification in Step 10b), the higher (i .e. , more severe) classification is to be used to determine recommended protective actions.
4 O FORM 372 22 - 3643
& ~ ~' PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 1 of 10
() WORKSHEET 3 i I ASSESSMENT OF RELEASE-UNMONITORED RELEASE This attachment is to be used only if the TI-59 calculator program is l not used. If the TT-59 program is used, Worksheet 4 is to be used. i This attachment is used to determine the following due to an unmonitored release via the Reactor Building Louvers or the PCRV ' Relief Valves: a) Estimated whole body and thyroid gamma dose and dose rate at the EAB; b) Classification of the relaase; c) Projected whole body and thyroid gamma dose at the EAB; and d) Recommended protective action for the general population.
- 1. Date/ Time of beginning of release
- 2. Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the c 'c=' *'o"-
O
- 3. Hours between 1. and 2. hours
- 4. Collect the following data:
a) Maximum CPM, RIS-9301: (RR-93256, Pt. 10) cpm b) Sensitivity RIS-9301: pCi/cc/ cpm c) Primary coolant 2821 equivalent circulating inventory: Ci d) Primary coolant 282I equivalent plateout inventory: Ci e) Primary Coolant Volume: sec f) Site Emergency Limit (as posted): 1) 6.6E-2 pC1/cc noble gas
- 2) 6.7E-5 pCi/cc i '2I g) Ten times Technical Specification Limits (as posted): 1) 2.5E-2 pCi/cc ncble gas O
FORM 372 22 3643
-,m - - , , , , - - - , - , , - _ _ - - - - - , , , _ , , , - , - --
E ' PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 2 of 10 G kJ 7.0E-8 vC1/cc "'I 2) l h) Average Wind Speed : at 10 meters: mph I i i) Wind Direction Degrees 1 at 10 meters: From ! NOTE: North = 0' increasing degrees - c.w. j) Differential Temperature *F Circle instrument used: 60m tower Reactor Building
- 5. Determine sectors affected using Site Sector Map (Figure 3):
Sector (s)
- 6. Determine Stability Category using Table 5, Step 41 and Step 4j:
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building
~O ^T 4#str== eats # sed-
- 7. Calculate the release noble gas concentration:
RIS-9301 concentration = (step 4a) x (step 4b)
=( )x( )
= pCi/cc
- 8. Calculate the source term, Q ng (n ble gas release rate):
a) Reactor Building Louvers Q ng = (step 7) x (5.8 E +7)* x (1 E -6 Ci/pci)
=( ) x (5.8 E +7)* x (1 E -6)
= Ci/sec
" Release rate (cc/sec) from louvers (FSAR, Section 14.11.2.6).
4 O FORM 372 22 3643
i PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 3 of 10 O b) PCRV Safety Valves Q ng = (step 7) x (1.9 E +7)** x (1 E -6)
=( ) x (1.9 E +7)** x (1 E -6) .
= C1/sec
** Release rate (cc/sec) from both PCRV safeties (FSAR, Section 6 .8).
I I I Classification of Event l I I
- 9. Determine weighted noble gas dose conversion factor from Table 2: 7.5E+2 Rem / hour Ci/m 2
- 10. Determine the EAB atmospheric dilution factor from Attachment 1 using Steps 6 and 4h:
Dilution Factor sec/m 2
~O General Emeroency Determination
- 11. Determine the whole body dose rate at the EAB:
a) Reactor Building Louvers Dose Rate = (step 8a) x (step 9) x (step 10)
=( )x( )x( )
= Rem / hour b) PCRV Safety Valves Dose Rate = (step 8b) (step 9) x (step 10)
=( )x( )x( )
= Rem / hour
~
l* 12. If the resulting dose rate at the EAB is 2 1 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the l Shift Supervisor of the General Emergency Condition. Then go directly to Step 15. . 4 O F OR M 372 - 22 3643
f PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION CR ALERT Worksheet 3 h' ' Issue 16 Page 4 of 10 O Site Area Emergency Determination i
- 13. If Step 8a. or 8b. is greater than or equal to 9.6E-1 C1/sec, the classification of event is SITE AREA EMERGENCY. Inform the !
Shift Supervisor of the Site Area Emergency Condition. Then go l directly to Step 15. Radiological Alert Determination
- 14. If Step 8a. or 8b. is greater than or equal to ten times the Technical Specification limit 3.7E-1 C1/sec, the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 15.
NOTE: Technical Specification Limit = 3.7E-2 Ci/sec. 10x Technical Specification Limit = 3.7E-1 Ci/ce, as stated above l I
! Curies of Noble Gas Released I I I -0 15. Calculate the curies of noble gas released to present time.
a) Reactor Building Louvers Curies Released = (step 8a) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3) l l = Curies b) PCRV Safety Valves l
Curies Released = (step 8b) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= Curies 4
O FORM 372 22 3643
l t .., g PUBLIC SERVICE COMPANY OF COLORADO CR ALERT y, FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3
, T Issue 16 Page 5 of 10 O ,
I l ' l Accumulated Whole Body Gamma Dose at EAB l I i I i
- 16. Calculate the dose received at the EAE. I a) Reactor Building Louvers Dose = (step 11a) x (step 3)
=( )x( )
= Rem b) PCRV Safety Valves Dose = (step lib) x (step 3)
I
=( )x( )
=_ Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
I I l Projections l I I l l 17. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has terminated, enter value from step 3. Preliminary estimate of release hours hour (s).
- 18. Project the total whole body gamma dose at the EAB.
a) Reactor Building Louvers i Projected Dose at EAB = (step 11a) x (step 17)
=( )x( )
= Rem I
i FORM 372 22 3643
t PUBLIC SERVICE COMPANY OF COLORADO CP, ALERT
- 4' ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 6 of 10 ( ' b) PCRV Safety Valves i Projected Dose at EAB = (step lib) x (step 17) l
=( )x( ) i i
= Rem 1
- 19. Calculate the release 222I equivalent concentration (Reactor Butiding Louvers or PCRV Safety Valves).
222I Equivalent Concentration =
,, a (step 4c) + (step 4d) x (5.7 E -3) + (step 4e) a,s
=( )+ ( ) x (5.7 E -3) +( ) ,
= Ci/cc
**" Amount of plateout 28 21 equivalent released (FSAR, Section 14.11.2.7.1).
- 20. Calculate the source term, Q (222I equivalent release rate).
_ a) Reactor Building Louvers i Q = (step 19) x (5.8 E~+7)
=( ) x (5.8 E +7)
= Ci/sec b) PCRV Safety Valves Q = (step 19) x (1.9 E + 7)
=( ) x (1.9 E +7)
= C1/sec i
I I l Classification of Event l 1 I t
- 21. Determine 2'2I dose conversion factor from Attachment 8. 1.2E+6 Rem / hour C1/m 3 4
O FORM 372 22 - 3&Q
t
.g' _
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 h Issue 16 Page 7 of 10 O V
- 22. Determine the thyroid dose rate at the EAB.
a) Reactor Building Louvers Dose Rate = (step 20a) x (step 21) x (step 10)
=( )x( )x( ) !
= Rem / hour b) PCRV Safety Valves Dc;e Rate = (step 20b) x (step 21) x (step 10)
=( )x( )x( ) .
= Rem / hour General Emergency Determination
- 23. If the resulting dose rate at the EAB is 2: 5 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency Condition. Then go directly to Step 26 cf this attachment.
(
~O Site Area Emergency Determination
- 24. If Step 20a. or 20b. is greater than or equal to 9.8E-4 Ci/sec, the classification of the event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Area Emergency Condition. Then go directly to Step 26 of this attachment.
Radiological Alert Determination
- 25. If Step 19 is greater than or ec;ual to ten times the Technical Specification limit 1.0E-7 Ci/sec, the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 26.
NOTE: Technical Specification Limit = 1.0E-8 C1/cc
- 10x Technical Specification Limit = 1.0E-7 Ci/cc, as stated above.
4 O FORM 372 22 3643
- PUBLIC SERVICE COMPANY OF COLORADO
.g'+ FORT ST. VRAIN NUCLEAR GENERATING STATION CR ALERT Worksheet 3 h' Issue 16 Page 8 of 10 O
I I l Curies of 222I Equivalent Released l l 1
- 26. Calculate the curies of 182I equivalent released to present time.
a) Reactor Building Louvers Curies Released = (step 20a) x (step 3) x (3.6 E +3 s/hr)
=( )x( ) x (3.6 E +3) ,
= Curies b) PCRV Safety Valves Curies Released = (step 20b) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= Curies
~O I I l Accumulated Thyroid Dose at EAB l l l
- 27. Calculate the dose received at the EAB.
a) Reactor Building Louvers Dose =
= (ttep 22a) x (step 3)
= Rem b) PCRV Safety Valves Dose = (step 22b) x (step 3)
=( )x( )
= Rem l*
NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release. 4 FORM 372 22 3643
- PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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Worksheet 3 k' FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 h ' Page 9 of 10 O I I l Projections l l l
- 28. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hour (s).
- 29. Project the total thyroid dose at the EAB.
a) Reactor Building Louvers Projected Dose at EAB = (step 22a) x (step 28)
=( )x( )
= Rem b) PCRV Safety Valves erosected oose >t EAB = csten 228) x (step 28)
~O
=( )x( )
= Rem'
- 30. Determine the recommended protective action for the general population based on the results of Steps 18 and 29. Refer to RERP-PAG.
I I I l Summary l l l l
- 31. The whole body gamma dose rate at the EAB is (Step 11a or lib): Rem /hr l
I 32. The classification of the event based l on noble gases is (Step 12 g Step 13 or Step 14):
- 33. The noble gas release rate is (Step 8a or 8b): Ci/sec 1, O FORht 372 22 3643 l
l
- PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
~ g'- Worksheet 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 10 of 10 -
O 34. The accumulated whole body gamma dose at the EAB is (Step 16a or 16b): Rem
- 35. The total number of curies of noble gas released to the present time is (Step 15a or 15b): Curies
- 36. The projected whole body gamma dose at the EAB is (Step 18a or 18b): Rem
- 37. Based on projected release duration of (Step 17):
hours
- 38. The thyroid dose rate at the EAB is (Step 22a or 22b): Rem / hour
- 39. *The classification of the event based on 222I equivalent is (Step 23 g Step 24 g Step 25):
- 40. The 222I equivalent release rate is (Step 20a or 20b): C1/sec
- 41. The accumulated thyroid dose at the EAB
_O is (Sten 27a er 27b): Rem. ! 42. The total number of curies of 222I equivalent released to the present time is (Step 26a or 26b): Curies
- 43. The projected thyroid dose at the EAB is (Step 29a or 29b): Rem l Based on projected release duration of (Step 28): hours l
l l l *If this classification differs from the classification in Step 31, the higher (i.e., more severe) classification is to be used to determine recommended protective action. a O FORM 372 3643
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i ; PUBLIC SERVICE COMPANY OF COLORADO CR ALERT F FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 1 of 10 0 WORKSHEET 3 ASSESSMENT OF RELEASE-UNMONITORED RELEASE This attachment is to be used only if the TI-59 calculator program is not used. If the TI-59 program is used, Worksheet 4 is to be used. This attachment is used to determine the following due to an unmonitored release via the Reactor Building Louvers or the PCRV Relief Valves: a) Estimated whole body and thyroid gamma dose and dose rate at the EAB; b) Classification of the release; c) Projected whole body and thyroid gamma dose at the EAB; and d) Recommended protective action for the general population.
- 1. Date/ Time of beginning of release l
- 2. Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the
-Q calculation.
hours
- 3. Hours between 1. and 2.
- 4. Collect the following data:
a) Maximum CPM, RIS-9301: - (RR-93256, Pt. 10) cpm b) Sensitivity RIS-9301: pCi/cc/ cpm , c) Primary coolant 5'2I equivalent circulating inventory: Ci
- d) Primary coolant l'1I equivalent j
plateout inventory: Ci e) Primary Coolant Volume: sec f) Site Emergency Limit (as posted): 1) 6.6E-2 pCi/cc noble gas
- 2) 6.7E-5 pCi/cc122I g) Ten times Technical Specification Limits (as posted): 1) 2.5E-2 pCi/cc noble gas 4
FORM 372 22 3643
1 - PUBLIC SERVICE COMPANY OF COLORADO CR ALERT i FORT ST VRAIN NUCLEAR GENERATING STATION tlorksheet 3 Issue 16 Page 2 of 10 O er 2) 7.0E-8 uCi/cc 2'I h) Average Wind Speed at 10 meters: mph i) Wind Direction at 10 meters: From Degrees i NOTE: North = 0* increasing degrees - c.w. j) Differential Temperature *F Circle instrument used: 60m tower Reactor Building
- 5. Determine sectors affected using Site Sector Map (Figure 3):
Sector (s)
- 6. Determine Stability Category using Table 5, Step 41 and Step 4j:
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building
~O 4T 4 stro eats # sea-
- 7. Calculate the release noble gas concentration:
RIS-9301 concentration = (step 4a) x (step 4b)
= ( )x( )
= pCi/cc
- 8. Calculate the source term, Q ng (n ble gas release rate):
a) Reactor Building Louvers Q ng = (step 7) x (5.8 E +7)* x (1 E -6 C1/pci)
=( ) x (5.8 E +7)* x (1 E -6)
= C1/sec
- Release rate (cc/sec) from louvers (FSAR, Section 14.11.2.6).
d O FORM 372 22 3643
i PUBLIC - SERVICE COMPANY OF COLORADO C3 ALERT
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 3 of 10 O b) PCRV Safety Valves Q ng = (step 7) x (1.9 E +7)" x (1 E -6)
=( ) x (1.9 E +7)** x (1 E -6)
= Ci/sec
** Release rate (cc/sec) from both PCRV safeties (FSAR, Section 6 .8).
I i l Classification of Event l l l
- 9. Determine weighted noble gas dose conversion factor from Table 2: 7.5E+2 Rem / hour C1/m'
- 10. Determine the EAB atmospheric dilution factor from Attachment I using Steps 6 and 4h:
Dilution Factor sec/m'
~O General Emeroency Determination
- 11. Determine the whole body dose rate at the EAB:
a) Reactor Building Louvers Dose Rate = (step Ba) x (step 9) x (step 10)
=( )x( )x( )
= Rem / hour b) PCRV Safety Valves Dose Rate = (step 8b) (step 9) x (step 10)
=( )x( )x( )
= Rem / hour
- 12. If the resulting dose rate at the EAB is 2: 1 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency Condition. Then go directly to Step 15.
d O FORM 372- 22 3643
5
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. . PUBLIC SERVICE COMPANY OF COLOR ADO - CR ALERT d' FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 y Issue 16 '
Page 4 of 10 O Site Area Emeroency Determination
- 13. If Step 8a. or 8b. is greater than or equal to 9.6E-1 Ci/sec, the classification of event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Area Emergency Condition. Then go directly to Step 15.
Radioloaical Alert Determination
- 14. If Step 8a. or 8b. is greater than or equal to ten times the Technical Specification limit 3.7E-1 Ci/sec, the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 15.
NOTE: Technical Specification Limit = 3.7E-2 Ci/sec. 10x Technical Specification Limit = 3.7E-1 C1/ce, as stated above i I l Curies of Noble Gas Released l l l
~ ()
- 15. Calculate the curies of noble gas released to present time.
a) Reactor Building Louvers Curies Released = (step 8a) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= Curies b) PCRV Safety Valves Curies Released = (step 8b) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= Curies e
4 O FORM 372 - 22 34E3
i PUBLIC SERVICE COMPANY - OF COLORADO CR ALERT FORT ST. VR AIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 5 of 10 O I I l Accumulated Whole Body Gamma Dose at EAB l l l
- 16. Calculate the dose received at the EAB.
a) Reactor Building Louvers Dose = (step 11a) x (step 3)
=( )x( )
= Rem b) PCRV Safety Valves Dose = (step lib) x (step 3)
=( )x( )
= Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release.
~O I i l Projections l l l
- 17. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hour ( s) .
- 18. Project the total whole body gamma dose at the EAb.
1 a) Reactor Building Louvers Projected Dose at EAB = (step 11a) x (step 17) i,
=( )x( )
= Rem ,
,, O FORM 372 22 3643
1
. PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 6 of 10 ;
O b) PCRV Safety Valves Projected Dose at EAB = (step lib) x (step 17)
=( )x( )
= Rem
- 19. Calculate the release 1'11 equivalent concentration (Reactor Building Louvers or PCRV Safety Valves).
182I Equivalent Concentration = (step 4c) + (step 4d) x (5.7 E -3) + (step 4e)
=( )+ ( ) x (5.7 E -3) +( )
= Ci/cc
*** Amount of plateout 28 2I equivalent released (FSAR, Section 14.11.2.7.1).
- 20. Calculate the source term, Q (1821 equivalent release rate).
a) Reactor Building Louvers
.O Q = (step 19) x (5.8 E +7)
=( ) x (5.8 E +7) i
= Ci/sec b) PCRV Safety Valves Q = (step 19) x (1.9 E + 7)
=( ) x (1.9 E +7)
= C1/sec I I l Classification of Event l 1 I
- 21. Determine 282I dose conversion factor from Attachment 8. 1.2E+6 Rem / hour Ci/m' 4
FORM 372 - 22 3643
1 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 Issue 16 Page 7 of 10 g O 22. Determine the thyroid dose rate at the EAB. a) Reactor Building Louvers , Dose Rate = (step 20a) x (step 21) x (step 10)
=( )x( )x( )
= Rem / hour b) PCRV Safety Valves Dose Rate = (step 20b) x (step 21) x (step 10)
=( )x( )x( )
= Rem / hour General Emeroency Determination
- 23. If the resulting dose rate at the EAB is 2 5 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency Condition. Then go directly to Step 26 of this attachment.
Site Ares Emergency Determination
- 24. If Step 20a. or 20b. is greater than or equal to 9.8E-4 Ci/sec, the classification of the event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site Area Emergency Condition. Then go directly to Step 26 of this attachme:t.
Radiological Alert Determination
- 25. If Step 19 is greater than or equal to ten times the Technical Specification limit 1.0E-7 Ci/sec, the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 26.
NOTE: Technical Spc ification Limit = 1.0E-8 C1/cc 10x Technical Specification Limit = 1.0E-7 C1/cc, as stated above. FORM 372 22 3643
1 . PUBLIC SERVICE COMPANY OF COLORADO. CR ALERT
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5 FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 k' ' Issue 16 Page 8 of 10 O I i i Curies of 2'2I Equivalent Released l l l
- 26. Calculate the curies of 2'2I equivalent released to present time.
a) Reactor Building Louvers Curies Released = (step 20a) x (step 3) x (3.6 E +3 s/hr)
=( )x( ) x (3.6 E +3)
= Curies b) PCRV Shfety Valves Curies Released = (step 20b) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3) l
= Curies O I I l Accumulated Thyroid Dose at EAB l l l
- 27. Calculate the dose received at the EAB.
a) Reactor Building Louvers Dose =
= (step 22a) x (step 3)
= Rem b) PCRV Safety Valves Dose = (step 22b) x (step 3)
=( )x( )
l -- = Rem NOTE: This calculation assumes the recipient was at the EAB for the entire duration of the release. 4 FORM 372 3643
l 1 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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FORT ST. VRAIN NUCLEAR CENERATING STATION t!orksheet 3 Issue 16 Page 9 of 10 - O I i l Projections l l l
- 28. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the re~ lease has terminated, enter value from step 3.
Preliminary estimate of release hours hour (s).
- 29. Project the total thyroid dose at the EAB.
a) Reactor Building Louvers Projected Dose at EAB = (step 22a) x (step 28)
=( )x( )
= Rem b) PCRV Safety Valves erosected oose et e^B = (ste, 22b) x (step 28)
~O
=( )x( )
= Rem
- 30. Determine the recommended protective action for the general population based on the results of Steps 18 and 29. Refer to RERP-PAG.
I I I l l Summary l l l
- 31. The whole body gamma dose rate at the EAB is (Step 11a or lib): Rem /hr
- 32. The classification of the event based on noble gases is (Step 12 g Step 13 or Step 14):
- 33. Tiie noble gas release rate is (Step 8a or 8b): Ci/sec O
F OR M 372 3643
1 , _ PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 2* Issue 16 y Page 10 of 10 0 34. The accumulated whole body gamma dose at the EAB is (Step 16a or 16b): Rem
- 35. The total number of curies of noble gas released to the present time is (Step 15a or 15b): Curies
- 36. The projected whole body gamma dose at the EAB is (Step 18a or 18b): Rem
- 37. Based on projected release duration of (Step 17):
hours
- 38. The thyroid dose rate at the EAB is (Step 22a or 22b): Rem / hour
- 39. *The classification of the event based on 2821 equivalent is (Step 23 or Step 24 or Step 25):
- 40. The 282I equivalent release rate is (Step 20a or 20b): __C1/sec
- 41. The accumulated thyroid dose at the EAB
_O is cSten 27 or 27b): Rem.
- 42. The total number of curies of 222I equivalent released to the present time is (Step 26a or 26b): Curies
- 43. The projected thyroid dose at the EAB is i
(Step 29a or 29b): _ Rem i l Based on projected release duration of
- (Step 28)
- hours
*If this classification differs from the classification in Step 31, the higher (i.e., more severe) classification is to be used l to determine recommended protective action.
4 O F OP AA 372 3643
e -
- m . , , _ ,
It a FUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Page 1 of 6 O WORKSHEET 4 ASSESSMENT OF RELEASE USING TI-59 CALCULATOR PROGRAM-UNMONITORED RELEASE This attachment is only to be used if the TI-59 calculator program is used. If the program is not used, use Worksheet 3. This attachment is used to determine the following due te an unmonitored release via the Reactor Building Louvers or the PCRV Relief Valves: a) Estimated whole body and thyroid gamma dose and dose rates at the EAB; b) Classification of the release; c) Projected whole body and thyroid gamma dose at the EAB; and d) Recommended protective action for the general population.
- 1. Collect the following data:
a) Date/ Time of beginning of release: 1
~O b) Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation:
c) Hours between la) and Ib): hours I (STO 07) d) Maximum CPM, RIS-9301: cpm (RR-93256,Pt. 10) (STO 01) e) Sensitivity RIS-9301: pCi/cc/ cpm (STO 02) f) Primary Coolant 2'2I equivalent Ci circulating inventory: (posted) (STO 03)
- g) Primary Coolant 2'2 equivalent Ci plateout inventory: (posted) (STO 04) l h) Primary Coolant Volume: (posted) cc (STO 05)
O FOT M 372 - 22 : 3643
,w- - - - - -
- - - ,, ;n.,-- ,., , , , - , . - - - - - - - _ _ - - - - - - - - - - - - - -
2 . PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
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i FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Page 2 of 6 O pCi/cc noble
- 1) Site Emergency Limit: (posted)1) 6.6E-2 gas
- 2) 6.7E-5 pC1/cc 2'21 j) Ten Times Technical Specification Limits (posted):
- 1) 2.5E-2 pCi/cc noble gas
- 2) 7.0E-8 pCi/cc 2'2I k) Average Wind Speed at 10 meters: mph
- 1) Wind Direction at 10 meters:
NOTE: North = 0 increasing degrees-c.w. From Degrees m) Differential Temperature 'F Circle instrument used 60m Tower Reactor Building _ ,-s
- 2. Determine sectors affected using Site i Sector Map (Figure 3):
Sector (s) l
- 3. Determine Stability Category using Table 5 and Steps 1.1) and 1.m).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
- 4. Determine the EAB dilution factor fron.
Attachment I using the Stability Category (Step 3) and wind speed (Step Ik). Dilution Factor sec/m' l (STO 06) l l O FORM 372 22 300 m , , , , _ , _ , . - m - - -- .-- c.-
t s DUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION 1:!orksheet 4 , id' Issue I6 T Page 3 of 6 O
- 5. If the release is continuing, consult with the Shift Supervisor and estimate the total :-umber of hours the release will continue (i.e., from beginning to end). If the release has termi-nated, enter value from step 1.c). .
Preliminary estimate of release hours hours.(STO 08)
- 6. Prepare the TI-59 for data entry.
a) Place TI-59 in printer / security cradle. b) Plug in printer / security cradle. c) Turn on printer / security cradle and TI-59. d) Depress " TRACE" button on printer. e) Obtain the magnetic card labeled "FSV Off-Site Dose Calculation (RERP) - Unmonitored Release." f) Read magnetic card into TI-59.
- 1) Depress 11l , lINVl ,l@l , l WRITE] keys.
-O 2) Insert magnetic card into right side of TI-59.
Card should be right side up with the "1" in the upper left-hand corner.
- 3) "1" will be displayed if the card was read properly - continue with Step 6f)4). If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card with the same title and repeat Step 6f).
- 4) Depress lEl ,llNV[ , l2n5l ,f l WRITE [ keys.
- 5) Insert card into right side of TI-59.
Card should be upside down with the "2" in the lower left-hand corner. , 6) "2" will be displayed if the card was read properly - continue with Step 7. If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card . with the same title and repeat Step 6f). 4 O FORM 372 22 3643
t PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Page 4 of 6 . O Input the necessary data into the indicated TI-59 storage registers. 7. a) Step 1c) = lSTOl 07 b) Step Id) = lSTOl 01 c) Step le) = lSTOl 02 i d) Step If) = lSTOl 03 e) Step ig) = lSTOl 04 f) Step 1h) = lSTOl 05 g) Step 4 = lSTOl 06 _ h) Step 5 = lSTOl 08
- 8. Run Dose Assessment Program.
i a) Depress lR/Sl key. b) Wait until a number is displayed. A flashing number indicates improper execution of the program. Depress lCIilland-l$l keys and repeat Steps 7 and 8. O FOf1M 372 22
- 3643 l
t
i .,
. PUBLIC SERVICE COMPANY OF COLORADO CR ALERT N, FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 y Issue 16 Page 5 of 6 0
l
SUMMARY
l
- 9. a) The release path is:
- 1) Reactor Building Louvers
- 2) PCRV Reliefs b) The whole body gamma dose at the EAB is (RCL 12 for louvers, RCL 13 for reliefs). rem / hour c) The classification of the event based on noble gases is:
- 1) If Step 10b) 2 1 Rem / hour, GENERAL EMERGENCY.
- 2) If Step 10c) 2 9.6E-1 Ci/sec SITE AREA EMERGENCY.
- 3) If Step 10c) 2 3.7E-1 Ci/sec and 5 9.6E-1 C1/sec, RADIOLOGICAL ALERT.
- 4) If RCL 11 2 9.6E-1 Ci/sec, SITE AREA EMERGENCY.
- 5) If RCL 11 > 3.7E-1 C1/sec and < 9.6E-1 C1/sec, RADIOLOGICAL ALERT.
e) The accumulated whole body gamma dose at the EAB is (RCL 16 for louvers, RCL 17 for reliefs): Rem f) The total number of curies of noble-gas released to the present time is (RCL 14 for louvers, RCL 15 for reliefs): .Ci g) The projected whole body gamma dose at the EAB is (RCL 18 for louvers, RCL 19 for reliefs): Rem Based on a projected release duration of (RCL 08): hours O F OR M 372 - 22 3643
t PUBLIC SERVICE COMPANY OF COLORADO CR ALETT I
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FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Page 6 of 6 O h) The thyroid dose rate at the EAB is (RCL 24 for louvers, RCL 25 for reliefs): Rem / hour
- 1) The 222 equivalent release rate is (RCL 22 for louvers, RCL 23 for reliefs): Ci/sec
*j) The classification of the event based on 2'2I equivalent is:
- 1) If Step 10h) 2 5 Rem / hour, GENERAL EMERGENCY.
- 2) If Step 101) 2 9.8E-4C Ci/sec SITE AREA EMERGENCY
- 3) If Step 101) 2 1.0E-7 Ci/sec and < 9.8E-4 Ci/sec RADIOLOGICAL ALERT.
k) The accumulated thyroid dose at the EAB is (RCL 28 for louvers, RCL 29 for reliefs): Rem
-O o The totai number of curies of equivalent released to the present 1
time is (RCL 26 for louvers, RCL 27 for reliefs): Ci i m) The projected thyroid dose at the EAB l 1s (RCL 30 for louvers, RCL 31 for reliefs): Rem Based on projected release duration of (RCL 08): hours
- 10. Determine the recommended protective action for the general-population. Refer to RERP-PAG.
*If this classification differs from the classification in Step 10b),
the higher (i.e., more severe) classification is to be used to l determine recommended protective actions. l i 1 O 4 - FORM 372 22 - 3643 t
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
- FORT ST. VR Altt NUCLEAR GENERATING STATION Worksheet 4 Issue I6 Page 1 of 6 O WORKSHEET 4 l
ASSESSMENT OF RELEASE USING TI-59 CALCULATOR PROGRAM-UNMONITORED RELEASE This attachment is only to be used if the TI-59 calculator program is used. If the program is not used, use Worksheet 3. l This attachment is used to determine the following due to an unmonitored release via the Reactor Building Louvers or the PCRV Relief Valves: a) Estimated whole body and thyroid gamma dose and dose rates at the EAB; b) Classification of the release; c) Projected whole body and thyroid gamma dose at the EAB; and d) Recommended protective action for the general population.
- 1. Collect the following data:
a) Date/ Time of beginning of release:
-O b) Date/ Time of ending of release. If release is still occurring, enter the Date/ Time of the calculation:
c) Hours between Ia) and Ib): hours (STO 07) d) Maximum CPM, RIS-9301: cpm (RR-93256, Pt. 10) (STO 01) e) Sensitivity RIS-9301: pCi/cc/ cpm (STO 02) f) Primary Coolant 2'2I equivalent Ci circulating inventory: (posted) (STO 03)
- g) Primary Coolant 2'2 equivalent Ci plateout inventory: (posted) (STO 04) h) Primary Coolant Volume: (posted) cc (STO 05)
O 4 FORM 372 3643
- - - - ~ _ - _ _ - _ _ - - - - - _ - - _ - _ - - _ _ - , , _
4 - PUBLIC SERVICE COMPANY OF COLORADO CR ALERT I' FORT ST. VRAIN NUCLEAR GENERATit+G STATION Worksheet 4 Issue 16 Page 2 of 6 (:)
- 1) Site Emergency Limit: (posted)1) 6.6E-2 pCf/cc noble gas
- 2) 6.7E-5 pCi/cc 282I j) Ten Times Technical Specification Limits (posted):
- 1) 2.5E-2 pCi/cc noble gas
- 2) 7.0E-8 pC1/cc 222I k) Average Wind Speed at 10 meters: mph
- 1) Wind Direction at 10 meters:
NOTE: North = 0* increasing degrees-c.w. From Degrees m) Differential Temperature *F Circle instrument used 60m Tower Reactor Building
~( 2. Determine sectors affected using Site Sector Map (Figure 3):
Sector (s)
- 3. Determine Stability Category using Table 5 and Steps 1.1) and 1.m).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
- 4. Determine the EAB dilution factor from Attachment I using the Stability Category (Step 3) and wind speed (Step Ik).
Dilution Factor sec/m' (STO 06) k FORM 372 22 - 300
i +
? ,
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT llorksheet 4 d' y FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 3 of 6 O
- 5. If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end). If the release has termi-nated, enter value from step 1.c).
Preliminary estimate of release hours hours.(STO 08)
- 6. Prepare the TI-59 for data entry.
l a) Place TI-59 in printer / security cradle. b) Plug in printer / security cradle. c) Turn on printer / security cradle and TI-59. d) Depress " TRACE" button on printer. e) Obtain the magaetic card labeled "FSV Off-Site Dose Calculation (RERP) - Unmonitored Release." f) Read magnetic card into TI-59. 7- 1) Depresslll , lMl , l2Ml , l WRITE l keys.
~
- 2) Insert magnetic card into right side of TI-59.
Card should be right side up with the "1" in the upper left-hand corner.
- 3) "1" will be displayed if the card was read properly - continue with Step 6f)4). If a flashing number is displayed, the card was not read j
properly. Obtain the other magnetic card i with the same title and repeat Step 6f). l
- 4) Depress l]l ,]@l , l2nci , l WRITE l keys.
l 5) Insert card irto right side of TI-59. Card should be upside down with the "2" in l the lower left-hand corner.
. 6) "2" will be displayed if the card was read properly - continue with Step 7. If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card with the same title and repeat Step 6f).
(~)
%)
4 F ORM 372 3643
4 g_ PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 O d' Issue 16 v Page 4 of 6 O
- 7. Input the necessary data into the indicated TI-59 storage registers, a) Step Ic) = lSTOl 07 b) Step Id) = lSTOl 01 c) Step le) = lSTOl 02 d) Step If) = lS10l 03 e) Step ig) = l5T6l 04 f) Step 1h) = lSTOl 05 g) Step 4 = lWOl 06
_ h) Step 5 = lSTOl 08
- 8. Run Cose Assessment Program.
a) Depress liU5l key. b) Wait until a number is displayed. A flashing number indicates improper execution of the program. Depress l@l and -]RSTl keys and repeat Steps 7 and 8. O a FORM 372 22 3643
---e,.
4 a PUBLIC SERVICE COMPANY OF COLORADO CR ALERT I' FORT ST. VRAIN NUCLEAR GENERATING STATION b!orksheet 4 Issue 16 Page 5 of 6 O l
SUMMARY
l
- 9. a) The release path is:
- 1) Reactor Building Louvers
- 2) PCRV Reliefs b) The whole body gamma dose at the EAB is (RCL 12 for louvers, RCL 13 for reliefs). rem / hour c) The classification of the event based on noble gases is:
- 1) If Step 10b) 2 1 Rem / hour, GENERAL EMERGENCY.
- 2) If Step 10c) 2 9.6E-1 Ci/sec SITE AREA EMERGENCY.
- 3) If Step 10c) 2 3.7E-1 Ci/sec and s 9.6E-1 C1/sec,
_ RADIOLOGICAL ALERT.
- 4) If RCL 11 2 9.6E-1 C1/sec, SITE AREA EMERGENCY.
- 5) If RCL 11 > 3.7E-1 Ci/sec and < 9.6E-1 Ci/sec, RADIOLOGICAL ALERT.
e) The accumulated whole body gamma dose at the EAB is (RCL 16 for louvers, RCL 17 for reliefs): _ Rem f) The total number of curies of noble-gas released to the present time is (PCL 14 for louvers, RCL 15 for reliefs): -Ci g) The projected whole body gamma dose at the EAB is (RCL 18 for louvers, RCL 19 for reliefs): Rem Based on a projected release duration of (RCL 08): hours O 4 FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
? FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 4 Issue 16 Page 6 of 6 i
V('T h) The thyroid dose rate at the EAB is (RCL 24 for louvers, RCL 25 for reliefs): Rem / hour
- 1) The l'1 equivalent release rate is (RCL 22 for louvers, RCL 23 for reliefs): C1/sec
*j) The classification of the event based on 2'*I equivalent is:
- 1) If Step 10h) 2 5 Rem / hour, GENERAL EMERGENCY.
- 2) If Step 101) 2 9.8E-4C C1/see SITE AREA EMERGENCY
- 3) If Step 101) 2 1.0E-7 Ci/sec and < 9.8E-4 C1/sec RADIOLOGICAL ALERT.
, k) The accumulated thyroid dose at the EAB is (RCL 28 for louvers, RCL 29 for reliefs): Rem
~ () 1) The total number of curies of 2'2I equivalent released to the present time is (RCL 26 for louvers, RCL 27 for reliefs): Ci m) The projected thyroid dose at the EAB is (RCL 30 for louvtrs, RCL 31 for reliefs): Rem Based on projected release duration of (RCL 08): hours
- 10. Determine the recommended protective action for the general-l population. Refer to RERP-PAG.
*If this classification differs from the classification in Step 10b),
the higher (i.e., more severe) classification is to be used to determine recommended protective actions. e O
< FORM 372 22 300
~~ w . - -
4 - PUBLIC SERVICE COMPANY OF COLORADO CR ALERT 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Issua 16 Page 1 of 2 O Datasheet 1 - Data Logger (or IBM) Monitored Release A. Projection - Option 2
- 1. Current and release start date and time:
a) _/ /_ b) : ___
- 2. Projected end of release date and time: ,
a) _/ / b) :
- 3. Radiation Monitor Values, Noble Gas a) RT-7324, I cpm b) RT-7324. 2 cpm
% If one of the above is offscale or inoperative:
a) E-500 or Cutie Pie? b) Instrument Reading mR/hr
- 4. Exhaust Stack Flow Rate cfm
- 5. Radiciodine Monitor Values; RT-73437, 1 a) Initial Reading from chart cpm b) Intermediate Reading from chi.rt cpm l
l c) Peak or Current Reading from chart cpm d) Time between a and b ,_ minutes l l e) Time between b and c minutes
- 6. Wind Direction (preferred sampling point is 10 meter instrument on 60 meter meteorological tower) a l
O F ORM 372 22 - 3643
? PUBLIC SERVICE COMPANY OF COLORADO CR ALERT ?
4. Tj, FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet i V Issue 16 Page 2 of 2 O Wind Speed (Preferred sampling point 7. is 10 meter instrument on 60 meter meteorological tower) mph
- 8. Distance between upper and lower temperature instruments meters
- 9. Delta Temperature between temperature instruments "F
- 10. Standard Deviation (Sigma Theta) of Wind Direction - 15 min. average B. Puff - Option 2
- 1. Current and release start date and .
time: a) / / b) :
- 2. End of Puff date and time (not to exceed 15 minutes after B.1) a) /___/-
b) : C '. Total for Ali Puffs - Option 3 Change option and execute DF 41-0-0. O < FORM 372 22 36MB
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
? FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Issue 16 Page 1 of 2 O
Datasheet 1 - Data Logger (or IBM) Monitored Release A. Projection - Option 2
- 1. Current and release start date and time:
a) / / b) :
- 2. Projected end of release date and time: .
a) / / b) :
- 3. Radiation Monitor Values, Noble Gas a) RT-7324, I cpm i
b) RT-7324. 2 cpm _ p If one of the above is offscale or
\, inoperative:
a) E-500 or Cutie Pie? b) Instrument Reading mR/hr
- 4. Exhaust Stack Flow Rate cfm
- 5. Radiciodine Monitor Values; RT-73437, I a) Initial Reading from chart cpm l
b) Intermediate Reading from chart epm c) Peak or Current Reading from chart cpm d) Time between a and b minutes e) Time between b and c minutes
- 6. Wind Direction (preferred sampling point is 10 meter instrument on 60 meter meteorological tower) o O
4 FORM 372 22 3643
% PUBLIC SERVICE COMPANY OF COLORADO CR ALERT ? -
FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Issue 16 Page 2 of ? O
- 7. Wind Speed (Preferred sampling point is 10 meter instrument on 60 meter meteorological tower) mph
- 8. Distance between upper and lower temperature instruments meters
- 9. Delta Temperature between temperature instruments
~
op
- 10. Standard Deviation (Sigma Theta) of Wind Direction - 15 min. average B. puff - Option 2
- 1. Current and release start date and .
time: [ a) _/ / b) :
- 2. End of Puff date and time (not to exceed 15 minutes after B.1) a) _/ /-
b) : C. Total for All Puffs - Option 3 Change option and execute DF 41-0-0. FORM 372 - 22 3643 i
- =
PUBLIC SERVICE COMPANY OF COLORADO- CR ALERT
?
~
FORT ST. VRAIN NUCLEAR GENERATING STATION D:tasheet 1 Issue 16 Page 1 of 2 Datasheet 1 - Data Logger (or IBM) Mnnitored Release A. Projection - Option 2
- 1. Current and release start date and time:
a) _/ /_ b) :
- 2. Projected end of release date and time: ,
a) _/ / b) :
- 3. Radiation Monitor Values, Noble Gas a) RT-7324, I cpm b) RT-7324. 2 cpm If one of the above is offscale or inoperative:
a) E-500 or Cutie Pie? b) Instrument Reading mR/hr
- 4. Exhaust Stack Flow Rate efm
- 5. Radioiod'ne Monitor Values; RT-73437, 1 1
- a) Initial Reading from chart cpm b) Intermediate Reading from chart cpm c) Peak or Current Reading from chart epm d) Time between a and b minutes I
e) Time between b and c minutes
- 6. Wind Direction (preferred sampling point is 10 meter instrument on 60 meter meteorological tower) o
( l* F ORM 372 - 22 3643
4 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
? FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Issue 16 Page 2 of 2 O
- 7. Wind Speed (Preferred sampling point is 10 meter instrument on 60 meter meteorological tower) mph
- 8. Distance between upper and lower temperature instruments l
meters
- 9. Delta Temperature between temperature instruments
*F
- 10. Standard Deviation (Sigma Theta) of Wind Direction - 15 min. average B. Puff - Option 2
- 1. Current and release start date and .
time: I-o 1 a) / / b) :
- 2. End of Puff date and time (not to exceed 15 minutes after B.1) a) / /-
b) : ! C'. Total for All Puffs - Option 3 Change option and execute DF 41-0-0. O FORM 372 22 3643
~ . , , ,c. ,-.e. - -
PUBLIC SERVICE COMPANY OF COLORADO
% CR ALERT - -
7 ' FORT Gr. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Issue 16 Page 1 of 2
! C)
Datasheet 1 - Data Logger (or IBM) Monitored Release A. Projection - Option 2
- 1. Current and release start date and time:
a) / / b) :
- 2. Projected end of release date and time: .
a) / / b) :
- 3. Radiation Monitor Values, Noble Gas a) RT-7324, I cpm b) RT-7324. 2 cpm
_ If one of the above is offscale or inoperative: i a) E-500 or Cutie Pie? b) Instrument Reading mR/hr
- 4. Exhaust Stack Flow Rate efm
- 5. Radiciodine Moniter Values; RT-73437, I a) Initial Reading from chart cpm b) Interrtdiate Reading from chart cpm c) Pet:- or '.urrent Reading from chart cpm d) T.ns : r .. men a and b minutes e) Time between b and c minutes
- 6. Wind Direction (preferred sampling point is 10 meter instrument on 60 meter meteorological tower)
O O FORM 372 22 - 36CB
Q CR ALERT f PUBLIC SERVICE COMPANY OF COLORADO Datasheet 1 ? FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 2 of 2 O
- 7. Wind Speed (Preferred sampling point is 10 meter instrument on 60 meter meteorological tower) mph
- 8. Distance between upper and lower temperature instruments meters
- 9. Delta Temperature between temperature instruments
*F
- 10. Standard Deviation (Sigma Theta) of Wind Direction - 15 min. average B. Puff - Option 2
- 1. Current and release start date and .
time: J a) /__/ b) :
- 2. End of Puff date and time (not to exceed 15 minutes after B 1) a) / /-
b) : C. Total for All Puffs - Option 3 Change option and execute DF 41-0-0. O FORM 372 22 3643
4 - PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
? -
FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Issue 16 Page 1 of 2 O Datasheet 1 - Data Logger (or IBM) Monitored Release A. Projection - Option 2
- 1. Current and release start date and time:
a) / / b) :
- 2. Projected end of , release date and time ,
a) _/ / b) :
- 3. Radiation Monitor Values, Noble Gas a) RT-7324, I cpm b) RT-7324. 2 cpm l _ If one of the above is offscale or inoperative:
a) E-500 or Cutie Pie? b) Instrument Reading mR/hr
- 4. Exhaust Stack Flow Rate cfm
- 5. Radioiodine Monitor Values; RT-73437, I a) Initial Reading from chart cpm b) Intermediate Reading from chart cpm c) Peak or Current Reading from chart cpm d) Time between a and b minutes e) Time between b and c minutes
- 6. Wind Direction (preferred sampling point is 10 meter instrument on 60 meter meteorological tower) o d
O I l FORM 372 22 3643
4 PUBLIO SERVICE COMPANY OF COLORADO CR ALERT ? FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Issue 16 Page 2 of 2 C)
- 7. Wind Speed (Preferred sampling point is 10 meter instrument on 60 meter meteorological tower) mph
- 8. Disttnce between upper and lower temperature instruments meters
- 9. Delta Temperature between temperature instruments
*F
- 10. Standard Deviation (Sigma Theta) of Wind Direction - 15 min. average B. Puff - Option 2
- 1. Current and release start date and .
time:
.[)
a) ___/ /___ b) : _ _ _
- 2. End of Puff date and time (not to excted 15 minutes after B.1) a) / /-
b) : C. Total for All Puffs - Option 3 Change option and execute DF 41-0-0. 9 V e FORM 372 22 - 3643
' ' " -- -v .-_
4 4 PUBLIC SERVICE COMPANY OF COLORADO CR ALECT 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 2 Issue 16 Page 1 of 2 O Datasheet 2 - Data Logger (or IBM) Unmonitored Release)
- 1. Date and Time of beginning of release a) / /
b) :
- 2. Time of Louvers closed
- 3. Maximum CPM, RIS-9301 cpm
- 4. a) Primary coolant I-131 equivalent circulating inventory Ci b) Primary coolant I-131 equivalent plateout inventory .
C1 ( 5. Primary Coolant Volume sec l
- 6. a) PCRV Pressure Before Release pS19 b) PCRV Pressure After Release psig
- 7. Wind Direction (prefererd sampling point is 10 meter instrumentation on 60 meter meteorological tower)
O
- 8. Wind speed (preferred sampling point is 10 l
meter instrumenation on 60 meter I meteorological tower) mph a O , FORM 372 22- 300 4
4 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
/
FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 2 Issue 16 Page 2 of 2 O 9. Distance between upper and lower temperature instruments meters
- 10. Delta Temperature between temperature instruments
*F
- 11. Standard Deviation (Sigma Theta) of wind Direction - 15 min. average 1
~O E
l l O 4 O F OR M 372 - 27 3643 l { 1
4 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT g), .sJ e r FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 2 Issue 16
- Page 1 of 2 O Datasheet 2 - Data Logger (or IBM) Unmonitored Release)
- 1. Date and Time of beginning of release a) _/ /_
b) :
- 2. Time of Louvers closed
- 3. Maximum CPM, RIS-9301 cpm
- 4. a) Primary coolant I-131 equivalent circulating inventory Ci b) Primary coolant I-131 equivalent plateout inventory .
Ci
- 5. Primary Coolant Volume sec
- 6. a) PCRV Pressure Before Release psi 9 b) PCRV Pressure After Release psig
- 7. Wind Direction (prefererd sampling point is 10 meter instrumentation on 60 meter meteorological tower) o
- 8. Wind speed (preferred sampling point is 10 meter instrumenation on 60 meter meteorological tower) mph O
a FORM 372 *7 3643
4 - PUBLIC SERVICE COMPANY OF COLORADO CR ALERT I FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 2 Issue 16 Page 2 of 2 O upper and lower
- 9. Distance between temperature instruments meters
- 10. Delta Temperature between temperature instruments
'F
- 11. Standard Deviation (Sigma Theta) of wind Direction - 15 min. average
-O l
l l l O O FORM 372 22 3643 {.
1 g' , PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION CR ALERT Datasheet 3 h' Issue 16 Page 1 of 2 O PRELIMINARY ASSESSMENT OF PLANT CONDITIONS' TECHNICAL ADVISOR
- 1. Brief description of event
- 2. Date/ Time of event i 3. Date/ Time of assessment
- 4. If the data logger is operating, obtain the Demand Function i Printout (or printe the specified displays):
NOTE: All screens and demand functions are accessible from Display 900. DF 69-0-0 l DF 76-0-0 0 DF 77-1-0 Post Trip Review Helium Inventory PRIMARY SYSTEM l
- 5. Curt ent Reactor Power
- 6. Rod Runback Occur (Y/N)
If yes, record positions 2B 4A
- 7. If shutdown, are all rods fully inserted (Y/N)
- 8. Circulators Operating A B C D MODE:
Steam /Feedwater/Cond./ Firewater
- 9. Purification Train A B To: Storage PCRV, or Ventilation
- 10. Is heat removal capability adequate at this time (Y/N) l b
I F OR M 372 - 22 3643 l
1 a PUBLIC SERVICE COMPANY OF COLORADO CR ALERT J FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 3 Issue 16 i Page 2 of 2 O SECONDARY SYSTEM
- 11. Loops Operating I II i 12. Feed to S/G's: Norm FW Emer. FW Emer. Cond.
Firewater
- 13. Status of Aux. B;ilers Remarks Time Description l_
i i I O FORM 372 22 3643
?>
g' PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
-~ FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 3 h' Issue 16 Page 1 of 2 PRELIMINARY ASSESSMENT OF PLANT CONDITIONS ~
TECHNICAL ADVISOR
- 1. Brief description of event
- 2. Date/ Time of event
- 3. Date/ Time of assessment
- 4. If the data logger is operating, obtain the Demand Function Printout (or printe the specified displays):
NOTE: All screens and demand functions are accessible from Display 900. DF 69-0-0 __ DF 76-0-0
- DF 77-1-0 Post Trip Review Helium Inventory PRIMARY SYSTEM T
5,. Current Reactor Power
- 6. Rod Runback Occur (Y/N)
If yes, record positions 2B 4A
- 7. If shutdown, are all rods fully inserted (Y/N)
- 8. Circulators Operating A B C D MODE:
Steam /Feedwater/Cond, / Firewater
- 9. Purification Train A B To: atorage, PCRV, or Ventilation
- 10. Is heat removal capability adequate at this time (Y/N) 6
.. FORM 372 22 3643
it PUBLIC SERVICE COMPANY OF COLORADO CR ALERT ,- FORT ST. VRAIN NUCLEAR- GENERATING STATION Datasheet 3 ' I Issue 16 Page 2 of 2 l O SECONDARY SYSTEM
- 11. Loops Operating I II
- 12. Feed to S/G's: Norm FW Emer. FW Emer. Cond.
l Firewater
- 13. Status of Aux. Boilers Remarks Time Description O
l l 4 O h FORM 372 22 3643
I g'. . PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
~
FORT ST. VRAIN NUCLEAR GENERATING STATION Checkligt 1 Issue 16 Page 1 of 2 EMERGENCY COORDINATOR /CR DIRECTOR CHECKLIST
- 1. Initiate Emergency Procedure actions.
- 2. Technical Advisor notified.
- 3. Obtain preliminary assessment of release.
l
- 4. Obtain meteorological data.
l l
- 5. Initiate protective actions for station personnel.
- 6. Contact plant management and confirm accident classification.
- 7. Complete Notifications Form.
ALERT or Higher - Attachment 1
- 8. Sound Plant Emergency Alarm if ALERT or higher and announce nature of the emergency.
- 9. Receive initial personnel accountability report.
O l 1 0 FORM 372 - 22 3643
i . PUBLIC SERVICE COMPANY OF COLORADO CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1 Issue 16 Page 2 of 2 0
- 10. Notify Visitor's Center if Alert or higher; specify departure route 1, 2, or 3 (see Figure 2).
- 11. Make notifications.
(ALERT or Higher) PSC Operator Weld County Communications Center NRC Operations Center
- 12. Select the PCC location based upon consideration of the dominant win <
direction and accessability to emergency respondants from o f f si tr,. O The list below available alternative locatio.s. summarizes the t
- a. Inside Protected Arta
*1) Warehouse
- 2) Craft-Shaps
! b. Outside Pratocted Area. l
*1) Mea-City
- 2) GA Field Office
- 13. Confirm communications with TSC and notifs of PCC location.
l 1
- Preferred locations for the PCC are either the warehouse or Mod-City, based upon equipment storage.
I FORM 372 22. M43
I ' PUBLIC SERVICE COMPANY OF COLORADO CR ALERT . ~~ FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1 Issue 16 Page 1 of 2 EMERGENCY COORDINATOR /CR DIRECTOR CHECKLIST
- 1. Initiate Emergency Procedure actions.
- 2. Technical Advisor notified.
- 3. Obtain preliminary assessment of release.
- 4. Obtain meteorological data.
- 5. Initiate protective actions for 2 station personnel.
[ ])
- 6. Contact plant management and confirm accident classification.
- 7. Complete Notifications Form.
ALERT or Higher - Attachment 1
- 8. Sound Plant Emergency Alarm if ALERT or higher and announce nature of the emergency.
4
- 9. Receive initial personnel accountability report.
O o F OR M 3 Mt 22 3NO
i PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
~
FORT ST. VRAIN NUCLEAR GENER ATING STATION Checklist 1 Issue 16 Page 2 of 2 0
- 10. Notify Visitor's Center if Alert or higher; specify departure route 1, 2, or 3 (see Figure 2).
- 11. Make notifications.
(ALERT or Higher) PSC Operator Weld County Communications Center NRC Operations Center
- 12. Select the PCC location based upon consideration of the dominant wind direction and accessability to emergency respondants from offsite.
O The list below summarizes the available alternative locations.
- a. Inside Protected Area.
*1) Warehouse
- 2) Craft-Shops
- b. Outside Protected Area.
*1) Mod-City
- 2) GA Field Office
- 13. Confirm communications with TSC and notify of PCC location.
Preferred locations for the PCC are either the warehouse or Mod-City, based upon equipment storage. f I O i 0 FORM 372 3643
,% o a PUBLIC SERVICE COMPANY OF COLORADO CR ALERT 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. 1
[ Issue 16 Page 1 of 4 O NOTIFICATION TO ACTIVATE STATE EMERGENCY RESPONSE-CENTERS i A. The Emergency Coordinator wi'l complete Pages 1 and 2 of this attachment with the assistance of the first management contact. I I i l Required Information l I I
- 1. This is (Name) , Shift Supervisor et the Fort St.
Vrain Station.
- 2. At (Time) we experienced an ( ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident.
- 3. a) There is NO, repeat NO, radioactive release taking place, and no special protective actions are recommended at this time.
OR O b) A radioactiva release I!, repeat I}, taking place, in areas and we recommend that people remain indocrs with windows and doors closed. OR c) A radioactive release 11, repeat I}, taking place, and we recommend that evacuation of areas be considered.
- 4. Further information on incident conditions will be provided in followup messages.
l O O FORM 372 22 3443
t - -- PUBLIC SERYlCE COMPANY OF COLOR ADO- CR ALERT FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. 1 l Issue 16 Page 2 of 4 SUPPLEMENTAL INFORMATION NOTE: This information is to be supplied to the NRC and the Colorado Department of Health when requested. The radiological data can be determined as specified in Section 2.2.1.2 of.this procedure. i
- 1. Date and Time of Incident
- 2. Class of emergency (ALERT)(SITE AREA EMERGENCY) i (GENERAL EMERGENCY)
- 3. Type of release (airborne, waterborne, surface)
- 4. Current release rate:
Noble Gas Ci/sec Iodine Ci/sec
- 5. Estimated curies released Noble Gas Ci Iodine Ci
- 6. Wind Velocity MPH, from degrees. Air Temp.
- F.
g-V 7. Stability Category , Form c f Precip. 1
- 8. Dose rate at EAB - WB rem /hr Thyroid rem /hr _
- 9. Projected dose at EAB - WB rem Thyroid rem
- 10. Estimated accumulated dose at EAB-WB rem Thyroid rem
- 11. Estimate of any surface radioactive contamination l
- 12. On-site response actions under way l
l l l l O d FOR M 372 22 ".,643
% , PUBLIC SERVICE COMPANY OF COLORADO CR ALERT /
e FORT ST. VR AIN NUCLEAR GENERATING STATH3N A-tach. I
' h'jg$ Issue 16 Page 3 of 4
- 13. Recommended Protective Action based on the projected dose at the EAB (NOTE: Refer to RERP-PAG):
Circle Appropriate Protective Actions and Read Aloud Projected Dose Recommended (rem) Protective Action Whole Cody <1 No planned protective actions. State Thyroid <5 may issue advisory to seek shelter and await instructions. Monitor rcdiation levels. Whcle Body 1 to 5 Take shelter and consider selective Thyroid 5 to 25 evacuation. Monitor radiation levels. Establish Controlled Area and limit
~
access. Whole Body 5 and above Conduct mandatory evacuation. Monitor Thyroid 25 and above radiation levels and adjust area for mandatory avacuation based on these levels Control Access.
- 14. Prognosis for worsening of event
- 15. Date and time of report B. The Emergency Coordinator will make noti fications in sequence as follows:
I l PSC Company Operator I or l l l l
- 1) INSTRUCT the Operator to initiate the " Fort St.
l Vrain Padiological Emergency Call List."
- 2) READ verbatim the information recorded in Part A (Page 1 of this attachment).
- 3) RECORD the following information:
l Time PSC Operator Notified I Time Operator Callback Received 4 FORM 372 22 36 4
% PUBLIC SERVICE COMPANY OF COLORADO CR ALERT r FORT ST. VRAIN NUCLEAR GENERArlNG STATION Attach. 1 Issue 16 Page 4 of 4 0
I l l Weld County (911 Using Greeley Line) l l l
- 1) READ verbatim the information recorded in Part A (Page 1 of this attachment).
- 2) RECORD the following information:
Time Weld County Notified Time Weld County Callback Received l l l NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l 1 I (Use HP Network Line if NRC Hot Line and Land Line l are inoperable.)
- 1) READ Items 1) through 4) from Part A.
_ 2) READ the following sentences verbatim. "THIS EVENT IS BEING REPORTED PURSUANT TO 10-CFR50.72, ITEM NUMBER 1. WE ARE PRESENTLY ACTIVATING STATE AND LOCAL EMERGENCY RESPONSE CENTERS." l
- 3) READ the suoplemental information (Page 2 of this attachment).
- 4) RECORD the following information:
NAME of NRC Contact TIME of NRC Contact 4 O o FOptM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR ALERT r FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. 1 Issue 16 Page 1 of 4 O NOTIFICATION TO ACTIVATE STATE EMERGENCY RESPONSE- CENTERS A. The Emergency Coordinator will complete Pages 1 and 2 of this attachment with the assistance of the first management contact. I I l Required Information l l l
- 1. This is (Name) , Shift Supervisor at the Fort St.
Vrain Station. I 2. At (Time) we experiencedan(ALERT,SITEAREA EMERGENCY, GENERAL EMERGENCY) Class incident.
- 3. a) There is NO, repeat NO, radioactive release taking place, and no special protective actions are recommended at this time.
OR O ! _ b) A radioactive release I}, repeat IE, taking place, and we recommend that people in areas l reinain indoors with windows and doors closed. QR c) A radioactive release I}, repeat I!, taking place, l and we recommend that evacuation of areas ' be considered.
- 4. Further information on incident conditions will be provided in followup messages.
l l t l* O l FORM 372 22 3643 l . - _ - _ - - _ - _
% : PUBLIC SERVICE COMPANY OF COLORADO' CR ALERT ~
CORT ST. VRAIN NUCLEAR GENERATING STATION Attach. 1 Issue 16 Page 2 of 4 O SUPPLEMENTAL INFORMATION , NOTE: This information is to be supplied to the NRC and the Colorado Department of Health when requested. The radiological data can be determined as specified in Section 2.2.1.2 of this procedure.
- 1. Date and Time of Incident
- 2. Class of emergency (ALERT)(SITE AREA EMERGENCY)
(GENERAL EMERGENCY)
- 3. Type of release (airborne, waterborne, surface)
- 4. Current release rate:
Noble Gas Ci/sec Iodine Ci/sec
- 5. Estimated curies released Noble Gas Ci Iodine Ci
- 6. Wind Velocity MPH, from degrees. Air Temp.
- F.
, _ 7. Stability Category , Form of Precip. l
- 8. Dose rate at EAB - WB rem /hr Thyroid rem /hr
- 9. Projected dose at EAB - WB rem Thyroid rem
- 10. Estimated accumulated dose at EAB-WB rem Thyroid rem
- 11. Estimate of any surface radioactive contamination
- 12. On-site response actions under way 4
FORM 372 22 3643
~. -
-l _' PUBLIC SERVICE COMPANY OF COLORADO CR ALERT ? j FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. I y Issue 16 Page 3 of 4
- 13. Recommended Protective Action based on the projected dose at the EAB (NOTE: Refer to RERP-PAG):
Circle Appropriate Protective Actions and Read Aloud Projected Dose Recommended (rem) Protective Action Whole Body <1 No planned protective actions. State Thyroid <5 may issue advisory to seek shelter and await instructions. Monitor radiation levels. Whole Body 1 to 5 Take shelter and consider selective Thyroid 5 to 25 evacuation. Monitor radiation levels. Establish Controlled Area and limit access. Whole Body 5 and above Conduct mandatory evacuation. Monitor Thyroid 25 and above radiation levels and adjust area for mandatory evacuation based on these levels Control Access.
- 14. P-ognosis for worse,ing of event
- 15. Date and time of report B. The Emergency Coordinator will make notifications in sequence as follows:
. I l [ PSC Company Operator
. l or ,
I I
- 1) INSTRUCT the Operator to initiate the " Fort St.
i Vrain Radiological Emergency Call List." I
- 2) READ verbatim the information recorded in Part A (Page 1 of this attachment).
- 3) RECORD the following information:
Time PSC Operator Notified Time Operator Callback Received l 4 FORM 372 22 3643
4 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT g[y FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. 1 Issue 16 Page 4 of 4 O l l l l l Weld County (911 Using Greeley Line) l l l
- 1) READ verbatim the information recorded in Part A (Page 1 of this attachment).
- 2) RECORD the following information:
i Time Weld County No.tified Time Weld County Callback Received l l l l 1 l NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l ) l l l l l (Use HP Network Line if NRC Hot Line and Land Line are inoperable.)
- 1) READ Items 1) through 4) from Part A.
_ 2) READ the following sentences verbatim. "THIS EVENT IS BEING REPORTED PURSUANT TO 10-CFP50.72, ITEM NUMBER 1. WE ARE PP.ESENTLY ACTIVATING STATE AND 1 l LOCAL EMERGENCY RESPONSE CENTERS." I
- 3) READ the supplemental information (Page 2 of this attachment).
- 4) RECORD the following information:
NAME of NRC Contact TIME of NRC Contact O i o FORM 372 22 - 3643
I PUBLIC SERVICE COMPANY OF COLORADO CR ALERT t FORT ST. VRAIN NUCLEAR GENERATING STATION WS/03/Cl Issue 16 Page 1 of 3 O Work /Datasheet/ Checklist Control List Worksheet No. Title Number Copies 1 Monitored Release Calculations (Manual) 2 2 Monitored Release Calculations (TI-59) 2 3 Unmonitored Release Calculations (Manual) 2 4 Unmonitored Release Calculations (TI-59) 2 Datasheet No. 1 Datalogger Monitored Release 5 2 Datalogger Unmonitored Release 2 0 3 ereiimi ars Assessmeat of eiaat Co#:<tio#s a l Checklist No. I Emergency Coordinator / Control Room 2 Director Checklist Attachment No. 1 Notification to Activate State Emergency 2 Response Centers O O a For*M 372 3643
I . PUBLIC SERVICE COMPANY OF COLORADO CR ALERT
-~
FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 16 Page 2 of 3 () i FORMS USE REPORTING SHEET Technical Clerk and Recorder: l This sheet is being transmitted to report use of forms from a j controlled copy of the Radiological Emergency Response Plan i Implementing Procedures, BOOK NO. , located at l . The following forms have been utilized from this copy: Worksheet Numbers Copies Used l , (2) l Datasheet Numbers Copies Used l Checklist Numbers Copies Used l l 1 l 1 The procedure affected by this sheet is shown in the header to this i page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace O the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. O FORM 37J 22 - 364
# 7 PUBLIC SERVICE COMPANY OF COLORADO CR ALERT WS/ CTS /CL FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 16 Page 3 of 3
! O i FORMS USE REPORTING SHEET (Continued) COMMENTS 1 t Reported By: l Date: Technical Clerk and Recorder Date Received Date Replaced Technical Clerk and Recorder will transmit this form to the O originating individual / department upon completion of this form to notify users that the procedure has been updated and that all , ~ worksheets, checklists, and datasheets are present in the required number of copies. l l l l O FORM 372 22 3643
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T PUBLIC SERVICE COMPANY OF COLORADO NON-CONTROLLED COPY FORT ST. VRAIN NUCLEAR GENERATING STATION BOOK 2 ggC 1/3/83 b Q r~;)
\ o RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATION ISSUE EFFECTIVE NO. SUBJECT NUMBER DATE l
l RERP-ECP Executive Command Post Procedure 6 01-03-83 RERP-EXP Emergency Exposure Guidelines 1 08-02-82 l RERP-FCP Forward Command Post Procedure 8 01-03-83 RERP-FIELD Field Monitoring Procedure 2 09-01-82 RERP-HOME Home Packet for Off-Shift Notifications 2 10-26-82 i RERP-0RG FSV Emergency Organization and l Responsibilities 3 01-03-83 RERP-PAG Protective Action Guideline Recommendations 1 08-02-82
~T (U RERP-PCC Personnel Control Center Procedure 8 12-20-82 l RERP-SEOC State Emergency Operations Center l Procedure 5 01-03-83 RERP-SURVEY Inplant/Onsite Radiological Monitoring 1 09-09-82 RERP-THYROID Thyroid Blocking Agent
- Administration 2 12-03-82 l
l t FORM 372 22 3643 u-
PUBLIC SERVICE COMPANY OF COLORADO RF.RP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 1 of 5 /, U ' TITLE: EXECUTIVE COMMAND POST PROCEDURE ISSUANCE ggg 4 AUTHORIZED 1 / BY Mk T!1eAA PORC EFFECTIVE PORc 49 7 DEC 2 71982 DATE I-3-83 REVIEW TABLE OF CONTENTS i Section Description Page 1.0 Criteria for Implementation... ... ................. ........ 2 2.0 Procedure...... .. ...... ...... ........... ...... .. ...... 2 3.0 Responsibilities .. ................................. ....... 3 4.0 References ..... ...... ... ................................. 4 v 5.0 Referenced or Supporting Procedures............... ........... 5 Figure 1 Executive Command Post Organi:ation..... ........ ...... 1 Figure 2 Emergency Organization ... ............. ..... .. . .... 1 Attachment 1 Support Equipment / Material................. ......... 1 Checklist 1 ECP Director's Checklist.. ................. ........ 1 Work /Datasheet/ Checklist Control List . . . . ....... ... . ........ 1
. Forms Use Reporting Sheet *........... ........................... 2
- ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FORWARD IT TO THE TECHNICAL CLERK AND RECORDER, FORT ST. VkAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
O,1 FORM 372 22 3842
PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 2 of 5 ESTABLISHING THE EXECUTIVE COMMAND POST 1.0 Criteria for Imolementation When the FSV Radiological Emergency Response Plan (RERP) requires augmentation of resources, the Executive Command Post Director shall activate the Executive Command Post (ECP). 2.0 Procedure 2.1 Staffing The ECP Director shall perform personnel accountability to assure that the initial manning functions of the ECP can be met. If not during normal working hours, those personnel required to man the ECP are notified by telephone (see RERP-HOME). It is the responsiblity of the ECP Alternate Director, or the first individual contacted by the ECP Director, to ensure that the notifications are made. Refer to the RERP PHONE LIST for the ECP for instructions, o names, and telephone numbers. V 2.2 Communications The ECP Director shall establish communications with the Forward Command Post (FCP). 2.3 Activation The Executive Command Post (ECP) shall be established and be operational within ninety (90) minutes after an ALERT or higher level accident. 2.3.1 The ECP will be located: a) Primary - Room 620, Headquarters Building. i b) Alternate - PSC Lookout Center in Golden. 2.3.2 The ECP is manned by senior corporate personnel, facilities, equipment, and financial resources in an emergency situation. The ECP supports PSC personnel stationed at onsite and offsite emergency centers. l
.i FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VR A,1N NUCLEAR GENERATING STATION lssue 6 Page 3 of 5 (3
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3.0 Resconsibilities 3.1 Executive Command Post Director - Checklist 1 1
3.1.1 The ECP Director will perform personnel accountability to assure that the ECP staffing requirements can be met.
3.1.2 Assumes overall responsbility for providing the Corporate Emergency Director (located at the Forward Command Post) with the counsel, expertise, and resources available within the PSC organization.
3.1.3 Coordinates emergency assistance, provides reentry and recovery support, station and co-ordinates site modifications review by the Nuclear Facility Safety Committee as appropriate.
3.1.4 Supervises the ECP emergency operations Mangers, communications, and clerical personnel, briefs ECP staff.
3.1.5 Dispatches headquarters management, administrative
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PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION Attach. 1 Issue 6 Page 1 of 1 SUPPORT EQUIPMENT / MATERIALS
- 1. Communications equipment - telephones.
- 2. Fort St. Vrain Radiological Emergency Response Plan.
- 3. State Radiological Emergency Response Plan.
- 4. Local Government Emergency Plan.
l 5. Maps a) Fort St. Vrain area and environs. b) Regional. l 6. Fort St. Vrain Station layout drawings (see RERP-SURVEY). l 7. Other support available. a) Reproduction Equipment. O b) Commerical television station monitoring equipment. c) Radio-television recording equipment. O FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1 Issue 6 Page 1 of 1 A V ECP DIRECTOR'S CHECKLIST NOTE: All information is to be recorded by the Clerical Assistant Time
- 1. Personnel Accountability
- a. Manager of iechnical Support - Nuclear Design Department Manager / Nuclear Services Manager
- b. Manager of Media Relations - VP Public Affairs /
Manager of Media Relations.
- c. Manager of Resources - VP Accounting /VP of Finance & Treasurer. ,___
- d. Manager of Security - Manager of Claims, Safety
& Security / Security Coordinator.
() e. Clerical assistants - Secretary to VP Accounting.
- f. Communications Support Person.
- 2. Staffing requirements met.
- 3. Communications established with FCP.
l 4. FCP informed that ECP is manned and ready and location.
- 5. Status of plant and emergency and assessment of condition received from FCP.
~6 . Location of PCC requested and received.
- 7. Staff briefing conducted.
l l l l 1 l l I (" < (x,1 l FORM 372 - 22 3643 l l l
l PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION WS/03/CL Issue 6 Page 1 of 3 O Work /Datasheet/ Checklist Control List Worksheet No. Title Numbt- Cocies None N/A N/A Datasheet No. None N/A N/A Checklist No. 1 ECP Director's Checklist 2 O O FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENET ATING STATION WS/DS/CL l Issue 6 i Page 2 of 3 FORMS USE REPORTING SHEET l Technical Clerk and Recorder: This sheet is being transmitted to report use of forms from a i controlled copy of the Radiological Emergency Response Pian Implementing Procedures, BOOK NO. , located at The following forms have been utilized from this copy: Worksheet Numbers Copies Used Datasheet Numbers Cood es Used Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form i: received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting O Sheet" for the affected procedure in the affected book. FOR M 372 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 6 Page 3 of 3 O FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: Technical Clerk and Recorder Date Received Date Replaced Technical Clerk and Recorder will transmit this form to the originating individual / department upon completion of this form to l O notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required . number of copies. l FORM 372 22 - 3643
,- PUBLIC SEP.VICE COMPANY OF COLORADO RERP-ECP T FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1
( Issue 6 Page 1 of 1 O ECP DIRECTOR'S CHECKLIST NOTE: All information is to be recorded by the Clerical Assistant Time
- 1. Personnel Accountability
- a. Manager of Technical Support - Nuclear Design Department Manager / Nuclear Services Manager
- b. Manager of Media Relations - VP Public Affairs /
Manager of Media Relations.
- c. Manager of Resources - VP Accounting /VP of Finance & Treasurer.
- d. Manager of Security - Manager of Claims, Safety
& Security / Security Coordinator.
- e. Clerical assistants - Secretary to VP Accounting.
({})
- f. Communications Support Person.
- 2. Staffing requirements met.
- 3. Communications established with FCP.
- 4. FCP irformed that ECP is manned and ready and location.
- 5. Status of plant and emergency and assessment of condition received from FCP.
- 6. Location of PCC requested and received. '
- 7. Staff briefing conducted.
O . FORM 372 3643
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PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1 Issue 6 Page 1 of I C:) . ECP DIRECTOR'S CHECKLIST NOTE: All information is to be racorded by the Clerical Assistant Time
- 1. Personnel Accountability
- a. Manager of Technical Support - Nuclear Design Department Manager / Nuclear Services Manager
- b. Manager of Media Relations - VP Public Affairs /
Manager of Media Relations.
- c. Manager of Resources - VP Accounting /VP of Finance & Treasurer.
- d. Manager of Security - Manager of Claims, Safety
& Security / Security Coordinator.
- e. Clerical assistants - Secretary to VP Accounting.
(a)
- f. Communications Support Person.
- 2. Staffing requirements met.
- 3. Communications established with FCP.
- 4. FCP informed that ECP is manned and ready and location.
- 5. Status of plant and emergency and assessment of condition received from FCP.
- 6. Location of PCC requested and received. -
- 7. Staff briefing conducted.
F OR M 372 22 3543
7 PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP
> FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL v, Issue 6 Page 1 of 3 O
Work /Datasheet/ Checklist Control List Worksheet No. Title Number Copies None N/A N/A Datasheet No. None N/A N/A I i Checklist No. I 1 ECP Director's Checklist 2 O FORM 372 22 3643 l
PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 6 Page 2 of 3 () , FORMS USE REPORTING SHEET Technical Clerk and Recorder: This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at
. The following forms have been utilized from ,
this copy: Worksheet N;mbers Copies Used () Datasheet Numbers Copies Used Checklist Numbers Copies Used 1 I l l i l l The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this - form is received, it will be necessary to replace l Q v the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. F OR M 372 300
PUBLIC SERVICE COMPANY OF COLORADO RERP-ECP FORT ST. VRAIN NUCLEAR GENERATING STATION WS/DS/CL Issue 6 Page 3 of 3 FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: _ Date: Technical Clerk and Recorder Date Received Date Replaced Technical Clerk and Recorder will transmit this form to the originating individual / department upon completion of this form to O notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies. G O FORM 372 22 3643 l l l .- .--
PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRAlN NUCLEAR GENERAT)NG STATION Issue 8 Page 1 of 7 v TITLE: FORVARD C0XMAND POST PROCEDURE -
)
ISSUANCE py, g,,, ,,,, g, g AUTHORIZED BY 4 &"r7]cAA EFFECTIVE PORC REVIEW 9 EORc 4 9 7 DEC 2 71982 DATE l b3 TABLE OF CONTEN S Section Description Page 1.0 Criteria for Implementation... .. .. .. .. ..... . ...... 3 2.0 Proced g . . . .. . .... .... ..... ....... ... . ..... 3 3.0 kcaponsibilities . ........ . ... . . . .4 4.0 References .... ... .. . .. .. ..... ........ ....... .. 7 5.0 Referenced or Supporting Procedures.. ...... ....... ... .... 7 U Figure 1 Location Map . ..... .... . ... .. ... ....... 1 Figure 2 Forward Command Post Floor Plan... . .. .. ........ . 1 Figure 3 Forward Command Post Organization...... . ..... ..1 Figure 4 Emergency Organization .... .. ... . ......... .... 1 Figure 5 Site Sector Map.... .. .... .. . .. ... ... ... 1 Figure 6 Aerial View Map of Plant ..... ........ . ..... ... 1 Attachment 1 Support Equipment / Materials .... .. ..... ..... 1 Datasheet 1 Forward Command Post Status Board ... ......... 1 Checklist 1 Corporate Emergency Director's Checklist. . .... 1 O v FORM 371 22 3642
(
; PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP e
FORT ST. VRAIN NUCLEAR GENERATING STATION 1 t l Q" Work /Datasheet/ Checklist Control List .. .. ......... 1 Forms Use Reporting Sheet *.. ... .. . ... . .. ......... 2
- ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN l ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FORWARD IT TO THE TECHNICAL CLERK AND RECORDER, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, l DATASHEETS, CHECKLISTS. OR REPORTING SHEETS IN ~HE PROCEDURE l ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN I FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
l l 1 l l l l l l O l ~ eonu an-22. sus 1 l
PUBLIC SERVICE COMPANY OF (,OLORADO RERP-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION 3 of 7 U ESTABLISHING THE FORWARD COMMAND POST 1.0 Criteria for Imolementation When the FSV Radiological Emergency Response Plan (RERP) requires augmentation of resources, generally for an ALERT or higher amergency classification, the Corporate Emergency Director (CED) shall activate the Forward Command Post (FCP). 2.0 Procedure 2.1 The Forward Command Post (FCP) shall be established in the garage of the PSC Fort Lupton Service Center. (See Figure 1) The FCP functions as the control and coordination center for on-scene stete/ local / federal emergency response forces, and communicates with the State EOC and with the Weld County EOC (Weld County Communication Center) for effective coordination of county forces. A senior representative of D0 DES is responsible for control and l coordination of FCP emergency response activities. l (m) 2.2 Corporate Emergency Director (Checklist 1) 2.2.1 The CED will perform personnel accountability to assure that the FCP staffing requirements can be met. If not during normal working hours, those personnel required to man the FCP are notifed by telephone. It is the responsibility of the CED alternate to ensure that the notifications are made. Refer to RERP PHONE LIST for the FCP for instructions, names, and phone numbers (after hours, see RERP-HOME). 2.2.2 Assumes overall command of PSC emergency operations and is the prime contact between Fort St. Vrain and governmental authorities. 2.2.3 The CED shall establish communications and verify that primary and secondary communcation links to the Technical Support Center (TSC) are available. p G FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP O FORT ST. VRAIN NUCLEAR GENERATING STATION v 2.3 Station Technical Liason The Station Technical Liason shall provide technical interpretation, assistance, and guidance, as requested, throughout the course of events. He shall review the incoming plant data and advise the Corporate Emergency Director as to the trend of the accident. Additionally, he shall assist state / local / federal FCP personnel in areas of plant technical data. 2.4 Radiological Assessment Coordinator The Radiological Assessment Coordinator shall evaluate or perform the offsite dose consequence assessments (see RERP-DOSE), provide technical advice to the Corporate Emergency Director with regard to Protective Action recommendations (see RERP-PAG), and shall assist the Senior Health Physics representative at the TSC with decisions regarding emergency exposure limits for emergency team members (see RERP-EXP), the need for administration of thyroid blocking agent (see RERP-THYROID), and receive / interpret field monitoring data (see RERP-FIELD). 'p 3.0 Responsibilities v/ 3.1 Corporate Emergency Director 3.1.1 The CED is responsible Pr direction and coordination of: a) PSC onsite and offsite emergency functions. b) Interface between PSC and local / state / ederal emergency response activities. c) Transmission of plant status updates and radiological release data to the ECP and PSC Personnel at the State EOC and media center personnel, and briefing the PSC FCP staff. d) Notification of state and local agencies concerning reccmmended protective actions. e) Provision of administrative, technical, and logistical support to station emergency operations. f) Continuity of emergency organization resources. f%. FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRA!N NUCLEAR GENERATING STATION Issue 8 Page 5 of 7 m 3.1.2 The CED provides direction to, and coordination for, the TSC Director and the Nuclear Engineering Manager (assigned to the State ECC). He will coordinate additional headquarters support via the Executive Command Post (ECP). 3.1.3 Terminates the FCP when the emergency condition has been brought to a recovery phase. 3.1.4 Acts as Recovery Director per Section 9.0 of the RERP. 3.2 Communications Personnel 3.2.1 Establish communications with the TSC. (See Figure 2 for Emergency Kit and phone jack locations). Primary Telephone (open line) l l Secondary l l q v PSC Radio Verify secondary system. 3.2.2 Inform the TSC that the FCP is manned and ready. 3.2.3 Receive status of plant and emergency and assessment of condition and inform CED. 1 i 3.2.4 Request location of Personnel Control Center (PCC). 3.2.5 Communication is to be established with the Executive Command Post (ECP) and the State l Emergency Operations Center (EOC). Inform the CED when accomplished. a) Appraise them of the situation as directed by the CED. 1 b) Inform them of the location of the PCC, should it be necessary to dispatch assistance to the plant. 3.2.6 Maintain communications flow between the TSC, ECP, and State EOC. p
'v' F ORM 372 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION 6 of 7 U_ ! 3.3 The FCP staff keeps an ongoing record (log) of all actions taken. The Radiological Assessment Coordinator will assign one of the clerical staff responsibility for updating the FCP status board at approximately 15 minute intervals. Data for updates is to be obtained from, and reviewed by, the Radiological Assessment Coordinator prior to posting. Datasheet 1 is provided as a working copy for all status board updates. These sheets shall be retained for record keeping purposes. 3.4 Station Technical Liaison a) Provide assistance and substantiated data on emergency status and conditions. b) Coordinate company emergency response actions with those of state / local / federal agencies. 3.5 Media Relations Provide assistance to the FCP Public Information Team (PICT) in the preparation of news and related media releases. p 3.6 Radiological Assessment Coordinator. 3.6.1 In coordination with the TSC Radiological . Assessment individual, perform and/or evaluate a preliminary assessment of the actual and/or potential radiological release. Utilize this information to complete Status Board Update She ets. Verify any calculations in question via manual or TI-59 calculations. 3.6.2 Based on the above assessment, identify and recommend to the Corporate Emergency Director the classification of the emergency (ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY) and recommended protective actions to reduce exposures to the - general population (see RERP-PAG). 3.6.3 Monitor radiation levels and meteorological data, and provide the Corporate Emergency Director with estimates of the dose to the general population based on actual releases and meteorology. 3.6.4 Obtain a 12 hour weather prediction from Stapleton Airport National Weather Service (refer to Outside Assistance Phone Numbers) and provide the FCP Director with estimates of the projected dose to the general population based upon plant conditions o and foreseeable contingencies. V FORM 372 22 3643
l PUBLIC SERVICE COMPANY OF iOLORADO RERP-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION ssue 8 n v 3.6.5 Assign a member of the clerical staff responsibility for posting updates to the FCP status board located outside the PSC staff area. The Radiological Assessment Coordinator will supply l and review all data to be posted. 3.6.6 Provide guidance to the TSC Senior Health Physics representative on matters regarding acministration of thyroid blocking agent to site personnel (see RERP-THYROID). 4.0 References 4.1 FSV Radiological Emergency Response Plan 4.2 State Radiological Emergency Response Plan 5.0 Referenced or Succortina Procedures 5.1 RERP-ORG, FSV Emergency Organi:ation and Responsibilities 5.2 RERP-DOSE, Offsite Dose Calculations 5.3 RERP-EXP, Emergency Exposure Guidelines b) 5.4 RERP-FIELD, Field Monitoring Procedure 5.5 RERP-HOME, Home Packets for Offshift Notifications 5.6 RERP-PAG, Protective Action Guideline Recommendations 5.7 RERP-THYROID, Thyroid Blocking Agent Administration 5.8 EP-CLASS, Event and Emergency Classification Overview l 5.9 RERP-SURVEY, Inplant/Onsite Radiological Monitoring l 5.10 Fort St. Vrain Final Safety Analysis Report
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V F OR M 372 22 - 3643
- PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION Figure 1 Issue 8 Page 1 of I O
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- 1. Communication equipment - telephones and radios
- 2. Fort St. Vrain Radiological Emergency Response Plan (FSV RERP)
- 3. State FSV Radiological Emergency Response Plan (State RERP) l 4. Local government emergency plans - Weld County Plan l s. Evacuation time study 1 6. Maps (See RERP implementing procedures RERP-DOSE, RERP-SURVEY, I and RERP-PCC.)
a) Fort St. Vrain area and environ b) Sectors c) Regional d) Health Physics Survey Maps of FSV Buildings n# l 7. Public Information Plan l 8. RERP Implementing Procedures
- 9. Office supplies i
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PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRAIN NUCL9AR GENERATING STATION Checklist 1 Issue 8 Page 1 of 2 O V CHECKLIST 1 CORPORATE EMERGENCY DIRECTOR'S CHECKLIST NOTE: Ali information is to be recorded by the Clerical Assistant. Time
- 1. Fort Lupton PSC office notified of intent to occupy building.
- 2. Personnel Accountability a) Station Technical Liaison b) Radiological Assessment Coordinator c) Clerical Assistants d) Media Relations e) Additional personnel from outside agencies.
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(_) 1. Colorado Department of Health a) Radiological monitoring, technical, and health units, as required b) Public information representative
- 2. State Division of Disaster Emergency Services
- 3. Weld County Sheriff's Office l
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- 3. Staffing requirements met.
- 4. Communications established with TSC.
l 5. TSC informed that FCP is manned and activated. l O v FORM 372 360
PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1 Issue S Page 2 of 2 Time
- 6. Status of emergency and assessment of plant condition received from TSC.
- 7. Staff briefing conducted.
- 8. Outside agency briefing conducted.
- 9. Location of PCC requested and received. __
- 10. Communications established by ECP.
- 11. ECP appraised of plant condition and informed of location of PCC.
- 12. Communication established by State EOC.
- 13. State EOC appraised of plant condition and informed of location of PCC.
- 14. Initial Radiological Assessment (Actual) obtained Release Rate Curies Released Dose Rate Dose Received Protective Action Guide
- 15. Preliminary Radiological Assessment (Projected) obtained Release Rate Curies Released Dose Rate Dose Received Protective Action Guide
~16 . Meterological forecast obtained (12 hour).
A FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION
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WORK /DATASHEET/ CHECKLIST CONTROL LIST Worksneet No. Title Number Copies None N/A N/A Datasheet No. 1 Forward Command Post Status Board 25 Checklist No. 1 Corporate Emergency Director's Check 11st 2 t O I 1 1 O 1 FORM 372 22 3643 l
PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRAiN NUCLEAR GENERAT NG STATION Page 2 of 3 O v FORMS USE REPORTING SHE_ET Technical Clerk and Recorder: This sheet is being transmitted to report use of forms from a controlled ccpy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at The following forms have been utilized from this copy: Worksheet Numbers Copies Used l O oatasheet Numbers Cooies Used l l Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. J FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION g Page 3 of 3 FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: Technical Clerk and Recorder Date Received Date Replaced Technical Clerk and Recorder will transmit this form to the originating individual / department upon completion of this form to O n tify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies. l l l i O l FORM 372 - 22 3643
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