ML20098H314
| ML20098H314 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/07/1984 |
| From: | PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20098H312 | List: |
| References | |
| PROC-840807-01, NUDOCS 8409120387 | |
| Download: ML20098H314 (630) | |
Text
{{#Wiki_filter:- - PUBLIC SERVICE COMPANY OF COLORADO BOOK 4 MC c FORT ST. VRAIN NUCLEAR GENERATING STATION 8/6/84 1
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RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATION I ISSUE EFFECTIVE NO. SUBJECT NUMBER DATE l RERP-MET Meteorological Data Acquisition 4 08-06-84 l RERP-TEAMS Emergency Team Formation , I and Direction 3 08-06-84 l RERP-SUPORG Use and Coordination of l Non-PSC Support Organizations 2 08-06-84 RERP-CORE Core Damage Evaluation 1 06-01-84 l l I B409120387 840007 PDR ADOCK 05000267 p PDR l PORM 372 22 3A43
RERP-MET PUBLIC SERVICE COMPANY OF COLORADO Issue
- FORT ST. VRAIN NUCLEAR GENERATING STATION page 1 of 8 l
l FORT ST. VRMN TITLE: METEOROLOGICAL DATA ACQUISITION NON - CONTROLLED COPY VERIFYISSUE STATUS M1TH 000UMENT CENTER ISSUANCE AUTHORIZED g?m w,, _ &, g PRfD9 TO USE FORM 37.r.3567 BY MM'77bf'M REV EW PORc 5 8 0 AUG 2 - 1984 ATE h.b-$9 Sections Description Pace General ......................................................... 3 1.0 Criteria ................................................... 3 2.0 Procedure................................................... 3 2.1 Primary Meteorological System Data Acquisition ....... 3 2.2 Back-up Meteorol ogi cal Data . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 3.0 Responsibilities ........................................... 9 4.0 References ................................................. 9 5.0 Referenced Procedures....................................... 9 Figure 1, Sample PROFS MESONET Output ........................... 1 Figure 2, PROFS MESONET System Station Locations and Identifiers ....................................... 1 Figure 3, Conversion Plots for Temperature and Dewpoint Temperature................. ................. 1 Table 1, Legend of Symbols 'or Figure 1 ......................... 1 Table 2, Stability Classification Criteria....................... 1 Datasheet 1, Back-up Meteorological Data......................... 1 Datasheet 2, Collection of Data Utilizing Raw Voltages........... 1 FORM 372 22 3642
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- i PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VR AIN NUCLEAR GENERATING STATION RERP-MET Issue 4 Page 2 of 8 Worksheet/Datasheet/ Checklist Control Sheet ..................... 1 Form Use Reporting Sheet * ...................................... 2 ANY TIME A WORKSHEET,DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, l COMPLETE THE REPORTING SHEET ATTACHED AND FORWARD IT TO THE HOCLEAR I DOCUMENTS SPECIALIST, FORT ST. VRAIN.
FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO Mf FORT ST. VR AIN NUCLEAR GENERATING STATION
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Page 3 of 8 f General This procedure provides guidance for the acquisition of meteorological data from the existing meteorological instrumentation and displays at FSV, as well as from the backup 10 meter tower operated by the National Oceanic and Atmospheric Administration (NOAA). Display of parameters from these systems is available at several locations: chart recorders in the Control Room, chart recorcers in the meteorological equipment shack adjacent to the 60 meter tower directly north of the plant, on the data logger computer displays in the TSC and CR, and for the 10 meter tower NOAA instrumentation, by telephone dial-up utilizing the Silent 700 in Radiochemistry. This procedure will discuss, in general, the means for obtaining meteorological data from displays and various alternative sources of back-up data. 1.0 Criteria This procedure is valid for use uader any conditions and is not solely provided for use during a radiological emergency. The main purpose for placing this procedu e in the RERP implementing procedures is to assure the rapid access to meteorological data during an emergency, should that information be needed. 2.0 Procedure 2.1 Primary Meteorological System Data Acquisition (60 meter tower) Data from the primary meteorological system is available from four (4) locations: chart recorders in the control room on I-09; chart recorders in the meteorological equipment shack adjacent to the sixty meter tower, directly north of the plant; from the data logger displays in the control room; and from the data logger display in the Technical Support Center. 2.1.1 Chart Recorders * (1) The following parameters are displayed on the chart recorders on I-09 in the Control Room:
- Wind Speed and Direction at the fifty-eight (58) meter elevation on the 60 meter tower; Wind Speed and Direction at the ten (10) meter elevation on the 60 meter tower;
- Differential Temperature between 58 meters and 10 meters on the sixty meter tower ('C);
PORM 372 22 3643
E 3 PUBLIC SERVICE COMPANY OF COLORADO [ g , FORT ST. VRAlM NUCLEAR GENERATING STATION Page 4 of 8
- Ambient Temperature at 10 meters; ;
- Dew point temperature; and a Rain guage level (inches).
(2) The following parameters are displayed on the chart recorders in the meteorological equipment shack:
- Wind Speed and Direction at the fifty-eight (58) meter elevation on the 60 meter tower;
- Wind Speed and Direction at the ten (10) meter elevation on the 60 meter tower;
- Differential Temperature between 58 meters and 10 meters on the sixty meter
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tower (*C);
- Ambient Temperature at 10 meters;
- Dew point temperature; and a Rain guage level (inches).
2.1.2 Data Logger Display The following data is telemetered into, or s calculated by, the plant data logger system, and is available for use in both the TSC and the Control Room. Differential Temperature (58m-10m) (*F);
- Dew Point Temperature ( F);
- Rain Guage depth (inches);
Fifteen (15) minute average wind direction at both 10 meters and 58 meters; 15 minute average wind speed at both 10 meters and 58 meters; Standard deviation of the wind direction (15 minutes worth of data at five second intervals) at both 10 meters and 58 meters (ce); Ambient temperature at 10 meters (*F); FORM 372 22 3643
-; PUBLIC SERVICE COMPANY OF COLORADO RERP-M:' IssueY s'# FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 8 Calculated Pasquill category by ( AT), ,
a Calculated Pasquill category by sigma theta (ae);
- Wind Speed and Wind Direction at both the 58 meter and 10 meter elevation.
Tne data from the primary meteorological system (60 meter tower) is available on several data logger displays. The knowledge of how to obtain displays by number is implicit in obtaining data from the data logger (Press "HOME", type the given four digit display number, press " DISPLAY", and the requested display will be shown on the selected CRT). The data discussed in this procedure may be di played on the following data logger displays: 8029, 0666, and 0667. 2.2 Back-up Meteorological Data (10 meter tower) 2.2.1 Data Logger Display Certain key parameters from the back-up (10 meter tower) are telemetered into the plant data logger. Of the back-up meteorological parameters available from the data logger (display 8029), wind speed and wind direction are the essential parameters for performing offsite dose computations. Parameters available are: Wind Speed (PSC Instrument); Wind Direction (PSC Instrunnt); Ambient Temperature (NOAA Instrument); Dew Point Temperature (NOAA Instrument); Rain Guage Depth (NOAA Instrument-DOS);
- Standard Deviation of Wind Direction-ce (Calculated)
Stability Classification by oe from 10 meter tower (see display 0667) I 2.2.2 Modem Data Acquisition (Personal Computer) The entire spectrum of data from the back-up meteorological tower is available via the use of l any Personal Comouter with a modem attached. The parameters available, and their identifiers on the FORM 372 - 22 3643
"ET PUBLIC SERVICE COMPANY OF COLORADO g Page 6 of 8 FORT ST. VRAIN NUCLEAR GENERATING STATION MESDNET output, are shown on Table 1. The Fort St.
Vrain back-up tower is represented by the identifier "PTL" on the printout (see Figure 1 for a sample printout). Representation of the locations of the stations participating in the MESONET system is shown on Figure 2. Instructions i for the use of a Personal Computer for data acquisition follow: l (1) Turn on printer and computer. .(The modem i switch should be in the " voice" position, set I up for 300 BAUD, and no disk need be inserted l in the drive.) l 2) When "C)" is seen on the terminal, type in l "pc-talk". Press enter where prompted. l 3) Press the " Ctrl" key simultaneously with the l "prtsc" key to print all screens. l 4) Dial 8-303-447-9179. When the high pitched l carrier tone is received, rlace the modem l switch in the " data" position and place the l phone in its receiver. 8-303-447-9179, is provided by NOAA to provide a listing of the last three available 5 minute updates of the MESONET system, and then drop the user automatically off the telephone line at the end of the transmission. 8-303-447-0992 is generally used by the Solar Energy Research Institute (SERI), and provides an update every 5 minutes. If possible, use of this line sFould be limited to the hours 0000 to 0800 to avoid conflicts with SERI. In l an emergency, 8-303-447-0992 could be made available on a continual basis, by contacting Mr. Val Swarcz (Office, 8-303-231-1816; Home, 8-303-494-1578) NOTE: The PROFS MESONET network issues weather updates every five (5) minutes on the 8-303-447-0992 line. Since the network is likely to be either between updates or in the process of transmitting an update, it may be 1 necessary to wait for up to 5 minutes for the l first complete printout to begin to be received (see Figure 1 for sampie PROFS i MESONET printout and Table 1 for an explanation and legend of symbols). 1 PORM 372 22 3643
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RERP-MET o' PUBLIC SERVICE COMPANY OF COLORADO Issue 4 FORT ST. VRAIN NUCLE AR GEM 5 RATING STATION Page 7 of 8 l 5) When prompted to enter a password, enter l l " SURF". The shift key must be depressed for ' l the proper password to be received. l NOTE: This password has been issued to l l authorized users only, and should be kept I confidential. - l 6) Turn off unit and printer when all data is l received. Record the data, as appropriate to needs, on Datasheet 1, and perform stability classification calculations (see Table 2). 2.2.3 Remote Data Readout at Back-up Tower Remote determination of key back-up meteorological parameters is possible via two (2) methods. Wind speed, wind direction, ambient temperature, and dewpoint temperature may be readily determined from read-out of post-conditioner voltages utilizing a permanently installed switching box and performing linear conversion calculations. In addition, should read-out of data from the back-up tower become necessary for a prolonged time, NOAA has available for PSC use, data conversion and display units that will continuously display the current back-up meteorological parameters. 2.2.3.1 Use of Post-Conditioner Voltages Utilizing the installed switching box at the meteorological equipment shack, enter on Datasheet 2 the displayed voltages for channels 1, 3, 5, and 8. Datasheet 2 provides for recording the wind speed, wind direction, ambient temperature, and dewpoint temperature, as well as for performing data conversion calculations and stability classification calculations. 2.2.3.2 NOAA Conversion / Display Unit Install the NOAA scanning conversion / disp. lay unit in accordance with NOAA instructions. Record data, as appropriate, and perform stability classification calculations as shown on Datasheet 1. PORM 372 22 3643
g . PUBLIC SERVICE COMPANY OF COLORADO f l FORT ST. VRAIN NUCLEAR GENERAT!WG STATION Pace 8 of 8 l l l l 2.2.4 Telephone Voice Transfer l Data from any of the MESONET system towers is generally available direct from NOAA personnel weekdays between 0800 hours and 2400 hours by calling any of the following telephone numbers, identifying you*self (PSC/FSV), and reouesting data for station "PTL":
- Call the U.S. Department of Commerce in Boulder, Colorado by dialing 8-303-497-6987*
(0B00-2400 hours, Monday through Friday).
- Backup phone numbers are 8-303-497-6895, 8-303-497-6964, 8-303-497-6116.
Record data received on Datasheet 1 and determine stability classification as shown. 3.0 Resconsibilities Data collection, calculations, and meteorological parameter determinations utilizing this procedure under emergency conditions shall be performed by the following RERP assigned individuals, or their designees:
- Radiological Assessment Coordinator
- Radiological Assesment Individual at the TSC
- Shift Supervisor Use of this procedure under non-RERP conditions is at the discretion of the user.
4.0 References 4.1 Surface MESONET Manual, U. S. Department of Commerce (Internal Document) 5.0 Referenced Procedures 5.1 SR-TE-3-M, Back-up Meteorological Data Collection 5.2 RERP-DOSE, Offsite Dose Calculations . l 5.3 RERP-CR, Control Room Procedure i l l l l PORM 372 22 3643
RERP ' MET PUBLIC SERVICE COMPANY OF COLORADO Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Figuro 1 Page 1 of 1 FIGURE 1 Sample PROFS Mesonet Outout
' ENTEP PA9 SWORD -
FROF5 E/.FERIt1 ENTAL MESONET 26-JUL-84 16:05Z 5 MINUTE AVERAGES ET ATI D:J T TD 5 A2 PP.-GUST PCP SR ZEN SR 40DEG PRES A R '.' 71 61 e 34 10 22 O.00 692 640 844.7 RBO 74 56 7 62 10 68 0.00 686 647 847.6 BRI 70 59 4 05 7 27 0.00 522 443 646.2 1.GM 74 55 7 60 12 71 0.00 663 672 854.7 i IJB 70 60 6 41 10 71 0.00 540 502 856.4 ROL 50 49 6 254 8 254 O.00 209 0 805.O EFr 64 48 0 101 6 91 0.00 749 674 773.0 LAM 67 39 7 15 10 00 0.00 093 051 825.7 LTrJ c.S 57 4 1 7 056 0.00 089 340 834.0
!?G 47 42 9 15 11 23 0.00 194 167 677.8 lPTL 7 57 5 9 9 051 0.00 510 464 860.4l LVE 7; be s 347 8 345 0.00 039 053 857.7
&YE 74 59 5 052 10 17 O.00 606 586 850.1 FOR 'O 54 2 342 3 006 O.00 572 566 848.6 AUR 71 59 6 009 9 355 0.00 O O 847.2 IJUN 72 52 6 57 8 58 O.00 824 791 846.2 GLY 74 57 5 38 8 05 0.00 710 698 867.0 FTM =7 59 14 52 17 51 0.00 525 458 871.e ELE 59 SC 11 224 14 019 0.00 31 74 797.4 WAD 50 47 2 46 5 34 0.00 141 121 717.4 LGD 72 05 8 22 11 22 0.00 653 611 861.0 EPI 70 59 6 18 10 8 0.00 O O 850.8 l
1 PORM 372 22 3643
RER -MET PUBLIC SERVICE COMPANY OF COLORADO Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Figure 2 Page 1 of 1 FIGURE 2 PROFS MESONET System Station Locations and Identifiers PROFS Surface Mesonstwork 1981 vire.n can , l vot i ONUN
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RERP-MET PUBLIC SERVICE COMPANY OF COLORADO 1ssue 4
'. FORT ST. VR AIN NUCLEAR GENERATING STATION Figure 3 Page 1 of 1 FIGURE 3 Conversion Plots for Temoerature and Dewooint Temoerature 9!i
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PUBLIC SERVICE COMPANY OF COLORADO [ue" l FORT ST. VR AIN NUCLEAR GENERATING STATION Tabl@ 1 ' Page 1 of 1 TABLE 1 Lecend of Symbols for Ficure 1 SYMBOL MEANING T Temperature (*F) @ 10m Elevation TD Dew Point (*F) S Windspeed - Average (knots) AZ Wind direction - Average (degrees) PK-GUST Windspeed - Peak (knots) and Peak Wind Direction (degrees) PCP Precipitation (inches) VIS Visibility (miles) SR ZEN Solar Radiation - Zenith (watts /m8 ) SR 40 DEG Solar Radiation - 40* above horizon (watts /m2 ) P Atmospheric Pressure Explanation of Printout: The backup meteorological tower is identified as station "PTL" on the printout. A sample output is shown on Figure 1, and a legend defining the symbols on the printout is listed above. It must be noted that the time shown on the PROFS outout is in Coordinated Universal Time (UTC) which is seven (7) hours later than Mountain Standard Time (MST) or six (6) hours later than Mountain Daylight Time (MDT). PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO u FORT ST. VRAIN NUCLE AR GENER ATING STATION Table 2 Page 1 of 1 TABLE 2 Stability Classification Criteria
- AT ( F) from Pasquill Stability o0**
60m Tower Categories Classification (Degrees) s-1.7 A Extremely Unstable 222.5
>-1.7 to s -1.5 B Moderately Unstable <22.5 to 217.5
>-1.5 to s -1.3 C Slightly Unstable <17.5 to 212.5
>-1.3 to s -0.4 D Neutral <12.5 to 2 7.5
>-0.4 to s1.3 E Slightly Stable < 7.5 to 2 3.8
>+1.3 to 53.5 F Moderately Stable < 3.8 to 2 2.1
>+3.5 G Extremely Stable <2.1 Per proposed Revision I to Regulatory Guide 1.23, September 1980.
Standard Deviation of horizontal wind direction fluctuation (plume meander) over a period of 15 minutes to I hour. PoRM 372 22 3643
l PUZLIC SERVICE COMPANY OF COLORADO " ue FORT ST. VR AIN NUCLEAR GENERATING STATION Datasheet 1 ) Page 1 of 1 DATASHEET 1 Backup Meteorological Data l _ l l l PRDFS Network data via l_l Personal Computer l I I l ((["NDAAStaff" l I I l l(("Lo:allyat10metertower" l I i l TIME /DATE TIME /DATE TIME /DATE l l l l / / / I I I l[AZ) Wind Direction *- l l Average (degrees) l I I ((S] Wind Speed- l l Average (knots) l 1 l l[-GUST] Wind Direction- l l Peak (degrees) l l l ((PK-] Wind Speed- l l Peak (knots) l l l ((T] Temperature (*F) l l l l[TD] Dew Point (*F) l 1 l l[VIS] Visibility l l (Miles) l 1 I l[PCP] Precipitation- l l (inches) . l l l l[SRZEN] l l Solar Radiation- l l Zenith (watts /m*) l l l l[SR40DEG] l l Solar Radiation-40' { l above Horizon l 8 l (watts /m ) l l l l[P] Atmospheric l l Pressure l l l l l l l* e6 = Square root of maximum difference in wind direction l ll noted over the three 5 minute updates. l PORM 372 22 3643 _ _ - _ _ _ - _ - _ _ _ _ _ _ _ _ _ _ ___________m
.PUBLIC SERVICE COMPANY OF COLORADO Mf FORT ST. ' .AIN NUCLEAR GENERATING STATION Datasheet 2 Page 1 of 1 DATA SHEET 2 Collection of Data Utilizing Raw Voltages ! I I I I I l TIME /DATE TIME /DATE TIME /DATE l l l l / / / l l 1 l Wind Direction l l Position No. 1 (V) (V) (V)l l 1 I l l Wind Direction, degrees (*) = l l (1) 1.25 volts-5.0 volts : 450.0-;72.0 xoutputvoltage) l l (2) 0.00 volts-1.25 volts : 90.0 ,72.0 x output voltage] l l Wind Direction l l Degrees l l l l Wind Speed l l Position No. 3 (V) (V) (V)!
I i l Wind Speed = Output voltage /0.05 l l l l Wind Speed (mph) l l l l Ambient Temperature, l l Position No. 5 (V) (V) (V)l l 1 l Ambient Temperature (see Figure 3 for data conversion) l l l l Ambient Temperature 'F l l l l Dewpoint Temperature l l Position No. 8 (V) (V) (V)l l l l Dewpoint Temperature (see Figure 3 for data conversion) l l l l Dewpoint Temperature 'F l l l l Stability Classification: oo = l l Square root (maximum difference in wind direction over three 5 l l minute updates) l 1 l l The preferred sampling frequency for these purposes is to l l collect three sets of data five (5) minutes apart. ' l , I I ! l Refer to RERP-DOSE for use of this data for dose calculations l l l PoRM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO g,;(3)'c FORT ST. VRAIN NUCLEAR GENERATING STATIOh Issue 4 Page 1 of 3 Worksheet/Datasheet/ Checklist Control Sheet Datasheet No. Title Cooies 1 Back-up Meteorological Data 2 2 Collection of Data Utilizing Raw Voltages 2 O PORM 372 22 3643
RERP-MET PUZLIC SERVICE COMPANY OF COLORADO WS/DS/CL Issue 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 3 FORMS USE REPORTING SHEET l Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a controlled copy of the Emergency Plan Implementing Procedures, BOOK NO. , located at . The following forms have been utilized from this copy: Worksheet Numbers Cooies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. PORM 372 2; .2 M43
E PUBLIC SERVICE COMPANY OF COLORADO S C{ FCRT ST. VRAIN NUCLEAR GENERATING STATION l$ sue 4 Page 3 of 3 FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: 1 Nuclear Documents Specialist
- Date Received Date Replaced
[* Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies. e I PORM 372 22 3643 l l
PUBLIC SERVICE COMPANY OF COLORADO ~"f FORT ST. VR AIN NUCLE AR GENERATING STATION Datasheet 1
' Page 1 of 1 DATASHEET 1 Backup Meteorological Data i _ l l l PROFS Network data via l_l Personal Computer l 1 l l l[l"NDAAStaff" l l l l l[l"Locallyat10metertower" l l l l TIME /DATE TIME /DATE TIME /DATE l l l l / / / l l 1 l[AZ) Wind Direction *- l l Average (degrees) l I l l[5] Wind Speed- l l Average (knots) l l l l[-GUST] Wind Direction- l l Peak (degrees) l l l l[PK-] Wind Speed- l l Peak (knots) l l l l[T] Temperature (*F) l l l l[TD] Dew Point (*F) l l l l[VIS] Visibility l l (Miles) l l l l[PCP) Precipitation- l l (inches) l l l l[SRZEN] ,l l Solar Radiation- l l Zenith (watts /m') l l l l[SR40DEG] l l Solar Radiation-40' l l above Horizon l l (watts /m8 ) l l l l[P] Atmospheric l l ** Pressure l l l l l l l* e6 = Square root of maximum difference in wind direction l ll noted over the three 5 minute updates. l FORM 372 22 + 3443
; ; PUBLIC SERVICE COMPANY OF COLORADO ue i'- FORT ST. VRAIN NUCLEAR GENERATING STATION Datasheet 1 Page 1 of 1 DATASHEET 1 Backup Meteorological Data I _ l l l PROFS Network data via l_l Personal Computer l I ~ I l l l "NOAA Staff" l l l l l[l"Locallyat10metertower" l 1 l l TIME /DATE TIME /DATE TIME /DATE l l l 1 / / / I I l l[AZ] Wind Direction *- l l Average (degrees) _l 1 l l[5] Wind Speed- l l Average (knots) l l l
((-GUST) Wind Direction- l l Peak (degrees) l l l l[PK-] Wind Speed- l l Peak (knots) l l l l[T] Temperature (*F) l l l l[TD] Dew Point (*F) l l 1 l[VIS] Visibility l l (Miles) l l 1 l[PCP] Precipitation- l l (inches) l l l l[SRZEN] l l Solar Radiation- l l Zenith (watts /m*) l l l ((SR40DEG) l l Solar Radiation-40' l l above Horizon l l (watts /m8 ) l l 1 l[P] Atmospheric l l ** Pressure l l l l l l l* e6 = Square root of maximum difference in wind direction l ll noted over the three 5 minute updates. l PORM 372 22
- 3643
gm PUBLIC SERVICE COMPANY OF COLORADO Mf ' FORT ST. VRAIN NUCLEAR GENERATING STATIOrd Datasheet 2 '
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I DATA SHEET 2 Collection of Data Utilizing Raw Voltages i I I I I I l TIME /DATE TIME /DATE TIME /DATE l l I I / / / I I l l Wind Direction l l Position No. 1 (V) (V) (V)l l I l l l Wind Direction, degrees (*) = l l (1) 1.25 volts-5.0 volts : 450.0-;72.0 x output voltage] l l (2) 0.00 volts-1.25 volts : 90.0 - 72.0 x output voltage] l l Wind Direction l l Degrees l 1 l l Wind Speed l l Position No. 3 (V) (V) (V)l l l l Wind Speed = Output voltage /0.05 I I i l Wind Speed (mph) l l l l Ambient Temperature, l l Position No. 5 (V) (V) (V)l l l l Ambient Temperature (see Figure 3 for data conversion) l l l l Ambient Temperature 'F l l l l Dewpoint Temperature l l . Position No. 8 (V) (V) (V)l ' l l l Dewpoint Temperature (see Figure 3 for data conversion) l l l l Dewpoint Temperature 'F l l 1 l Stability Classification: o8 = l l Square root (maximum difference in wind direction over three 5 l l minute updates) l 1 l l The preferred sampling frequency for these purposes is to l l collect three sets of data five (5) minutes apart. l 1 I l Refer to RERp-DOSE for use of this data for dose calculations l l l POmM 372 22 3443
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PUBLIC SERVICE COMPANY OF COLORADO $ ,M[.T FORT ST. VR AIN NUCLEAR GENERATING STATION Datasheet 2 i Page I cf 1 l DATA SHEET 2 Collection of Data Utilizing Raw Voltages l I I I I i 1 l TIME /DATE TIME /DATE TIME /DATE l l l J / / / I I l l Wind Direction l l Position No. 1 (V) (V) (V)l l l J l l Wind Direction, degrees (*) = l l (1) 1.25 volts-5.0 volts : 450.0-;72.0 xoutputvoltage[ l l (2) 0.00 volts-1.25 volts : 90.0 .72.0 x output voltage,' l l Wind Direction l l Degrees l l l l Wind Speed l l Position No. 3 (V) (V) (V)l l 1 l Wind Speed = Output voltage /0.05 l l l l Wind Speed (mph) l l l l Ambient Temperature, I l Position No. 5 (V) (V) (V)l l l . l Ambient Temperature (see Figure 3 for data conversion) l l 1 l Ambient Temperature 'F l l l l Dewpoint Temperature . l , l . Position No. 8 (V) (V) (V)l t i I l Dewpoint Temperature (see Figure 3 for data conversion) l l t l l l Dewpoint Temperature 'F l ! I I l Stability Classification: oo = l l Square root (maximum difference in wind direction over three 5 l l minute updates) l l l l
- The preferred sampling frequency for these purposes is to l l collect three sets of data five (5) minutes apart. l 1 I i l Refer to RERP-DOSE for use of this data for dose calculations l l l l F OR M 372 22 3443 1
- 7. PUBLIC SERVICE COMPANY OF COLORADO g.f [)ft PORT ST. VR AIN NUCLE AR GENERATING STATION lssue 4 Page 1 of 3 s ,
Worksheet/Datasheet/ Checklist Control Sheet DatasNet No. Title Copies 1 Back-up Meteorological Data 2 2 Collection of Data Utilizing Raw Voltages 2 e I POmW 372 33 3H3
(Y " - PUBLIC SERVICE COMPANY OF COLORADO RERF-MET WS/05/CL Issue 4 l h FOTIT ST, VRAIN NUCLEAR GENEftATING STATION l [ Page 2 of 3 FORMS USE REPORTIN3 SHEET l l Nuclear Documents Specialist: l This sheet is being transmitted to report use of forms from a , controlled copy of the Emergency Plan Implementing Procedures, BOOK ! NO. , located at . The following forms j have been utili:ed from this copy: I Worksheet Numbers Copies Used l Datasheet Numbers Copies Used i l Checklist Numbers Copies Used 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 the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. l *
- POmW 373 33 3640 i
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>T F03T ST. VR AIN NUCLEAR GENERATING STATION Issue 4
; Page 3 of 3 FORM.S USE REPORTIN3 SHEET (Continued)
COM.M.ENTS Reported By: Date: l Nuclear Documents Specialist Date Received Date Replaced l* Nuclear Documents S ecialist will transmit this form to the 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. f P0mW 373
- 88 ' 3HS
RERP-TEAMS i
. . PUBLIC SERVICE COMPANY OF COLORADO Issue 3 I
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FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 7 l FORT ST.VRM TITLE: EMERGENCY TEAM FORMATION AND DIRECTION NON .C0 .ROL G VERFYISSUI STATUS M H DOCUMENT CENTER monToUSE ISSUANCE AUTHORIZED W FORM 372 22 3567 BY A 1%!h PORC g/ EFFECTIVE REVIEW PORc 5 8 0 JUL 311984 DATE h b-b Sections Description Page General ......................................................... 2 1.0 Criteria...................................................2 2.0 Procedure................................................... 2 2.1 Search and Rescue Teams............................... 2 2.2 Corrective Action Teams............................... 4 3.0 Responsibil.ities ........................................... 5 4.0 References ................................................. 7 5.0 Referenced Procedures....................................... 7 Datasheet 1 Pre-dispatch Requirements ..................... 1 Work /Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Forms Use Reporting Sheet * ..................................... 2
. ANYTIME A W']RKSHEET. DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPGRTING SHEET ATTACHED IN THE TABBED l ' WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, ~ CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE r
ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN ( FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE. s w A. N. , I FORM 372 22 3642 _ . . ~. ; . + - . .m. w,
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PUBLIC SERVICE COMPANY OF COL.ORADO f'S FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 7 General This procedure provides guidance for formation and direction of emergency teams during a radiological emergency at Fort St. Vrain. The formation of radiological monitoring teams is not discussed in this procedure, as it is discussed in detail in RERP-FIELD and RERP-SURVEY. The purpose of this procedure is to provide guidance in forming search and rescue / corrective action teams and to assure that all adequate controls for team members' safety are followed. The dispatch of all field teams is subject to the determination of the Technical Support Center Director, or prior to emergency organization activation, the determination of the Shift Supervisor, that the team's dispatch is warranted. All emergency teams shall be composed of at least two individuals. 1.0 Criteria This procedure is valid for use during any radiological emergency event that is an ALERT or higher emergency classification, or at the discretion of the duty Shift Supervisor. This procedure is ng to be utilized during the recovery phase following a radiological emergency. The recovery phase is subject to normal station and corporate procedures. .~ 2.0 Procedure 2.1 Search and Rescue Teams Search and Rescue Teams may be dispatched from the Personnel Control Center (PCC) following activation of the FSV emergency organization. Prior to the activation of the FSV emergency organization, search and rescue teams shall te comprised of fire brigade members and/or health physics personnel. For incidents where radiation levels are unknown and/or suspected to be greater than routine radiation levels, the search and rescue team shall be composed of at least one health physics technician with survey instrument. i 2.1.1 Exposure Control Emergency exposure guidelines for search and rescue of station personnel during a radiological emergency are described in detail in RERP-EXP, Emergency Exposure Guidelines. RERP-EXP requires l that a need to exceed established radiation i exposure guidelines be established (i.e., life saving actions or accident mitigation actions) and that dose projections and stay times be established prior to exceeding the occupational exposure guidelines in existence at FSV. It is FORM 372 3643
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PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 7 l l mandatory that prior to the dispatch of a search and rescue team, all available area and airborne radiological information be considered, even for the situation where exposure levels are expected to be within occupational limits. Datasheet 1, Pre-dispatch Requirements, is provided herein to assist in determinations of the protective equipment, dosimetric equipment, and stay-time requirements for the Search and Rescue Team prior to its dispatch. This form should be completed for cases where radiological hazards or greater than occupational personnel exposures are anticipated. Datasheet I may also be utilized as a guide in performing the pre-dispatch job briefing described below in section 2.1.4. A Health Physics representative shall be consulted, as appropriate, to assist in the completion of Datasheet 1. 2.1.2 Field Communications Communications for the search and rescue team shall be channeled to the attention of the duty Shift Supervisor, who is responsible for the initial personnel accountability. Communications . - equipment may be comprised of Gai-tronics, plant radio, or telephone, as deemed appropriate by the Shift Supervisor at the time of team dispatch. 2.1.3 Team Accountability The team accountability status is maintained by the Shift Supervisor, or for the case of dispatch from the Personnel Control Center, by the Personnel Accountability and Exposure Controller. 2.1.4 Team Briefing A pre-dispatch briefing shall be conducted prior to the dispatch of the search and rescue team. As a minimum, the briefing shall consist of the following information: Description of the areas to be searched;
- Identities of the individual (s) to be searched for; Areas that the individual (s) was last known to be working in; u
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- Description of radiological, physical, or I chemical hazards which may be anticipated in l the search areas;
- Protective equipment, dosimetric equipment, and stay-time limitations;
- Designation of a team leader to assume responsibility for team accountability in the field, communications with the Shift Supervisor, and leading the search.
2.2 Corrective Actions Team Corrective Actions Teams shall be formed in the event that emergency repairs or corrective actions are necessary to mitigate the consequences of a radiological accident. These teams shall be dispatched from the Personnel Control Center at the direction of the TSC Director, and are under the control of the Emergency Maintenance individual at the TSC. A Corrective Actions Team may also be dispatched by the Shift Supervisor prior to the activation of the FSV emergency organization. 2.2.1 Exposure Control The emergency exposure limits for the Corrective Action Team (s) shall be dictated by the guidance given in RERP-EXP, Emergency Exposure Guidelines. Pre-dispatch calculations of stay-time, determinations of dosimetric requirements, and protective clothing / equipment shall be made by the senior Health Physics representative at the Technical Support Center utilizing Datasheet 1, provided herein. If team dispatch is required prior to the activation of the FSV emergency organization, and available radiological information leads the Shift Supervisor to the conclusion that occupational radiation exposure limits could be exceeded, the duty Shift Supervisor shall complete Datasheet I with the assistance of the most senior Health Physics representative available for consultation. 2.2.2 Communications Communications with the Corrective Actions Team (s) shall be made utilizing Gai-Tronics, plant radio, or telephone, as deemed appropriate by the PCC Director or Emergency Maintenance individual at the TSC. The team leader shall be responsible for i maintaining adequate communications with the l Emergency Maintenance individual at the TSC (prior l l l b l FORM 372 22 3643 l
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, , PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLE AR GENERATING STATION Page 5 of 7 to FSV emergency organization activation, communication shall be with the duty Shift Supervisor or his designee).
2.2.3 Pre-dispatch Briefing It is the responsibility of the PCC Director to assure that a pre-dispatch briefing is given to the Corrective Actions Team prior to its dispatch. If the team is dispatched prior to emergency organization activation, and radiological, chemical, or physical hazards exist, a pre-dispatch briefing shall be given to the Corrective Actions Team by the duty Shift Supervisor. The pre-dispatch briefing shall cover the following topics:
- Description of the work that must be accomplished, special precautions associated with performance of the task, and any special equipment required to perform the jot, Description of radiological, phv ical, or chemical hazards which may be anticipated in
... ._ the work or access areas; . -
Protective equipment, dosimetric equipment, and stay-time limitations;
- Designation of a team leader to assume responsibility for team accountability in the work area, communications, and leading the search.
2.2.4 Team Accountability The personnel accountability of the Corrective
. Actions Team (s) shall be the ultimate responsibility of the PCC Director when the team has been dispatched from the Personnel Control Center, and the Shift Supervisor when the team has been dispatched from within the plant prior to activation of the FSV emergency organization.
3.0 Responsibilities 3.1 Technical Support Center Director The TSC Director has ultimate responsibility over site
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activities after the activation of the FSV emergency i organization, and shall have the ultimate authority to l determine when emergency teams of any nature shall be l l 1 FORM 372- 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO 3 FORT ST. VR AIN NUCLEAR GENERATING STATION page 5 of 7 to FSV emergency organization activation, communication shall be with the duty Shift Supervisor or his designee). 2.2.3 Pre-dispatch Briefing It is the responsibility of the PCC Director to assure that a pre-dispatch briefing is given to the Corrective Actions Team prior to its dispatch. If the team is dispatched prior to emergency organization activation, and radiological, chemical, or physical hazards exist, a pre-dispatch briefing shall be given to the Corrective Actions Team by the duty Shift Supervisor. The pre-dispatch briefing shall cover the following topics:
- Description of the work that must be accompluhed, special precautions associated with performance of the task, and any special equipment required to perform the job;
- Description of radiological, physical, or chemical hazards which may be anticipated in
- the work or access areas; Protective equipment, dosimetric equipment, and stay-time limitations;
- Designation of a team leader to assume responsibility for team accountability in the work area, communications, and leading the search.
2.2.4 Team Accountability The pe.rsonnel accountability of the Corrective Actions Team (s) shall be the ultimate responsibility of the PCC Director when the team has been dispatched from the Personnel Control Center, and the Shift Supervisor when the team has been dispatched from within the plant prior to activation of the FSV emergency organization. 3.0 Responsibilities 3.1 Technical Support Center Director The TSC Director has ultimate responsibility over site activities after the activation of the FSV emergency organization, and shall have the ultimate authority to determine when emergency teams of any nature shall be 1 FORM 372- 22 3643
. . PUBLIC SERVICE COMPANY OF COLORADO 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 7 to FSV emergency organization activation, communication shall be with the duty Shift Supervisor or his designee).
2.2.3 Pre-dispatch Briefing It is the responsibility of the PCC Director to assure that a pre-dispatch briefing is given to the Corrective Actions Team prior to its dispatch. If the team is dispatched prior to emergency organization activation, and radiological, chemical, or physical hazards exist, a pre-dispatch briefing shall be given to the Corrective Actions Team by the duty Shift Supervisor. The pre-dispatch briefing shall cover the following topics:
- Description of the work that must be accomplished, special precautions associated with performance of the task, and any special equipment required to perform the job;
- Description of radiological, physical, or chemical hazards which may be anticipated in the work or access areas; -r
- Protective equipment, dosimetric equipment, and stay-time limitations;
- Designation of a team leader to assume responsibility for team accountability in the work area, communications, and leading the
?, search.
2.2.4 Team Accountability The personnel accountability of the Corrective Actions Team (s) shall be the ultimate responsibility of the PCC Director when the team has been dispatched from the Personnel Control Center, and the Shift Supervisor when the team has been dispatched from within the plant prior to activation of the FSV emergency organization. 3.0 Responsibilities 3.1 Technical Support Center Director The TSC Director has ultimate responsibility over site ~ activities after the activation of the FSV emergency organization, and shall have the ultimate authority to determine when emergency teams of any nature shall be b tu 372 22 3s43
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, , PUBLIC SERVICE COMPANY OF COLORADO, 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 7 dispatched, and when the 10CFR20 radiation exposure limits may be exceeded (see RERP-EXP).
3.2 Emergency Coordinator (duty Shift Supervisor) The duty Shift Supervisor, in the role of Emergency Coordinator, has the responsibility and authority to determine when emergency teams shall be dispatched, and when the 10CFR20 radiation exposure limits may be exceeded (see RERP-EXP). Prior to activation of the FSV emergency organization, the Emergency Coordinator shall be responsible for assessing, with Health Physics assistance, the existing radiological conditions and for determining if stay-time limits are necessary for emergency teams. 3.3 Senior Health Physics Representative (TSC) The senior Health Physics representative at the TSC is responsible for evaluating the existing exposure rate / airborne concentration data prior to team deployment and for the determination of maximum stay-times. Prior to the activation of the FSV emergency organization, the most senior Health Physics representative onsite shall be available tc assist the Shift Supervisor in assessing the existing rac!ological conditions, and the need for protective equipment, dosimetric requirements, and stay-time limitations. 3.4 Personnel Control Center Director After the activation of the FSV emergency organization, emergency teams shall be assembled by the Personnel Control Center Director at the direction of the TSC Director. The PCC Director shall assume responsibility for personnel accountability of emergency teams after dispatch of the teams.
, 3.5 Team Leader The Team Leader of an emergency team is responsible to maintain communications during the time that the team is dispatched into the field, and is responsible to assure the maintenance of personnel accountabilty for team members while the team is dispatched.
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. . PUBLIC SERVICE COMPANY OF COLORADO Issue 3 FORT ST. VRAIN NUCLEAR GENERATING STATION page 7 of 7 4.0 References 4.1 10CFR20, Code of Federal Regulations 4.2 Health Physics Manual 5.0 Referenced Procedures 5.1 RERP-EXP, Emergency Exposure Guidelines 5.2 RERP-PCC, Personnel Control Center Procedure 5.3 RERP-SURVEY, Inplant/Onsite Radiological Monitoring 5.4 RERP-TSC, Technical Support Center Procedure 5.5 APM G-5, Personnel Emergency w
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FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 3 DATASHEET 1 Pre-dispatch Requirements
- 1) Area (s) to be entered
- 2) Known parameters:
a) General Radiation Level (mrem /hr) Detector RIS-b) Airborne Activity Level __(pci/hr) Detector ,. c) Surface Contamination Levels
- DPM/100cm2
- 3) Projected Time to complete task (br)
- 4) Projected Exposure 2)a) x 3) x 1.2E = (mrem)
- 5) Maximum Stay Time Based upon 10CFR20 limits (3 rem / quarter whole body with completed NRC Form 4, 3 E-09pci/cc unidentified airborne contamination) or, with the T3C Director's Concurrence (NOTE:
Prior to activation of emergency organization, the Shift Supervisor may authorize exposures in excess of 10CFR20 limits), the guidelines of RERP-EXP, Emergency Exposure Guidelines (hr) This parameter may be unknown prior to team deployment. l 2 F OR M 3M 22 - >H3
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.' . PUBLIC SERVICE COMPANY OF COLORADO Datasheet 1 l FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 l Page 2 of 3
- 6) Team Members:
- 7) Briefing of Team By:
- 8) Dosimetry requirements:
Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range TLD Finger Ring
- 9) Protective Equipment requirements (Circle required equipment):
Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator Scott Air Pack l Thyroid Blocking Agent (see RERP-THYRDID) b PomM 2n. 22 3sc
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FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 3 i Page 3 of 3 I l No Respiratory Protection Required
- 10) Comments:
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PUBLIC SERVICE COMPANY OF COLORADO g,5 C FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 2 of 3 i FORMS USE REPORTING SHEET l Nuclear Docuuents Specialist: This sheet is being transmitted to report use of forms from a controlled copy of the Emergency Plan Implementing Procedures, BOOK NO. , located at . The following forms have been utilized from this copy: Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. D.. FORM 372 - Mt - 3643 o---e , +y -- m - . - - - -
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PUBLIC SERVICE COMPANY OF COLORADO RE g,3 ['S FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 3 of 3 FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By:_ Date: l Nuclear Documents Specialist
- Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the 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.
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is PUBLIC SERVICE COMPANY OF COLORADO hRP , FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 3 l Page 1 of 3 I DATASHEET 1 Pre-dispatch Requirements ,l l
- 1) Area (s) to be entered -!
- 2) Known parameters:
a) General Radiation Level (mrem /hr) Detector RIS-b) Airborne Activity Level (vci/hr) Detector - c) Surface Contamination Levels
- DPM/100cm"
- 3) ~~ Projected Time to complete task (br)
- 4) Projected Exposure 2)a) x 3) x 1.25 = (arem)
- 5) Maximum Stay Time
- Based upon 10CFR20 limits (3 rem / quarter whole body with completed NRC Form 4, 3 E-09pci/cc unidentified airborne .
contamination) or, with the TSC Director's Concurrence (NOTE: Prior to activation of emergency organization, the' Shift Supervisor may authorize exposures in excess of 10CFR20 limits), the guidelines of RERP-EXP, Emergency Exposure Guidelines - (hr)
- This parameter may be unknown prior to team deployment.
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RERP-TEAMS PUBLIC SERVICE COMPANY OF COLORADO Datasheet 1 l FORT ST. VRAIN NUCLE AR GENERATING STATION lssue 3 Page 2 of 3 I ( 6) Team Members:
- 7) Briefing of Team By:
- 8) Dosimetry requirements:
Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge _ . _ _ _ . .
- Pocket Dosimeter'-t.orRange- - - - - - - - - - - - - - - - - - - -
TLD Finger Ring l
- 9) Protective Equipment requirements (Circle required equipment): ,
Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required Full-Face Respirator . Scott Air Pack . Thyroid Blocking Agent (see RERP-THYROID) A -- - . . . . . . . - .
' RERP-TEAMS PUBLIC SERVICE COMPANY OF COLORADO Datasheet 1 s
FORT ST. VRAIN WUCLEAR GENERATING STATION Zssue 3
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- 10) Comments:
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- Page 1 of 3 DATASHEET 1 Pre-dispatch Requirements ,
- 1) Area (s) to be entered I
- 2) Known parameters:
a) General Radiation Level (mrem /hr) j Detector RIS-b) Airborne Activity Level (uci/hr) Detector - , c) Surface Contamination Levels
- DPM/100ca"
- 3) Projected Time to complete task (hr)
- 4) Projected Exposure 4
2)a) x 3) x 1.25 = (mrem)
! 5) Maximum Stay Time
- Based upon 10CFR20 limits (3 res/ quarter whole body with i completed NRC Form 4, 3 E-09pci/cc unidentified airborne -
contamination) or, with the TSC Director's Concurrence (NOTE: Prior to activation of emergency organization, the Shift Supervisor may authorize exposures in excess of 10CFR20 s limits), the guidelines of RERP-EXP, Emergency Exposure Guidelines (hr) i This parameter may be unknown prior to team deployment. l
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- 6) Team Members:
1
- 7) Briefing of Team By:
- 8) Dosimetry requirements:
Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range TLD Finger Ring
- 9) Protective Equipment requirements (Circle required equipment): ,
Full Anti-C's Shoe Covers and Gloves No Protective Clothing Required i i Full-Face Respirator Scott Air Pack l Thyroid Blocking Agent (see RERP-THYROID) t- _. . _ __. FORM 372 22- 3M3
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- 10) Comments:
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f, . gc PUBLIC SERVICE COMPANY OF COLORADO . {MS FORT ST. VRAIN NUCLEAR GENERATING STATION I$$ue 3 Page 2 of 3 FORMS USE REPORTING SHEET l Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a controlled copy of the Emergency Plan Implementing Procedures, BOOK NO. , located at . The following forms have been utilized from this copy: Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book.
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PORM 372 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO WS/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 3 Page 3 of 3 i FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: l Nuclear Documents Specialist
- Date Received Date Replaced I
Nuclear Documents Specialist will transmit this form to the i l* 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. i I l i i i I . I s.
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PORM 372 22 3M3 1 _ _ _ . - . . . , _ . _ . . .m . . , , . _ , _ _ _ _ , , _ _ . . _ _ _ _ _ . _ _ . . _ . . . . . . . . , . _ . _ . . . _ .__,____..,,_,.I
r-RERP-SUPORG PUBLIC SERVICE COMPANY OF COLORADO Issue 2 FORT ST. VRAIN NUCLEAR GENERAT:NG STATION Page 1 of 3 FORT ST. VRAlk' TITLE: USE AND COORDINATION OF NON-PSC SUPPORT ORGANIZATIONS NON - CONTROLLED COPY VER!FYISSUE STATUS WITH DOCUMENT CEATER ISSUANCE FR'OR 10 usE AUTHORIZED 7'/IMM FORM 372c35c BY C,.s w_ L . . / , PORC / EFFECTIVE REVIEW PORC 5 8 0 AUG 2 - 1984 04TE 8-L.Sy TABLE OF CONTENTS Section Oescription Page 1.0 Criteria for Imo1ementation.................................. 1 2.0 Procedure.................................................... 1 3.0 Resoonsibilities ............................................ 2 4.0 References .................................................. 2 5.0 Referenced or Suocorting Procedures.......................... 2 Figure 1 Support Organizations' Services and Capabilities Matrix.................................... 1 4 i PORM 372 22 3542
b PUBLIC SERVICE COMPANY OF COLORADO S[0RG { FORT ST VRAIN NUCLEAR GENERATING STATION page 2 of 3 1.0 Criteria for Imolementation Tnis procedure governs tne use of non-PSC support organizations and consultants during a radiological emergency, and should be implemented if the need for outside assistance is identified. 2.0 Procedure 2.1 Any emergency center individual may initiate a request for offsite/ support assistance. All requests must be channeled through the appropriate emergency center director. 2.2 The PCC director shall transmit any requests for support assistance to the TSC director. 2.3 The TSC director shall consider the request for assistance. If he determines that the request is valid, he shall transmit appropriate information to the Corporate Emergency Director (CED) at the Forward Command Post. 2.4 The CED shall, upon concurrence, relay the request for
-assistance to the Manager of Resources or the Manager of Technical Support at the Executive Command Post.
2.5 The Manager of Resources or the Manager of Technical Support shall assess the need for assistance. If it is determined that support cannot be supplied from within PSC, the appropriate ECP manager shall initiate contact with non-PSC support organizations as required. Figure 1, Support Organizations' Services and Capabilities Matrix, should be used as a guide when determining the organization (s) to be contacted. Addresses and phone numbers of the organizations, as well as more detailed documentation of services available, are found in RERP-PLANT, Section 10A. 4 S I FORM 372 22 200
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E PUBLIC SERVICE COMPANY OF C3LORADO Sf0RG
. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 3 3.0 Resconsibilities 3.1 Corporate Emergency Director (CED)
The CED is ultimately responsible for the decision to utilize outside assistance and for the direction and coordination of such use. 3.2 Manager of Resources Provides requested technical and craft manpower; purchasing, financial, legal, general office, and logistics support; and assistance for engineering / design and construction reviews from available personnel or a consultants as appropriate. 3.3 Manager of Technical Support Provides engineering support, technical experts, and consultants as requested. 3.4 TSC Director Coordinates requests for outside assistance with the CED. 3.5 PCC Director Directs any requests for outside assistance to the TSC D1 rector. 4.0 References 4.1 FSV Radiological Emergency Response Plan, Section 10A, Agreement Letters and Summary of Referenced Interfacing Emergency Plans 5.0 Referenced or Supporting Procedures 5.1 RERP-ORG, FSV Emergency Organization and Responsib111 ties 5.2 RERP-FCP, Forward Command Post Procedure 5.3 RERP-ECP, Executive Command Post Procedure 5.4 RERP-PCC, Personnel Control Center Procedure 5.5 RERP-TSC, Technical Support Center Procedure 6 i PORM 372 22 M43 1 l
r .. Y E PUBLIC SERVICE COMPANY OF COLORADO 7 f0RG
, FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 1 SUPPORT ORGANIZATIONS' SERVICES AND CAPABILITIES MATRIX l Organization" l 1l2[3l4l5l6l7l8l 9l 10 l 11 l engineering iXl XlXl Xl 1 l l l lX l l operations lXlX[Xl l l l l l l l l maintenance lXlXl l l l l l l l l l construction lXl l l l l l l l lX l l start up lXl l l l l l l l l l l system design / l l l i l l l l l l l l modification l lXlXl l l l l l l l l component design / l l l l l l l l l l l [
modification l l lXl l l l l l l l [ instrumentation & l l l l l l l l l l l l control - l l lXl l l l l l l l l l procurement lXl l l l l l l l lX l Xl planning & scheduling lXl l l l l l l l [ [ [ procedural modification l l lXl l l l l l l l l QA lXlXl l l l l l l l l l l inspections / auditing l l lXl l lXl l l l l Xl fire protection l l lXl l l l l l l l l l radiation protection lXl l X ]~X l X l l l lX l- l l temporary shielding lXl l l l l l l l l l l environmental l l l l l l l l l l l l monitoring l l lXlXlXl l lXl l l l l sampling l l l l lXl l l l l l l dosimetry processing l l l l l l l lXl l l [ dose assessment / l l l l l l l l l l l l l calculations lXl l lXl lXl l l l l l metallurgical consulting l l l l l l lXl l l l l Y
*0rcani:ations:
- 1. Stone & Webster Engineering Corporation
- 2. Nuclear Power Consultants
- 3. Proto-power Management Corporation
- 4. NUS
- 5. Controls for Environmental Pollution, Inc.
l 6. Dr. H. G. Olson l 7. Donald T. Klodt, PhD, Consulting Metallurgist l 8. R. S. Landauer, Jr. & Co. l 9. Western Radiation Consultants, Inc. l 10. EBASCO Services Incorporated l 11. INPO t \ PORM 372 22 3643 l
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_ RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATION ISSUE EFFECTIVE I NO. SUM ECT NUMBER DATE RERP CR-ALERT DELETED 04-25-84 l RERP CR Control Room Procedure 2 08-06.-84 lNdRP-DOSE Offsite Dose Calculations Methodology 6' 08-06-84
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RERP-CR PUBLIC SERVICE COMPANY OF COLORADO CORT ST. VRAIN NUCLEAR GENERATING STATION age 1 o,. 17 3 FORTS ~I l'RAly t; , TITLE: CONTROL ROOM PROCEDURE
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STAyuS MTH UMEyyCENTER l CRToygg fcy ISSUANCE & AUTHORIZED M* 1 y BY }O*n 'Q
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PORC f EFFECTIVE REVIEW PDRc 5 8 0 AUG 2 - 1984 DATE h- b. h TABLE OF CONTENTS Section Description Pace 1.0 Cri teri a for Imo1 ementati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Procedure.................................................... 3 3.0 R e s p o n s i b i l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 4.0 References .................................................. 15 5.0 Referenced or Supoortino Procedures.......................... 16 Figure 1 Response Center Manning Requirements .................. 1 Figure 2 Visitor's Center Evacuation Routes .................... 1 Table 1 Non-Emergency Events: Four-Hour Reports .............. 1 Table 2 Non-Emergency Events: One-Hour Reports................ 1 Table 3 NOTIFICATION OF UNUSUAL EVENT.......................... 1 Table 4 ALERT.................................................. 1 Table 5 SITE AREA EMERGENCY.................................... 1 Table 6 GENERAL EMERGENCY...................................... 1 Table 7 Initiating Event Cross-Reference ...................... 1 Tabic 8 Emergency Condition Cross-Reference.................... 1 l Table 9 Protective Action Guides .............................. 1
. Attachment 1 Phone Numbers for Notification.................. 1 Attachment 2 Non-Emergency Event Notification................ 1 ~
Attachment 3 Noti fication of Unusual Event . . . . . . . . . . . . . . . . . . 1 FORM 372 22 3642
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. PUBLIC SERVICE COMPANY OF COLORADO 2
. ,y : FORT ST. VR AIN NUCLEAR GENERATING STATION page 2 of 17
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0 Attachment 4 Notification of Emergency Event ................. I Datasheet 1 Preliminary Assessment of Plant Conditions...... 1 Checklist 1 Emergency Coordinator / Control Room Di rector Checkli st. . . . . . . . . . . . ................. 1 Checklist 2 Emergency Coordinator /CR Director Checklist: Part 2 - ALERT or Higher Event.................. 1 Work /Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e Re p o rt i n g S h e e t* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE. FORM 372- 22 3643
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-C PUBLIC SERVICE COMPANY OF COLORADO ,2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 3 of 17 o
I 1.0 Criteria for Imple entation l i This procedure is to be utilized by Control Room personnel in ' the event of an occurrence which is classified in Tables 1 through 6 of this procedure to be a Non-Emergency Event or an FSV Radiological Emergency Response Plan (RERP) event. Guidance to assist in the accident classification process can be found in Emergency Procedure EP CLASS. Initial accident classification is the responsibility of the Shift Supervisor, in the role of Emergency Coordinator. 2.0 Procedure 2.1 General Responses 2.1.1 Under any emergency condition, the Shift Supervisor and onsite personnel will immediately initiate those actions required to limit the consequences of the event and return the plant to a safe and stable condition. 2.1.2 Implementation of the FSV Radiological Emergency Response Plan (RERP) is required whenever any of the Initiating Events of Tables 3 through 6 of this procedure occurs. Additional guidance on accident classification is contained in Emergency Procedure EP Class, as well as in each individual Emergency Procedure. Initial accident classification is the responsibility of the Shift Supervisor. 2.1.3 Notification of offsite authorities will be initiated within 15 minutes after the declaration of an emergency. 2.1.4 Checklists I and 2 are for use by the Emergency Coordinator and/or the CR Director. These checklists present a brief summary of actions, and are to be used for guidance purposes to assist in verifying execution of required responses. 2.1.5 If the RERP is to be implemented for on ALERT or higher classification, PSC personnel required to man the response centers (Figure 1) are notified by telephone, if the event occurs during non-working hours. It is the responsiblity of the individual response center Alternate Directors (or the first individual contacted by the Director) to ensure : that these notifications are made (see RERP-HOME). I Refer to RERP-PHONE LISTS for instructions and personnel names and telephone numbers. 1 FO9M 372 22 3C43 l
a PUBLIC SERVICE COMPANY OF COLORADO RERP-CR Issue 2
- FORT ST. VR AIN NUCLEAR GENERATING STATION Page 4 of 17 2.2 On-Shift Control Room Personnel - Procedure 1 2.2.1 Implement Emergency Procedure actions required to limit the consequences of the event and return the l plant to a safe and stable condition. ]
2.2.2 If a radiological release is involved, make a preliminary assessment of the release utilizing implementing procedure RERP-DOSE to perform offsite dose calculations. Worksheets, Datasheets, and Checklists for dose calculations are contained in RERP-DOSE, as summarized below: Worksheet 1 Monitored Release - Manual; Worksheet 2 Monitored Release - TI-59; Worksheet 3 Unmonitored Release - Manual; Worksheet 4 Unmonitored Release - TI-59; Datasheet 1 Monitored Datalogger; Datasheet 2 Unmonitored Datalogger; and Checklist 1 Monitored Datalogger. It is the Shift Supervisor's responsbility to ensure that the offsite consequence assessments are performed as required. Radiological Assessment will become the responsibility of the Technical Support Center after full facility activation. 2.2.3 As soon as possible, inform the Emergency Coordinator of the results of the preliminary radiological assessment. 2.2.4 Maintain the plant in a safe and stable condition. 2.2.5 Implement corrective actions as directed by the Emergency Coordinator or CR Director. 2.3 Technical Advisor - Procedure 2.3.1 Repo t to the Control Room immediately when the Plant Emergency Alarm sounds, or when directed by the Shift Supervisor (Emergency Coordinator). 2.3.2 Datasheet 1, " Preliminary Assessment of Plant Conditions," is provided to assist in making initial assessment of plant status. 2.3.3 Provide technical support to Control Room staff, as required. PORM 372 22 - 3643 m . - -
. PUBLIC SERVICE COMPANY OF COLORADO ]PCR u
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 17 0 2.4 Shift Supervisor (Emergency Coordinator) - Initial Responses to all Events 2.4.1 Assume the position of the Emergency Coordinator until relieved by the Control Room Director (Primary: Superintendant of Operations; l Alternate: Shift Supervisor, Training), or the TSC Director. 2.4.2 As Emergency Coordinator, direct onsite emergency responses and initiate any required corrective actions to mitigate the consequences of the event. 2.4.3 Checklist 1 is provided as guidance to verify execution of required responses. Checklist 2, a continuation of Checklist 1, is provided for use in the event of an ALERT or higher incident. 2.4.4 If a radiological release or potential radiological release is involved, preliminary radiological assessment may be delegated to a Reactor Operator. (This calculation should be performed at an average rate of approximately once every 30 minutes until relieved of this responsibility by the TSC or until , the offsite release is terminated.) 2.4.5 For additional assistance in assessing the magnitude of the release, attempt to contact the Radiation Protection Manager (see Attachment 1, Phone Numbers for Notification.) 2.4.6 Initiate radiological protective actions for station personnel. 2.4.7 Classify the event as a Non-Emergency Event, Unusual Event, or an ALERT or more severe emergency event, utilizing event status and preliminary radiological assessment, if applicable. Additional guidance for classification is provided in Emergency Procedure EP CLASS. Table 7, Initiating Event Cross-Reference, and Table 8, Emergency Condition Cross-Reference, are also provided for use in classifying the event category and summarizing emergency response actions. FORM 372 22 3643
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C PUBLIC SERVICE COMPANY OF COLORADO 2 k , FORT ST. VR AIN NUCLEAR GENER ATING STATION Page 6 of 17
- n 2.4.7.1 Non-Emergency Events l This group of operating events comprises l a series of occurrences for which, in the wake of Three Mile Island 2, there was a i need to receive notification and data i early-on in the situation's course of i events. The reporting requirements for !
this group of events have been revised to ' include only reports of those events which are related to the operations of the NRC and which affect the safety of the operating power plant. The category has been changed from "Significant Events" to "Non-Emergency Events" and split into two categories -- those events which should be reported as soon as possible but in all cases within one hour, and those which should be reported as soon as possible but in all cases within four hours. Table 1 summarizes those events and representative occurrences which would require a four-hour report and Table 2 summarizes those that would require a one-hour report. Refer to section 2.5, Non-Emergency Event Procedure, for actions required for this event classification. It should be noted that if an occurrence listed herein also falls under a higher level category, the actions required for the more severe category shall take precedence. PORM 372 22 3643
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. PUBLIC SERVICE COMPANY OF COLORADO u;2 FORT ST. VR A,1N NUCLEAR GENERATING STATl10N Page 7 of 17 2.4.7.2 NOTIFICATION OF UNUSUAL EVENT This classification is the least severe Emergency Class and applies to situations where unusual events are in process (or have occurred) which indicate a potential fcr degradation of the level of safety of the plant.
The plant is placed in a position of readiness for a possible cessation of routine activities and/or an augmentation of on-shift resources, however, the FSV Emergency Organization is not activated for the bNUSUAL EVENT. Notifications to State and Federal officials should be initiated within 15 minutes after declaration of the UNUSUAL EVENT. Table 3 outlines initiating events and Emergency Action Levels for this class of incident. Required responses for this classification are presented in section 2.6, NOTIFICATION OF UNUSUAL EVENT. FORM 372 22 36d0
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E R PUBLIC SERVICE COMPANY OF COLORADO ue 2 FORT ST. VR AIN NUCLE AR GENERATING ET ATl'ON page 6 of 17 s 2.4.7.3 ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY Declaration of an ALERT or higher Emergency Class will require implementation of the RERP and activation of emergency response centers. Notification of State and Federal authorities should be initiated within 15 minutes after declaration of the emergency. If the event is an escalation of a previous emergency classification, followup notification to the NRC should be made immediately if an open line has not already been established. Actions to take for these events are described in section 2.7, the procedure for ALERT or higher events. If the event l is an escalation from a lower category, proceed directly to step 2.7.3. Tables 4, 5, and 6 outline initiating events and Emergency Action Levels for the three classes of incidents:
- Table 4 - ALERT;
- Table 5 - SITE AREA EMERGENCY; and, Table 6 - GENERAL EMERGENCY.
FORM 372 22 3543
RERP-CR PUTLIC SERVICE COMPANY OF COLORADO Issue 2 FORT ST VRAIN NUCLEAR GENERATING STATION page 9 of 17 2.5 Non-Emergency Event Procedure 2.5.1 In the event of an occurrence believed to be defined by Table 1 or 2, the Shift Supervisor or his authorized delegate may contact one member of l plant management listed in order of preference in l Atta:hment 1, although the responsibility of I initial event classification is that of the Shift I Supervisor, and may not be delegated. 2.5.2 The Shift Supervisor shall inform the management contact of the event classification, or may request management advice regarding the classification. 2.5.3 The Shift Supervisor and the management contact shall jointly fill out the "Non-Emergency Event Notification" Form (Attachment 2) to ensure that both have the same information. 2.5.4 The management contact shall then contact other management personnel listed, as appropriate. 2.5.5 The Shift Supervisor shall noti fy the NRC Operations center of the event as soon as possiole, and in all cases, within one hour or four hours as applicable to the Non-Emergency Event category. Notification should be made via the NRC " hot line," if possible. Alternative methods of notification are given in Attachment 1, should the " hot line" be unavailable. 2.5.6 Maintain an open, continuous communication channel with the NRC Operations Center, upon request by the NRC. 2.5.7 If an open line is not established, a followup notification should be made to report any of the following, if applicable: any further degradation of plant conditions; a results of evaluations or assessments of plant conditions;
- effectiveness of response or protective measures taken; or, information related to plant behavior that is not understood.
( . PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-CR Issue 2
;- FORT ST. VRAIN NUCLEAR GENERATING STATION Page 10 of 17 o
2.5.5 No further action is required unless there is an escalation to an RERP emergency classification as shown in Tables 3-6 of this procedure. In case of an escalation, refer to the appropriate section:
- Section 2.6 - UNUSUAL EVENT;
- Section 2.7 - ALERT or higher event.
FORM 372 22 3642
PUBLIC SERVICE COMPANY OF COLORADO u$2
, FORT ST. VRAIN NUCLEAR GENERATING STATION page 11 of 17 2.6 NOTIFICATION OF UNUSUAL EVENT 2.6.1 In the event of an occurrence believed to be defined by Table 3, the Shift Supervisor shall assume the position of Emergency Coordinator until relieved by the Superintendent of Operations l (alternate: Shift Supervisor, Training).
2.6.2 Notify the on-duty Technical Advisor. (Refer to Attachment 1, Phone Numbers for Notification.) 2.6.3 Contact cae member of plant management listed in order of preference in Attachment 1, Phone Numbers for Notification. l NOTE: In the event that no management person l listed can be contacted, it is the Shift l Supervisor's responsibility to classify l the event and make notifications as I required. 2.6.4 Inform the management contact of the classification of the event,.or if desired, request management advice regarding the classification. 2.6.5 Jointly complete the " NOTIFICATION OF UNUSUAL EVENT" form with the management contact to ensure that the same information is recorded by both parties. The management contact will then contact other management personnel as required, and the Resident NRC Inspector. (SeeAttachment1.) 2.6.6 Notify the State of Colorado and the NRC Operations Center of the event by following the instructions on the notification form (Attachment 3). Notifications should be initiated within 15 minutes after declaration of the emergency category. Alternate backup methods of contacting the NRC are
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l given in Attachment 1, Phone Numbers for Notification. The on-duty Technical Advisor should be kept , abreast of the event status. 2.6.7 Maintain an open, continuous communication line with the NRC upon request. Report any degradation of plant conditions, results of evaluations, or response actions and results. ( t l FomM 372 22 3643 i
C PUBLIC SERVICE COMPANY OF COLORADO 2
, FORT ST. VRAIN NUCLEAR GENERATING STATION Page 12 of 17 2.6.8 No further action is required unless the event escalates to a higher RERP emergency classification as shown in Tables 4-6 of this procedure.
Continue to step 2.7.3 if an escalation occurs. FORM 372 22 83643
C PUBLIC SERVICE COMPANY OF COLORADO 2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 13 of 17 O 2.7 ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY 2.7.1 In the event of an occurrence believed to be defined as an ALERT or higher emergency by Tables 4-6 of this procedure, the Shift Supervisor shall assume the position of Energency Coordinator, until relieved by the Control Room Director (Primary: Superintendent of Operations; Alternate: Shift l Supervisor, Training), or the TSC Director. 2.7.2 Notify the on-duty Technical Advisor if not already done. (Refer to Attachment 1, Phone Numbers for Notification.) 2.7.3 Contact one member of plant management listed in order of preference in Attachment 1, Phone Numbers for Notification. l NOTE: In the event that no management person l can be contacted, it is the Shift l Supervisor's responsibility to classify l the event and make notifications as l required. 2.7.4 Inform the management contact of the classification of the event, or if desired, request management advice regarding the classification. 2.7.5 Checklist 2 is provided as guidance to verify completion of required responsibilities. l 2.7.6 Sound the Plant Emergency Alarm, if not already l done, and announce the nature of the emergency. All onsite personnel will report to their Personnel Accountability Stations (refer to Administrative Procedure G-5, Personnel Emergency Response) for initial accountability. Rapid evaluation of departmental accountability will be accomplished using plant rosters and computer printouts delivered by Security'to the accountability stations. 2.7.7 In cooperation with the first management contact, l complete the " Notification of Emergency Event" Form (Attachment 4). PORM 372 22 3643
C PUBLIC SERVICE COMPANY OF COLORADO 2 FORT ST. VR AIN NUCLEAR GENERATING STATION Page 14 of 17 l 2.7.8 Initiate notifications to the PSC Company Operator, Weld County Communications Center, and the NRC Operations Center within 15 minutes after declaration of the emergency (these numbers are on the auto-dialer telephone in both the Control Room and Shift Supervisor's office). Alternate methods of contacting the NRC are listed in Attachment 1, Phone Numbers for Notification, and are to be used in the event that the NRC " hot line" cannot be used. l Read the information on the " Notification of l Emergency Event" Form (Attachment 2) to the above contacts. The information should also be conveyed to the Technical Advisor. 2.7.9 The PSC Operator will notify Emergency Response Center Directors, who will in turn notify their Alternates. During an off-hour event, Alternates will contact the remainder of the personnel to report to each response center. 2.7.10 Inform Visitor's Center (VC) to instruct visitors at the VC to depart to the Fort Lupton Fire Station and, depending on the wind direction, specify the departure route (see Figure 2). Wind from North Route #3 Wind from South Route #1 Wind from East Route #1 Wind from West Route #2 2.7.11 Notify Security of the impending arrival of emergency personnel and provide adequate clearance l for Protected Area access, where required. (If l access is required to activate TSC, refer to RERP-l Phone Lists or RERP-HOME, Attachment 9, for TSC l Director's call list for personnel requiring l access.) 2.7.12 Establish communications with the TSC after [ facility activation using extension 292. (See Attachment 1, Phone Numbers for Notification, for alternate numbers if required.) l 2.7.13 Utilize the Fire Brigade or a team from the PCC to locate and/or rescue any unaccounted-for personnel as indicated by reports from Security (see RERP-TEAMS). FORM 372 22 3643 w.,..
r RERP-CR s PUBLIC SERVICE COMPANY OF COLORADO Issue 2
, 7 FORT ST. VRAIN NUCLEAR GENERATING STATION page 15 of 17 i
2.7.14 Upon arrival at the Control Room, the CR Director shall request a briefing regarding incident status and actions currently in progress. After the briefing, he may assume responsibility for Control Room actions and direct the control of plant operations. He shall notify the Shift Supervisor, duty Reactor Dperators, and the TSC of his assumption of the role of CR Director. 2.7.15 Request supplemental Dperations personnel from the TSC Director, as required, to control the emergency. (The TSC Director will relay the request to the PCC Director and thus maintain re-entry control). 2.7.16 Initiate corrective actions recommended by the TSC Director to minimize the consequences of the emergency. 2.7.17 Recovery The CR Director is responsible for recommending a termination or de-escalation of the emergency status, from a plant operational viewpoint, to the TSC Director. This recommendation shall be based upon the CR Director's determination that: Radiation levels are stable or decreasing with I time;
- Releases of radioac ve materials to the environment have cea: , or are controlled l within Technical Specification Limits; Fires, flooding, or similar hazards no longer pose a threat to plant environment or l personnel; and Measures have been successfully instituted to repair or compensate for malfunctioning plant equipment.
1 PORM 372 22 3643
C PUBLIC SERVICE COMPANY OF COLORADO 2
, FORT ST. VRAIN NUCLEAR GENERATING STATION page 16 of 17 0
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 l Organization (see Figure 1). The Emergency Coordinator is responsible for:
- Initial accident classification;
- Recommending protective actions;
- Initiating emergency actions to mitigate the accident;
- Notifying offsite authorities (NOTE: Notifications are required to be initiated within 15 minutes after declaration of an emergency);
- Diagnosing accident conditions;
- Estimating radiological exposures; and
- Establishing communications with the TSC should the FSV Emergency Organization be activated.
Responsibility for the decision for offsite notification and protective action recommendation may not be delegated. 3.2 Control Room Director The Control Room (CR) Director is responsible for control of plant operations, assessing plant operational aspects, and for implementing any recommended corrective acticns. In addition, the CR Director may request any additional operations personnel necessary through the TSC Director. 3.3 Technical Advisor The Technical Advisor is responsible to provide technical analysis and advice as requested, and to provide recommendations of corrective actions necessary to restore the plant to a safe and stable condition. PORM 372 22 3643
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, PUBLIC SERVICE COMPANY OF COLORADO 2
, , FORT ST. VRAIN NUCLEAR GENERATING STATION pagt 17 of 17 0
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 Sucoorting Procedures 5.1 RERP-TSC, Technical Support Center Procedure l 5.2 EP CLASS, Event and Emergency Classification Overview 5.3 RERP-DOSE, Offsite Dose Calculation Methodology 5.4 RERP-PAG, Protective Action Guideline Recommendations 5.5 RERP-PCC, Personnel Control Center Procedure 5.6 RERP-HOME, Home Packet for Off-Shift Notifications 5.7 Station Security Plan and Procedures 5.8 RERP-PHONE LISTS 5.9 RERP-VC, Visitor's Center Procedure 5.10 Administrative Procedure G-5, Personnel Emergency Response 5.11 RERP-TEAMS, Emergency Team Formation and Direction FORM 372 22 3442
PUBLIC SERVICE COMPANY OF COLORADO RERP-CR Figure 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 1 FIGURE 1 RESPONSE CENTER MANNING REQUIREMENTS g "E w , 3
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RERP-CR
. PUBLIC SERVICE COMPANY OF COLORADO Figure 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 1 FIGURE 2 VISITOR'S CENTER EVACUATION ROUTES I
Coletado Hww. 60 Johnstoun : Milliken b I u vs.itor'. rett st.
.3; ra a Center _
u O 1 O Calerade Hvv. 66 t , e ,1.t t..m./ . N e Calerede thrv. $2 Fort Lwton East g g fort Lupton I *. O 4th st. E J 9 [ [; Fort Lupten Huntelpal 8143
** (618 4th St.)
as ponM 272 22 3643
PUBLIC SERVICE COMPANY OF COLORADO $,-CR FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 2 Page 1 of 4 TABLE I NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Tyoical Indi:atien Initiating Event
- 1. Any event, found while 1. Determination as result of the reactor is shut- surveillance testing of Plant down, that, had it Protective Systems (PPS) that been found while the failure of PPS modules would reactor was in oper- have prevented a required ation, would have re- reactor scram from occurring.
suited in the plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that significantly compromises plant safety.
- 2. Any event or cordition 2. Reactor scrams, loop shutdowns, that results in and automatic starting and manual or automatic loading of diesel generators actuation of an only.
Engineered Safety Feature, including EXCEPTIONS: the Reactor Protection System. a) Manual scram initiated at 2% during a normal shutdown. b) Only one of three channels tripped manually or auto-matically, but no final protective action takes place, nor is required. c) Actuation of the afore-mentioned systems which result from, and are a part of, the planned sequence during surveil-lance testing or reactor operation. POMM 373 23 3643
PUBLIC SERVICE COMPANY OF COLORADO y,E[~,
, FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 , Page 2 of 4 TABLE 1 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Tyoical Indication Initiatino Event
- 3. Any event or condition 3.a) During refueling operations, that alone could have a .0 lap shutdown margin prevented the ful- is not maintained due to fillment of the safety incorrect rod removal function of structures sequence.
or systems that are needed to: b) Incorrect valve lineup which results in shut off a) shut down the reactor of secondary system decay and maintain it in heat removal sequence. a safe shutdown l condition; c) Liquid waste monitor setpoints l raised for liquid waste release l b) remove residual heat; completed. Reactor Building l sump Sumps taken out of pull-to-l c) control the release lock. Setpoints not reset, of radioactive material; or d) Loss of HEPA filtration, d) mitigate the con-sequences of an accident. PORM 272 22 M43
R CR
. PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 l Page 3 of 4 l TABLE 1 NON-EMERGENCY EVENTS: FO'JR-HOUR REPORT Event Tyoical Indication Initiatinc Event
- 4. a) Any airborne radio- 4. As determined by analysis active release that and evaluation.
ext:eds 2 times the appiicable concentra-tions of the limits specified in Appendix B, Table II of 10CFR20 in unrestricted areas when averaged over a time period of one hour, b) Any liquid effluent release that exceeds 2 times the limiting combined MPC (see Note 1 of Appendix B of 10CFR20) at the . point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour. NOTE: Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and . (b)(2) of 10CFR20.403.
- 5. Any event requiring 5. As occurring.
the transport of a radioactively contam-insted person to an offsite medical facility for treatment. PORM 372 22 364
RE CR PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 4 of 4 TABLE 1 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Tyoical Indication Initiatino Event
- 6. Any event or situation, 6. a) Onsite fatality for which related to the health a news release will be made.
and safety of the public or onsite personnel, or b) Inadvertent release of protection of the environ- radioactive material not ment, for which a news in excess of 10CFR20 limits release is planned or for an unrestricted area, notification to other but requiring report to government agencies has the State. been or will be made. c) Oil or chemical spill which could reach the South Platte River or St. Vrain Creek and which is therefore reportable to-the-EPA. PORM 372 22 3443 w
PUBLIC SERVICE COMPANY OF COLORADO Cj l , FORT ST. VRAIN NUCLE AR GENERATING STATION Issue 2 l Page 1 of 3 l 1 l l TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical Initiatino Event
- 1. a) The initiation of 1. a) As occurring.
any plant shutdown required by Technical Specifications. b) Any deviation from b) Any deviation from a Tech-Technical Specifica- nical Specification, when tions authorized the action is immediately pursuant to needed to protect the 10 CFR 50.54(x). public health and safety, and no action consistent with Technical Specifica-ions which can provide adequate or equivalent protection is immediately I apparent. (The action should l be approved, as a minimum, l by a senior licensed l operator.) POMM 372 22 3643
1 RE CR PUBLIC SERVICE COMPANY OF COLORADO ., F03T ST. VRAIN NUOLEAR GENERATING STATION !ssue 2 Page 2 of 3 TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Tyoical Initiatine Event
- 2. Any event or condition during operation that results in the condi-tion of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:
a) In an unanalyzed 2. a)Asdetermined, condition that significantly compromizes plant safety; b) In a condition b) 1. Reactor pressure in that is outside excess of design the design basis limits with failure of the plant; or to trip plant.
- 2. Winds experienced in excess of FSAR design levels.
c) In a condition c)Asdetermined. not covered by the plant's operating and emergency procedures.
- 3. Any natural phenomenon 3. a) Toxic gas release in imme-or other external diate vicinity of plant.
condition that poses an actual threat to the b) Extremely high winds or safety of the plant or severe storm proventing significantly hampers plant personnel from site personnel in the completing requisite performance of duties assignments. necessary for the safe operation of the plant. l P ORM 3 72 + 32 3443 i
RE PUBLIC SERVICE COMPANY OF COLCRADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 3 of 3 TABLE 2 NON-EMERGENCY EVENTS: ONE-HOUR rep 0RT Event Tyoical Initiating Event
- t. Any event-that results 4. a) Loss of significant in a tr.ajor loss of portion of Control Room emergency assessment , indication.
capability, offsite res,ionse capability, - b) Loss of all offsite or cornmunications communication systems, capability.
- 5. Any event that poses 5. a) Fire posing undue in actual threat to the personnel hazard.
Safety of the plant, or Tignificantly hampers b) Severe chlorine release site personnel in the ~ from chlorine cylinders, performence of dettes necessary for the tafe c) Accidental gaseous radio-operation. of the plant, logical release resulting including fires ,, in onsito concentrations gas releases, or, toxic in excess of 10 CFR 20 radioactive releases. Appendix B, Table I.
/
P om M Sit - 21. M43 U- _ _ .
R CR PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2
, Page 1 of 4 TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 1. Any unplanned radio- 1. Alarms on:
logical release to RT 7312 the Reactor Building CAM (s) or its ventilation RT 7324-1 system. RT 7324-2 RT 7325-1 RT 7325-2 RT 4801 RT 4802 RT 4803 RT 73437-1, 2
- 2. Any liquid waste re- 2. a) RT 6212 or 6213 alarm lease resulting in with inability to prevent offsite 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). b) SR 5.2.11 results.
- 4. Serious fire at the 4. a) Any of various alarms plant lasting more on Fire Control Alarm than 10 minutes Panel; which could lead to substantial b) Fire Pump 1A auto degradation of plant start; safety systems, or which could result c) Verbal reports.
in the release I of radiologia1 I or toxic materials. I PORM 372 22 3843
I R CR PUBLIC_ SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 4
~
s TABLE 3 _ NOTIFICATION OF UNUSUAL EVENT Event Indication
.5. Abnormal coolant temo- 5. Violations of eratures or core region LCO 4.1.7 or LCO 4.1.9 temperature rises for region outlet to the extent mismatch, or region requiring shutdown in AT, respectively, accordance with to the extent that Technical Speci- shutdown per Station fications. Technical Speci-fications is required (SOP 12-04).
- 6. Natural phenomenon that 6. a) Seismic Recorder may be experienced Operate; or threatened that represent risks beyond b)-d) As visually observed normal levels; by, or reported to, a) earthquake station personnel.
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 cf 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, FORM 372 22 - 3643
RE C
; PUBLIC SERVICE COMPANY OF COLORADO , 3 FORT ST VR AIN NUCLEAR GENERATlNG STATION Issue 2 Page 3 of 4 l
TABLE 3 NOTIFICATION OF UNUSUAL EVENT Even* Indication
- 7. c) Onsite or near site plant related accidents that could result in the release of toxic material or spills of flammable materials.
- 8. Any serious- radio- 8. As occurring.
logical exposure of plant personnel or the transportation to offsite facilities of contaminated personnel who may have been injured. (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 fue? shipments or plant radio-active waste shipments. 10 1.oss of Engineered 10. Shutdown required in
._ ' ety 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-LC0 4.5.1
- 2) Steam / Water Dump System - LCO 4.3.3 F OR M 372 300
PUBLIC SERVICE COMPANY OF COLORADO (CR FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 2
Page 4 of 4 TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indicatier
- 10. (Cont). 3) PCRV penetration flow restriction dev 6 : - LCO 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
- 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 l b) RT 73437-1, 2, RT 4802, ' l a_nd RT 7325-1; or c) RT 73437-2 and RT 4801; or- . d) RT 6212 a_nd RT 6213. NOTE: Use ELCO 8.1.1 Technical Specification Limits as basis. 1 i 1 I I l Foph 372 - 22 3643 l
.. . . . , . , . . - - - . . . . . . - - . . . . - - - - - l l
l
l CR
.. PUBLIC SERVICE COMPANY OF COLORADO f,E g FORT ST. VR AIN NUCLEAR GENER ATING STATION lssue 2 i Page 1 of 4 TABLE 4 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 a.nd RAT undervoltage/ loss of power alarm.
- 3. Primary coolant pressure 3. PAL 9335 decay (to a value greater PAL 9347 than 100 psi less than PAL 9359 normal pressure, an.d area monitor accompanied by area and or stack monitor alarm stack radiation monitor alarms).
- 4. High radiation levels or 4. RT 7312 high airborne contamination CAM (s) alarm which indicates severe RT 6212 degradation in control of RT 6213 radioactive materials. RT 93252-12 (Increase by factor Area Monitors 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. l i PORM 372 22 3643 __ s. __
PUBLIC SERVICE COMPANY OF COLORADO RERP-CR ! FORT ST. VRAIN NUOLEAR GENER ATING STATION
. Page 2 of 4 l
l l TABLE 4 l ALERT I I 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 l undervoltage, 480V bus under-voltage, and Diesel Trouble alarms.
- 6. Icss of all vital 6. DC bus 1 < 10 volts and DC power for up to DC bus 2 < 10 volts 30 minutes.
- 7. Loss of primary coolant 7. All He flow indicators read forced circulation for zero, between 2 and 5 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 degradation of plant safety systems. .b) Fire Pump 1A auto start c) ' Verbal reports These times are LOFC from 100% power. Times may be l correspondingly longer for lower power levels. (See LCO 4.2.18 l for time available to initiate depressurization as a function of l reactor power level.)
l l 1 l FORM 3M. 22 3bn
..m
RE CR PUBLIC SERVICE COMPANY OF COLORADO , g FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 2 Page 3 of 4 TABLE 4 ALERT Event Indication
- 11. Radiological effluents 11. a) RT 7324-1 indicating exceed 10 times technical 22.5 x 10 2 pCi/cc specifications instan-tenous limits. b) RT 7324-2 indicating 22.5 x 10 2 pCi/cc c) RT 7325-1 indicating 27.0 x 10
- pCi/cc d) RT 7325-2 indicating 27.0 x 10
- pCi/cc e) RT 73437-1 indicating 27.0 x 10 8 pCi/cc I-131.
f) RT 4802 indicating 2 7.0 x 10 ' pCi/cc I-131. g) RT 4803 indicating 2 2.5 x 10 2 pCi/cc Utilize reading from above instruments and calculate dose rate per procedures l 12. Ongoing security 12. a) As observed or reported. l compromise. 13.- Severe natural phenom- 13. a) Seismic recorder operate enon being experienced (2.05 g) or projected, such as: a) earthquake exceeding b) As Reported Operating Basis Earthquake levels; c) As Reported b) flood near design level; or, c) tornado striking facility. FORM 372 22 - 3643
- . - . . . . . . ~,y. m ..
_v _ ,_ _- -
RE CR PUBLIC SERVICE COMPANY C,F COLORADO , 9; FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2
. Page 4 of 4 TABLE 4 ALERT Event I_ndication
- 14. Other hazards being 14. As reported by, or to, experienced or projected station personnel.
such as: a) aircraft crash on facility; b) missile impact on facility; c) explosion damage affecting plant operation; or, d) entry into facility environs of toxic or flammable gas. (Some effect on facility ex-perienced or anticipated.)
- 15. Evacuation of control 15. As deemed necessary by room anticipated or Shift Supervisor required, with control of shutdown systems established from local stations.
(Control room integrity 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 indication still functional.)
- 17. Other plant conditions 17. As deemed necessary by warranting precautionary Shift Supervisor.
activation of the PCC, TSC, and FCP. FORM 372 22 3643
, . . . - , - . ,.-, - .v.- .
RE -CR PUBLIC SERVICE COMPANY OF COLORADO , ,5 FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 4 TABLE 5 SITE AREA EMERGENCY Event Indication
- 1. Loss of primary coolant 1. All He flow indicators read forced circulstion for zero.
over 5 hr. from 100% power. (Lower power levels preceeding LOFC extends time available before core damage is incurred. l See LCO 4.2.18)
- 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 open. decreasing Reactor pressure.
- 4. Determination of inability 4. 230 KV OCB trips and RAT to restore onsite AC undervoltage/ loss of power power. alarm accompanied by 4Ky 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 I inability to maintain .014p at 220'F.
- 6. Major damage to spent 6. a) Visual observation.
fuel due to severe cask damage resulting in release b) Area radiation monitor of radioactivity to plant alarms. environs. FORM 372 ' 22 - 36JJ 3.. ,,-m.,- m
R PUBLIC SERVICE COMPANY OF COLORADO a FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 4 TABLE 5 SITE AREA EMERGENCY Event Indication
- 7. Fire adversely affecting 7. a) Fire pump 1A start; safety systems.
b) Fire Control Alarm Panel c) Various alarms according t> affected safety system. d) Shift Supervisor determines fire beyond capability of station staff.
- 8. a) Effluent monitors 8. Stack monitor alarm with cetect levels corresponding stack corresponding to concentration indications greater than 50 crer./ on:
br,or greater than 500 mrem /hr a) RT 73437-1, RT 4802, whole body for two and RT 7325-1, 2 , minuter at the 26.7 x 10 pCi/cc site boundary under I-131; or, adverse meteorology (or levels 5 tires b) RT 7324-1, 2, the above for thyroid and RT 4S03
~
dose rate). >6.6 x 10 2 pCi/cc b) .These dose rates are mixed noble gasses. projected based on other l plant parameters or are ' measured in the environs.
- 9. Imminent loss of physical 9. Situation evident.
control of the plant due to security breach. (Response detailed in Station Security Plan.) l l l l l \ l 1 FORM 372 22 3643
,-y , --e.- ,-
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 2 Pace 3 of 4 TABLE 5 SITE AREA EMERGENCY Event Indication
- 10. Severe natural phenomenon 10.
being experienced or projected (with plant not in cold shutdown), such as; a) earthquake greater a) Seismic Recorder Operate than Safe Shutdown alarm with indication of Earthquake ground motion greater than 0.10g horizontal or greater than 0.067g vertical. b) flood greater than b) As reported or observed. design levels c) winds in excess of c) Average wind velocity design levels greater than 90 mph or 10-second gusts exceeding 99 mph. d) tornado in excess of d) Horizontal wina desicn levels velocity greater than 202 mph.
- 11. Otner hazards being 11. As observed by or experienced or projected reported to statior, 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.
I PORM 372 3643
CR PUBLIC SERVICE COMPANY OF COLORADO (,E , FORT ST. VR AIN NUCLEAR GENERATTNG STATION Issue 2 Page 4 of 4 TABLE 5 SITE AREA EMERGENCY Event Indication
- 13. Evacuation of control 13. F. emote shutdown 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 notification. i l l t FORM 372 22 3MG
1 l RER C PUBLIC SERVICE COMPANY OF COLORADO , 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 1 TABLE 6
)
GENERAL EMERGENCY Event Indication
- 1. a) Effluent monitors 1. Stack monitor RT-7324-1, 2 detect levels alarm, or corresponding to corresponding dose 1 rem /hr whole rates determined with body (or 5 rem /hr E-500 or cutie pie thyroid) at the detector per exclusion area procedure HPP-56 and boundary under associated graphs.
a:tual 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' oreach).
- 3. Other plant conditions 3. As determined by exist that make release Shift Supervisor.
of large amounts of radioactivity possiole. l 1 l l PORM 372 22 36*3 l l
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EtRP-CR lablo B isstso 2 Page 1 of 1 1hBLTJ LH1RLCINCY CON.DlT1QN. CROSS-RErlREMC_( NOTIriCATION SITE AREA GINLRAL UNUSUAL EVENT ALERT EMERCENCY IMERGINCY events are In A have potential for have potential for involve actual or leivolve acttsal or progress or have degradation of plant substatici degra- Ilkely fallstre(s) imminent l occurred tlant level or safety dation or plant or plant protective substantial core level of safety equipment deg ratta t ion exists l rad ioac t ive i none requiring orr small fractions < EPA PACS except- may exceed EPA PACS releases site monitoring or EPA PACS nea r s i te bounda ry notIrlestion ' Stato/1oca1/restera1 State /1ocai/rederal State /1oca1/rederai SLato/Ioca1/rederaI emergency responsemot manned manned manned manned centers rndlation r not dispatched could be dispatched dispatched dispatched sumitoring teams protective actions +none none cons ide red initiated onsite evacuatlosmo no could occur could occur stattes Upstates ' none ir applicablo p rovided p rov isted to orrsite aut ho ri t ies State monitoring +not dispatched not dispatched dispatched dispatched teams i
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PUBLIC SERVICE COMPANY OF COLOR ADO R5RP-CR FORT ST. VRAIN NUCLEAR GENERATING STATION 3 Page 1 of 1 PHONE NUMBERS FOR NOTIFICATIONS Plant Manacement Contacts Page Plant Home Phone_ Ext. Phone
! W. J. Franek, Supt. of Operations 890-0558 218 9-532-3489 l 0. P. Hood, Alternate N/A 347 78-776-1843 l L. M. McBride, Station Manager 890-0698 201 8-303-442-3829 l C. H. Fuller, Tech./ Admin.
I Services Manager 890-0810 202 8-303-663-2363 1 D. W. Warembourg, Manager l Nuclear Production 890-0699 200 8-303-833-4092 l F. J. Borst, Radiation I Protection Manager 890-1775 203 8-303-663-1230 1 0. R. Lee, Vice Pres., Prod. N/A 797-4122, l 8-571-7305 8-301-659-1180 Resident NRC Insoector l Page Plant Home l Office Phone Ext. Phone 1 G. L. Plumlee 785-2282 890-2225 490 776-9541 Technical Advisors Page Plant Home Phone Ext. Phone i J. Sills 890-2223 265 221-5059
! J. Eggebraten 890-7220 285 651-1523 A. Reed 890-1942 325 772-5312 Alternate Numbers for NRC Operatiens Center Notification NOTE: The preferreJ anethod fer notification is the " hot line."
These numbers, listed in order of preference, should only be used if the " hot line" 's not available. Commercial Telephone System (202)951-0550 (301)427-4056 (301)427-4259 (301)492-8893 (301)492-7000 Health Physics Network *22 (Touch-Tone) 22 (Rotary Dial) Technical Succort Center _ _ Preferred extension: 292 Alternate extensions: 291 or 294 PORM 372 22 3M3
PUBLIC SERVICE COMPANY OF COLORADO Rja 2
, FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 2 L Page 1 of 4 NON-EMERGENCY EVENT NOTIFICATION Report No. -
Year Sequence No. IMDORTANT: It is important that the time of all calls and names of people contacted be logged. Any further follow-up calls received or made should be logged as to time and identity of persons involved and the information transmitted or received snall also be logged.
- 1. Name and Identity of Caller:
- 2. Date of Event: Time of Event:
- 3. This notification appears to be required pursuant to 10CFR 50.72, paragraph ((b)(1), "One-Hour Report"; or (b)(2) l "Four-Hour Report")(circle one).
- 4. Description of Event:
Reactor power prior to event: Loop Shutdown? Scram? Initiating signal (s): Was event result of an LCO Action Statement? Other pertinent information:
- 5. Actions Taken:
FORM 372 - 22 300
-r
R C PUBLIC SERVICE COMPANY OF COLORADO ,h 2
- FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 4
- 6. Status:
Reactor power at time of report: Under control by onsite staff, no offsite assistance anticipated. Final report. Under control by onsite staff. Will keep NRC advised. Offsite assistance may be required. Will advise. (See Item #7) Offsite assistance required. (See Item #7)
- 7. If offsite assistance is anticipated or required, describe assistance that has been or may be requested:
- 8. Does the event involve offsite releases or the potential for offsite release that would affect the general health and safety of the public as the result of Fort St. Vrain conditions?
Yes No
- 9. If.yes, provide a good description:
- 10. Contacts made by Shift Supervisor:
a) Name of NRC contact: _ b) Time of NRC contact: l FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLE AR GENER ATING STATION [a[E lssue 2 2 Page 3 of 4 Management Contact a) Name of management contact: b) Time of management contact:
- 11. Contacts made by management:
a) Per attached call sheet log.
- 12. The Shift Supervisor and Management Contact shall send their copies of the completed forms directly to Technical Services who will:
a) Determine if a Licensee Event Report is required and prepare a facsimile copy if a 30 day report is indicated. b) Send a copy to the Superintendent, Operations. c) Send a copy to PORC. l l l l
. . . m . , m, l
l i PUBLIC SERVICE COMPANY OF COLORADO kE 2
^
FORT ST. VRAIN NUCLEAR GENERATING STATION 155yg 2 Page 4 of 4 l l l l 1 I I CALL I TIME I DATE I CONTACT (NAME) i COMMENTS / REMARKS I I I i i l i I I l l l l l 1 l ! I I l l I I ! I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 1 1 I I I I I I I I I I I I I I I I l l l l l 1 1 I I I I I l l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i l I I I I I I I I I I I I I I I I I I I l l- 1 I l l l l l l ! I l l I I I I I ! ~I I I I l l l i I I I I I I I I l i I I I I I I I I I I I I I I I I I . I I I I I I I I I I I I I I I I I I I l l 1 1 I l l I I I I I I I I I I I I I I I I I I
! ! I I I i 1 I I I I l
! I I I I I I i FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ft 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 3 NOTIFICATION OF UNUSUAL EVENT A. The Emergency Coordinator and first management contact will complete the following information jointly:
- 1. Name and identity of caller
- 2. Date of Event Time of Event
- 3. General Category of Event Unplanned Radiological Release to Reactor Building Fuel Failure Fire Natural Phenomenon (circle one)
Earthquake Flood Tornado Winds Unusual Hazards (circle one) Aircraft Explosion Toxic Material Other (Specify) ______ Spent Fuel Incident
- 4. Description of Event E. Actions Taker. _
- 6. Status:
Under control by onsite staff, no offsite assistance anticipated. Under control by onsite staff. Will keep State and NRC advised. Offsite assistance reay be required. Will advise. (See Item 7.) Offsite assistance required. (See Item 7.) PORM 372 22 3543 O
PUBLIC SERVICE COMPANY OF COLORADO ft h 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 3
- 7. If offsite assistance is anticipated or required, describe assistance that has been or may be required:
- 8. At the present time, the event does not involve offsite release or the potential for offsite releases that would affect the general health and safety of the public.
B. The Emergency Coordinator will make notifications as follows: l Contact with State EOC (279-8855) and Governor's Office (866-2471)I l or Mansion (837-8350) l I I
- 1. READ the following statement verbatim:
"THIS IS A NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION. THIS NOTIFICATION DOES NOT REQUIRE ACTIVATI0ti UF EMERGENCf RESPONSE CENTERS. THIS NOTIFICATION REQUIRES VERIFICATION CF RECEIPT BY THE STATE.
VERIFY BY CALLING 571-7436 or 785-2223.
- 2. READ all the information recorded in Step A (Page 1 of this ATTACHMENT).
1 l t l PORM 372 - 22 3643 l MOM 8 MW
T PUBLIC SERVICE COMPANY OF COLORADO f.f.c 3
. FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 2 Page 3 of 3
- 3. RECORD the following information:
Name of State EOC contact Date/ Time Name of Governor's Office / Mansion Contact Date/ Time Call back verification from State EOC, Date/ Time Call back verification from Governor's Office / Mansion Date/ Time l l l Contact with NRC Operations Center (Hot Line or 202-951-0550) l l 1 (Alternate means of notification are given in Attachment 1.)
- 1. READ the following statement verbatim:
"THIS IS NOTIFICATION OF AN UNUSUAI. EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION AT PLATTEVILLE, COLORADO. THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO IOCrR50.72, PARAGRAPH (a)(3). THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE ORGANIZATIONS."
- 2. READ the NRC Operations Center all of the information recorded in Step A (Page I of this Attachement).
- 3. RECORD the following information:
Name of NRC Contact Date/ Time l FORM 372 22 3243
PUBLIC SERVICE COMPANY OF COLORADO [(a h 4 FORT ST. VRAIN NUCLEAR GENERATING STATNDN Issue 2 Page 1 of 5 l NOTIFICATION OF EMERGENCY EVENT A. The Emergency Coordinator will complete Pages 1 and 2 of this attachment with the assistance of the first management Contact. I I l Required Information l l l
- 1. This is (Name) , Shift Supervisor at the Fort St.
Vrain Station.
- 2. At (Time) we experienced an (ALERT, SITE AREA EMERGENCY, GEN 2RAL EMERGENCY) Class incident.
- 3. a) There is NO, repeat Ng, radioactive release taking place, and no special protective actions are recommended at this time.
93 l b) A small release Il taking place, but at this time l NQ protective actions are recommended and are not l anticipated to be.
! 93 l c) A radioactive release Ij, repeat Ij, taking place, and we recommend that people in areas remain indoors with windows and doors closed.
S3 l d) A radioactive release 11, repeat lj, taking place, and we recommend that evacuation of areas be considered.
- 4. Further information on incident conditions will be provided in followup messages.
- 5. Personnel Control Center to be located
\
l FORM 372 22 M4 ) l
I l PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VR AIN NUCLEAR GENERATING STATION [. Issue 2 4 l
- I Page 2 of 5 I
l 1. l l l SUPPLEMENTAL INFORMATION l l 1 I l NOTE: This informetion is to be supplied to the NRC and the Colorado l Department of Health when requested. The radiological data i can be determined as specified in RERP-DOSE. l 1. Date and Time of Incident l 2. Class of emergency (ALERT)(SITE AREA EMERGENCY) l (GENERAL EMERGENCY) l l 3. Type of release (airborne, waterborne, surface) 1 4. Estimated duration of release (Hours) l 5. Current release rate: l l Noble Gas Ci/sec; Iodine Ci/sec l 6. Estimated curies released: l Noble Gas Ci; Iodine Ci l 7. Wind Velocity MPH, from degrees. l to degrees, Air Temp *F - I 8. Stability Category . Form of Precip. l 9. Dose rate at EAB: WB _ rem /hr; Thyroid rem /hr l 2 Miles: WS rem /hr; Thyroid rem /hr l 5 Miles: WB rem /nr; Thyrcid rem /hr . I 10. Projected dose at EA9: WB rem; Thyroid rem l 2 Miles: WB rem; Thyroid rem l 5 Miles: WB rem; Thyroid rem l 11. Estimated accumulated dose at EAB: I WB rem; Thyroid rem ( FORM 372 - 22 3643
/
_ f PUBLIC SERVICE COMPANY OF COLORADO [g 4 FORT ST. VR AIN NUCLE AR GENERATING STATION Issue 2 Page 3 of 5
, l 12. Areas expected to be impacted by release l
f I _ l 13. Estimate of ani surface radioactive contamination I i 14. On-site response actions under way l l 15. Recommended Protective Action based on the projected dose at i the EAB (Read appropriate Protective Actions) l Projected Dose Recommended l (rem) . protective Action l Whole Body <1 No planned protective actions. State l Thyroid <5 may issue advisory to seek shelter l and await instructions. Monitor l radiation levels. , - - - - l Whole Body 1 to 5 Take shelter and consider selective l Thyroid 5 to 25 evacuation. Monitor radiation levels. l Establish Controlled Area and limit l access. l Whole Body 5 and above Conduct mandatory evacuation. Monitor l Thyroid 25 and above radiation levels and adjust area for l mandatory evacuatic,n baseo on these l lovels Control Access. l 16. Prognosis for worsening of event i 17. Date and time of report l 18. Name of person providing report l 19. Telephone number for call back FORM 372 22 3643
RP-C PUBLIC SERVICE COMPANY OF COLORADO ,eh 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 4 of 5 I 20. Description of any requested off-site assistance l I l l l l B. The Emergency Coordinator will make notifications in sequence as follows: I I l l PSC Company Operator 8-571-4591 l l or 8-571-0111 l l l
- 1. INSTRUCT the Operator to initiate the " Fort St. Vrain Radiological Emergency Call List."
- 2. READ verbatim the infomation recorded in Part A (Page 1 of this attachment).
- 3. RECORD the following information:
Time PSC Operator Notified Time Operator Callback Receivea l l l Weld County (911 Using Greeley Line) l I 1
- 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 FORM 372
- 22 3643 l
. 1 PUBLIC SERVICE COMPANY OF COLORADO ht, R g FORT ST. VRAIN NUCLEAR GENERATING STAllON Issue 2
, Page 5 of 5 I .
I l NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l I 1 (Alternate means of notification are given in Attachment 1).
- 1. READ Items 1) through 4) from Part A.
- 2. READ the following sentences verbatim. "THIS EVENT IS BEING REPORTED PURSUANT TO 10-CFR50.72, PARAGRAPH (a)(3).
WE ARE PRESENTLY ACTIVATING STATE AND LOCAL EMERGENCY RESPONSE CENTERS."
- 3. READ the supplemental information (Page 2 of this attachment).
s
- 4. RECORD the following information:
NAME of NRC Contact TIME of NRC Contact f e l
> l P OR M 372 - 22 3843
PUBLIC SERVICE COMPANY OF COLORADO Dat et 1 FORT ST. VRAIN NUCLGAR GENERATING STATION Issue 2 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 print 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
- 5. Current Reactor Power 6;
Rod Runback Occur (Y/N) If yes, record positions 2A 4F
- 7. If shutdown, are all rods telly 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) __
FORM 372 22 300 l
RERP-CR
, FUBLIC SERVICE COMPANY OF COLORADO Datasneet 1
. FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 2 SEC0t:DARY 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 1
l l l l l FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RR-C , I FORT ST. VRAIN NUCLEAR GENERATING STATION IS$ye 2 1 Page 1 of 1 EMERGENCY C00RDINATOR'S CHECKLIST
- 1. Initiate Emergency Procedure actions.
- 2. Technical Advisor notified. (Not necessary for l NON-EMERGENCY events.)
- 3. Assign preliminary assessment of raciological release taking place.
- 4. Initiate protective actions for station personnel.
- 5. Classify event, using preliminary radiological assessment, if applicable.
- 6. Contact management and confirm classification.
- 7. If event is classified as an ALERT or more severe emergency, turn to Checklist 2 for ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY.
- 8. Complete Notifications Form.
NON-EMERGENCY EVENT NOTIFICATION - Attachment 2 NOTIFICATION OF UNUSUAL EVENT - Attachment 3
- 9. Make Notifications NON-EMERGENCY EVENT NOTIFICATION NRC Operations Center NOTIFICATION OF UNUSUAL EVENT State E0C Governor's Office or Mansion NRC Operations ". enter i
FOMM 372 22 M43
RERp-CR PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION e Page 1 of 2 EMERGENCY COORDINATOR /CR DIRECTOR CHECKLIST, PART 2: ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY l
- 1. Sound Plant Emergency Alarm if ALERT or higher and announce nature of the emergency.
- 2. Select the PCC location based upon consideration of the dominant wind direction:
1 1) Training Center (Primary)
- 2) Engineering /QA Office Complex l (Alternate) l NOTE: If both onsite locations are l uninhabitable, alternate l offsite locations are, in the l order of preference, the l Johnstown County Shops, l Platteville Volunteer Fire l Department, and Longmont PSCo l Service Center.
- 3. Complete Notifications form (Attachment 4).
- 4. Make notifications.
PSC Operator Weld County Communications Center NRC Operations Center PORM 372 22 3843 l
PUBLIC SERVICE COMPANY OF COLORADO C 5 st 2 FORT SJ VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 2
- 5. Noti fy Visitor's Center and specify departure route 1, 2, or 3 (see figure 2):
Wind from North Route #3 Wind from South Route #1 Wind from East Route #1
- Wind from West Route-#2 4
- 6. Notify Security to provide clearance for protected area access, if required.
l
- 7. Receive initial personnel accountability reports.
- 8. Dispatch Fire Brigade and/or Search and Rescue teams as necessary.
- 9. Establish communications with TSC (dial 292) and notify of PCC ic stion.
1 PORM 372 22 3643 1
l RE R PUBLIC SERVICE COMPANY OF COLORADO 5 jcL
. FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 1 of 3 Work /Datasheet/ Checklist Control List NOTE: Extra attachments as listed are found in the working copy of this procedure in the Control Room.
Worksheet No. Title Number Copies None N/A N/A Datasheet No. 1 Preliminary Assessment of Plant Conditions 2 Checklist No. 1 Emergency Coordinator / Control Room 2 Director Checklist 2 Emergency Coordinator / Control Room 2 Director Checklist, Part 2: ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY Attachment No. 2 Non-Emergency Event Notification 2 3 Notification of Unusual Event 2 j 4 Notification of Emergency Event 2 , y l F OR M 372 22 - 360
RA R PUBLIC SERVICE COMPANY OF COLORADO S CL FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 3 FORMS USE rep 0RTING SHEET Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a contrclied copy of the Radiclogical Emergency Response Plan Implementing Procedures, BOOK NO. , located at
. The following forms have been utilized from thf3 copy:
Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used 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 the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book.
FORM 372 22. M43
RE PUBLIC SERVICE COMPANY OF COLORADO 3 CL FORT ST. VRAIN h!UCLEAR GENERATING STATION lssue 2
.,s Page 3 of 3 FORMS USE rep 0RTING SHEET (Continued)
COMMENTS Reported By: Date: t Nuclear Documents Specialist
- Date Received Date Replaced Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.
t FORM 372 22 3643 ) l
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PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE Issue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 9 l l i'Oiii ST. EM TITLE: OFFSITE DOSE CALCULUION METHODOLOGY NON - CONT, ROLLED CCP'r VERIFYISSUE STATUS VilTH C00tWENT CENTER ISSUANCE AUTHORIZED FORM 37'b224MI BY /L, en , L_1. erMM'd U" ECME REV Ew PORc 5 8'0'AUG 2 - 1984 7/7g . .g Sections Des:-intion Pace General...........................................................3 1.0 Criteria.....................................................3 2.0 Procedure......................................................S 2.1 Monitored Release Calculations ......................... 4 2.1.1 Monitored Release - Manual....................... 4 2.1.2 Monitored Release - TI-59 Program ............... 4 2.1.3 Monitored Release - Data Logger Program ......... 5 2.1.4 Monitored Release - IBM 370 Program ............. 6 2.2 Unmonitored Release Calculations ................ ...... 7 l 2.2.1 Unmonitored Release - Manual..................... 7 l 2.2.2 Unmonitored Release - TI-59 Program ............. 7 l 2.2.3 Unmonitored Release - Data Logger Program ....... 7 1 2.2.4 Unmonitored Release - IBM 370 Program ........... 7 3.0 Resoonsibilities.............................................7 4.0 f.eferences ................................................... 8 5.0 Referenced or Supportino Procedures........................... 9 Figure 1 Local Determination of Stack Concentration ............. 1 l Figure 2 Site Sector Map......................................... 1 Table 1 Atmos;,heric Stability Categories ....................... 1 1 t 1 Table 2 Potentially Affected Sectors ........................... 1 l PORM 372 22 3642 l
1 PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIM NUOLEAR GENERATING STATION Zssue 6 Page 2 of 9 l l l Table 3 Do se Conversi on Factors . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 l Attachment 1 Dispersion Factors............................... 1 Worksheet 1 Monitored Release Calculations (Manual) ......... 1 i Worksheet 2 Monitored Release Calculations (TI-59)........... 1 Worksheet 3 Unmonitored Release Calculations (Manual) ....... 1 Worksheet 4 Unmonitored Release Calculations (TI-59)......... 1 Datasheet 1- Data Logger (or IBM) Monitored Release. . . . . . . . . . . 1 - Datasheet 2 Data Logger (or IBM) Unmonitored Release......... 1 Datasheet 3 Status Board Update Sheet ....................... 1 Checklist 1 Data Logger Monitored Release ................... 1 Work / Data sheet /Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e Re po rti ng S he e t* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN Oh, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSEuF. ALL WORKSHEETS/DATASHEETS/ CHECKLIST 3 ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE. 1 FORM 3M.32 3bu l
RERP-DOSE PUBLIC SERVIC":. COMPANY OF COLORADO 1ssue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 9 General This procedure provides an overview of the available methodology for offsite dose calculations during an emergency at Fort St. Vrain. The methodology available provides a large degree of flexibility in performing offsite dose calculations, and allows the user to select whatever method he feels the most proficient at using. For both the monitored and unmonitored cases, the options provided are essentially identical in their methodology employed. This procedure is primarily intended for use by radiological assessment personnel at the Technical Support Center (TSC) and/or .~ l Forward Command Post (FCP) during the course of an emergency, and for l Control Room personnel for initial dose calculations. 1.0 Criteria l This procedure provides direction to CR, TSC and/or FCP personnel in the performance of offsite dose calculations under emergency conditions. This procedure does not govern calculations for routine release of radiological effTuents as provided by station Technical Specifications. This procedure may be implemented in the event of a radiological release to the extent warranting activation of the FSV Radiological Emergency Response Plan (RERP). 2.0 Procedure - Emergency offsite dose calculations may be required for cases where the radiological effluents are being monitored by the exhaust ventilation monitors, or for cases where reactor building louvers have opened and primary coolant is escaping, unmonitored. The first four (4) parts of this procedure are related to calculational options for a monitored release. The last four (4) parts discuss calculational options for an unmonitored release. For the case of unmonitored release, it is appropriate to
. utilize unmonitored release assumptions at the outFet, and revert to monitored release calculations after the building louvers have closed.
l All parts of this procedure are centered around the necessary worksheets and datasheets required for their use. Descriptive text is supplied to provide any general information required for l adequate performance of that set of calculations. Worksheets are constructed in such a manner that they do not require a step-by-step reference to this procedure for use. As all of these calculations, whether ccmputer assisted or not, l , are extremely time consuming, it is imperative that the I individual utilize as much additional assistance from available personnel as they feel necessary. At the TSC, Computer Support l l
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DDSE FORT ST. VRAIM NUCLEAR GENERATING STATION Issue 6 Page 4 of 9 l personnel have been adequately trained to provide assistance in both racords keeping and data entry if required. Completion of the datasheets and checklists is optional, but should be perfo'med as time permits. ! 2.1 Monitored Release Calculations Monitored release offsite dose calculations are performed utilizing the indications of plant ventilation exhaust monitors for noble gases and radioiodines. The primary monitors of interest are RT-7324, 1, and 2, and RT-73437, 1. The RT-7324 monitors are for noble gases, and RT-73437, 1 is for' radiciodines. Radioiodine monitors, RT-7325, 1 and 2 may be utilized if required, but could' provice overly conservative results in the presence of noble gases. l In the event that the primary monitors are inoperative due l to power loss, etc., the emergency stack monitors RT-4802 l and 4803, powered by the ACM diesel, may be utilized per l HPP-13 to determine the activity concentration of Iodine l and Noble gas, respectively. As a back up in the event that stack noble gas monitors are offscale or inoperative, there is a manual method of - determination of stack noble gas concentration. This method is described in detail in HPP-56. Figure 1 of this procedure provides the necessary conversion from a manual portable radiation detector reading to a stack noble gas concentration (pCi/cc). The criterion for determining the need for a manual stack concentration is whenever one, or both, of the stack noble gas monitors (RT-7324,1, and 2) are offscale, or inoperative, during a radiological emergency. These readings should be obtainad as frequenty as possible, so as to verify the ncble gas release rates. Offsite dose calculations should be performed at least l every thirty minutes during a radiological emergency. These calculations should be utilized in determining the recommended protective actions (see RERP-PAG) and for keeping the Corporate Emergency Director (CED) and Technical Support Center Director appraised of radiological conditions. l Dose conversion factors used in each of the methods l described are given in Table 3. PORM 372 22 3843
a PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION 5 of 9 2.1.1 Monitored Release - Manual This method is provided for situations where use of computer or calculator programs is not possible or to provide a manual verification of dose calculation results. This calculation is easiest when carried out with the aid of a pocket calculator. The procedure for this calculation is itemized on Worksheet 1 of this procedure.
. 2.1.2 Monitored Release - TI-59 Program The method is, quite simply, the monitored release
- manual method performed with the use of a TI-59 program recorded on magnetic cards.
The procedure for this calculation is itemized on Worksheet 2 of this procedure. 2.1.3 Monitored Release - Data Legger Program For personnel located at the Technical Support Center or in the Control Room, this is the most desireable way of performing offsite dose calculations. This system allows a more precise ongoing tabulation of dose projection results for a series of release calcuations, as well as finger-tip a: cess to key plant parameters required for these calculations. For record keeping purposes, it is desireable to print all screens utilized in performance of this calculation. In the Control Room, this can be done l with the " PRINT CRT" key. In the TSC, a screen may be transferred to the Tektronix screen and then
. printed as follows. First, on the Tektronix keyboard press the " SCREEN RESET" button in the upper lefthand corner. Second, on the 2-on-1, press the " COPY CRT" key. This action begins transfer of the screen image to the Tektronix screen. After transfer of the screen is completed (about 20 seconds on average) the screen may oe copied to paper by pressing either the white " Copy" button on the Tektronix printer, or by pressing the
" COPY" button in the upper right hand corner of the ,
l Tektronix keyboard. (If the line printer is connected to the TSC terminal, l screen copy is ' pe-formed by pressing the " PRINT CRT" button on the [ 2-on-1 console.) POnM 372 22 3843 l
1 1
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PUBLiC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIM NUCLEAR GENERATING STATION lssue 6 Page 6 of 9 Jhecklist 1 is available in this procedure to assist in the proper sequence of actions for ) printing the required screens of this calculation. Datasheet 1 is provided for use in gathering and summarizing the data utilized in performance of this computer assisted calculation (as well as for the IBM program). This program is accessible by pressing the upper
" DEMAND FUNCTION OVERVIEW" button on the 2-on-1 to get the Demand Function menu (or by accessing
" DISPLAY" 941). On the menu, locate the cursor in the DF-41-0-0 box, and press "XMIT CURSOR". The instructions for performing the calculations are printed on each screen when brought up, in oroer.
It is advisable that an inexperienced user follow the printed instructions carefully and slowly. During a long release where the release ending time is not precisely known or estimated, perform two calculations utilizing Program Ootion #2. First, make a 2 hour dose projection (substitute projected release duration where known) and then make a l thirty minute " puff" release projection using Program ootion #2. The " puff" projection allows tabulation of doses received. The puff projections should be for discrete time intervals. Simply stated, this means that a " puff's" starting time should be the previous " puff's" ending time. These calculations may then be totaled (Step 8) utilizing ootion 3 and rerunning DF-41-0-0, 2.1.4 Monitored Release - IBM 370 Program This program is set up to operate from any of the IBM computer terminals available throughout the company. It provides very detailed output and serves as an excellent data base for post-accident l . dose analysis. Its principal drawback is the job turnaround time on the company computer, and the availability of the ROSCOE programming utility. Additionally, users must have available a ROSCOE sign-on. The first step of this calculation is to gather data just as was done in 2.1.3 using datasheet 1. Data entry for this program is done by utilizing an interactive ROSPROC developed specifically for this purpose. The user should log onto ROSCOE and then issue the following command: .
- " EXEC LP. DOSE" l
l l conu sn za.as4 I
. PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION e6 ,
l Issuing this command will invoke a data deck I structuring program allowing instream data deck < structuring and job submission for as many " puffs" anc projections as desired. When the user is completed executing puff data, he should route his output to hardcopy by entering "END", while in output runout, and exiting the ROSPROC. This method is setup so that the long term projection and puff accumulation calculations are done simultaneously. Entry of a projected duration l of release is done for each 30 minute update. This value is then added to the time elapsed from start of the update to current. Values calculated in this manner (first set of output) represent projections from the start of the puff at the current release rate, under current meteorological conditions. Calculations from this program will result in three pages of output for each set of data entered and a final summary output. The first page summarizes program inputs and the sigma y and sigma z o calculations for dispersion. The second page summarizes dose rates and integrated doses for both l the projected release and for the 30 minute puff. The third page summarizes dispersion factors, meteorology, release rates, and accumulated doses to that point of the release. 2.2 Unmonitored Release Calculations These calculation methods are provided for use in the extremely unlikely event that primary coolant leakage is so rapid and extreme that it causes the reactor building louvers to open. In 'this even'., design assumptions from the FSAR indicate that no more than 1/3 of the primary
. coolant could escape unmonitored. Therefore, these 1 calculations are performed once to estimate the projected <
dose commitment as a result of such a release. Once the I louvers have reseated, all calculations will be able to be 1 performed utilizing the stack monitors as described in Section 2.1. l l 2.2.1 Unmonitored Release - Manual Worksheet 3 itemizes the necessary steps for the i performance of this calculation. , l I l l FORM 372 22 3843
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION 7g 2.2.2 Unmonitored Release - TI-59 Program As was the case for the monitored release TI-59 program, this is a magnetic card recorded program that mimics the manual calculation method. Worksheet 4 itemizes the necessary steps for the performance of this calculation. 2.2.3 Unmonitored Release - Data Logger Program The data logger is the most convenient method for performance of unmonitored release calculations. Datasheet 2 is provided to record program inputs. As was the case for monitored release calculations, be certain to print all screens of input and output tnat were utilized in performing the calculation. 2.2.4 Unmonitored Release - IBM 370 Program (Program In Development) 2.3 Protective Action Recommendations Protective action recomendations are, in large part, based upon the - ca-lculations contained herein. Recommendations of offsite protective actions should be based upon the criteria set forth in RERP-PAG. 3.0 Responsiblities l 3.1 Control Room Personnel l Perform initial radiological assessemnt as directed by the l Emergency Coordirator (Shift Supervisor). Utilize l Worksheets 1 or 3 for manual calculations, or Datasheets 1 l or 2 and Checklist 1 for data logger use. Report results l to Emergency Coordinator. Perform assessment as required l (or at least every 30 minutes) until the TSC is activated. l 3.2 Radiological Assessment Coordinator l Obtain 30 minute updates of offsite dose calculations from Radiological Assessment personnel at the Technical Support Center. Use this to complete the status board update sneet, datasheet 3. Verify any calculations in question via manual or TI-59 calculations. PORM 372 22 3843
o PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE Ue FORT ST. VRAIN NUCLEAR GENERATING STATION l 3.3 Technical Support Center Radiological Assessment l Perform calculations at an average rate of every 30 minutes during a radiological emergency, and transmit results to both the TSC Director and the Radiological Assessment Coordinator. Save all data sheets, checklists, worksheets and program outputs for transmission to Rec.ord Storage at the conclusion of the emergency. l 3.4 Computer Support Personnel (TSC) Assist the TSC Radiological Assessment indfvidual on an as-needed basis, when available. 4.0 References - 41 NRC Regulatory Guide 1.145 4.2 Slade, Meteorology and Atomic Energy, 1968 5.0 Referenced er Suecorting Procedures 5.1 HPP-56, Manual Release Rate Determination 5.2 RERP-PAG, Protective Action Guideline Recommendations (To be developed). 5.3 RERP-ORG, FSV Emergency Organization and Responsibilities l 5.4 HPP-13, Continuous Air Monitors l 5.5 RERP-TSC, Technical Support Center Procedure l 5.6 RERP-FCP, Forward Command Post Procedure l 5.7 RERP-CR, Control Room Procedure l PORM 372 22 3843 6
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R $ PUBLIC SERVICE COMPANY OF COLORADO a e FORT ST. VR AIN NUCLE AR GENER ATING STATION IS$ue 6 Page 1 of 1 TABLE 1 FORT ST. VRAIN ATMOSPHERIC STABILITY CATEGORIES
- AT (*F) from Pasquill Stability c0** -
60m Tower Categories Classification (Degrees) s-1.7 A Extremely Unstable 222.5
>-1.7 to s -1.5 B Moderately Unstable <22.5 to 217.5
>-1.5 to s -1.3 C Slightly Unstable <17.5 to 212.5
>-1.3 to s -0.4 0 Neutral <12.5 to 2 7.5
>-0.4 to $1.3 E Slightly Stable < 7.5 to 2 3.8
>+1.3 to 53.5 F Moderately Stable < 3.8 to 2 2.1
>+3.5 G Extremely Stable <2.1 per Proposed Revision 1 to Regulatory Guide 1.23, September 1980.
Standard deviation of horizontal wind direction fluctuation (plume meander) over a period of 15 minutes to I hour. POMM 372 22 3443
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- RE D SE PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENER ATING STATION IS5ue 6 l
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i TABLE 2 POTENTIALLY AFFECTED SECTORS WITHIN 5 MILE EPZ (WIND FROM e DEGREES) (SEE SITE FIGURE 1 FOR LOCATION OF SECTORS) Stability Stability Category 0'ss<22i' Cateoory 221*49<45' A D,E,N,0,P A D,E,N,0,P,EE B D,E,N,0 B D,E,N,0,P,EE C D,E,N,0 C D,E,N,0,P,EE D D,N,0 9 D,E,N,0,P,EE E D,N,0 E D,E,0,P,EE F D,N,0 F D,E,0,P,EE G D,N,0 G D,E,0,EE Stability Stability Category 45'se<671* Category 671'se<90' A D,E,F,N,0,P,Q,EE A A,D,E,F,0,P,Q,R,EE B D,E,F,0,P,Q,EE B A,D,E,F,0,P,Q,EE C D,E,0,P,EE C A,D,E,F,0,P,Q,EE D D,E,0,P,EE D A,D,E,F,P,Q E D,E,0,P,EE E A,0,E,F,P,Q F D.E,0,P,EE F A,D,E,F,P,Q G D,E,0,P,EE G D,E,F,P,Q Stability Stability Category 90'50<1121' Category J112
- p<135' A A,0,E,F,G,P,Q,R A A,D,5,F,G,H,P,0,R B A,D,E,F,G,P,Q,R B A,D,E,F,G,H,P,Q,R C A ,0, E , F,G , P ,Q , R C A,D,E,F,G,P,Q,R D A,D,E,F,P,Q,R D A,D,F,G,Q,R E A,0,E,F,P,Q,R E A,D,F,G,Q,R F. A,0,E,F,P,0 F A,F,G,Q,R G A,0,E,F,P,Q G A,F,G,Q,R Stability Stability Category 135'se<1571' Category 1571*cs<180' A A,B,D,F,G,H,Q,R A A,B,F,G,H,I,Q,R B . A,F,G,H,Q,R B A,B,F,G,H,R C A,F,G H,Q,R C A,B,F,G,H D A F,G,H,Q,R D A,B,F,G,H E A,F,G,R E A,B,F,G,H l F A,F,G,R F A,B,F,G,H G A.F,G,R G A,F,G,H l
PORM 373 22 3843
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D SE PUZLIC SERVICE COMPANY OF COLORADO f, FORT ST. VRAIN NUCLEAR GENERATING STATION IS$ue 6 i Page 2 of 2 Stability Stability Category 180*se<2021* Category 2021*se<225* A A,B,F,G,H,1,J A A,B,C,H,1,J,K B A,B,G,H,I B A,B,H,I,J,K C A,B,G,H,I C A,B,H,I,J,K D A,B,G,H,I D A,B,H,I,J E A,B,G,H,I E A,B,H,I,J F A,B,H F A,B,H,I,J G A,B,H G B,H,I,J Stability Stability category 225'se<2471* Cateoory 2471'*se<270* A A , B , C , H ,1,J , K , L A B,C,H,I,J,K,L,M B A,B , C ,H , I ,J , K, L B B,C,I,J,K,L,M C A,B,C,H,1,J,K C B,C,I,J,K,L D B,C,H,I,J,K D B,C,I,J.K,L E B,C,I,J,K E B,C,I,J,K,L F B,I,J,K F B,C,I,J,K,L G B I,J,K G B , C ,1,J , K , L Stability Stability Category 270*se<2921* Category 2921*se<315* A B , C , D ,1,J , K , L, M , N A B,C,D,J,K,L,M,N B B , C ,0,I ,J , K, L,M ,N B C,0,J,K,L,M,N C B,C,D,J,K,L,M C C,D,L,M,N D B ,C ,D ,J , K , L D C,D,L,M,N E B,C,J,K,L E C,D,L,M,N F B,C,J,K,L F C,D,L,M,N G C,J,K,L G C,D,L,M,N Stability Stability Category 315*se<3371* Category 3371'19<360* A C ,D, L,M , N ,0 A C,D,M,N,0 B C ,0, L,M, N B C,D,M,N,0 C C,D,M,N C C,D,M,N,0 0 C,0,M,N D C,D,N,0 E C,D,M,N E D,N F C,0,M,N F D,N
,G C,D,M,N G D,N l
FORM 372 72 3843
. 1 RERP-DOSC FUBLIC SERVICE COMPANY OF COLORADO Table 3 l FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 1 of 1 TABLE 3 DOSE CONVERSION FACTORS (DCF'S)
Radionuclide rem /hr 3 DCF(Ci/m )* Kr-83m 2.7E-1 Kr-85m 1.3E+2 Kr-85 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 Noble gas weighted average total body DCF 7.5E+2 l l (based on 879 Mw(t) design inventory) l l l I-131 1.2E+6 I-132 1.7E+4 I-133 2.3E+5 I-134 5.6E+3 I-135 5.7E+4 l Radioiodine weighted average thyroid DCF 5.3E+4 I l (based on 879 Mw(t) design inventory) l
- I I I
*DCF's for noble gases from "The EXREM III Computer Code for Estimating External Radiation Doses to Populations from Environmental Releases," ORNL-TM-4332, with the exception of
! DCF's for Kr-89 and Kr-90, which are from " Final Environmental ; l Statement, Light Water Breeder Reactor Program," Volume 3 of 5, i
" Commercial Application of LWBR Technology," ERDA-1541.
DCF's for radiciodines from "INREM II: A Computer l Implementation of Recent Models for Estimating the Dose Equivalent to Organs of Man from an Inhaled or Ingested Radionuclide," ORNL/NUREG/TM-84 PORM 372 22 3643 l
I I J 4 s
=
l I TABLE 1A X/Q VALUES (X10 sec/m' ) AT Tile E/CLUSION AREA BOUNDARY (590m) FOR AN AMEMOMETER 1.OCATED AT A IIElGili 0F 10 ME1[ItS ACCORDING TO Tile EQUAll0005 0F NHC REG GUIDE 1.145 WINOSI*EED AT 10 ME1ERS (Mf*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 i
't
; A 3.469 1.735 1.156 0.694 0.496 0.386 0.289 0.231 0.114 0.116 0.069 8 11.490 5.746 3.830 2.298 1.642 1.2TT 0.958 p.166 0.515 0.383 n.230
} C 23.250 11.630 7.751 4.650 3.22 2.584 1.938 1.550 1.163 0.775 o. te 65 D 36.56 18.28 12.19 7.844 6.928 5.988 4.491 3.593 2.695 1.796 1.018 E 48.46 24.23 16.15 10.83 10.83 9.449 7.089 5.6To 4.252 2.83'2 1.10:
...I I F 88.42 44.21 29.4T 20.35 18.54 14.42 10.81 8.650 6.488 4.375 2.595 l -{ .
t : i C 140.20 70.11 46.74 33.52 r0.06 e 31.16 23.37 18.70 14.02 9.3'88 5.609 i . i - Ik se 1 .t l T M 3* N WmdM LOW &N s, <D c = a it O I
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RERP. DOSE Attachment 1
- - Issue 6
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' DISPER$10h FACTOR (X/Q) vs.WINDSPEED FOR THE EXCLt.!5 ION AREA BOUND ARY (590 METERS). ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATI FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS.
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TABLE 2A
. X/Q VALUIS (X10' sec/m') AT A DOWNWIND DISTANCF Of 2 HlLES FOR AN A.*t[M0 METER LOCATED AT A It[ICIIT OF 10 ME1[ftS ACCoit01NC TO THE EQUAllONS OF NRC ftLC CUIDE 1.145
. WINDST((D AT 10 ME1ERS (Mrtl) l StahlIity x CIsss 1.0 2.0 3.0 5.0 7.0 9.0 17.0 15.0 Po.o so.o 5:s.o A 0.I24 0.062 0.041 0.025 0.0t8 0.014 0.010 0.008 O.096 4s . oc as o.sm? ;
5 1.751 0.876 0.584 0.353 0.250 0.195 0.146 0.117 0.088 o.u5s o.u25 l C 12.97 6.483 4.322 2.593 1.852 1.441 1.081 0.8% 0.68s o.s s32 0.759 0 38.13 19.07 12.71 7.859 6.104 5.019 3.912 3.111 2.383 1.5n9 sr.953 E 64.89 32.44 21.63 13.74 11.46 9.821 7.961 6.369 4.716 3.1me 1.981 1 r l T 130.4 65.18 43.45 28.33 25.27 22.53 17.98 14.33 10 ;4 r. e4.1 4.798 l C 250.1 125.0 83.35 56.60 SG.14 51.72 38.79 31.03 23.28 15.57 9.110 l l l ~* i l l l "Ue-*33"U DP m rt m f CM MM
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. . RERP-DOSE Attachment 1 Issue 6
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Page 4 of 14 g se: - S FIGURE .A.
,p DtSPER$10N FACTOR (X/Q) vs.WINDSPEED FOR A DOWNWIND D! STANCE OF 2 MILES, ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.143. WINDSPEEDS SHOWN ARE THE INDICATIONS I FOR AN ANEMOMETER LOCATED AT - A HEIGHT OF 10 METERS.
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-6 3 X/Q val.UES (X10 sec/m ) AT A 00WNWif40 DESIANCE Or le MILES '
T0ft AN AN[MOMET[R LOCAT[D AT A 1101C118 of 10 MET [its ACC0ftDING TO Till. rQoA110NS of NilC ltlG ColllE 1.18s5 WINOSI'((0 AT 10 METERS (He'll) Stability Class - 1.0 2.0 3.0 5.0 7.0- 9.0 12.0 15.0 20.0 30.0 50.o r i 1
. A 0.069 0.034 0.023 0.01 er 0.010 0.008 0.006 0.005 0.003 '
0.002 0.001 D 0.155 0.078 0.052 0.031 0.022 0.017 0.013 0.010 0.018 0.005 0.00.1 C 3.963 1.982 1.321 0.793 0.566 0. ht:0 U.330 ' O.264 0.198 0.132 0. il19 0 14.87 7.434 84.956 3.028 2.211 1.824' 1.415 1.132 0.849 0.566 0 . 38 0 E E9.17 14.59 9.725 6.053 4.757 3.918 3.095 2.476 1.857 1.238 0 . 18 3 i r 65.46 32.73 21.82 13.e5 11.8:0 9.626 7.585 6.068 4.551 3.03's 1.820 G 132.81 66.42 44.28 29. 08a 25.85 22.67 19. '. i 13.90 . it). 42 6.988 4 4.169 i-I f1 m ,-e y n m in r+ m
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- RERP-DOSE Attachment 1 Issue 6
- Page 6 of 14 te-2 5
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1c 3 FIGURE 3.A. ' _ DISPERSION FACTOR 4/Q) vs.WINDSPEED FOR A DOWalWIND DISTANCE OF 4 MILES, ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS - FOR AN ANEMOMETER LOCATED AT A HElGHT OF 1C METERS.
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TABLE 8sA X/Q VALUES (X10~ sec/m3) AT A 00WNWitID DISIANCE of 5 MILES B OR AN ANEMOHCl[R LOCAT[D AT A IILIGill OF 10 HEititS ACC06! DING TO lilE EQUA110NS of HRC ltfG CUIDE 1. 18 5 8 WIN 0 SPEED AT .10 HETERS (Hril) 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 0.057 0.026 0.019 0.011 0.008 0.006 0.005 0 , 0 08: 0.003 0.002 0.001 i 1 ft 0.072 0.036 0 . 0 284 0 . 0 18 0.010 0.006 0.006 0.005 0.00's 0.002 0.001 C 2.70's 1.352 0.902 0.5r:1 0.386 0.301 0.225 0.180 0.135 0.090 0. 0 58: 0 10.96 5.8s78 3.652 2.224 1. 6% 1.322 1.017 0.816 0.612 0.808 p.Pr 5 1 E 22.43 11.21 7.8476 84.630 3.586 2.927 2.29fs 1.831 1.371 0.918 0.551 F 52.01 26.03 17.36 10.93 8.819 7. 38:7 5.759 8#.608 3. 8:56 2.30's 1. ift? O 107.7 53.86' 35.91 23.30 2 0. 18s 1 7. 381 13.34 10.67 8.005 5.336 3.702 Wec4
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i RERP-DOSE I ;' - ' Attachment 1 Issue 6 Page 8 of 14 i
. 16 i l
"IGURE 4.A.
- - "l5PER$10N FACTOR (X/Q) vs.WINDSPEED FOR A DOWNY.'!ND i
' DISTANCE OF 5 MILES ACCDRDING TO THE EQUATIONS OF I
. NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS ,
i FOR AN ANEMOMET R LOCATED AT A HEIGH *T OF 10 METIPS.
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TAllLE 5A X/Q VALUES (X10~ soc /m')' AT A DOWNWIND DISTANCE or 6 HILES FOR AN ANEMOMEif R LOCATED AT A IIEICill or 10 METERS ACCORDINC 10 THE EQUATIONS Or NRC REC CUIDE 1.18 5 3 WINOSPEED AT 10 METERS (MI'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 G.fs85 0.243 0.162 0.091 0.069 0.054 0.040 0.032 0 .0 28: 0.016 0.010 + 0 0.616 0.308 0.206 0.123 0.068 0.068 0.051 0 . 08:1 0.038 0.071 0.012 C 19,72 9.859 6.573 3.944 2.817 2.191 1.643 1.315 0.986 0.651 0 . 398: D 85.61 8:2.81 28.54 17.35 1 2. 88 10.21 7.830 6. 2nts 8s.713 3 . 18s2 1.on5 E 179.6 89.e1 59.87 36.93 28.31 22.96 17.88 18s. 3 3 10.75 7.166 is.799 r 8:31.9 215.9 144.0 90.18 71.66 59.15 8s6.17 36.93 21.10 18. 8s t 11.0a C 909.7 is58s .9 303.2 195.3 165.2 I fso.8s 108.1 86.8:5 6's . o rs 8:3.23 75.9t S m~ N n?
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RERP-DOSE Attachment 1 Issue 6
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Page 10 of 14 10-r - s FIGURE ~5.A. DISPERSION FACTOP. (X/Q) vs.WINDSPEED FOR A DOWNWIND D! STANCE OF 6 MILES, ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS 10'4 FOR AN ANEMOMETER LCCATED AT A HEIGHT OF 10 METERS
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3 TABLE 6A
~7 3 X/Q VALUES (X10 soc /m ) AT A DOWNWlfl0 DISTANCE Of 8 HILES TUR AN Afl[HOME1FH 1.0 Gall'D AI A liflGill Of 10 Mi1[RS t
ACC061 DING TO THE EQUATIONS Of NRC RIG CUIDE 1.185 6 i WINDSr[IH AT 10 HEi[ILS (Hl'lI) Stability Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 , I . , g A 0.379 0.190 0.126 0.0T6 0 . 0 581 0 . 086 2 0.032 0.075 0.019 0.013 0. ems D 0.8 S81 4 0 . 28:2 0.161 0.097 0.069 0 . 0 58: 0.080 0.03? 0. 0Fs 0.016 0.010 C 12.66 6.329 88.219 2.531 1.808 1.806 1 1.055 0. 88 6's 0.6 13 0. is?? 0.?53 4 0 5 7.988 28,97 19.31 11.71 8.599 6.808 5.195 is.169 3.1 A, P. 0118 1.pst i E 126.3 63.15 8:2.10 2 5 . 881 1 9. 58: 15.71 1 2 . 18: 9.735 7.301 #s.867 ?.970 F 322.7 161.84 107.6 66.87 52.07 is2. fs7 32.93 76.35 19.76 13.17 r . 908: 0 698. fe , 38s9.2 232.8 1888 . 2 121.7 101.6 78.19 6?.55 86.91 31.78 1a.77 i i t. T *-* > M tb in rt m
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- RERP-DOSE
- Attachment 1 Issue 6 Page 12 of 14 10
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,4 s FIGURE 6.A. .
- 3 10 DISPER510N FACTOR (X/Q)vs.WINDSPEED FOR A DOWNWIND ._
DISTANCE OF S MI' *% ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSP EED5 SHOWN ARE THE INDICATIONS 8 g FOR AN ANEMOMETER LOCATED *AT A HEIGHT OF 10 METEPJ5.
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j TABLE 7A , X/Q VALUES (X10 soc /m') AT A DOWNWIND DISTANCE Or 10 MILES d FOR AN ANLHOMElrit LOCAIED A1 A ilLIGill OF 10 HCillts
; ACCORDING TO Tile EQUAll0NS 00 NitC It[G GUIDE 1.18e5
) WINDSPELD Al 10 HE1 Lits (HMI) 3 St, ability Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 A 0.313 0.156 0. 108: 0.063 0 . 08:5 0.035 0.026 0.0?t 0.016 0.01o n.or 6 4
J B 0. 8:02 0.201 0 . 1 384 0.080 0.057 0 . 08:5 0.033 0.021 0.020 0.083 0.008 i I C 8.833 is . 8s 16 2 . 9 848 1.767 1.262 0.981 0.736 0.589 0. 8s's 2 0 . 2 98: 0.111 0 8s3.02 21.51 184. 386 8.678 6. 3845 5.000 3.810 3. 0's 7 2.293 1.52n 16.911 i E 99.81 89.90 8 33.27 20.35 15.26 12.20 9 . 3 88 T.521 5. 6'a 5 3.163 2.P53 r 256.9 128.5 8 5 . 68: 52.96 80.71 6 32.95 25. 's's 20.35 15.26 10.18 6.In5 G 568.7 2 884. 3 189.6 119.8 96.8:0 79.62 61.16 88.93 36.TO Pri . si6 18.63 6 I TH>N cu en c+ rii tO (A v4 N ED C ED T 4 (D O O s W W C1 (4 Ch ~3 O l, SD U1 O :3 trl
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-- RERP-DOSE Attachment I !
Issue 6 ) Page 14 of 14 l ( ! t:-: i l 5-t l FIGURE 7.A.
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PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VR AIN NUCLEAR GENERATING STATION t!orkshiet 1 Issu2 6 Page 1 of 10 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 w'n ole 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) uCi/cc/ cpm c) Maximum CPM, RIS-7324-2: (RR-93539, blue pen) cpm d) Sensitivity, RIS-7324-2: (I-14,203-P7) uC1/cc/ cpm e) Maximum CPM / Min, RIS-73437-1: cpm / min NOTE: Maximum CPM / Min must bc ;alculated as: (Maximum CPM - Initial or Intermediate CPM) ( Elapsec Time (min) ,) from strip chart. FORM 3Mt. 22 3DQ
. , . . . . . . - -~
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheot 1
... Issue 6 Page 2 of 10 f) Sensitivity, RIS-73437-1: pCi/cc/ cam / min g) Site Area Emergency Limit (as posted):
- 1) 6.6E-2 uti/cc noble gas
- 2) 6.7E-5 vCi/cc282I h) Ten Times Technical Specification Limits (as posted):
- 1) 2.5E-2 uCi/cc noble gas
- 2) 7.0E-8 vCi/cc282I 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 at 10 meters: From Degrees NOTE: North = 0* increasing degrees - c.w.
m) Differential Temperature: 'F (60m Tower) l n) ce = From Data Logger, or square root of l (maximum fluctuation in wind direction over l period of 15. minutes to one hour). l (OPTIONAL CALCULATION) l
- 5. Determine Stability Category using Table 1 and i l Step 4m) or 4n). '
Stability Category l l
- 6. Determine potential sectors affected within 5 '
mile EPZ using Table 2 and Site Sector Map (Figure 2). ! Sectors l l l FORM 372 22 3843
) - PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE ! FORT ST. VR AIN NUOLEAR GENERATING STATION EforksheGt I
- Issue 6 Page 3 of 10 l
l l 1 I l Noble Gas Concentration l 1 I i
- 7. Calculate the exhaust stack noble gas concentration.
a) RIS-7324-1 concentration = (step 4a) x (step 46)
=( )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 Figure 1 for instructions).
l If readouts are not available for RIS-7324-1 or RIS-7324-2' l due to power loss, etc., record the stack concentration as l obtained from RT-4803, located on level 11 of the Turbine l Building adjacent to the reactor plant exhaust stack l (refer to HPP-13 for instructions). Local Indicated Concentration = uC1/cc d) Enter the highest of 7a), 7b), or 7c) pCi/cc I I [ Noble Gas Release Rate l I I i
- 8. Calculate the Source Term, Q (i.e., Noble Gas Release Rate). l Q = (step 7d) x (step 4j) x (1 E -6 Ci/uci)
=( )x( ) x (1 E -6)
= Ci/sec
( l
. PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN WUCLEAR GENERATING STATION tforksheet 1 Issue 6
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Page 4 of 10 j l l l Classification of Event l l l l 9. Determine the EAB dilution factor from Attach-l ment 1, Table IA, using the Stability Category J l (Step 5) and wind speed (Step 4k). J l Dilution Factor = sec/m' General Emeroency Determinatio? l l 10. Determine whole body dose rate at the EAB. l Dose Rate = (step 8) x (7.5 E+2 Rem / hour) x (step 9) I ( ci/m') l l =( ) x (7.5 E+2) x ( )
= Rem / hour If the resulting dose rate at the EAB is 21 Rem / hour, the classification of the event is GENERAL EMERGENCY. Inform the Shift Supervisor of the General Emergency condition. Then go l directly to Step-13 of this attachment.
Site Area Emeroency Determination l 11. Criteria for Site Emergency: If Step 7d) is greater than or equal to 6.6 E-2 pCi/cc, the classification of the event is SITE AREA EMERGENCY. Inform the Shift Supervisor of the Site l Emergency Condition. Then go directly to Step 13 of this attachment. Radiolooical Alert Determination l 12. Crite'ria for Radiological Alert: If Steo 7d) is greater than or l equal to 2.5 E-2 pCi/cc (ten times the Technical Specification , l limit), the classification of the event is RADIOLOGICAL ALERT. ; Inform the Shift Supervisor of the Radiological Alert Condition. l l Then proceed with Step 13. l l l i
~ PUBLIC SERVICE COMPA NY OF COLOR ADO agap-coss FORT ST. VRAIN NUOLEAR GENERATING STATION Worksheet 1 Issue 6 Page 5 of 10 l I I Curies of Noble Gas Released i I I l 13. 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 l Accumulated Whole Body Gamma Dose at EAB l l l l 14. Calculate the dose received at the EAB.
l Dose = (step 10) 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 l l l l 15. If the release is continuing, consult with the Shift Supervisor and estimate the total numoer of hours tne release will continue l (i.e., from beginning to end). A projected release duration of I two hours may be reasonable if no better estimate is available. If the release has terminated, enter value from step 3. Preliminary estimate of release hours hours. F0mW 3M 22 360 on-w
r PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION llorkshent 1 Issue 6 Page 6 of 10 l 16. Project the total whole body gamma dose at the EAB. I Projected dose at EAS = (step 10) x (step 15)
=( )x( )
= Rem l l l 131 I Conientration i l l l 17. Calculate the exhaust stack "il concentration.
l a) RIS-73437-1 concentration = (step 4e) x (step 4f) l
=( )x( )
= uCi/cc l b) If RIS-73437-1 is off-scale high or if a readout is not l available due to power loss, etc., record the stack l '
concentration as obtained from RT-4802, located on level .. 1 11 of the Turbine Building adjacent to the reactor plant l l exhaust stact (Refer to HPP-13 for instructions). l Local Indicated Concentration = pCi/cc l l l 131I and Total Radiciodine Release Rate l 1 l l 18. - Calculate the source term Q ("2I release rate). l Q = (step 18) x (step 4j) x (1 E-6 C1/vCi)
=( )x( ) x (1 E-6)
= Ci/sec ._
PORM 372 3843 __ _. ,- - - - -m . w,a
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION k!orkshict 1 Issue 6 Page 7 of 10 l 19. Calculate Q. for total radioicdine release. l QT = (step 18) x (1.05 E + 2)*
=( ) x (1.05 E + 2)*
= Ci/sec
- Ratic of total radiciodines to 1'2! in design inventory.
I I l Classification of Event l l l General Emeroency Determination i 20. Determine the thyroid dose rate at the EAB. l Dose Rate = (step 19) x (5.3 E+4 Rem / hour) x (step 9) l ( Ci/m3 ) I =( ) x (5.3 E+4) x ( )
= Rem / hour If the resulting dose rate at the EAB is 2: 5 Rem / hour, the classification of the event is GENERAL EMERGENCY. Infom the Shift Supervisor of the General Emergency Condition. Then go l directly to Step 23 of this attacnment.
Site Area Emeroency Determination l 21. Criteria for Site Area Emergency: If Step 17 is greater than or equal to 6.7 E-5 pCi/cc, the classification of the event is SITE l AREA EMERGENCY. Inform the Shift Supervisor of the Site Area l , Emergency Condition. Then go directly to Step 23 of this attacnment. Radiological Alert Determination l 22. Criteria for Radiological Alert: If Step 17 is greater than or l equal to 7.0 E-8 pCi/cc (ten times the Technical Specification l limit), the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. l Then proceed with Step 23. l l l FORM 372 22 3843
'. PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION llorkshtet 1 Issue 6 Page 8 of 10 l
l l l Curies of Radiciodine Released l l 1 l 1 l 23. Calculate the curies of radiciodine released to present time. l l Curies Released = (step 19) x (step 3) x (3.6 E+3 sec/hr)
=( )x( ) x (3.6 E*3)
= curies l l l Accumulated Thyroid Dose at EAB l l l l 24. Calculate the dose received at the EAB.
l Dose = (step 20) 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 l 1 l l 25. -' If the release is continuing, consult with the Shift Supervisor and estimate tne total number of hours the release will continue l (i.e., from beginning to end). Use two hours if no better l estimate is available. If the release has terminated, enter value from step 3. Preliminary estimate of release hours hours. FORM 3M- 22 3bu
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN MUCLEAR GENERATING STATION Ucrksheet. 1 Issue 6 Page 9 of 10 1
)
1 l 26. Project the total thyroid dose at the EAB. l l Projected Dose at EAB = (step 20) x (step 25)
=( )x( )
= Rem l 27. Determine the recommended protective action for the general l population based on the results of steps 16 and 26. (Refer to l RERP-PAG.)
l 28. The whole body gamma dose rate at the EAB is (step 11): Rem / hour l 29. The classification of the event based on noble I gases is (step 10 g step 11 g step 12): l 30. The noble gas release rate is (step 8): Ci/sec i 31. The accumulated whole body gamma dose at the EAB l is (step 14): Rem l 32. The total number of curies of noble gas release l to the present time is (step 13): Curies l 33. The projected whole body gamma dose at the EAB is l (step 16): Rem l Based on projected release duration of (step 15): hours l 34. The thyroid dose rate at the EAB is (step 20): Rem / hour I i 1
- - - 1 FORM 372 - 22 + 3843 l
r a PUBLIC SERVICE COMPANY OF COLORADO RERP-DOS: 1 FORT ST. VR AIN NUCLEAR GENERATING STATION Worksh:et 1 l Issue 6 Page 10 of 10 l 35. The classification of the event based on radio-1 iodines is (step 20 g step 21 g step 22):
- l 36. The radiciodine release rate is (step 19): C1/sec l 37. The accumulated thyroid dose at the EAB is l (step 24): Rem l 38. The total number of curies of radiciodine l released to the present time is (step 23): Curies
! 39. The projected thyroid dose at the EAB is I (step 26): Rem l Based on projected release duration of (step 25): hours
*If this classification differs from the classification in step l 29, the higher (i.e., more severe) classification is to be used l to determine recommended protective actions.
4 1 l i PORW 372 - 22 3843
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PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE l
- FORT ST. VRAIN NUCLEAR GENERATING S ATION Ucrksheet 2 l 1ssue 6 Page 1 of 6 l
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 g 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. Cn' lect 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 (STO 11) d) Maximum CPM, RIS-7324-1: cpm (RR-93539, red pen) (STO 03) e) Sensitivity RIS-7324-1: uCi/cc/com (I-14,403-P7) (STO 04) f) Maximum CPM, RIS-7324-2: cpm (RR-93539, blue pen) (STO 05) g) Sensitivity. RIS-7324-2: uC1/ce/ cpm (I-14,203-P7) (STO 06) i l POmM 372 22- 3843 l
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE rORT ST. VR AIN 12UCLEAR GENER ATING STATION Worksheet 2 1ssue 6 l Page 2 of 6 l
*h) Maximum mR/hr, Cutie Pie-2520 Probe: mR/hr (ST0 01)
*i) Maximum mR/hr, E-500-GM Prebe mR/hr j (STO 02) j) Maximum CPM / MIN, RIS-73437-1: cpm / min (STO 07) I 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: pCi/cc/ cpm / min I (STO 08)
- 1) Site Emergency Limit (as posted): 1) 6.6E-2 pC1/cc noble gas
~~~
- 2) 6.7E-5 pCi/cc 282I m) Ten Times Technical Specification l Limits (as posted): 1) 2.5E-2 pCi/cc noble gas
- 2) 7.0E-8 uti/cc 282I 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 (60m Tower) Steps lh) and li) used only if RIS-7324-1 or RIS-7324-2 off-scale high.
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PUBLIC SERVICE COMPANY OF COLOR ADO RERP-COSE FORT ST. VRAIN NUCLEAR GENERATING STATION Uorksneet 2 Zssue 6 Page 3 of 6 I r) ce = From Data Logger, or square root of l 1 (maximum fluctuation in wind direction ' I over period of 15 minutes to cne hour). l (OPTIONAL CALCULATION) I
- 2. Determine Stability Category using l Table 1 and Steps Iq) or 1r).
Stability Category
- 3. Determine potentially affected sectors l within 5 mile EPZ from Table 2 and using l Steps Ip) and 2. (See Site Sector Map, I Figure 2.)
Sectors
- 4. Determine the EAB dilution factor from 1 Attachment 1, Table 1A, using the l Stability Category (Step 2) and wind speed (Step lo).
Dilution Factor sec/m8 (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 l beginning to end). Use two hours if no better l estimate is available. If the release has terminated, enter value from step Ic).
Preliminary estimate of release hours hours. (STO 12)
- 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." l PORM 3M
- 22 3&O i
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR . GENERATING STATION Worksheet 2 l Issue 6 Page 4 of 6 l l l l \ f) Read magnetic card into TI-59. I
- 1) Depress 111 , [INVl , [2ndl , l WRITE l keys.
- 2) Insert magnetic card into right side of TI-59. I Card should be right side up with the '1" in 1 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 othee magnetic card with the same title and repeat Step 6f).
- 7. Input the necessary data into the indicated TI-59 storage registers.
a) Step Ic) = l3T6l 11 b) Step Id) = l@l 03 c) Step le) = lSTOl 04 d) Step If) = 13TDI 05 e) Step Ig) = lSTOl 06 ,, f) Step 1h) = l3T6l 01 Step li) = l@l 02
' g) h) Step lj) = l3T61 07 i) Step Ik) = l3TDl 08 j) Step In) = l@l 09 k) Step 4) =
l@l 10
- 1) Step 5) =
lS10l 12 i l 1 i _ l POmM 372 22,3843
PUBLIC SERVICE COMPANY OF COLORADO RERP-DDSE FORT ST. VRAIN NUCLEAR GENERATING STATION Ucrksheet 2 Issue 6 Page 5 cf 6 l
- 8. Run Dose Assessment Program l l
a) Depress lR/Sl key. b) Wait until a number is displayed. A flashing number indicates i improper execution of the program. Depress lCLRl and lRSTl ' keys and repeat Steps 7 and 8. l 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 en 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 uCi/cc (Step 1.m)1) and s 6.6E-2 vC1/cc, RADIOLOGICAL ALERT.
c) The noble gas release rate is (RCL 18): C1/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 tne EAS is (RCL E2): Rem g) The thyroid dose rate at the EAB is (RCL 27): Rem / hour l FORM 3M 22 3be
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUOLEAR GENERATING STATION Ucrksheet 2 - Issue 6
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Page 6 of 6
*h) The classification of the event based on radiciodines is:
1 1) If Step 9g) 2 5 Rem / hour, GENERAL EMERGENCY.
- 2) If RCL 23 2 6.7E-5 pCi/cc , _. , I (Step 1.1)2),~ - r SITE AREA EMERGENCY.
- 3) If RCL 23 2 7.0E-8 pCi/cc (Sten 1.m)2) and
< 6.7E-5 vCi/cc, RADIOLOGICAL ALERT.
- 1) The radioiodine 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) The orojected 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 population based on RERP-PAG.
l *If this classification differs from the classification in Step 9b), the higher (i.e., more severe) classification is to be used to l determine recommended protective actions. FORM 3Mt. 22 3bO
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN MUCLEAR GENERATING STATION Sorksheet 3 Issue 6 Page 1 of 10 WORKSHEET 3 ASSESSMENT OF RELEASE-UNMONITCRED 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 thyrcid 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 calculation.
- 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 182I equivalent circulating inventory: C1 ' i d) Primary coolant 182I equivalent ) plateout inventory: C1 e) Primary Coolant Volume: sec f) Site Emergency Limit (as posted): 1) 6.6E-2 uCi/cc noble gas
- 2) 6.7E-5 uCi/cc282I g) Ten times Technical Specification Limits (as costed): 1) 2.5E-2 vCi/cc noble gas FORM 3Mt. 22 - 3&O
1
. , PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE l FORT ST. VRAIN NUCLEAR GENERATING STATION Ucrksheet 3 l Issue 6 l Page 2 of 10 l
- 2) 7.0E-8 pCi/cc 181I h) Average Wind Speed at 10 meters: mph
- 1) Wind Direction at 10 meters: From Degrees NOTE: North = 0 increasing degrees - c.w.
. j) Differential Temperature *F (60m Tower) l k) c0 = Data logger or square rcot of l (maximum fluctuation of wind direction over I a period of 15 minutes to one hour). l (OPTIONAL CALCULATION)
- 5. Determine Stability Category using Table 1, 1 Step 4j or 4k:
Stability Category
- 6. Determine potentially affected sectors within 5 mile EPZ using Table 2 and Steps 41
' ~
l l and 5 (see Site Sector Map, Figure 2). Sectors
- 7. Calculate the release noble gas concentration:
RIS-9301 concentration = (step 4a) x (step 4b)
=( )x( )
= uC1/cc
- 8. Calculate the source term, Q ng (n le gas release rate):
- a) Reactor Building Louvers O
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).
FORM 3M 32 3bu G
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Workshtet 3 Issue 6 Page 3 of 10 b) PCRV Safety Valves o 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
(,FSA'4, Section 6 .8). I i l Classification of Event i I I
- 9. Determine weighted noble gas dose conversion factor from Table 3: 7.5E+2 Rem / hour C1/m*
- 10. Determine the EAB atmospheric dilution factor l from Attachment 1, Table 1A, using Steps 5 and 4h: - - -
Dilution Factor sec/m' General Emergency Determination
- 11. Determine the whole body dose rate at the EAB:
a) Reactor Building Letre es Dose Rate = (step Ba) x (step 9) x (stop 10)
=( )x( )x( *
)
= Rem / hour b ', PCRV Safety Valves Dose Rate = (step 8b) (step 9) x (step 10)
=( )x( )x( )
= Rem / hour PORM 372 - 22 3M3
-- w-- "" - ' '--- "-'
F
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION E!orksheet 3 Issue 6 Page 4 of 10
- 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.
Site Area Emercency 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.
' adiological Alert Determination R
l 14. If Step 8a. or 8b. is greater than or equal to 3.7 E-1 Ci/sec l (ten times the Technical Specification limit), the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 15.
~
l l l Curies of Noble Gas Released l l 1
- 15. Calculate the curies of noble gas released to present time.
a) Reactor Building Louvers l Curies Released = (step 8a) x (step 3) x (3.6 E+3 sec/hr)
=( )x( ) x (3.6 E+3)
= Curies
- b) PCRV Safety Valves Curies Released = (step 8b) x'(step 3) x (3.6 E +3) 1
=( )x( ) x (3.G E +3)
= Curies l
l i PORM 3Mt. 22 3bu
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Uorksheet 3
, Issue 6 Page 5 of 10 I I l Accumulated Whole Body Gamma Dose at EAB l l 1
- 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.
I I l Projections l l l
- 17. If the release is continuing, corsult with the Shift Supervisor and estimate the total number of hours the release will continue l (i.e., from beginning to end). Use two hours if a more l reasonable es'imate is not available. 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 Projected Dose at EAB = (step 11a) x (step 17)
=( )x( )
= Rem PORM 372 22 3843
~ '
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST VRAIN NUOLEAR GENERATING STATION Morksheet 3 1ssue 6 Page 6 of 10 b) PCRV Safety Valves Projected Dose at EAB = (step lib) x (step 17)
=( )x( )
= Rem
- 19. Calculate the release 2811 equivalent concentration (Reactor Building Louvers or PCRV Safety Valves).
222! Equivalent Concentration = (step 4c) + (step Ad) x (5.7 E-3) * (step 4e)
=( )+ ( ) x (5.7 E-3) +( )
= Ci/cc
*"* Amount of plateout 122I equivalent released (FSAR, Section 14.11.2.7.1).
- 20. Calculate the source term, Q (18II equivalent release rate).
a) . Reactor Building Louvers l Q = (step 19) x (5.8 E+7 cc/sec)
=( ) x (5.8 E+7)
= Cf/sec b) PCRV Safety Valves l Q = (step 19) x (1.9 E+7 cc/sec)
=( ) x (1.9 E+7)
= Ci/sec I l l Classification of Event i I I
- 21. Dete rmine l'2I dose conversion factor from Table 3. 1.2E+6 Rem / hour Ci/m 3 PORM 2n. 22 MW3
- ~ ~ . - -
- - . ~ ,
. . PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLE AR GENERATING STATION Uorksheet 3 Issue 6 Page 7 of 10
- 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 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 of this. attachment. Site Area Emeroency Determination
- 24. If Step 20a. or 20b. is greater than or equal to 9.8E-4 Ct/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.
Radiolocical Alert Determination . I 25. If Step 19 is greater than or equal to 1.0 E-7 Ci/sec (ten times , l the Technical Specification limit), the classification of the event is RADIOLOGICAL ALERT. Inform the Shift Supervisor of the Radiological Alert Condition. Then proceed with Step 26. FORM 372. Mt . 3SMI
, m---,-.
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 3 1ssue 6 Page 8 of 10 l l l 1 1 I Curies of ***I Equivalent Released l , I I l
- 26. Calculate the curies of ***I equivalent released to present time.
a) Reactor Building Louvers l Curies Released = (step 20a') x (step 3) x (3.6 E+3 sec/hr)
=( )x( ) x (3.6 E+3)
= Curies b) PCRV Safety Valves Curies Released = (step 206) x (step 3) x (3.6 E +3)
=( )x( ) x (3.6 E +3)
= Curtes
! l l Accumu:ated Thyroid Dase at EAB l I
- 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( )
= Rem NOTE: This calculation assumes the recipient was at the EAB for tne entire duration of the release.
'~'
pomu ara.22.au l l
^
l
PUBLIC SERVICE COMPANY OF COLORADO RERP-DDSE FORT ST. VR AIN NUOLEAR GENERATING STATION dorksheet 3 1ssue 6 , Page 9 of 10 l i l l l Projections l l l
- 28. If the release is continuirg, consult with the Shift Supervisor and estimate the total number of hours the release will continue l (i.e., from beginning to end). Use two hours if a more l reasonable estimate is not available. 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 Butiding Louvers Projected Dose at EAB = (step 22a) x (step 28)
=( )x( )
= Rem b) PCRV Safety Valves Projected Dose at EAB = (step 225) x (step 28)
=( )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.
~
l l l Summary I 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 or Step 13 l or Step 14): ,
l
- 33. The noble gas release rate is (Step Sa or 8b): Ci/sec l
FORM 3M 300
,...a,..,
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE , FORT ST. VRAIN NUOLEAR GENERATING STATION t!orksheet 3 I lssue 6 Page 10 of 10
- 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. *Ths classification of the event based on 181I equivalent is (Step 23 g Step 24 g Step 25):
- 40. The 1811 equivalent release rate is (Step 20a or 20b): C1/sec
- 41. The accumulated thyroid dose at the EAB is (Step 27a or 27b): Rem
- 42. The total number of curies of 182I 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 Based on projected release duration of (Step 28): hours l *If this classification differs from the classification in Step l 32, the higher (i.e., more severe) classification is to be used to determine recommended protective action.
I l
\
PORM 372 22 3843 i
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VR AIN NUCLEAR GENER ATING STATION Worksheet 4 l Issue 6 Page 1 of 6 ) WORKSHEET 4 1 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 s used, use Worksheet 3. 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: 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-33256, Pt.10) (STO 01) e) Sensitivity RIS-9301: vCi/cc/ cpm (STO 02) l f) Primary Coolant 182I equivalent Ci circulating inventory: (posted) (STO 03) g) Primary Coolant 182 equivalent Ci plateout inventory: (posted) (STO 04) h) Primary Coolant Volume: (posted) cc (STO 05)
- ~ - -
~ . . -
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VR AIN NUCLEAR GENERATING STATION t!orksh12t 4 Issue 6 Page 2 of 6 i) Site Emergency Limit: (posted)1) 6.6E-2 uCi/cc noble gas
- 2) 6.7E-5 vCi/cc 1'2I j) Ten Times Technical Specification Limits (posted):
- 1) 2.5E-2 vC1/cc noble gas
- 2) 7.0E-B uCi/cc **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 (60m Tower) l n) c0 = From Data Logger, or square root of l (maximum fluctuation in wind direction l over period of 15 minutes to one hour). 1 (OPTIONAL CALCULATION)
- 2. Determine Stability Category using l Table 1 and Steps 1.m) and 1.n).
Stability Category
- 3. Determine potentially affected sectors I within 5 mile EPZ using Table 2 and Steps l 11) and 2 (see Figure 2, Site Sector Map).
Sectors
- 4. Determine the EAB dilution factor from Attachment I using the Stability l Category (Step 2) and wind speed (Step ik).
Dilution Factor sec/m2 (STO 06) l l PORM 3t2 22- 360 l
PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VR AIN NUCLEAR GENERATING STATION dorksheet 4 , Issue 6 l Page 3 of 6 1
- 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 l beginning to end). Use two hours if a more I reasonable estimate is not available. If the release has terminated, 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 yLd 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 l1l ,lMl ,lEl,lWRITElkeys.
- 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) Depressl)) ,IMI,l@l , lWRITEl 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 l properly. Obtain the other magnetic card with the same title and repeat Step 6f).
l -... .--- - . . . conu sn . 22. aus
PUBLIC SERVICE COMPANY OF COLOR ADO RERP-DOSE FORT ST. VR AIN NUCLEAR GENERATING STATION Ldorksheet 4 Issue 6 Page 4 of 6 l l
- 7. Input the necessary data into the indicated TI-59 storage registers.
a) Step Ic) = lST0] 07 b) Step Id) = l@l 01 c) Step le) = l3T61 02 d) Step If) = l5T6l 03 e) Step ig) = l@l 04 f) Step lb) = lST0l 05 g) Step 4 = lST6l 06 h) Step 5 = l@l 08 .
- 8. Run Dose Assessment Program.
a) Depress lRLSl key. b) Wait until a number is displayed. A flashing number indicates improper execution of the program. Depress lCLR] and l E l keys and repeat Steps 7 and 8. POMM 372 22 3843 i
l
. 1 PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE 1 FORT ST. VR AIN NUOLEAR GENERATING STATION Workshoet 4 )
Issue 6 l Page 5 of 6 l
SUMMARY
l
- 9. a) The release path is:
- 1) Reactor Building Louvers
- 2) PCRV Reliefs b) Tne 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 IOb) 2 1 Rem / hour, GENERAL EMERGENCY.
- 2) If Step 10c) 2 9.6E-1 C1/see SITE AREA EMERGENCY.
- 3) If Step 10c) 2 3.7E-1 C1/see ~~
and s 9.6E-1 Ci/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 (RCL 14 for louvers, RCL 15 for reliefs): _Ci g) The projected whole body gamma dose at tne EAB is (RCL 18 for louvers, RCL 19 for. reliefs): Rem Based on a projected release duration of (RCL 08): hours
. l PORM 3M 22 Shu I
RERP-DOSE PUZLIC SERVICE COMPANY OF COLORADO Worksheet 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 6 of 6 h) The thyroid dose rate at the EAB is (RCL 24 for louvers, RCL 25 for reliefs): Rem / hour i i) The 181I equivalent release rate is (RCL 22 for louvers, RCL 23 for reliefs): Ci/sec "j) The classification of the event based on 281I equivalent is:
- 1) If Step 10h) 2 5 Rem / hour, '
GENERAL EV.ERGENCY. -
- 2) If Step 101) 2 9.8E-4C C1/sec SITE AREA EMERGENCY
- 3) If Step 101) 2 1.0E-7 C1/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 The total number of curies of ***I 1) equivalent released to the present time is (RCL 26 for louvers, RCL 27 for reliefs): Ci m) The arojected thyr::id dass at the CAD is (ILL 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.
l l *If this classification differs from the classification in Step 9c), l the higher (i.e., more severe) classification is to be used to determine recommended protective actions. l PORM 372 22 3443
I
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"U RADIOLOGICAL ELIERG RESPONSE PLAN E 0944 h a o ,, c STEP 2e VERIFY AND/BR MANUALLY ENTER THE FOLLOWING STANDARD DATA: ?>
-4 RADIATIO.4 MONITORS SENSITIVITY: (FROM I-14) m (h
-4 m i
RIS-7324-1 .........................( ) E( ) UCI/CC/ CPM
'< <27 RIS-7324-2 .........................( ) E( ) UCI/CC/ CPM {g RIS-73437-8 ............... ~........( ) Et ) UCI/CC/ CPM /M Z m RIS-9301 .......................e..'.(. ,) E( ) UCI/CC/ CPM g.) ,
gO LIMITS: (VERIFY) , , . . SITE EMERGENCY NOBLE GAS - - '
. . . ,1, - 6.-[g.~ hI
.[6c . . . . ... (~2) UCI/CC $
SITE EMERGENCY I-131 .. .s .........'.P.t(CS. o
. K E.(-53-UC1/CC m z 10 TIMES TECH SPEC NBBLE ' GAS~ .. <. v. . es.vn. s3J 15 -<
.a f.'.u .:.-):f: E.- f.-2 5 UCI/CC x 10 TIMES TECH SPEC I-ISI . - . . . . . . . a,e...r.:: y. 7:0)-E.(-8) UCI/CC >
, y: >. 2O gm DOSE CONVERSION FACTORS i f .;.91.j U ;- ,
I WEIGHTED NOBLE GAS ...........',... ..(fJ,5L E,(+2) REM /HR/CI/M3 ya WEIGHTED IBDINE FOR MONIT.15 .-RED
.> 5(EL.
E4SK('. 5,3) E.1+4) REN/HR/CI/M3
- a. .
PO
-4 I-ISI FOR UNMONITORED RELEASE ...... ( l. 2 ) E (+6) REN/HR/CI/M3 @O r-DISTANCES SELECTED FOR DOSE CALCU.L.ATISNS ANY. NUMBER FROM 0.1 TO 60.0 f I ( .367) 2( l.0) 3( 2.0) 4 ( 2.5) 5( 3.0) O i 6 ( 5.0) 7 ( 6.0) 8( 7.0) 9 ( 8.5) 10 ( 10.0) O lI ( 12.0) 12 ( 15.0) 13 ( 17.0) 14 ( 20.0) 15 ( 2S.0) mens (D C 07 7 i
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,18:24:IS 06/26/84 RADIOLOGICAL EMERG RESPONSE PLAN E 0951 h E D m C 1
STEP 4: ENTER THE NETEROLOGICAL DATA: OO ! WIND SPEED ELEVATION SELECTION 15 MIN AVE to CI) ENTER SELECTED ELEVATION ( ) METERS AND AVERAGE C ) MPH 'am
< :D XST-93tO8 60 METER TBWER 10.0 NETERS PRIMARY ,
g g< , XST-93101 10 METER TSWER 10.0 METEfts.lST ALT zm XST-93IOS 60 METER T9WER ~S8.011ETER$ 2ND ALT . g NO INST # TBP RX BLDG 55.8 NETER4 3Rb' ALT' (FRON CHART ON I-13) ;;; O WINO DIRECTION . : i, ,
.,j[.;.I HIN' AVE DEVIATION ENTER AVERAGE AND DEVIATIEN FROM AVERhGE }f;l: . ] . .. ( . ) ( ) g2 XT-93109 60 HETER TOWER .
E 4 XT-93IO2 10 HETER TOWER' -
' ~.I O.O.'. METER 5.* Phli1AN[('
'IO.0.METERN-o'iSY.'hlbT.
f .w 1 <
$O zn j XT-93107 58.0.NETERS 2 o l
60 RX NS INST lt TBP HETER BLDG TOWER , j5.EiIM5TER(,h.ypALT n; _; fy.. < RQ'hY
.,u,- T (FRBM CHART ON I-IS) fy O l DIFFERENTIAL TEMPERATURE UPPER-LOWER.' . 15 MIN AVE @O ENTER THE UPPER TB L9WER ( ) METERS AND AVERAGE ( ) DEG F f TT-93flO-2 60 NETER TOWER 48.5 METERS PRIMARY O l
NO INST 18 TOP RX BLDG 42.7 NETERS IST ALT (FROM CHART ON I-13) NOTE: SELECT THE WIND SPEED AND WIND DIRECTION INSTRUMENTS FRBM o .-. o :o THE SAME TOWER'AND ELEVATION. $$%E
*8 ?
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'I
o e, a u W T t C to r-MONITORED RELEASE MANUAL ENTRY E D942 PAGE I 3o N O A m STEP SAs MANUALLY ENTER THIS PAGE ............ ENTER l ( 1) TYPE 4m DATE AND TIMES: ( MM/ DD/ YY) ( HH MM) j BEGINNING OF RELEASE ...DATE ( / / ) TIME ( : ) EO ENDING OF RELEASE ......DATE ( / / ) TIME ( : )
' zm 2
CURRENT DATE AND TIME ..DATE ( / / ) TIME ( ) EO O MONITORED RADIATION LEVELS: hg RIS-7324-1 (RR-93539 PT # I) . . . . . . . - ( , ) E( ) MAXIMUM CPM %
- sz RIS-7324-2 (RR-93539 PT # 43 . . . . . . ..-(' . .) E ( ) MAXIMUM CPM $
$0 zn RIS-73437-1 (RR-73437 BLUE. PEN) . ENTER,0N SEPARATE PAGE (LATER) o
~ un PROBE READING BY HEALTH PHYSICS .... C. ) E( ) MR/HR y PROBE TYPE: (ENTER D IF NOT USED)'............( . ) TYPE yZ g ENTER I FOR E-500 WITH GM PROBE :n i
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@O ENTER THE FIVE READINGS FROM RR-73437 (GLUE PEN) "; (n
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- f. CD RADIOLOGICAL EMERG RESPONSE PLAN E 0944 ,, r-E D gO STEP 2: VERIFY AND/OR MANUALLY ENTER THE FOLLOWING STANDARD DATA: " (f3 RADIATIBH MONITORS SENSITIVITY: (FROM I-14) $
RIS-7324-1 .........................( 3E( ) UCI/CC/ CPM $$
>o RIS-7324-2 .........................( ) EC ) UCI/CC/ CPM Em RIS-73437-8 .............5.........(- ) Et ) UCI/CC/CPt1/ M g RIS-930I .......................;...T' '
.) E( ) UCI/CC/ CPM Po LIMITS: (VERIFY) ., "i,.,'.J.'".<.,..
h5 SITE EMERGENCY :. NOBLE GAS .... . . . . .-[5Tlk BEG .'.'(-*2 N. w.a 7 UCI/CC o3 m
$z<
SITE EMERGENCY I-131 . . g . . ; . . . . . . ,.Y. . . . : ..,0? ts.19Q ).. E . (-5.3 UCI/CC 10 TIMES TECH SPEC NOBLE' GAS . .;.<y . . ; [6 s ; 10 TIMES TECII SPEC I~-l31
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,16:24:l3 06/26/84 RADIOLOGICAL ENERG RESPONSE PLAN E 0951 ,C E D ga STEP 4: ENTER THE METER 0 LOGICAL DATA: (/)
WIND SPEED ELEVATION SELECTION IS HIN AVE -)$ ENTER SELECTED ELEVATION ( ) METERS AND AVERAGE ( ) MPH $b
*o XST-93108 60 METER TOWER 10.0 METERS PRIMANY Em XST-93101 ID METER TOWER 10.0 METERS I,ST ALT $g XST-93106 60 METER TOWER '69.0 METERi1 dNifALf.' hO
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.R.g.gT(FROMCHARTONI-IS) g DIFFERENTIAL TEt1PERATURE UPPER-LOVER." 15 MIN AVE y ENTER THE UPPER TB LOWER ( )ME;TERS. AND AVERAGE ( ) DEG F -
O TT-93I10-2 60 METER TOWER 48.5 METkRS PRIMARY NB INST 11 TOP RX BLDG 42.7 METERS IST ALT (FROM CHART BH I-13) NOTE: SELECT THE WIND SPEED AND WIND DIRECTION INSTRUMENTS FROM $$%9 THE SAME TOWER AND ELEVATION. E O, nm M to
5 o, 3 b T UNMBNITORED RELEASE MANUAL ENTRY E 0943 C (D E D ,c STEP 38: MANUALLY ENTER THIS PAGE ............ ENTER 2 ( ) TYPE @O DATE AND TIMES: . ( MM/ DDI YY) ( HHs MM) N (/) BEGINNING BF RELEASE ....DATE C / / ) TIME ( : ) - n ENDING OF UNMON RELEASE..DATE ( / / ) TIME ( : ) 55 1 o CURRENT DATE AND TIME ...DATE ( / / ) TIME ( : ) 2m NONITBRED RADIATION LEVELS: g RIS-93DI (RR-93256 PT 88 10) ........i ( ) E( ) MAXIMUM CPM t- O PLANT CONDITIONS:
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) PSIA $O REACTOR PRESSURE AFTER RELEASE ,........... ( ) PSIA hO :D
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ENTER 3 IF RELEASE IS THRU LBUVERS AND SAFETYS 3N%9
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PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE FORT ST. VRAIN NUCLEAR GENERATING STATION Checklist 1 Issue 6 Page 1 of 2 Checklist 1 - Data Logger Monitored Release l 1. Collect data for calculation, using copies i of Datasheet 1 as required for instrument l sensitivities, meteorological data, and l radiation monitor readings. I l 2. Access the dose assesseent menu via demand l function 41 or screen 941. l l 3. Before performing calculations, initialize l the summing screen by going to step 1 on l the menu, entering option 4, returning to l the menu and submitting DF-41-0-0. l l NOTE: Option 2 must be used when performing calculations for l record keeping or dose reporting purposes. This l - automatically resets to option 1 every time DF-41-0-0 is l run, and must be set to ootton 2 for each calculation. l 4. Following the screens on the menu, perform l a " duration of release" calculation. To l accomplish this, enter the release start l date and time, the current time, and the l projected or estimated end of release l time. Use two hours from current as a l default value whenever this value isn't l known. I l 5.. After entering all data and returning to l the menu, submit OF-41-0-0. l l 6. Print all screens used for input and l results. Screens that should be printed ( l are: 944, 942, 948, 951, 945, and 947. l l l l e , qpg POrtM 372 22 3843
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. _.RERP-DOSE PUZLIC SERVICE COMPANY OF COLORADO Chscklist 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 2 of 2 l 7. Perform a " puff" calculation. To do this, l change the release start time to the I current time, and resubmit DF-41-0-0. Be l sure that option = 2.
I l 8. Print screens used for input and results. l Screens that should be printed are: 944 l and 942. I l 9. Set option to 3, and resubmit DF-41-0-0 to i total the results. l l 10. Print screen 949, which displays total l results. l l-11. Complete applicable sections of l datasheet 3, and transmit information to ~ l Radiological Assessment Coordinator at the l FCP. l l 12. Discuss results of assessment with senior l Health Physics representative for use in l dispatching monitoring teams, etc. l l 13. Transmit prints of result screens to TSC l Direc, tor for use in completing fact sheet. I I l l l l l PORM 372 22 3843 y, _ , . . . _ _ _ _ . _ , . _ , . . - , _ _ - _ . . . _ _ _ , _ _ , - _ _ , - _ . _ _ _ - . _ _ , .%. ,-.c-_
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PUBLIC SERVICE COMPANY OF COLORADO RERP-DDSE FORT ST. VRAIN NUCLEAR GENERATING STATION t/S/DS/CL Issue 6 Page 1 of 3 Work /Datasheet/ Checklist Control List Worksheet No. Title Number Cooies 1 Monitored Release Calculations 5 (Manual) 2 Monitored Release Calculations 10 (TI-59) 3 Unmonitored Release Calculations 2 (Manual) 4 Unmonitored Release Calculations 2 (TI-59) Datasheet No. 1 Data Logger (or IBM) Monitored Release 20 2 Data Logger (or IBM) Unmonitored Release 2 3 Status Board Update Sheets 20 Checklist No. 1 Data Logger-Monitored Release 20 l l l l l l l PORM 372 22 3843 _, -y . . . , . _ , _ , - _ . _ . _ . . - - - , _ . . _ . _ _ _ , . _ _ _ . -
r PUBLIC SERVICE COMPANY OF COLORADO RERP-DOSE l FORT ST. VRAIN NUOLEAR GENERATING STATION WS/DS/CL l Issue 6 Page 2 of 3 I l FORMS USE REPORTING SHEET l Nuclear Documents Specialist: This sheet is being transmitted to report use of forms frem a controlled copy of the Radiological Emergency Response Plan Implementing Procecures, BOOK NO. , located at
. Tha following forms nave oeen utilized from this copy:
Worksheet Numbers Cooies Used Datasheet Numbers Cooies Used Checklist Numbers Cootes Used . 1 The procedure affected by this snee: 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 ncted number of forms, as well as this "Fo rms Use Reporting Sheet" for the affected procedure in the affected book. , l PORM 3M . 22 3hu
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PUTLIC SERVICE COMPANY OF COLORADO RERP-DOSE l FORT ST. VRAIN NUCLEAR GENER ATING STATION WS/DS/CL
\- Issue 6 Page 3 of 3 FORMS USE REPORTING SHEET (Continued)
COMMENTS Reported By: Date: _ l Nuclear Docuzents Specialist
- Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the originating-individual / department upon completten 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 1 l PORM 373 22
- 3543
, PUBLIC SERVICE COMPANY OF COLORADO BOOK 3 FORT ST. VRAIN NUCLEAR GENERATING STATION t
RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATION ISSUE EFFECTIVE j NO. SUBJECT NUMBER DATE I RERP-TSC Technical Support Center Procedure 13 08-06-84 RERP CR-UE DELETED 04-25,-84 RERP-VC Visitors Center Procedure 3 01-03-84 l RERP-PHONE LISTS 24 08-06-84
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l l l l POMM 372 22 3643 l
RERP-TSC PUBLIC SERVICE COMPANY OF COLORADO 1ssue 13 FORT ST. VRAIN NUCLEAR GENERATING STATION page 1 of 12 e rGi;T GT. Vi!!JK TITLE: TECHNICAL SUPPORT CENTER PROCEDURE f!0N - CONTPOU.c0 CO?y VERjFYi3 SUE STATUS WITH DOCUVENT CENTER ISSUANCE /2, Lde*
- b-') D FRIOR TO USE AUTHORIZED FORM 372 22 3M' BY W M. WMA.
PORC EFFECTIVE EORc 5 8 0 AUG 2 - 1984 REVIEW DATE h- b b TABLE OF CONTENTS Section Description Page 1.0 Cri te ri a f or Imol ementa ti o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Procedure..................................................... 3 3.0 Re s po n s i b i l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 4.0 References..................................................11 5.0 Referenced or Suocorting Procedures.......................... 11 Figure 1 Site Sector Map......................................... 1
, Figure 2 EAB Map................................................. 1 Figure 3 Response Center Manning Requirements ........ .......... 1 Attachment 1 Support Equipment / Material........................... 1 Datasheet 1 Assessment Fact Sheet - TSC Director.. .............. 1 Datasheet 2 Assessment of Plant / Core Status ..................... 1 Checklist 1 TSC Director Check List ............................. 1 Work /Datasheet/ Checklist Control List . ........................... 1 1
h FORM 372 22 3442 l l
PUBLIC SERVICE COMPANY OF COLORADO Tj FORT ST VRAIN NUCLEAR GENERATING STATION Page 2 of 12 4 Fo rm s U s e Repo rti ng S hee t" . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ANYTIME A WORKSHEET, DATASHEET. OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE FROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE. F O R M 372 - 22 3643
PUBLIC SERVICE CCMPANY OF CO.LORADO u 4 ^ FORT ST. VR AIN NUCLEAR GENER ATING STATION Page 3 of 12 1.0 Criteria for Implementation When the FSV Radiological Emergency Response Plan (RERP) requires augmentation of resources, generally for an ALERT or higher emergency classification, the Technical Support Center (TSC) Director shall activate the TSC. l 2.0 Procedure The TSC serves as the center for site emergency command activities and provides a central location for technical appraisal of plant conditions. The TSC operates under the direction of the Technical Support Center Director, and also serves as the focal point for onsite-offsite communications. 2.1 Personnel Activation During non-working hours, those PSC personnel required to ; man the TSC are notified by telephone (see RERP-HOME). It is the responsiblity of the TSC Alternate Director, or the first individual contacted by the center director, to insure those notifications are made. Refer to the RERP PHONE LIST for instructions and personnel names and numbers. 2.2 Communications Establish communication with the Control Room and verify primary and secondary communication links are available. Await communications to be established by the Personnel Control Center (PCC) and by the Forward Command Post (FCP). 2.3 Initial Responses 2.3.1 TSC Director (Checklist 1) The TSC Director assumes overall responsibility for the coordination and direction of onsite emergency response centers. Based upon the preliminary assessments provided by the TSC Staff, the TSC Director completes the
" Assessment Fact Sheet" (Datasheet 1) in preparation for transmission of information to the Forward Command Post (FCP).
In addition, the TSC Director shall brief his staff to inform them of general plant conditions and inform personnel of any particular assignments of responsiblity. F O R M 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO
. FORT ST. VR AIN NUCLE AR GENERATING STATION Page 4 of 12 l I
l 2.3.2 Off-Duty Shift Supervisor I l On an as-required basis, the off-duty Shift l Supervisor will make a preliminary assessment of the plant status, focusing on significant plant problems and trends. l If requested, he will also make a preliminary I assessment of the sequence of events that led to l the emergency, and report his findings to the TSC Director. 2.3.3 Technical Services Engineering Supervisor / Senior Plant Engineer The Technical Services Engineering Supervisor / Senior Plant Engineer performs a preliminary assessment of the plant / core status by completing " Assessment of Plant / Core Status" l (Datasheet 2). He also verifies the data logger information and receives a briefing on the assessment form that the Technical Advisor in the Control Room has completed. With the concurrence of the CR Director, he obtains the " Alarm Typer" printout, if required. An alternative to the Alarm Typer printout is to utilize the " EVENTS LOG" on the 2 on I console. 2.3.4 Superintendent of Maintenance / Maintenance l Supervisor - Electrical The Su'perintendent of Maintenance / Maintenance l Supervisor - Electrical advises for the necessity of performing repair work on damaged mechanical and electrical equipment, estimates time and manpower requirements for emergency repairs, and develops emergency repair work procedures as required. l 2.3.5 Superintendent of Nuclear Betterment l Engineering /Results Engineering Supervisor l The Superintendent of Nuclear Betterment l Engineering /Results Engineering Supervisor advises for the necessity for repair / installation / modification of instrument and control equipment. 1 FORM 372 22 3643 i l
RERP-TSC PUBLIC SERVICE COMPANY OF COLORADO Issue lo FORT ST. VRAIN NUCLEAR GENERATING STATION page 5 of 12 a l 2.3.6 TSC Radiological Assessment (Senior Plant i Engineer /Tecnnical Services Engineer) l The Radiological Assessment Individual performs offsite dose projection calculations on an as l needed basis (approximately every 30 minutes) and provides the results of these calculations to the TSC Director and the Radiological Assessment Coordinator (at the FCP). He will also confer with the Radiological Assessment Coordinator with regard to plant status and protective action recommendations. In addition, he will relay offsite dose projections to the senior Health Physics representative at the TSC, as requested, for use in directing field monitoring teams. 2.3.7 Health Physics Supervisor / Health Physicist (Senior Health Physics representative) a) Directs Health Physics / Radiochemistry to remove charcoal cartridges and analyze for the I-131 release, if necessary. b) Obtains airborne contamination and radiation surveys in the Control Room, and informs the TSC Director of the results. c) Ensures personnel dosimetry is distributed and emergency worker exposure criteria is followed (see RERP-EXP). d) Evaluates doses of personnel from inhalation of radiciodines (projected or received) and confers with tiie Radiological Assessment Coordinator with regard to the need for administration of Thyroid Blocking Agent (see RERP-THYRDID). Directs any such administration authorization through the PCC Director and station Health Physice staff. FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-TSC Issue 13 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 12 l 2.3.8 Nuclear Documents Supervisor / Nuclear Documents l Specialist l The Nuclear Documents Supervisor / Nuclear Documents l Specialist provides technical documents, as required, assures that TSC personnel have obtained necessary documents and supplies for performance of their eme rg er.cy assignments, and assists the TSC Director in transmission of information to other emergency response centers. I 2.3.9 Ser.ior Computer Analyst / Senior Programmer I a) The Senior Computer Analyst / Senior Programmer will assist in software / hardware problems as directed by the TSC Director, and arrange for offsite advice / assistance as directed by the TSC Director in the area of software / hardware problems. I b) The Senior Computer Analyst / Senior Programmer will also provide assistance on an as-needed, as available basis to the TSC Radiological Assessment individual in the tasks of data collection and/or data entry to the offsite dose calculation programs (RERP-DDSE). 2.4 Follow-up Responses 2.4.1 TSC Director As soon as the Personnel Control Center has been activated and communications established, the TSC Director will: a) Inform the PCC Director of the preliminary assessment of the emergency. b) Direct the PCC Director to organize repair and damage control teams, radiological survey teams, or search and rescue teams (as required), c) Direct the PCC Director to assemble additional Operations personnel to assist in operating plan equipment (as required). d) If plant conditions warrant, direct PCC Director to evacuate non-essential personnel from the plant. t FORM 372 22 - 3643
<; PUBLIC SERVICE COMPANY OF COLORADO RERP-TSC Issue 13
FORT ST. VR AIN NUCLEAR GENERATING FTATION page 6 of 12 i
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l l 2.3.8 Nuclear Documents Supervisor / Nuclear Documents . Specialist l [ l The Nuclear Documents Supervisor / Nuclear Documents l Specialist provides technical documents, as required, assures that TSC personnel have obtained necessary documents and supplies for performance of their emergency assignments, and assists the TSC Director in transmission of information to other emergency response centers. l 2.3.9 Senior Computer Analyst / Senior Programmer l a) The Senior Computer Analyst / Senior Programmer will assist in software / hardware problems as directed by the TSC Director, and arrange for offsite advice / assistance as directed by the TSC Director in the area of software / hardware problems. l b) The Senior Computer Analyst / Senior Programmer will also provide assistance on an as-needed, as available basis to the TSC Radiological Assessment individual in the tasks of data collection and/or data entry to the offsite dose calculation programs (RERP-DOSE). 2.4 Follow-up Responses 2.4.1 TSC Director As soon as the Personnel Control Center has been activated and communications established, the TSC Director will: a) Inform the PCC Director of the preliminary assessment of the emergency. b) Direct tha PCC Director to organize repair and damage control teams, radiological survey teams, or search and rescue teams (as required). c) Direct the PCC Director to assemble additional Operations personnel to assist in operating plan equipment (as required). d) If plant conditions warrant, direct PCC Director to evacuate non-essential personnel from the plant. s FORM 372 22 3W3
PUBLIC SERVICE COMPANY OF COLORADO Tj FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 12 As 'soon as the Forward Command Post (FCP) is activated and communications established, the TSC Director will: e) Inform the FCP Corporate Emergency Director of the status of the emergency using the
" Assessment Fact Sheets" ccmoleted by the TSC Staff as required. The TSC Directer is provided Datasheet I to summarire the data and calculations performed at the TSC.
f) Maintain a continuous open line to the FCP to provide prompt updating of the status of the emergency. l 2.4.2 TSC Radiological Assessment Individual (Senior l Plant Engineer / Technical Services Engineer) a) Continue making offsite dose projections at l approximately thirty (30) minute intervals (see RERP-DOSE) until the release has been terminated and the situation mitigated. b) Confer with the Radiological Assessment Coordinator and advise him of changes in plant status, release characteristics (rate, form, point, etc.), and meteorological conditions. c) Advise the Senior Health Physics representative of dose projections, as requested, for use in emergency team assignments and dose projections. 2.4.3 Health Physics Supervisor / Health Physicist (senior Health Physics representative) a) Ensure that monitoring teams obtain in plant radiological surveys. b) Depending upon the duration of the event and the exposure rate, the senior Health Physics representative will make recommendations to the TSC Director for personnel relief or stay times (see RERP-EXP). c) Maintain continued contact with the Radiological Assessment Coordinator and Personnel Control Center Director regarding any needs for Thyroid Blocking (see RERP-THYROID). t FORM 312. gg . m
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. PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 12
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d) Continue to evaluate the incoming field monitoring data (see RERP-FIELD) and prepare data sheets allowing comparison of actual data with dose projections being made by the TSC Radiological Assessment individual. Adequate supply of data sheets are provided in RERP-FIELD for this task. In addition, the senior Health Physics representative will maintain ongoing communications with, and control over, the field monitoring teams dispatched from the PCC. He will utilize dose projection data as a basis for determining stay times and thyroid blocking need. 2.4.4 TSC Staff a) Continue to collect da^a for evaluation of the emergency. b) Assess trends and operating status for the purpose of providing advice to Operations personnel acting through the Control Room Director. c) Analyze the effects of equipment failures, temporary modifications and changes in operating status and procedures. d) Assess the accident potential, and the effect of such potential on the health and safety of the public. e) Request other technical assistance (either in-house or contract) on an as-needed basis to cope with various situations that develop or may develop. f) Provide periodic updates to the TSC Director who will relay this information to the FCP. Updates will be of sufficient detail and frequency so that the FCP can effectively communicate and coordinate with the state / local / federal emergency response forces. 2.5 Recovery l The decision to recommend de-escalation or initiation of post-emergency recovery efforts rests with the TSC Director. ( FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-TSC .ssue 13
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S FORT ST. VRAIN NUCLEAR GENERATING STATION page 9 of 12 l f The TSC Director will base his decision on the following guidelines:
- Radiation levels are stable or decreasing with time.
- Releases of radioactive materials to the environment have ceased or are controlled within permissible license limits.
- Fi re , flooding, or similar emergency conditions no longer constit.te a hazard to the plant or statior personnel.
- Measures have been successfully instituted to correct or compensate for malfunctioning equipment.
The recommendation of the CR Director. When the TSC Director deems it advisable, he will l recommend de-escalation or termination of the emergency to the Corporate Emergency Director at the FCP. The l authority and responsibility to declare de-escalation to a [ lower emergency class or termination of the emergency response activities and conversion to a recovery phase rests solely with the Corporate Emergency Director at the FCP (see RERP-FCP). 3.0 Responsibilities Site emergency command activities are centered in the Technical Support Center, located immediately adjacent to the Reactor Building and within short walking distance of the Control Room. The TSC also serves as the primary point for onsite-offsite communications. 3.1 TSC Director The TSC Director is in command of onsite emergency operations. The TSC Director is authorized to initiate emergency actions, including declaration of a particular emergency class and providing protective action recommendations to offsite authorities. The TSC Director's responsibilities are: Assumes overall responsibility for the coordination and direction of onsite emergency response centers;
- Transmits preliminary assessment information to the FCP; 1
Directs the Personnel Control Center (PCC) actions; PORM 372 22 - M43
i PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION
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Page 10 of 12 t
- Confers, on an on going basis, with the Corporate Emergency Director (CED) after activation of the FCP; and
- Notifies the CED of the need for additional support or assistance.
3.2 Engineering and Technical Analysis Engineering and Technical Analysis personnel are responsible for direction of core physics anal; sis, electrical and mechanical engineering activities, liscensing related activities, procedures development, and system analysis as required. 3.3 Plant Condition Assessment Plant Condition Assessment personnel are responsible for the assessment of plant status, focusing on significant plant problems and trends, and for providing recommended corrective actions to the TSC Director. 3.4 Emergency Maintenance Emergency Maintenance personnel are responsible to recommend repair / damage control and corrective actions for plant mechanical and electrical systems. This individual estimates time and manpower requirements for emergency repairs, and develops emergency repair work procedures, as required. 3.5 Instrumentation and Control Support The Instrumentation and Control (I&C) individual determines alternative I&C capabilities or configurations, and advises for the repair / installation / modification of I&C equipment. I l l l l l l PORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-TSC Issue 13
-\. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 11 of 12 3.6 TSC Radiological Assessment The TSC Radiological Assessment individual is responsible to assess offsite radiological doses and consequences, determine affected offsite areas, and confer with both the TSC Director and the Radiological Assessment Coordinator (FCP) regarding calculation results and recommended offsite protective actions. In aedition, the TSC Radiciogical Assessment individual should confer with the Health Physics representative at the TSC regarding offsite dose projections in areas where field monitoring teams are to be deployed. The TSC Radiological Assessment individual is responsible for verification of any calculation prior to transmission to the Radiological Assessment Coordinator at the FCP.
3.7 Health Physics The senior Health Physics representative at the TSC is responsible for the assessment of onsite radiological doses, direction of all Health Physics / Radiochemistry survey personnel or teams, ensuring that adequate personnel dosimetry measures are taken, and evaluation of doses of field and emergency team personnel (particularly with regard to a need for thyroid blocking). 3.8 Administrative and Logistics Support The Administrative and Logistics Support individual provides technical documents, provides assistance with communications and analytical equipment, arranges required clerical support beyond the personnel directly assigned to the TSC, and makes any arrangements necessary for food / transportation / housing support as required. 3.9 Computer Support Computer support personnel provide technical support in the areas of computer hardware and software
, modifications / development /or recair, as recuired. In addition, this individual is responsible to arrange for timely offsite advice or assistance as directed by the TSC Director.
Computer support personnel also have received training in offsite Dose Calculation methodology. This training is provided for the purpose of assisting the TSC Radiological Assessment individual in gathering data and, where requested, assist in data entry at the TSC plant computer console. l [ FORM 372 22 - 3643
m. RERP-TSC PUBLIC SERVICE COMPANY OF COLORADO Issue 13
, . FORT ST. VRAJN NUCLEAR GENERATING STATION page 12 of 12 4.0 References 4.1 FSV Radiological Emergency Response Plan 5.0 Referenced or Succortina Procedures 1 5.1 RERP-CR, Control Room Procedure 5.2 RERP-FCP, Forward Command Post Procedure 5.3 RERP-PCC, Personnel Control Center Procedure 1 5.4 RERP-VC, Isitor's Center Procedure 5.5 RERP-HOME, Home Packet for Off-shift Notifications 5.6 RERP-DOSE, Offsite Dose Calculations 5.7 RERP-PAG, Protective Actior Guideline Recommendations 5.8 RERP-EXP, Emergency Exposurs Guidelines 5.9 RERP-THYROID, Thyroid Blocking Agent Administration 5.10 RERP-FIELD, Field Monitoring Procedure 5.11 RERP-ORG, FSV Emergency Organization and Resposibilities 5.12 RERP PHONE LISTS 5.13 RERP-SUPORG, Use and Coordination of Non-PSC Support Organizations l
l l l FORM 372 22 M43
PUBLIC SERVICE COMPANY OF COLORADO RERP-TSC ricure 1-
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-4 O FIRE BRIGADE TECHNICAL ADVISOR RADIOLOGICAL A%5E55t1E!;T gy TECll. SERV.
O OPERATING STAFF SUPPOR1 SR. PL/JiT ENGR. EHrP. EQPI OPERATORS & AUIILIARY TENDERS NOTE: > d g-- O FUTEERS OF STAFF SUPPORT PER50t:I:EL oO itP / HEAL 1H 1:1 PCC HILL VA'tY ACCORDING TO SUPV / PHYSICIST Z SEVERITY OF E!1ERCENCY AND $PECIFIC
$1TUAil0HAL NEEDS.
ADf!!N & LOGISTICS SUPP1 N ,/ PRiflARY/ ALTERNATE O O COMPUTER SUPPORT SR. COMP./ SENIOR 7733,] o vi o :;u E1YST / PR091At21P PERSONNEL CONTROL CENTER TECHNICAL SUPPORT CENTER CONIROL ROOM l0RWARD 00ttWIU POSI o (a w n e
.. PUBLIC SERVICE COMPANY OF COLORADO 3ERP-TSC attach. 1
.-. FDRT ST. VR AIN NUCLEAR GENER ATING STATION Issue 13 Page 1 of 1 SUPPORT EQUIDMENT/ MATERIAL
- 1. Communications equipment
- 2. P & I's (one-half size set)
- 3. FSAR, Reference Design Manuals, EP's, SOPS, OPOPs, RERP
- 4. Office supplies a) pen / pencils b) chalk c) graph paper d) calculator
- 5. Sector / regional maps
- 6. Health Physics survey maps (of FSV buildings-see HPP-1 as required)
- 7. Site maps
- 8. Dosimetry for TSC staff
- 9. Personnel Accountability Records
- 10. Scott-Air Paks
- 11. RM-14/15 l
l I FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO $[,P sh t1
;- } FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 13 i
Page 1 of 2 ASSESSMENT FACT SHEET TSC Director
- 1. Date of Event Time of Event
- 2. " Based upon the current release and the potential for further release this emergency is classified as":
ALERT SITE AREA EMERGENCY GENERAL EMERGENCY
- 3. Description of Event l 4. Radiological Assessment (Attach screen printout from l Radiological Assessment if desired.)
l Wind speed at 10 meters . Stability Category . l Location of Hazard: From _ _ degrees to degrees for miles. 1 Sectors Affected: . I Release Rates (Ci/Sec): Noble Gas . l Radioiodine . l Total Curies Released: Noble Gas . I Radiciodine . l Dose Rates At EAB (Rem /hr): Whole Body Dose Rate . l Thyroid Dose Rate . l FORM 372 22 3643 1
;,3 PUBLIC SERVICE COMPANY OF COLORADO Da t1
, . FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 13 Page 2 of 2 l
l
" Based upon the projected dose to the population the Recommended '
Protective Action per Table 6.2-2 of the RERP is": (Reference RERP-PAG per Radiological Assessment recommendation)
- 5. Current Plant and Core Status (refer to completed Datasheet 2, supplied by Senior Plant Engineer / Reactor Engineer).
- 6. Emergency Repairs required (per discussion with Maintenance /Results).
- 7. Personnel Accountability completed (Y/N) .
- 8. Personnel Injuries a) Number of injured persons .
b) Description of Injuries c) How many of injured persons are also contaminated? d) How many have been sent to hospital? Which Hospitals? - e) Relatives of all injured persons notified? (Y/N) If not, who has not been notified?
- 9. Plant Evacuation Non-essential plant personnel evacuated from (location) at (time).
F OR M 372 22 - 3643
.j PUBLIC SERVICE COMPANY OF COLORADO h.Ra 2 FORT ST. VR A,1N NUCLEAR GENERATING STATION lssue 13
- - Page 1 of 3 ASSESSMENT OF PLANT / CORE STATUS
- TECHNICAL SERVICES ENGINEERING SUPERVISOR / SENIOR PLANT ENGINEER
- NOTE: Completion of all lines not required. The Datasheet is provided for guidance only, and should be utilized to the extent necessary, as determined by the Senior Plant Engineer / Reactor Engineer Primary System Date/ Time
- 1. Date/ Time of Event
- 2. Current Reactor Power %
- 3. Primary Coolant Pressure psia
- 4. Primary Coolant Flow %
- 5. Operating Circulators A B C D.
Motive Power: Steam Water If water, which header? Emer. F.W. Emer. Cond. l 6. Purification train in use A B: Storage, PCRV, or Ventilation
- 7. Indication of fuel damage (Y/N)
RT-9301 reading (RR 93256, pt 10) cpm RT-9301 trend
- 8. Is heat removal capability adequate (Y/N)
- 9. Can cold-shutdown conditions be met (Y/N)
(Refer to 50P 12-02 or SR 5.1.a-W-P)
- 10. Obtain Technical Advisor assessment sheet data, as required (/)
Secondary System
- 1. Loops Operating I II l
- 2. Feed pumps operating A B C
- 3. Feed to S/G's Norm F.W. Emer. F.W.
l Emer. Cond. FORM 372 - 22 354
RERE'
- l
, PUBLIC SERVICE COMPANY OF COLORADO Datashee: 2 FORT ST. VRAIN NUCLEAR GENERATING 5TATION Issue 13 - t Page 2 of 3 l
l
- 4. Se::ondary flow I Klb/hr. II kib/hr.
- 5. Status of aux. boilers.
l l l l l i { l FORM 372 22 3643 i
;. PUBLIC SERVICE COMPANY OF COLORADO RE{"
, t2
/, FORT ST. VR AlN NUCLEAR GENER ATING STATION Issue 13
- 2 Page 3 of 3 ASSESSMENT OF PLANT / CORE STATUS TECHNICAL SERVICES ENGINEERING SUPERVISOR / SENIOR PLANT ENGINEER Remarks Time Description FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO $h k : 1
, FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 13 - - Page 1 of 2 i
TSC DIRECTOR CHECKLIST
- 1. Communications established (primary and secondary) TIME Control Room Personnel Control Center Forward Command Post
- 2. Personnel dosimetry distributed
- 3. Preliminary TSC Staff assesscents obtained and information transmitted l 4. Initial Radiological Assessment (Projected) obtained I from the CR or FCP.
Release Rate Curies Release Dose Rate Dose Received l Protective Action Guide l 5. Radiological Assessment (Actual and Projected) obtained. Release Rate Curies Released Dose Rate Dose Received Protective Action Guide l 6. PCC Evacuation Recommended i l l FORM 372 - 22 3643
R PUBLIC SERVICE COMPANY OF COLORADO h k 1 7 ' 1 FORT ST. VRAIN h!UCLEAR GENERATING STATION Issue 13 Page 2 of 2 l 7. Personnel Accountability Status obtained l Verify that Visitor's Center notified Initial (from Shift Supervisor - may pass through the CR Director) Continuing (from PCC Director) [ 8. Injury Reports Obtained. No. of Injured Hospital Called Relatives Emergency Transport
- 9. Estimates of emergency repairs to equipment /
instruments / systems obtained
- 10. Requests for Additional Personnel Made Site Personnel Other PSC Contract l 11. In-Plant Survey Teems Status Dispatched Report Received i 12. Site Survey Teams Status Dispatched Report Received l 13. Exposure criteria for emergency workers being followed (see RERP-EXP)
F ORM 372 3643
C PUBLIC SERVICE COMPANY OF COLORADO E5 g,3 g
, FORT ST. VRAIN NUCLEAR GENERATING STATION Itsue 13 Page 1 of 3 Work /Datasheet Checklist Control List Worksheet No. Title Number Copies None N/A N/A Datasheet No.
1 Assessment Fact Sheet - TSC Director 10 2 Assessment of Plant / Core Status 5 Checklist No. 1 TSC Director Checklist 2 l l FORM 372 - 22 3643
RE
, PUBLIC SERVICE COMPANY OF COLORADO g,5 C
L
.;. ; FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 13 .-- Page 2 of 3 FORMS USE REPORTING SHEET l Nuclear Documents Specialist:
This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at
. The following forms nave been utilized from this copy:
Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting I form. When this form is received, it will be necessary to replace the noted numoer of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. FORM 372 22 3643
RE
; ., PUBLIC SERVICE ' COMPANY OF COLORADO g Issue 13 FORT ST. vRAIN NUCLEAR GENERATING STATION .e -
Page 3 of 3 FORMS USE REPORTING SHEET (Continued) COMMENTS s
.. ~
Reported By: N Ddte: Nuclear Documents Specialist *
} ,
s Date Received ' Date Replaced
\
s ', l* Nuclear Documents Specialist will. transmit this form to the originating individual / department upen 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. -
- .c N
- S
\.
4 4 FORM 272 22.' 3643
i .
.- PUBLIC SERVICE COMPANY OF COLORADO RERP Phone Lists 5 Issue 24 X .. ., ..j FORT ST. VRA!N NUCLEAR GENERATING STATION Page 1 of 74 F0ET ST. VRAll NON - CONTROLLED TITLE: RADIOLOGICAL EMERGENCY RESPONSE PLAN (RERP) PHONE LIST,5 CU?Y VERIFYISCUE STt.TJ5 %:iH DD UMENTCENTER PR;0R TO USE ISSUANCE fjew M ave b r7 4 F0EM 3'2C3567 AUTHORIZED BY % M 1 77ct? M PORC EFFECTIVE REVIEW IDRc 5 8 0 AUG 2- 1984 DATE b- b" TABLE OF CONTENTS Page
- 1. Fort St. Vrain Phone System 2
- 2. RERP Phone List Index 3
- 3. Company Operator's Call List 5
- 4. ECP Director's Call List 8
- 5. FCP (CED's) Call List 10
- 6. PCC Director's Call List 12
- 7. State EOC Call List 15
- 8. TSC Directoe's Call List ,
17
- 9. Command Centers / Posts Numbers 20
- 10. Outside Assistance Numbers 24
- 11. Visitor's Center 26
- 12. RERP Phone List 27 l
FORM 372 22 - 3642
I* . - j PUBLIC SERVICE COMPANY OF COLORADO , P ne Lists
, '. 'RT ST. VR AIN NUCLE AR GENERATING STATION Page 2 of 74 FORT ST. VRAIN PHONE SYSTEM DIMENSION SYSTEM DIALING INSTRUCTIONS From Fort St. Vrain:
Area to be Called Proper Dialine Prefix Denver Exchange PSCo number 8 + Number Outside PSCo 8 + 303 + Number Longmont Exchange 78 + Number Greeley Exenange 9 + Number All other areas in Colorado 8 + 303 + Number Outside the State of Colorado 8 + Area Code + Number (unless a toll free number) Pacing Using Phone System: To Page: Dial 60-@ (all areas) or 62-@ (in plant only)
@ = (1, 2, 3, 4, 5, 6, or 7) whichever "@" is used, announce " CODE @" after page is complete, depress switch once, wait for answer.
To Answer: Dial #7-@ 0 = (1,2,3,4,5,6, or 7) in place of "@", use whichever code number was announced. 1 l FORM 372 - 22 + M4
RERP Phone Lists l , PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VR AIN NUCLEAR GENER ATING STATION age 3 of 74 l l RERP PHONE LIST INDEX A- Deleted B- Deleted C- Significant Event Notification to American Nuclear ~ Insurers D- Control Room Procedure E- Control Room Procedure, Attachment #I F- Control Room Procedure, Attachment #3 G- Control Room Procedure, Attachment #4 H- Control Room Procedure, Checklist #2 I- Personnel Control Center Procedure, Attachment #2 J- PSC Company Operator Call List K- ECP Director's Call List
- L- Corporate Emergency Director's Call List
- M- PCC Di >ector's Call List
- N- State EOC Call List
- O- TSC Director's Call List
- P- Centers / Posts Phone Numbers Q - Outside Assistance Phone Numbers R- Visitor Center Phone Numbers S- Fort St. Vrain Medical Emergency Plan T- Notification Procedure - Emergency Spills (G-5A)
U- Automatic Dialing System (Shift Supervisor's Office and Control Room) These call lists are found in both RERP-PHONE LISTS and RERP-HOME. FORM 372 3643 e
n Lists PUBLIC SERVICE COMPANY OF COLORADO E[Pue P page 4 of 74 , FORT ST. VR AIN NUCLEAR GENER ATING STATION 1 V- Home Packet For Off-Shift Notifications (RERP-HDME), Table #1 W- Home Packet For Off-Shift Notifications (RERP-HOME) Attachment #3 X- Home Packet For Off-Shift Notifications (RERP-HOME), Attachment #4 Y- Home Packet For Off-Shift Notifications (RERP-HOME), Attachment #10 2- Home Packet for Off-Shif t Notifications (RERP-HOME), Checklist #1 FORM 372 22 - 3643
- P
.. PUBLIC SERVICE COMPANY OF COLORADO gNneLists r ORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 74
~
RADIOLOGICAL EMERGENCY RESPONSE PLAN PSC COMPANY OPERATOR CALL LIST A. Obtain the following information from your contact at Fort St. Vrain.
- a. Name and identity of caller:
- b. Date/ Time of event:
- c. Classification of event (circle one):
Radiological Alert Site Emergency General Emergency
- d. At the present time, a radiological release (circle one)
IS/IS NOT occurring.
- e. Location of the Personnel Control Center B. Your Name:
Date/ Time call was received: FORM 372 22 3643
P $ $ PUBLIC SERVICE COMPANY OF COLORADO e2 FORT ST. VR AIN NUCLEAR GENERATING ETATl'ON Page 6 of 74
- l i
PSC COMPANY OPERATOR CALL LIST (continued) C. Fill in the blanks of the following statemer.t which will be read verbatim to the individuals on your call list using the above information. READ SLOWLY At approximately (b) this date at the Fort St. Vrain Nuclear Generating Station near Platteville, Colorado, an event believed to involve a potential radiological hazard occurred. This event has been classified as a (c) . At the present time, a radiological release (circit one) IS/IS NOT occurring. The Personnel Control Center is to be established at (e) . D. IMMEDIATELY, (day or night) contact the following individuals and read them your prepared statement verbatim. Log the time each is reached.
- 1. Call Fort St. Vrain and verify the report:
l a. Call 5-785-1220. Read your prepared statement VERBATIM.
- 2. Colorado State Health Department:
- a. Duty Hours: 320-8333, Ext. 6246.
FORM 372 22 - 364
PUBLIC SERVICE COMPANY OF COLORADO 3 W Phone Lists issue 24 f 7 FORT ST. VR AIN NUCLEAR GENER ATING STATION page 7 of 74
- b. After duty hours: 320-1465 (this is an answering service and they will contact the on-duty person at the State Health Department).
l 1 i FORM 372 22 - 3643
a e RERP Pfl0NE LISIS lasue 24 rage 8 or 74 i PSC COMPANY OPERATOR CALL LI5T fContInued1 D. (Continued)
- 3. Contact one of each of the following pairs or primaries / alternates.
l Extension City L'o_as Time 1 l a. Prima ry: D. W. Wa rembourg 5-785-1200 F rede rick 5-303-833-4092 l Alte rna te: L. M. McBride 5-785-1201 Boulder 5-303-442-3829 1 l b. Prima ry: W. J. Franek 5-785-1218 Berthoud 5-303-532-3489
- Al terna te: D. P. Hood 5-785-1347 Longmont 5-303-776-18t:3 1
l c. Primary: J. Class 5-785-1253 Brighton 5-303-659-4118 Al te rna te: S. R. Wi l l ro rd 5-785-1450 Brighton 5-303-659-5258
- d. Prima ry: C. H. Fuller 5-785-1202 Loveland 5-303-663-2363 i
Al terna te: J. W. Cahm 5-785-1350 Northglenn 5-303-452-0507 ! e. Prima ry: O. R. Lee 797-4122,571-7305 Brighton 9-659-1180
. Al ternate: J. M. Fuller 329-1104 Denver 9-779-1109 4
l r. Prima ry: R. F. Walker 571-7333 Denver 9-234-9298 i Alternate: 8. O'Donnell 571-7381 Denver 9-388-0211
- g. Primary: D. McNeills 571-7254 Denver 9-985-3197 Al terna te: H. L. Brey 571-8404 Broemrield 9-469-4238 ,
- 4. Contact American Nuclear Insurers 1-800-243-3172 or (203) 677-7305 (Day or Night)
- 5. Contact General Atomic Technologies, Inc. (619) 455-2010
- 6. Contact o_ng or the following at the Colorado State University Radiation Biology Department, Work City loosee Ilse
! a. Dr. James E. Johnson 5-303-491-5380 Ft. Collins 5-303-482-3029
- b. Marlon Mcdonald 5-303-491-5094 Ft. Collins 5-303-484-0084 ~
- c. Department Orrice 5-303-491-5222 Ft. Collins i 7. Contact American Nuclear Society (312) 352-6611 1'
- 8. NRC Resident Inspector - Orrice 5-785-1490 or 5-303-785-2282
- ! G. L. Pluelee, t il 303-776-9541 or 890-2225 ( Pege Number) l 9. Contact Institute of Nuclear Power Operations (INPO) (404) 953-0904, 953-0922, or
! l 953-3600, extension 239, Rapicon (404) 953-9208 or 952-6728.
- 10. Contact PSC Fort St. Vrain Shirt Supervisor at 5-785-1219 to report results of telephone contacts above.
J i
P.one Lists
. PUBLIC SERVICE COMPANY OF COLORADO e page 9 of 74
- FORT ST. VR AIN NUCLEAR GENER ATING STATION ECP DIRECTOR'S CALL LIST INTRUCTIC M In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the response cpoter/ post Director:
- a. Call your response center / post Alternate Director (and the alternate will complete the calls on the attached list).
- b. If you cannot contact your Alternate Director, call the first person on the attached list and inform him to complete the call list.
- 2. If you are the response center / post Alternate Director and are contacted by the Director:
- a. Complete the attached call list.
- 3. If you are the response center / post Alternate Director and are contacted by the PSC Operator:
- a. Call the first person on the attached list and inform him to complete the call list.
F OR M 372 22 3643 j
~ PUBLIC SERVICE COMPANY OF COLORADO -- Phone Lists
,p
, FORT ST. VRAIN NUCLEAR GENERATING STATION page 10 of 74 l l
ECP OIRECTOR'S CALL LIST First call all primaries, then call all alternates. PSC Extension Home Time Manager - Technical Support l Primary - M. E. Niehoff 785-1403 690-3879 Alternate - Mike Holmes 571-8409 988-4522 Manager - Media Relations Primary - R. T. Person, Jr. 571-7323 753-9292 Alt. - W. D. Fitzmaurice 571-7158 424-8053 Manager - Resources Primary - D. D. Hock 571-7211 394-3063 l Alternate - J. Bumpus 571-7821 388-7645 Manager - Security Primary - E. O'Neal 571-7709 757-0038 l Alternate - E. Lane 571-8533 321-4016 Note: Any change to this call list requires a change be made to RERP-HOME, Attachment #5. FORM 372 22 300
PUBLIC SERVICE COMPANY OF COLORADO Ph Lists e2 . FORT ST. VR AIN NUCLE AR GENERATING STATION Page 11 of 74 I CORPORATE EMERGENCY DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the resconse center / post Director:
- a. Call your response center / post Alternate Director.
- b. If you cannot contact your Alternate Director, call the first person on the attached list and inform him to complete the call list.
- 2. If you are the response center / post Alternate Director and are contacted by the PSC Operator or the center / post Director:
- a. Call the first person on the attached list and inform him to complete the call list.
- 3. If you are the first person on the attached list and are contacted by the Alternate Director or the Director:
- a. Complete the attached list.
FORM 372 22 3643
P n Lists
. . PUBLIC SERVICE COMPANY OF COLORADO e e .
FORT ST. VRAIN NUCLE AR GENER ATING STATION page 12 of 74 l CORPORATE EMERGENCY DIRECTOR'S CALL LIST (FCP) l First contact all primaries, then call all alternates. Extension Home Time Station Technical Liaison (One of the Station Technical Liaisons is also contacted by the PSC Operator.) Primary - C. H. Fuller 785-1202 663-2363 Alternate - J. W. Gahm 785-1350 452-0507 Radiological Assessment Primary - T. Borst 785-1203 663-1230 (Pager) 890-1775 Clerical Assistance Primary - D. Merritt 785-1271 737-2339 Primary - D. Heath 785-1272 223-5121 Alternate - S. Katcher 785-1212 356-0351 Media Relations Primary - M. Mora 571-8462 694-2369 Alternate - S. Volsted 571-7242 755-5164 Note: Any change to this call list requires a change be made to RERP-HOME, Attachment #6. FORM 372 22 3643
~.
" L$
PUBLIC SERVICE COMPANY OF COLORADO ue e FORT ST. VRAIN NUCLE AR GENER ATING STATION Page 13 of 74 pCC DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the response center / post Director:
- a. Call your response center / post Alternate Director (the alternate will complete the calls on the attached lis J.
- b. If you cannot contact your Alternate Director, call the first person on the attached list and inform him to complete the call list.
- 2. If you are the response center / post Alternate Director and are contacted by the Director:
- a. Contact persons to set up the facility by calling those individuals denoted by asterisks (*) after their names and four (4) Health Physics Technicians listed. Inform all persons of the location of the PCC. Notify the remainder of personnel upon your arrival at the PCC. (This responsibility may be delegated.)
- 3. If you are the response center / post Alternate Director and are contacted by the PSC Operator:
- a. Call the first person on the attached list and inform him to complete the call list as specified in 2.a. above.
6 FORM 372 22 3643 l
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P ne Lists PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 14 vf 74 PCC DIRECTOR'S CALL LIST Plant Extension Home Time Personnel Accountability and 1 & C Technicians G. Redmond* 251 9-339-3152 T. Bashline 262 8-303-686-9763 P. Bearly 455 8-303-669-6636 M. Benedict 313 9-353-7209 M. Blossom
- 297 9-785-6302 R. Dickerson 273 8-303-287-6089 T. Dillen 262 9-356-3370 R. Erwin 321 9-330-7178 D. Frye 276 9-587-4768 R. Hamblin 254 8-303-667-1703 C. Harding 311 9-785-2398 l K. Hays 319 8-303-778-7702 J. Hohn 260 9-785-6322 W. Holcomb 312 9-330-2068 R. Hooper 458 8-303-452-3614 D. Horihan 250 78-776-7976 S. Lehr* 451 8-303-422-1280 G. McAfee 260 8-303-857-6498 l R. Moler 456 78-772-9357 G. Murphy
- 254 9-785-2542 l M. Murphy 454 8-303-279-6762 G. Powers 252 8-303-426-1623 D. Reed
- 314 9-785-2159 l R. Rivera 453 8-303-667-1906 T. Shafer* 457 9-587-4061 C. Stieff* 209 9-587-2500 J. Switzer 452 9-587-4134 R. Teel 261 8-303-288-1959 R. Wyatt 262 8-303-493-3649 Maintenance, Repair, and Damace Control R. Webb* 229 78-776-8219 (Pager) 855-7257 R. Lamb
- 336 78-772-0757 D. Nelson
- 246 9-587-4189 I
l FORM 372 22 3643
~ PUZLIC SERVICE COMPANY OF COLORADO Pn n Li sts e2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 15 of 74 Monitoring Teams - Health Physics (Notify four of the following initially.) J. 3rown 245 9-339-3972 P. Glahn 245 8-303-450-5292 L. Hutchins 245 9-330-7187 l G. Madison 245 8-303-833-2278 K. Morse 245 9-353-6163 K. Nasveschuk 245 78-651-6254 l E. J. O'Donoghue 245 8-303-452-3514 S. Sherrow 245 9-353-1338 l S. Sieg 245 8-303-663-3468 l G. Valentine 245 8-303-532-4861 Radiochemistry V. McGaffic (P)* 278 9-587-2752 D. Miller (A)* 279 8-303-663-3595 S. Poet (A) 279 78-652-2297 M. Prochownik (A) 279 9-785-6010 S. Rima (A) 279 78-772-4068 Operating Staff Support As Required - See RERP Phone Lists. Maintenance (Electrical, Mechanical) As required at the discretion of the PCC Director - Refer to RERP Phone Lists. Hazards Control Team Fire Brigade Members Note: Any change to this call list requires a change be made.to RERP-HOME, Attachment #7. FORM 372 22 3643
P ne Lists PUBLIC SERVICE COMPANY OF COLORADO hP e j . FORT ST. VR AIN NUCLE AR GENER ATING STATION Page 16 of 74 1 l l STATE EOC CALL LIST INSTRUCTIONS (For Contacts by PSC) In the event you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the PSC primary contact:
- a. Call the PSC alternate contact and instruct him to complete the call list.
- b. If you cannot reach the PSC alternate contact, call the first person on the attached list and inform him to complete the call list.
- 2. If you are the PSC alternate contact and are notified by the PSC primary contact:
- a. Complete the attached call list.
- 3. If you are the PSC alternate contact and are notified by the PSC operator:
- a. Call the first person on the attached list and inform him to complete the call list.
PORM 372 22 M43
P PU1'LIC SERVICE COMPANY OF COLORADO , l ne Lists FORT ST. VRAIN NUCLEAR GENERATING STATION Page 17 of 74 STATE EOC CALL LIST (For Contacts by PSC) Extension Home Time Technical Assistance H. L. Brey (Primary) 571-8404 469-4238 l J. R. Reesy (Alt.) 571-8406 755-1720 Radiological Consultant Janet Johnson 491-5930 482-3029 Media Relations R. A. Burns (Primary) 571-8481 759-9740 G. Reeves (Alt.) 571-8479 424-4958 Note: Any change to this call list requires a change be made to RERP-HOME, Attachment #8. PORM 372 22 3643
r-RERP Phone Lists PUBLIC SERVICE COMPANY OF COLORADO Issue 24 FORT ST. VRAIN NUCLEAR GENERATING STATION page 18 of 74 l l TSC DIRECTOR'S CALL LIST INSTRUCTIONS l In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the response center / post Director:
- a. Call your response center / post Alternate Director (the alternate will complete the calls on the attached list).
- b. If you cannot contact your Alternate Director, call the first person on the attached list and inform him to complete the call list.
- 2. If you are the response center / post Alternate Director and are contacted by the Director:
- a. Complete the attached call list.
- 3. If you are the response center / post Alternate Director and are contacted by the PSC Operator:
- a. Call the first person on the attached list and inform him to complete the call list.
PORM 372 22. M43
P e Lists PUBLIC SERVICE COMPANY OF COLORADO ,
+ -
FORT ST. VR AIN NUCLEAR GENERATING STATION page 19 cf 74 TSC DIRECTOR'S CALL LIST First call all primaries, then call all alternates. Plant Reactor Physics Extension Home Time Primary - F. Novachek 270 457-8034 (Pager) 890-1941 Alternate - R. Heller 284 772-1093 Radiolooical Assessment l Primary - J. Sills 265 221-5059 I (Pager) 890-2223 Alternate - S. Johnson 267 663-1431 Plant Condition Assessment Call two off-duty Shift Supervisors M. Deniston 219 776-3776 D. Evans 219 776-9672 J. Hak 219 776-1904 l D. Hood
- 219 or 347 776-1843 l J. Hunter 219 330-1411 H. O'Hagan 219 776-8232 G. Reigel 219 330-4235 J. Vandyke 219 or 346 772-2476 Emergency Maintenance Primary - W. Craine 222 667-5427 Alternate - J. Petera 233 427-6273 Instrument and Control Primary - B. Burchfield 249 351-0373 -
Alternate - J. McCauley 248 ti67-0635 Health Physics / Health Physicist Primary - T. Schleiger 242 785-6314 l Alternate - B. Woodard 244 678-0818 l* Also contacted as alternate to Control Room Director by PSC l operator. PomM 372 22 3643
]
~
-pp PUBLIC SERVICE COMPANY OF COLORADO !bue2
. FORT ST. VR AIN NUCLEAR GENER ATING STATION page 20 of 74 Administration /Locistics Primary - A. Kitzman 206 737-2578 Alternate - P. Collins 207 587-2172 Alternate - P. Bollig 204 339-3972 Alternate - D. Connelly 210 353-4575 Telephone Console Ooerators Primary - D. Edwards 214 669-1680 Alternate - D. Libal 213 651-1404 Comouter Suoport
- Primary - D. Klaus 437 466-5046 __
" Alternate - D. Bilstein 333 532-2546 l " Alternate - D. Haloin 376 353-1993
- Computer Services Page Number: 855-3234 Note: Any changes made to this call list requires a change be made to RERP-HOME, Attachment #9.
1 i l l l l l PORM 372 22 34A3
ne Lists PUBLIC SERVICE COMPANY OF COLORADO [PP
. FORT ST. VR AIN NUCLEAR GENERAT!?@G STAThoM Page 21 of 74 CENTERS / POSTS PHONE NUMBERS
- Phone Control Room (CR) Lists Affected Denver Line 571-7436 P Greeley Line 785-2223 P Longmont Line 776-6710 P Site Extension 220 P Site Extension 221 P Executive Command Post (ECP)
Headouarters Building - Room 620 Denver Line 571-8459 P Denver Line 571-8460 P Denver Line 571-8461** P Lookout Center - Golden Denver Line 278-2222 P Denver Line 278-0287 P Emergency Operations Center - State (SEOC) Camp George West Denver Line 279-2511 P Denver Line 279-8855 D,P,U,W Forward Command Post (FCP) Fort Lupton Denver Line 571-7053 571-7070 571-7096 571-7061 P 571-7062 Ft. Lupton Line 857-6238 857-6246 857-6239 857-6022 P 857-6247 857-6248 857-6249 857-6001 857-6230 For any call into FSV from another PSC dimension phone, dial 8-785-1xxx, where xxx is the three digit FSV extension. This line reserved for conferencing between the FCP AND ECP. FORM 372 22 3443
P ne Lists PUBLIC SERVICE COMPANY OF COLORADO ,
. FORT ST. VRAIN NUOLEAR GEiVERATING STATION page 22 of 74 Governor Office 866-2471 F,P,W Mansion 837-8350 F,P,U,W F O R M 372223643
PUBLIC SERVICE COMPANY OF COLORADO Phone Lists . FORT ST. VRAlN NUCLEAR GENERATING STATH3N Page 23 of 74 CENTERS / POSTS PHONE NUMBERS Phone Personnel Control Centers Lists Affected Onsite Traininq Center Site Extension 450 P Engineering /0A Complex Site Extension 362 P Warehouse Site Extension 311 P Site Extension 312 P Craft Shoos Site Extension 433 P Offsite Johnstown County Shop Greeley Line 587-4508 P County Engineer, Drew Scheltinga 356-4000 P Ext. 4750 Maintenance Supervisor, Bud Schmuhl 587-2431 P (Home) Production Manager, Dave Becker 356-0177 P (Home) Maintenance Support Supervisor, 284-5451 P Jack Slife (Home) Lonomont PSC Service Center Denver Line (Louisville) 665-5511 P Longmont Line 776-0933 P Platteville Fire Department Greeley Line 785-2232 P,Q Contact Cliff Wright, Greeley Line 785-2835 P,Q Weld County, Maintenance 356-4000 ext. 777 P FORM 372 22 3443
~ Pn ne Lists PUBLIC SERVICE COMPANY OF COLORADO ,2 FORT ST. VRAIN NUCLEAR GENERATING STATION page 24 of 74 CENTERS / POSTS PHONE NUMBERS Phone Technical Support Center Lists Affected Site Extension 290 P Site Extension 291 E,P Site Extension 292 D,E,H,P Site Extension 293 P Site Extension 294 E,P Site Extension 295 P l l FORM 372 22 3643
n Lists PUBLIC SERVICE COMPANY OF COLORADO e2 FORT ST. VR AIN NUCLEAR GENER ATING STATION Page 25 of 74 OUTSIDE ASSISTANCE PHONE NUMBERS Phone Ambulance Services Lists Affected Platteville Fire Department (Platteville) 785-2232 Q (Greeley Line) 911 Q Professional Ambulance Service (Longmont) 776-1211 Q Weld County Ambulance Service (Greeley) 353-5700 Q St. Lukes Helicopter (ask for Admitting) 869-2012 Q 869-2013 Q or 869-2014 Emergency: 869-2111 Q Fire Departments Fcrt Lupton 857-6619 P,Q Johnstown 587-4477 Q Platteville 785-2232 P,Q Medical Facilities St. Luke's Hospital (Denver) 839-1000 Q,5 869-2111 Q,5 869-2112 Q,5 North Colorado Medical Center (Greeley) 352-4121 0,5 Memorial Hospital (Greeley) 352-3123 Q,5 Longmont United Hospital (Longmont) 651-5111 Q,5 Emergency: 651-5000 Q,5 National Weather Service Ask for LEAD Forecaster 837-4207 Q or 837-3611 Q Institute of Nuc1' ear Power Operations (INPO) (404) 953-0904 Q,J (404) 953-0922 Q,J (404) 953-3600, Extension 239 Q,J Rapicon: (404) 953-9208 Q,J (404) 952-6728 Q,J NRC Operations Center (202) 951-0550 E,F,G, Q,u,w,x (301) 427-4056 E,Q (301) 427-4259 E,Q (301) 492-8893 E,Q (301) 492-7000 E,Q FORM 372 22 + 3643
PP ne Lists PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENER ATING STAT'ON page 26 of 74 OUTSIDE ASSISTANCE PHONE NUMBERS Phone Lists Affected Backuo Meteorological Tower Data (NOAA) Bob Clark 497-6987 Q Dick Garrelts 497-6972 Q Audrene Brown 497-6159 Q Silent 700-300 Baud Modem
- 447-0992 Q Laboratory 497-6792 Q Administrative Office 497-6116 0 To have line cleared when busy, call Mr. Val Sware: (SERI) at 231-1816.
County Sheriff 356-4000 Q City Police Johnstown 587-4664 Q Platteville 785-2215 Q Stato Patrol 353-1151 Q or 9-911 Q Coast Guard 1-800-424-8802 Q,T Colorado State Health Department 320-8333 J,Q,T Environmental Protection Agency 234-2259 Q,T
.or 234-6069 Q,T American Nuclear Insurers (ANI) 1-800-243-3172 C,J,0,U (203) 677-7305, ext. 245 C,Q,U,J American Nuclear Society (312) 352-6611 J,0 l
l FORM 372 22 3643
~
, 1 Phone Lists PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION page 27 of 74 VISITOR CENTER PHONE NUMBERS Phone Lists Affected Site Extension 475 R 476 785-1475 R Persons living Within Property Boundary
- l 1. Ben Houston 785-2408 R,I l 2. Randy Russell 785-6326 R,I l 3. Bill Pitt 785-6274 R,I l 4. Raymond Marin 785-2862 R,I l S. Vacant No Phone l 6. Scott Houston 785-2358 R,I l 7. Keith Russell 785-2589 R,I l 8. Dave LaChance 785-6303 R,I When these telephone numbers are verified, updates must be
- reflected in the PCC Procedure, Attachment 2.
l PORM 372 22 3643
m-NE LISTS PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 28 of 74 ADMINISTRATIVE
- Phone Lists Affected BORST, F.J. C,E,L, S,U,V,Z*
Loveland tis 3-1230 (Home) 203 (Work) 890-1775 (Fage Number) Assigned To: FCP BREY, H.L. J,Y Broomfield 469-4238 . (Hone)
- 571-8404 '(Work)
Assigned To: SEOC BUMPUS, J.N. K Denver l 388-7645 (Home) 571-7821 '(Work) Assigned To: ECP BURNS, R.A. N,S,Z Denver 759-9740 (Home) 571-8481 (Work) Assigned To: SEOC FITZMAURICE, W. K,5 Denver 424-8053 (Hone) 571-7158 (Work) Assigned To: ECP
\
s
'N ,
s
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require'use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in 1
. parentheses to the left of the PSC system exchange. Telephone calls ;
' to FSV personnel from other PSC telephones is by dialing 785-1xxx, where l xxx is the three' digit work extension, or by dialing 785-2223, and using l the switchboard operator.
s ( FOMM 372 22 3643
~
l >
PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCt. EAR GENERATING STATION Page 29 of 74 ADMINISTRATIVE
- Phone Lists Affected FULLER, C. H. C,E,J, L,S,U, V,Y,Z Loveland 663-2363 (Home)
- 202 (Vork) 890-0810 (Page Number)
Assigned To: FCP FULLER, J.K. J,Y Denver 779-1109 (Home) 329-1104 (Work) Assigned To: FCP HOCK, D.D. K Denver 394-3063 (Home) 571-7211 (Work) Assigned To: ECP HOLMES, M.H. K Lakewood 988-4522 (Home) 571-8409(Work) Assigned to: ECP GAHM, J. W. J,L,U,Y Northglenn 452-0507 (Home) 350 (Work) , Assigned To: FCP l
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those l cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 22 3643
~ P PUBLIC SERVICE COMPANY OF COLORADO ,hNELISTS
+
FORT ST. VRAIN NUCLEAR GENERATilJG STATION Page 30 of 74 ADMINISTRATIVE
- Phone Lists Affected l LANE, E. K,5 l Denver l 321-4016 (Home) l 571-8533 (Work) l Assigned To: ECP LEE, 0.R. C,E,J, S,T,V, Y,Z Brighton 659-1180 (Home) 797-4122 (Work) 571-7305 (Alternate)
Assigned To: FCP McBRIDE, L.M. C,E,J, S,T,U, V,Y,Z Boulder 442-3829 (Herte)
- 201 (Work) 890-0698 (Page Number)
Assigned To: TSC McNELLIS, G. J,Y Denver 321-3142 (Home) 571-7254 (Work) Assigned To: SEOC MORA, MARILY L,S,Z Der,ver 694-2369 (Home) 571-8462 (Work) Assigned To: FCP l
- NOTE: Calls to PS: phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephoras is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
P OR M 372 3643
PUBLIC SERVICE COMPANY OF COLORADO (,ONEUSTS
. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 31 of 74 ADMINISTRATIVE
- Phone Lists Affected l NIEHOFF M. E. .K l Aurora l 690-3879 (Home) l 403 (Work) l Assigned to: ECP 0'DONNELL, B. J,Y Denver 388-0211 (Home) 571-7381 (Work)
Assigned To: ECP 0'NEAL, E. E. K,5 Denver 757-0038 (Home) 571-7709 (Work) Assigned To: ECP PERSON, R.T. , JR. K Cr.glewod - 753-9292 (Hooe) 571-7323 (Work) Assigned To: ECP REESY, JACK R. K Denver 755-1720 (Home) E71-3406 (Work) Assigned To: ECP REEVES, G.D. N,S,Z Arvada 424-4958 (Home) 571-8479 (Work) Assigned To: SEOC
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a dif ferent telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephc,ne calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO hPFhNELISTS , FORT ST. VRAIN NUCLEAR GENERATING STATION page 32 of 74 ADMINISTRATIVE
- Phone Lists Affected VOLSTAD, STEPHEN A. L Denver 755-5164 (Home) 571-7242 (Work)
Assigned To: FCP WALKER, R.F. J,Y Denver 234-9298 (Home) 571-7333 (Work) Assigned To: ECP WAREMBOURG, D.W. C,E,J, S,T,U, V,Y,Z Frederick 833-4092 (Home)
- 200 (Work) 890-0699 (Page Number)
. Assigned To: TSC
- NOTE: Calls to PSC phones from outside of the PSC telephone system my require use of a different telephone exchange. For those cases, the exchange for direct dial.from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 22 - 3643
P P. NE LISTS PUBLIC SERVICE COMPANY OF COLORADO ue FORT ST. VRAIN NUCLEAR GENERATING STATION page 33 of 74 CHEMISTRY Phone Lists Affected ADAMSKI, HANK Boulder 444-3533 (Home) 226 (Work) Assigned To: NONE BRUNGARDT, JESSE Loveland 667-2540 (Home) 226 (Work) Assigned To: NONE FETTER 0LF, DAVE L. Greeley 330-6073 (Home) 226 (Work) Assigned To: NOME LUCERO, VICTOR A. Greeley 352-0705 (Home) 225 (Work) l 855-5504 (Page Number) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 3643 I
NE LISTS y,
' ~
PUBLIC SERVICE COMPANY OF COLORADO f ,P
. ; FORT ST. VRAIN NUCLEAR GENERATING STATION Page 34 of 74 COMPUTER SERVICES Phone Lists Affected BILSTEIN, DON 0 Berthoud 532-2546 (Home) 333 (Work)
Assigned To: TSC HALOIN, DON Greeley 0 353-1993 (Home) l 376 (Work) Assigned To: TSC KLAUS DON L. O Broomfield 466-5046 (Home) 437 (Work) Assigned To: TSC METCALFE, DOUG Westminster 425-1695 (Home) ; 344 (Work) l Assigned To: NONE l 1
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 22 3643 l
PUBLIC SERVICE COMPANY OF COLORADO PP NE LISTS
, .; FORT ST. VR AIN NUCLEAR GENER ATING STATION page 35 of 74 ELECTRIC Phone Lists Affected BRUXV00RT, MARVIN J.
Loveland 669-7175 (Home) 233 (Work) Assigned To: NONE CRUZ, OAN Westminster 428-0157 (Home) 233 (Work) Assigned To: NONE HARTSOUGH, PATRICK J. Fort Lupton 785-2463 (Home) 233 (Work) Assigned to: NONE LAMB, ROBERT E. U,M Longmont 772-0757 (Home) 336 (Work) Assigned To: PCC
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 22 3643
D,P PENE LISTS PUBLIC SERVICE COMPANY OF COLORADO
. : FORT ST. VR AIN NUCLE AR GENERATING STATION page 36 of 74 j i
MAINTENANCE Phone Lists Affected ADAMS, DENNIS R. Longmont 772-7759 (Home) 232 (Work) Assigned To: NONE AMEN, TOM Greeley 330-9868 (Home) 232 (Work) Assigned To: NONE BASS, ROY J. , JR. Northglenn 452-2716 (Home) 232 (Work) Assigned To: NONE BATES, G. DEXTER Greeley 356-1894 (Home) 244 (Work) Assigned To: NONE BISHARD, LEVI V. Brighton 452-7245 (Home) 343 (Work) 855-7257 - (Page Number) Assigned To: NONE BURNETT, RANDALL Brighton 659-0787 (Home) 228 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
i FORM 372 22 - 3643 i
PENE LISTS PUBLIC SERVICE COMPANY OF COLORADO e FORT ST. VRAIN NUCLEAR GENERATING STAT!ON page 37 of 74 MAINTENANCE Phone Lists Affected BURTIS, JOHN R. Fort Lupton 857-2816 (Home) l 340 (Work) Assigned To: NONE CLARK, ARTHUR L. Berthoud 532-4081 (Home) 228 (Work) Assigned To: NONE CLAYTON, DWIGHT Johnstown 587-4700 (Home) 232 (Work) Assigned To: NONE COGDILL, LARRY Johnstown 587-4825 (Home) 232 (Work) Assigned To: NONE CRAINE, WARD A. 0,U Loveland 667-5427 (Home) 222 (Work) 890-0804 (Page Number) - Assigned To: TSC DAVIS, JENNIFER Evans 330-7076 (Home) t 231 (Work) l Assigned To: NONE l 1
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in l l parentheses to the left of the PSC system exchange. Telephone calls '
l to FSV personnel from other PSC telephones is by dialing 785-1xxx, where i l xxx is the three digit work extension, or by dialing 785-2223, and using i the switchboard operator. FORM 372 22 - 3643
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PP NE LISTS PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 38 of 74 MAINTENANCE Phone Lists Affected DESANTI, ROCKY Brighton 659-3942 (Home) 232 (Work) Assigned to: NONE DIXON, GEORGE D. Longmont 776-2634 (Home) 228 (Work) 855-7257 (Page Number) Assigned To: NONE FORREST, DEAN Firestone l 833-2199 ( H ome ) - - - - -- - 232 (Work) Assigned To: NONE GOODMAN, MICHAEL J. Platteville 785-2185 (Home) 340 (Work) Assigned To: NONE GUILLEN, ANTHONY Longmont 772-3191 (Home) 232 (Work) . Assigned To: NONE HALVORSON, JOHN Johnstown 587-2226 (Home) 232 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
l t FORM 372 22 3643
P PUBLIC SERVICE COMPANY OF COLORADO ,hNELISTS FORT ST. VRAIN NUCLEAR GENERATING STATION Page 39 of 74 f MAINTENANCE Phone Lists Affected HOOD, GREG l Longmont l 776-9804 (Home) 232 (Work) Assigned To: NONE HORIHAN, DEVIN P. , Longmont l 776-5308 (Home) 232 (Work) ] Assigned To: NONE JUDSON, RICK Johnstown , i 587-4120 (Home) ' I 232 (Work) ~~- - - - - - Assigned To: NONE KARICH, JACK Platteville 785-2959 (Home) 232 (Work) Assigned To: NONE KRUSE, QUENTIN L. Brighton 451-1901 (Home) 232 (Work) Assigned To: NONE LEWIS, ORVAL A. Commerce City 288-4370 (Home) 232 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO $,[ # FORT ST. VRAIN NUCLEAR GENERATING STATION page 40 of 74 1 MAINTENANCE Phone Lists Affected i LLANAS, FRANK Fort Lupton 857-2583 (Home) 232 (Work) Assigned To: NONE PANENTI, THOMAS Greeley 330-0978 (Home) 228 (Work) Assigned To: NONE MEDBERY, GERALD D. Greeley 330-6119 (Home) 232 (Work) Assigned To: NONE MEIER, EDWARD J. Denver 355-2988 (Home) 230 (Work) Assigned To: NONE MONT0YA, JOHN P. Platteville 785-2961 (Home) 228 (Work) Assigned To: NONE MORG'AN, GREGORY R. l Greeley i 353-2693 (Home) 389 (Work) Assigned To: NONE '
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial-from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 3643
l PUBLIC SERVICE COMPANY OF COLORADO N LISTS '
, e l .
FORT ST. VRAIN NUCLEAR GENERATING STATION page 41 of 74 f MAINTENANCE Phone Lists Affected I OWEN, JON E. I Johnstown 587-2385 (Home) 340 (Work) 855-7257 (Page Number) Assigned To: NONE PETERA, JAMES U,0 Westminster 427-6273 (Home) 233 (Work) 890-0832 (Page Number) Assigned To: TSC RHOTON, MICHAEL A. Longmont 833-4074 (Home) 232 (Work) Assigned To: NONE ROWELL, ROBERT L. Platteville 785-6268 (Home) 232 (Work) Assigned to: NONE SCHUYLER, TIMOTHY LEE Brighton 659-1183 (Home) 235 or 232 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 3643
PMNE LISTS PUBLIC SERVICE COMPANY OF COLORADO ,
. FORT ST. VRAIN NUCLEAR GENERATING STATION page 42 of 74 MAINTENANCE Phone Lists Affected SKAGGS, EDWARD ROY Greeley 352-6334 (Home) 232 (Work)
Assigned To: NONE SKELLY, GREGORY J. Arvada i 426-5661 (Home) I 232 (Work) l Assigned To: NONE SLABY, RICKY H. l Denver 287-0675 (Home) 232 (Work) Assigned To: NONE SMOOT, GREGORY ALAN Longmont 776-0338 (Home) 232 (Work) Assigned To: NONE SNYDER, JERRY Greeley 352-3032 (Home) 232 (Work) Assigned To: NONE STEPHENS, DEAN Denver i 296-4073 (Home) 232 (Work) Assigned To: NONE l
- NOTE: Calls to PSC phones from outside of the PSC telephone system l may require use of a different telephone exchange. For those l cases, the exchange for direct dial from any outside line is given in l parentheses to the left of the PSC system exchange. Telephone calls l to FSV personnel from other PSC telephones is by dialing 785-1xxx, where l xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
~
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ? NE LISTS ue FORT ST. VRAIN NUCLEAR GENERATING STATION Page 43 cf 74 MAINTENANCE Phone l Lists Affected I i TREGUNING, WILLIAM E. Johnstown 587-2133 (Home) 232 (Work) Assigned To: NONE WEBB, RONALD W. U,M, Longmont 776-8219 (Home) 229 (Work) 855-7257 (Page Number) Assigned To: PCC WEILNAU, LARRY L. Platteville 785-6050 (Home) 232 (Work) Assigned To: NONE WERNESS, STEPHEN J. Berthoud 532-2577 (Home) 232 (Work) Assigned To: NONE WIDOWS, RICH Loveland 663-1080 (Home) 232 (Work) Assigned To: NONE WINDHORST, WILLIAM Platteville 785-2194 (Home) 232 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC teiephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial.from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 3643
P PUBLIC SERVICE COMPANY OF COLORADO ,l0NELISTS FORT ST. VRAIN NUCLEAR GENERATING STATION page 44 of 74 MAINTENANCE Phone Lists Affected YODER, FRED Johnstown 587-4335 (Home) 232 (Work) Assigned To: NONE i
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where
, xxx is the three digit work extension, or by dialing 785-2223, and using l the switchboard operator. i FORM 372 3643 i
PP NE LISTS
. PUBLIC SERVICE COMPANY OF COLORADO ue FORT ST. VRAIN NUCLEAR GENERATING STATION page 45 of 74 MAINTENANCE Q.C.
Phone Lists Affected BASHLINE, TERRILL G. M Windsor 686-9763 (Home) 262 (Work) Assigned To: PCC DILLEN, TANDY M Greeley 356-3370 (Home) 262 (Work) Assigned To: PCC H0HN, JOHN M Platteville 785-6322 (Home) 260 (Work) Assigned To: PCC MCAFFEE, GEORGE K. M Fort Lupton 857-6498 (Home) 260 (Work) Assigned To: PCC MURPHY, GERALD J. M Platteville 785-2542 (Home) 262 (Work) Assigned To: PCC REDMOND, GEORGE M Evans 339-3152 (Home) 251 (Work) 890-1940 (Page Number) Assigned To: PCC
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator, l
i I FORM 372 22 3643 l l l
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. j P ENE LISTS PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 46 of 74 MAINTENANCE 0.C. Phone Lists Affected WYATT, RONALD M Fort Collins 493-3649 (Home) 262 (Work) Assigned To: PCC
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those ,
cases, the exchange for direct dial. from any outside line is given in ! parentheses to the left of the PSC system exchange. Telephone calls ; to FSV personnel from other PSC telephones is by dialing 785-1xxx, where i xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator. 1 l l FORM 372 22 - 3643 , i l l
PUBLIC SERVICE COMPANY OF COLORADO [,P$NELISTS
,, L FORT ST. VRAIN NUCLEAR GENERATING STATION page 47 of 74 MISCELLANE0US Phone Lists Affected JOHNSON, JAMES E. J Ft. Collins 482-3029 (Home) 491-5380 (Work)
Assigned To: NONE JOHNSON, JANET N Ft. Collins 482-3029 (Home) 491-5930 (Work) Assigned To: SEOC OLSON, HILOING G. Fort Collins 493-8797 (Home) 491-6558 (Work) 491-5450 (Work) Assigned To: NONE W Ac A ALL, MARI06 J Ft. Collins 484-0084 (Home) 491-5094 (Work) Assigned To: NONE PLUMLEE, G.L. , III E,J,Z Longmont 776-9541 (Home) 490 (Work) l 890-2225 (Pace Number) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial. from any outside line is given in parentheses to the left of the PSC systen exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO [PPHNELISTS FORT ST. VRAIN NUCLEAR GENERATING STATION Page 48 of 74 NUCLEAR DOCUMENTS Phone Lists Affected BOLLIG, PATRICIA L. 0 Evans 339-3972 (Home) 204 (Work) Assigned To: TSC CONNELLY, DANA 0 Evans 353-4575 (Home) 210 (Work) Assigned To: TSC COLLINS, MARGARET 0. O Johnstown 587-2172 (Home) 207 (Work) Assigned to: TSC EDWARDS, DONNA 0 Loveland 669-1680 (Home) 214 (Work) Assigned To: TSC , FLORES, ABBY Greeley 356-0038 (Home) 208 (Work) Assigned To: NONE FOSTER, BARB Longmont 772-5552 (Home) 205 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system l nLay require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 22 3643
NE LISTS
. PUBLIC SERVICE COMPANY OF COLORADO ,
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 49 of 74 NUCLEAR DOCUMENTS Phone Lists Affected VATCHER, SUE M. L Greeley 356-0351 (Home) 212 (Work) Assigned To: FCP KITZMAN, AUDREY L. O Flatteville 737-2578 (Home) 206 (Work) Assigned To: TSC LEHR, SUSAN M Westminster 422-1280 (Home) 451 (Work) Assigned To: PCC LIBAL, DEBBIE O Longmont 651-1404 (Home) 213 (Work) Assigned To: TSC MAROSTICA, CHRIS Johnstown 587-2104 (Home) 217 (Work) Assigned To: NONE RENVILLE, SCOTT l Thornton 427-2432 (Home) 216 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those ,
cases, the exchange for direct dial from any outside line is given in ' , parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator. FORM 372 - 22 3643
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P PUBLIC SERVICE COMPANY OF COLORADO ,fNELISTS FORT ST. VRAIN NUCLEAR GENERATING STATION Page 50 of 74 NUCLEAR DOCUMENTS Phone Lists Affected i SHAFER, TERRI M Johnstown l 587-4061 (Home) l 457 (Work) Assigned To: PCC STIEFF, CAROLE M Platteville 587-2500 (Home) 209 (Work) Assigned To: PCC STROH, CARLENE Johnstown 587-2150 (Home) 338 (Work) Assigned To: SAS l TAYLOR, MICHELLE l Fort Collins l l 484-6705 (Home) 337 (Work) Assigned To: CAS
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange fer direct dial.from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
F OR M 372 22 3643
g -- -__ _ _ _ _ PONE LISTS PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION page 51 of 74 l 1 OPERATIONS Phone Lists Affected ASHMORE, WILLARD J. Platteville 785-6344 (Home) 221 (Work) Assigned To: NONE DAHLSTROM, JOHN Greeley 353-6586 (Home) 221 (Work) Assigned To: NONE DECAT0 IRE, DAVID A. Johnstown 587-4038 (Home) 221 (Work) Assigned To: NONE DENISTON, MARTIN E. 0,U Longmont 776-3776 (Home) 219 (Work) Assigned To: TSC DICE, THOMAS J. Loveland 669-6950 (Home) 327 (Work) Assigned To: NONE EINIG, KENNETH J. Longmont 651-1279 (Home) 221 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 22 3643
f" . R LISTS
, PUBLIC SERVICE COMPANY OF COLORADO ,
T
;, FORT ST. VRAIN NUCLEAR GENERATING STATION page 52 of 74 l
l OPERATIONS . Phone Lists Affected EVANS, CHRISTOPHER J. Milliken l 587-2418 (Home) 221 (Work) Assigned To: NONE EVANS, DENNIS W. 0,U Longmont 776-9672 (Home) l 219 (Work) Assigned To: TSC FIELDS, M.D. Greeley 352-6976 (Home) 221 (Work) Assigned To: NONE FISHER, JEFFREY Greeley 330-6130 (Home) 221 (Work) Assigned To: NONE FOSTER, KENT E. Longmont 772-5552 (Home) 221 (Work) Assigned To: NONE FRANEK, WILLIAM J. C,E,J, Berthoud T,U,V, 532-3489 (Home) Y,Z 218 (Work) 890-0558 (Page Number) Assigned To: CR
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different i.elephone exchange. For those cases, the exchange for direct dial.from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 3643
e P NE LISTS PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENER ATING STATION Page 53 of 74 OPERATIONS 1 Phone Lists Affected I i FRAZIER, MICHAEL S. Northglenn l 457-3719 (Home) 221 (Work) Assigned To: NONE FROST, BRIAN C. Greeley 351-7430 (Home) 221 (Work) Assigned To: NONE HACKETT, LANE L. , JR. Greeley 330-1063 (Home) 221 (Work) Assigned To: NONE HAK, JOHN P. 0,0 Longmont 776-1904 (Home) 219 (Work) Assigned To: TSC HANLON, JOSEPH E. Windsor 686-9169 (Home) 221 (Work) Assigned To: NONE HANSEN, ERIC Greeley 356-3539 (Home) 220 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
h F OR M 372 - 22 3643
m-3 N LISTS PUBLIC SERVICE COMPANY OF COLORADO ue
- ~
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 54 of 74 OPERATIONS Phone Lists Affected HAWKINS, RUSSELL Greeley l 356-1326 (Home) 221 (Work) Assigned To: NONE HOCKENSMITH, DAN Loveland None (Home) 221 (Work) Assigned To: NONE HOLMES, DAVID B. Greeley 330-0757 (Home) 327 (Work) Assigned To: NONE l HOOD, DONALD P. E,J, l Longmont 0,U, 1 776-1843 (Home) Y 219 or 347 (Work) Assigned To: TSC HOOVER, JAMES A. Loveland 663-1835 (Home) 221 (Work) Assigned To: NONE l HUNTER, JOE J. 0,U Greeley 330-1411 (Home) l 219 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
PORM 372 - 22 3643
P PUBLIC SERVICE COMPANY OF COLORADO ,jNELISTS FORT ST. VRAIN NUCLEAR GENERATING STATION Page 55 of 74 I OPERATIONS Phone Lists Affected JOHNSON, DARRELL E. Platteville 785-6089 (Home) 221 (Work) Assigned To: NONE KASTEN, MICHAEL D. Platteville 785-2377 (Home) 221 (Work) Assigned To: NONE KEVAN, ROBERT L. Longmont 772-3922 (Home) 221 (Work) Assigned To: NONE K0LESKI, STANLEY V. Northglenn 457-3572 (Home) 221 (Work) Assigned To: NONE LAWLOR, BRUCE Evans 330-3312 (Home) 221- (Work) Assigned To: NONE LOPKOFF, WILLIAM W. Greeley 356-7677 (Home) 221 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system l may require use of a different telephone exchange. For those cases, the exchange for direct dial. from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls
, to FSV personnel from other PSC telephones is by dialing 785-1xxx, where l xxx is the three digit work extension, or by dialing 785-2223, and using l the switchboard operator. i F OR M 372 22 - 3643
c
; PUBLIC SERVICE COMPANY, OF COLORADO PP NE LISTS 4 FORT ST. VR AIN NUCLEAn GENERATING STATION page 56 of 74 b
OPERATIONS l s - h w Phone s Lists Affected
% 4 9
MAGNINIE, WAYNE H. ' Frederick - 833-4224 (Home) , 221 (Work) - Assigned To: NONE , MAYNARD, JOHN H.
> Longmont % s s 772-3634 (Home) ;
221 (Work) Assigned To: NONE MOORE, GAROLD E. Greeley 356-5378 (Home) 220 , (Mrk) Assigned To: NONE MORGAN, PHILIP C. Greeley 330-5269. - (Home) 221 (Work) A: signed To: NONE4. , MURPHY, SHAWN Thorton 427-7510 (Hor e) 221 (Work) -
' Assigned To: NONE N NETZEL,. KEN Longmont 772-4618 (Homo
, 220 (Work) 4 Assigned To: NONE
\
"3 NOTE: Calls to PSC_ phone's from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV persnnnel from other PSC telephones is by dialing 785-1xxx, where
! xxx is the three digit work extension, or by dialing 785-2223, and using I the switchboard operator. ORM 372 - 22 M
PP 4E LISTS PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VR AIN NUCLEAR GENER ATING STATION Page 57 of 74 OPERATIONS Phone Lists Affected O'HAGAN, HUGH J. 0,0 Longmont 776-8232 (Home) 219 (Work) Assigned To: TSC REIGEL, GLEN V. 0,U Greeley 330-4235 (Home) 219 (Work) Assigned To: TSC SHAFER, STEVEN Platteville 785-6042 (Home) 220 (Work) Assigned To: NONE TRUMBLEE, DENNIS Platteville 785-2593 (Home) 221 (Work) Assigned To: NONE VANDENB00GAARD, W. J. Longmont 651-3732 (Home) 221 (Work) Assigned To: NONE
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VAN DYKE, JEROME G. 0,U Longmont 772-2476 (Home) 219 or 346 (Work) Assigned To: TSC or CR
- NOTE: Calls to PSC phones from outside of the PSC telephone system ray require use of a different telephone exchange. For those cases, the exchange for direct dial. from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls i to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 - 22 3643
* . 1 I PENE LISTS l FUBLIC SERVICE COMPANY OF COLORADO ~
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 58 of 74 ! l l OPERATIONS Phone Lists Affected VIGIL, ANTHCNY L. Gilcrest 737-2753 (Home) 221 (Wark) Assigned To: NONE I WEIDERSPON, GARY L. l Greeley l 356-7038 (Home) l 221 (Work) i Assigned to: NONE WELLER, JACK R. Johnstown 587-2984 (Home) 221 (Work) Assigned 10: NONE s
- NOTE: Cells to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, th,e' exchange for direct dial from any outside line is given in parehthases to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extensinn, or hy dialing 785-2223, and using the switchboard operator.
PORM 372 . 3643
N L$$ PUBLIC SERVICE COMPANY OF COLORADO e 2j" FORT ST. VRAIN NUCLEAR GENERATING STATION page 59 of 74 RADIATION PROTECTION Phor.e Lists Affected BROWN, JAMES V. M Evans 339-3972 (Home) 245 (Work) Assigned To: PCC GLAHN, PAUL R. M Northglenn 450-5292 (Home) 245 (Work) Assigned To: FCC HUTCHINS, LESTER C. M Greeley 330-7187 (Home) 245 (Work) Assigned To: PCC l MADISON, GORDON S. M l Firestone l 833-2278 (Home) l 245 (Work) l Assigned to PCC McGAFFIC, VERNON J. M Johnstown 587-2752 (Home) 278 (Work) Assigned To: TSC MILLER, DONALD M Loveland 663-3595 (Home) i 279 (Work) Assigned To: TSC
- NOTE: Calls to PSC phones from outside of the PSC telephone system ,
may require use of a different telephone exchange. For those l cases, the exchange for direct dial from any outside line is given in l parentheses to the left of the PSC system exchange. Telephone calls l to FSV personnel from other PSC telephones is by dialing 785-1xxx, where ! xxx is the three di;it work extension, or by dialing 785-2223, and.using the switchboard operator. FORM 372 22 - 3643
.; PUBLIC SERVICE COMPANY OF COLORADO (,PHONELISTS FORT ST. VRAIN NUCLEAR GENERATING STATION Page 60 of 74 l
l RADIATION PROTECTION i Phone Lists Affected MORSE, KEITH M Greeley 353-6163 (Home) 245 (Work) Assigned To: PCC NASVESCHUK, KENT L. M Longmont 651-6254 (Home) 245 (Work) Assigned To: PCC O'00NOGHUE, E. JOHN M Northglenn l 452-3514 (Home) 245 (Work) Assigned To: PCC POET, STEWART M Longmont 652-2297 (Home) 279 (Work) Assigned To: TSC PROCHOWNIK, MICHAEL R. M Platteville 785-6010 (Home) 279 (Work) Assigned To: TSC RIMA, STEVEN D. M Longmont 772-4068 (Home) 279 (Work) Assigned To: TSC
- NOTE: Calls to PSC phones from outside of the PSC telephone system I m.ay require use of a different telephone exchange. For those cases, the exchange for direct dial.from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
PORM 372 22 3643
. PUBLIC SERVICE COMPANY OF COLORADO (,[,PhNELISTS FORT ST. VRAIN NUCLEAR GENERATING STATION page 61 of 74
_RASIATION PROTECTION Phone Lists Affected l SCHLEIGER, TIMOTHY E. 0,5 Platteville 785-6314 (Home) 242 (Work) Assigned To: TSC SHERROW, STEVEN S. M Greeley 353-1338 (Home) 245 (Work) Assigned To: PCC l SIEG, STEVEN E. M l Loveland l 663-3468 (Home)
- 245 (Work) -
1-l Assigned To: PCC l VALENTINE, GRANT D. M l Berthoud l 532-4861 (Home) l 245 (Work) l Assigned To: PCC WOODARD, WILLIAM E. O Longmont I 678-0818 (Home) 244 (Work) Assigned To: TSC -
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any.outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
1 FORM 372 22 3643 l
P PMNE LISTS PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Pago 62 of 74 RESULTS Phone Lists Affected ANDERSON, BARNEY J. Greeley 351-0722 (Home) 286 (Work) Assigned To: NONE l BALL, JOSEPH W. Denver 477-6013 (Home) 286 (Work) , Assigned To: NONE l BARTA, BRADLEY G. Denver 426-1832 (Home) i 256 (Work) ~~ --
~
Assigned To: NONE l l l BROWN, DANIEL J. l Lyons 823-6127 (Home) j f 286 (Work) i Assigned To: NONE l BURCHFIELD, ROBERT S. O Greeley 251-0373 (Home) 249 (Work) Assigned To: TSC
- BURGESS, CHARLES R.
Platteville 785-2154 (Home) 286 (Work) Assigned To: NONE -
- NOTE: Calls to PSC phones from outside of the PSC telephone system gy require use of a different telephone exchange. For those cases, the exchange for direct dial.from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 22 3643
P E LISTS PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION Page 63 of 74 ! j RESULTS Phone Lists Affected COLE, JAMES W. Johnstown 587-2989 (Home) 286 (Work) Assigned To: NONE CROWE, CURTIS W. l Lafayette l 665-7997 (Home) 247 (Work) Assigned To: NONE DUNHAM, DARYL Keensburg 732-4342 (Home) 288 (Work)
- ------ -- -~
Assigned To: NONE GALE, MIKE Gilcrest 737-2521 (Home) 286 (Work) Assigned To: NONE G0FF, ALAN Westminster 428-4421 (Home) 255 (Work) Assigned To: NONE JOHNSON, THOMAS Lafayette 665-9507 (Home) 258 (Work) Assigned To: NONE
" NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 - 22 3643
NE LISTS PUBLIC SERVICE COMPANY OF COLORADO $PP FORT ST. VRAIN NUCLEAR GENERATING STATION pgge 64 of 74
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RESULTS Phone Lists Affected JOHNSON, TINA Denver 452-5436 (Home) 257 (Work) Assigned To: NONE KENNEDY, THOMAS Broomfield 469-3531 (Home) 286 (Work) Assigned To: NONE McCAULEY, JERRY 0 Loveland 667-0635 (Home) 248 (Work) Assigned To: TSC NELSON, DON M. M Johnstown 587-4189 (Home) 246 (Work) Assigned To: PCC O'CONNOR, JAMES P. Denver 457-4882 (Home) 259 (Work) Assigned To: NONE ODENBAUGH, KATHY Platteville , 737-2306 (Home) 286 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For shose ,
cases, the exchange for direct dial from any outside line is given in I parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator. F ORM 372 3643
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NE LISTS PUBLIC SERVICE COMPANY OF COLORADO $PP,
. FORT ST. VRAIN NUCLEAR GENERATING STATION Page 65 of 74 RESULTS Phone Lists Affected PETTINGER, ALBERT J.
Brighton 536-4333 (Home) 288 (Work) Assigned To: NONE PINNER, R.S. JOE Greeley 330-9075 (Home) 286 (Work) Assigned To: NONE SCHMIDT, A.C. Louisville 666-6955 (Home) 286 (Work) Assigned To: NONE SHIBATA, BRAD Denver 388-2160 (Home) 286 (Work) Assigned To: NONE TELAROLI, JOHN Loveland 669-0267 (Home) 282 (Work) Assigned To: NONE WEBER, DAVID LEE Johnstown 587-4186 (Home) 286 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system gay require use of a different telephone exchange. For those cases, the exchange for direct dial.from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 - 22 3643
P PUBLIC SERVICE COMPANY OF COLORADO ,jNELISTS FORT ST. VRAIN NUCLEAR GENERATING STATION Page 66 of 74 SCHEDULING / STORES l I l l Phone Lists Affected 1 l BENEDICT, MARGIE M. M Greeley 353-7209 (Home) 313 (Work) Assigned To: PCC BLOSSOM, MIKE M Platteville 785-6302 (Home) 297 (Work) Assigned To: PCC ERWIN, RICHARD W. M Greeley 330-7178 (Home) 321 (Work) Assigned To: PCC GLASS, GERALD L. J,Y Brighton 659-4118 (Home) 253 (Work) Assigned To: PCC HAMBLIN, RICHARD D. M Loveland 667-1703 (Home) 254 (Work) Assigned To: PCC HARDING, CLIFF M Platteville 785-2398 (Home) 311 (Work) Assigned To: PCC
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and usir.g the switchboard operator.
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO P NE LISTS FORT ST. VRAIN NUCLEAR GENERATING STATION page 67 of 74 SCHEDULING / STORES l l l Phone Lists Affected HAYS, KAREN M l l Denver j l 778-7702 (Home) ; 319 (Work) l Assigned To: PCC HOLCOMB, WALTER E. M Greeley 330-2068 (Home) 312 (Work) Assigned To: PCC HORIHAN, DARLENE Longmont M 776-7976 (Home) 250 (Work) Assigned To: PCC POWERS, G. M Westminster 426-1623 (Home) 252 (Work) Assigned To: PCC REED, DALE L. M Platteville 785-2159 (Home) 314 (Work) Assigned To: PCC TEEL, RICHARD M Henderson 288-1959 (Home) 261 (Work) Assigned To: PCC l
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, a'nd using the switchboard operator.
l PORM 372 22 - 3643 k .
~~
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P NE LISTS PUBLIC SERVICE COMPANY OF COLORADO ,
- FORT ST. VRAIN NUCLEAR GENERATING STATION page 68 of 74 SECURITY l l
l 1 Phone ! Lists Affected ' l ALPS, DONALD R. U l Longmont l 772-9075 (Home) 298 (Work) Assigned To: NONE AMICK, DAVID B. Longmont 772-9378 (Home) 299 (Work) Assigned To: NONE BATES, WILLIAM S. Ft. Collins 484-2966 (Home) 299 (Work) Assigned To: NONE BENNETT, MICHAEL B. Longmont l 776-8311 (Home) 299 (Work) Assigned To: NONE HART, W. DARRIEL Denver 371-6745 (Home) 299 .(Work) l 855-1744 (Page Number) Assigned To: NONE HOLLAND, CHARLES C. Aurora 344-1327 (Home) 299 (Work) Assigned To: NONE
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
t FORM 372 22 3643
P NE LISTS PUBLIC SERVICE COMPANY OF COLORADO , Page 69 of 74 FORT ST. VRAIN NUCLEAR GENERATING STATION TECHNICAL SERVICES Phone Lists Affected BANAGAS, LAURIE Loveland 663-4434 (Home) 273 (Work) Assigned To: NONE BURROWS, RICHARD Fort Collins 493-4258 (Home) l 265 (Work) Assigned To: NONE CLAYTON, OWEN J. Loveland 663-3939 (Home) 277 (Work) Assigned To: NONE DAUM, MICHAEL J. Aurcra 690-9652 (Home) 269 (Work) Assigned To: NONE DICKERSON, ROBERT A. M Thornton 287-6089 (Home) 273 (Work) Assigned To: PCC i l
- NOTE: Calls to PSC phones from outside of the PSC telephone system l m_g require use of a different telephone exchange. For those l l cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls '
to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator. FORM 372 22 3643
P PUBLIC SERVICE COMPANY OF COLORADO ,[NELISTS
,e FORT ST. VRAIN NUCLEAR GENERATING STATION page 70 of 74 l
TECHNICAL SERVICES l
. Phone Lists Affected EGGEBROTEN, JAMES E,U Longmont 651-1523 (Home) 285 (Work) l 890-2220 (Page Number)
Assigned To: TSC FRYE, DUANE L. M Johnstown 587-4768 (Home) 276 (Work) Assigned To: PCC GAPPA, ROBERT Fort Collins 482-6551 (Home) l 283 (Work) Assigned To: NONE HEATH, DAWN L Fort Collins 223-5121 (Home) 272 (Work) Assigned To: FCP HELLER, ROGER A. O Longmont 772-1093 (Home) 284 (Work) Assigned To: TSC HILL, JIM F. Johnstown 587-2553 (Home) 276 (Work) l Assigned To: NONE l
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FORM 372 22 3643
P E LISTS PUBLIC SERVICE COMPANY OF COLORADO e l . FORT ST. VRAIN NUCLEAR GENERATING STATION page 71 of 74 TECHNICAL SERVICES Phone Lists Affected JOHNSON, SHARILYN O Loveland 663-1431 (Home) 267 (Work) Assigned To: TSC JOSEPH, MARK
-Westminster 465-1248 (Home) 275 (Work)
Assigned To: NONE MERRITT, DARLA L Gilcrest 737-2339 (Home) 271 (Work) Assigned To: FCP NOVACHEK, FRANK J. O Thornton 457-8034 (Home) 270 (Work) 890-1941 (Page Number) Assigned To: TSC REED, ASA B. E,U Longmont 772-5312 (Home) 325 (Work) 890-1942 (Page Number) Assigned To: TSC
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial. from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit werk extension, or by dialing 785-2223, and using the switchboard operator.
PORM 372 22 3643
RERP PHONE LISTS PUBLIC SERVICE COMPANY OF COLORADO Issue 24 l i
, FORT ST. VR AIN NUCLEAR GENERATING STATION Page 72 of 74 l l
TECHNICAL SERVICES 1 Phone Lists Affected SHERMAN, RUSSELL Lafayette 666-9836 (Home) 268 (Work) Assigned To: NONE SILLS, JUDD M. E,0,0 l Fort Collins l 221-5059 (Home) 265 (Work) l 890-2223 (Page Number) Assigned T7: TSC STUART, DAVE Longmont 651-1927 (Hr.ne) 274 (Work) Assigned To: NONE i
- NOTE: Calls to PSC phones from outside of the PSC telephone system I may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel frem other PSC telephones is by dialing 785-1xxx, where i
xxx is the three digit work extension, or by dialing 785-2223, and using l the switchboard operator. l l l I FORM 372 22 3643
PMNE LISTS PUBLIC SERVICE COMPANY OF COLORADO e FORT ST. VR AIN NUCLE AR GENERATING STATION Page 73 of 74 TRAINING Phene Lists Affected BEARLY, PHILIP B. M Loveland 669-6636 (Home) 455 (Work) Assigned To: PCC HOOPER, RON 0. M Northglenn 452-3614 (Home) 458 (Work) Assigned To: PCC MOLER, ROBERT M Longmont 772-9357 (Home) l 456 (Work) Assigned To: PCC MURPHY, MIKE M Golden 279-6762 (Home) l 454 (Work) Assigned To: PCC RIVERA, RICHARD M Loveland 667-1906 (Home) l 453 (Work) Assigned To: PCC SWITZER, JOSEPH R. M Johnstown 587-4134 (Home) 452 (Work) Assigned To: PCC
- NOTE: Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial.from any outside line is given in parentheses to the left of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where l
xxx is the three digit work extension, or by dialing 785-2223, and using i the switchboard operator. I FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO ( P WNE LISTS FORT ST. VR AIN NUCLE AR GENERATING STATION page 74 of 74 TRAINING Phone Lists Affected WILLFORD, STEVE R. J,Y Brighton 659-5258 (Home) 450 (Work) Assigned To: PCC f l l l
- NOTE: Calls to PSC phones from outside cf the PSC telephone system may require use of a different telephone exchange. For those cases, the exchange for direct dial from any outside line is given in parentheses to the lef t of the PSC system exchange. Telephone calls to FSV personnel from other PSC telephones is by dialing 785-1xxx, where xxx is the three digit work extension, or by dialing 785-2223, and using the switchboard operator.
FOMM 372 22 3643
3 MKL F % PUBLIC SERVICE COMPANY OF COLORADO ,,00X 2 c s jo g ogg FORT ST. VRAIN NUCLEAR GENERATING STATION
** 8/6/84 RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATION i i
ISSUE EFFECTIVE NO. SUBJECT NUMBER DATE l RERP-ECP Executive Command Post Procedure 8 03-06-84 l RERP-EXP Emergency Exposure Guidelines 2 08-06.-84 l RERP-FCP Forward Command Post Procedure 11 08-06-84 l RERP-FIELO Field Monitoring Procedure 6 08-06-84 l RERP-HOME Home Packet for Off-Shift l Notifications 12 08-06-84 l RERP-ORG FSV Emergency Organization and - l Responsibilities 6 08-06-84 l RERP-PAG Protective Action Guideline l Recommendations 3 08-06-84 1'RERP-PCC Personnel _ Control Center Procedure 14 08-06-84 l RERP-SEOC State Emergency Operations Center l Procedure 8 08-06-84 l RERP-SURVEY Inplant/Onsite Radiological l Monitoring 4 08-06-84 l RERP-THYROID Thyroid Blocking Agent l Administration 3 08-06-84 1 FORM 372 22 3443
RERP-E PUBLIC SERVICE COMPANY OF COLORADO Issue FORT ST. VRAIN NUCLEAR GENERATING STATION e 5 gT$N' l
?DY fg8 TITLE: EXECUTIVE COMMAND POST PROCEDURE 90% ~ 60Ti
,39 3
& 378 5 t D poN ISSUANCE AUTHORIZED g,, go ,,. j, y ,, g' 90 8
- BY erC// P1cC i, l PORC EFFECTIVE R EVIEW Pmc 5 8 0 AUG 2 - 1984 DATE b-b- k TABLE OF CONTENTS Section Description Page 1.0 Criteria for Implementation................................... 2 2.0 Procedure..................................................... 2 3.0 Resoonsibilities ............................................. 3 4.0 References ................................................... 4 5.0 Referenced or Supporting Procedures........................... 5 Figure 1 Executive Command Post Organization..................... 1 Figure 2 Emergency Organization ................................. 1 Attachment 1 Support Equipment / Material........................... 1 Checklist 1 ECP Di rector ' s Checkl i st. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Work /Datasheet/Checkl i st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e Re p o rti n g S he e t* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
1 FORM 372 22 3642 l
F. . PUBLIC SERVICE COMPANY OF COLORADO g[ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 5 ESTABLISHING THE EXECUTIVE COMMAND POST l l i 1.0 Criteria for Implementation the FSV Radiological Emergency Response Plan (RERD) When requires augmentation of resources, the Executive Command Post Director shall activate the Executive Cc= mand 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 l RERP-HOME or RERP PHONE LISTS). It is the responsiblity of the ECP Alternate Director, or the first individual ccntacted by the ECP Director, to ensure that the l nctifications are made. Refer to the call list for the ECP for instructions, names, and telephone numbers. 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 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, 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 su;. ports PSC personnel stationed at onsite and offsite energency centers.
. l l
1 P O R M 372222343 1
PUBLIC SERVICE COMPANY OF COLORADO [ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 5 3.0 Resoonsibilities 3.1 Executive Command Post Director - Checklist 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, l communications, and clerical personnel, and briefs ' ECP staff. 3.1.5 Dispatches headquarters management, administrative and technical support personnel as requested by the Corporate Emergency Director (CED). 3.1.6 Terminates the ECP when the emergency condition is j terminated. i 3.2 Communications Support 3.2.1 Establish communications with the Forward Command l Post (FCP) (see RERP PHONE LISTS for phone numbers, l if required). 3.2.2 When instructed to do so, inform the FCP that the l ECP is manned and ready and of the location (Room 620 or Lookout Center). 3.2.3 Receive status of plant and emergency and assessment of condition and inform ECP Director, who will brief the ECP staff. 3.2.4 Request location of Personnel Control Center (PCC). 3.2.5 Maintain communications flow between ECI' and FCP. 3.3 Clerical Support . Clerical assistant (s) keep an ongoing record (log) of all actions taken. A PORM 372 22 3643
Y PUBLIC SERVICE COMPANY OF COLORADO u _ FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5 l 3.4 Manager of Technical Support l l 3.4.1 Provide CED and onsite emergency operations with i technical advice in nuclear, mechanical, civil, and I electrical engineering. ' 3.4.2 Provide engineering support, technical experts, and I consultants as requested. (See RERP-Sup0RG, should the need for non-PSC orgar.1 ation assistance be identified.) 3.5 Manager of Media Relations 3.5.1 Coordinates communications between the ECP and FCP. 3.5.2 Assists the ECP Director and PSC media relations personnel in preparation of press releases, announcements, and interviews. 3.6 Manager of Resources 3.6.1 Coordinates provision of manpower and equipment from within PSC, and from consultants / contractors, to supports on-site emergency operations. 3.6.2 Provides requested technical and craft manpower; personnel or consultants for engineering / design and contruction reviews; temporary housing, office, transportation, and contruction equipment; purchasing, financial, legal and general office support; and, food deliveries and related logistics support to designated emergency operations. (See RERP-SUPORG, should the need for non-PSC organization assistance be identified.) 3.7 Manager of Security 3.7.1 Coordinates PSC security operations with public law enforcement agencies. 3.7.2 Acquires additional security manpower, hardware, and equipment, as requested. 4.0 References 4.1 FSV Radiological Emergency Response Plan l l l - l l I l1 PORM 372 22 3643 ) i
3 PUBLIC SERVICE COMPANY OF COLORADO RERP :rP
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Issue 8 FORT ST VR AIN NUCLEAR GENERATING STATION Page 5 of 5 5.0 Referenced or Succortino Procedures 5.1 RERP-FCP, Forward Command Post Procedure 5.2 RERP-HOME, Home Packet for Off-shift Notifications 5.3 RERP-SURVEY, Inplant/Onsite Radiological Surveys 5.4 RERP-SUPOR 3, Use and Coordination of Non-PSC Support Organizations i . 1 1 PORM 372 22 3643
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n e .. e o EXECUTIVE COMMAND POST ORGANIZATION c w Fort St.Vrain Nuclear Generating Station , C O O x DIRECTOR - EXECUTIVE COM& LAND POST $ .d C a <3 2 A
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-I NUCLE R SERVICES RELATIONS VP FINANCE & TREASURY COORDINATOR O
- ENGINEERING SUPPORT
- MEDIA RELATIONS
- MANPOWER SUPPORT
- SECURITY COORDINATION ORDINATION g
- TEC11NICAL EXPERTS
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- LAW ENFORCEMENT LI AISON Q
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3 PUBLIC SERVICE COMPANY OF COLORADO R5RP :CP rigure 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issut 8 Page 1 of 1 1 l l l l FIGURE 2 EMERGEiCY ORGANIZATION I
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w l, M m5 4 8 .. l l le FORM 372 3643
Y ' RERP-ECP PUBLIC SERVICE COMPANY OF COLORADO Attach. 1
' ~
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 8 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.
- 5. Maps a) Fort St. Vrain area and environs.
b) Regional.
- 6. Fort St. Vrain Station layout drawings (see RERP-SURVEY).
- 7. Other support available, a) Reproduction Equipment.
b) Commerical television station monitoring equipment. c) Radio-television recording equipment. '1 PORN 372 22 3643
4' c4 ggge_eep
, . 3. PUBLIC SERVICE COMPANY OF COLORADO Checklist 1 l
' Fo:T y vs Au. n r:.E An ces s Ame, ST Ai!ON ue 8 9
ECP '0IRECTOR'S CHECKLIST s NOTE: All information is to be recorded by the Clerical Assistant 3.. , ,f Time
- 1. Personnel Accountability l a. Manager of Technical Support Nuclear Site l Engineering Manager / Nuclear Services Manager
\ '\ s
- b. Manager of Media Relations - VP Public Affairs /
Manager of Public 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.
s 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.
s , i
-}
i k. 1 i
' j
\
,, l FoMM 372 22 3443
- p. .
- ) H . .- _ . - -
D RERP-ECP PUBLIC SERVICE COMPANY OF COLORADO WS/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 8 Page 1 of 3 Work /Datasheet/ Checklist Control List Worksheet No. Title Number Cooies None N/A N/A Datasheet No. None N/A N/A Checklist No. 1 ECP Director's Checklist 2 O FORM 372 22 3643 i.
'4 =' R.. PUBLIC SERVICE COMPANY OF COLORADO g,}i)Q [ FORT ST. VR AIN NUCLE AR GENERATING STATION Issue 8 Page 2 of 3
\
l l 1 FORMS USE REPORTING SHEET l Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at
. The following forms have been utilized from tnis copy:
Worksheet Numbers Copies Used Datasheet Numbers Copies Used
. Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting . form. When this form is recei.ed, it will be necenary to replace the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book.
1 FORM 372 22 3643
4 RERP-ECP PUBLIC SERVICE COMPANY OF COLORADO WS/DS/CL FORT ST. VRAIN NUCLGAR GENERATING STATION Issue S Page 3 of 3
)
l FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: 1 Nuclear Documents Specialist
- Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the 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.
F ORM 372 3643
4 SERVICE COMPANY OF COLORADO [g ; r' - 3*. ~ ; PUBLIC FOAT ST VRAIN twCLE Alt GENE R AllNG S1 All0N Issut 8
. Page 1 of 1 ECP DIRECTOR'S CHECKLIST NOTE: All information is to be recorded by the Clerical Assistant Time
- 1. Personnel Accountability l a. Manager of Technical Support - Nuclear Site l Engineering Manager / Nuclear Services Manager
- b. Manager of Media Relations - VP Public Affairs /
Manager of Public 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 informed that ECP is manned and ready and location. S. Status of plant and emergency and assessment of condition received from FCP.
- 6. Location of PCC requested and received.
- 7. Staff briefing conducted.
I o 1 FORM 372 22 2543
- p. 4
~
]' ' , ' ,' P U B L I C SERVICE COMPANY OF COLORADO "$$bst1 C I FORT ST. VR AIN NUCLE Ari GErd"4 AllNG ST ATION Issue 8 Page 1 of I !
ECP DIRECTOR'S CHECKLIST NOTE: All information is to be recorded by the Clerical Assistant l Time
- 1. Personnel Accountability l a. Manager of Technical Support - Nuclear Site l Engineering Manager / Nuclear Services Manager
- b. Manager of Media Relations - VP Public Affairs /
Manager of Public 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 - Stcretary to VP Accounting.
- 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.
FORM 372 22- 3443 V* e -
4 7., ' PUBLIC SERVICE COMPANY OF COLORADO ('s L FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 8 Page 1 of 3 Work /Datasheet/ Checklist Control List Worksheet No. Title Number Conies None N/A N/A Datasheet No. None N/A N/A Checklist No. 1 ECP Director's Checklist 2 l
=
l j 9 FORM 372 22 3643 _ - _ . 1
' ~ ~~ ~
4 " ' ,, 7 Fut5LIU s t:MVIU t: UUNIVANY N W5/05/CL l-? FORT ST. vRAIN NUCLEAR GENERATING STATION lssue 8 rt Page 2 of 3 FORMS USE REPORTING SHEET l Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emargency Response Plan Implementing Procedures, 200K NO. , located at
. The following forms have been utilized from this copy:
Worksheet Numbers Copies Use_d Datasheet Numbers Copies Used Checklist Numbers Copies Used 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 - the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. $ FORM 372 22 3643
-. - -..~..v-%..~....,.-... --_-; , . ~ . , _ , . .m . . . . . . , _ . . . . _ , . . . . _ _
J' RERP-ECP PUBLIC SERVICE COMPANY OF COLORADO WS/DS/CL FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 8
,,- Page 3 of 3 FORMS USE REPORTING SHEET (Continued)
COMMENTS Reported By: _ Date: l Nuclear Documents Specialist Date Received _ _ _ Date Replaced l* Nuclear Documents Specialist will transmit this form to the 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, i
I 1
.- a.
l6 _ l FORM 372 - 22 3643 l l
l PUBLIC SERVICE COMPANY OF COLORADO RW-W Issue 2 6 X FORT ST. VR AIN NUCLEAR GENERATING STATION page 1 of 4 FORT ST. VRt,il,' TITLE: EMERGENCY EXPOSURE GUIDELINES NON CONTROLLED COPY VERIFY!SSUE STATU! ETH DOCUMENT CENTER ISSUANCE AUTHORIZED g,, g,.m L,,I PRIOR TO USF FORM 372-22 .7 BY a &l *Yl]e/]O PORC EFFECTIVE Review PORC 5 8 0 AUG2 - 1984 DATE b" b" b Section Description Pace General ........................................................... 2 1.0 Criteria For Imo1ementation................................... 2 2.0 Procedure..................................................... 2 3.0 Responsibilities ............................................. 3 4.0 References ................................................... 3 5.0 Referenced or Supporting Procedures........................... 4 Table 1 Exposure Criteria for Emergency Workers................. 1 Datasheet 1 Job Briefing Verification Sheet ................. 1 Work /Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Forms Use Reporting Sheet *......................................... 2 ANYTIME A VORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE. 'a 'b lL FORM 372 22 3642
IE
- RERP-EXP o
PUBLIC SERVICE COMPANY OF COLORADO Issue 2 o FORT ST. VR AIN NUCLEAR GENER ATING STATION Page 2 of 4 General This procedure provides guidance and maximum exposure criteria for use in the event of a severe radiological emergency at Fort St. Vrain where it may be necessary for members of emergency teams to exceed established quarterly or annual radiation exposure limits. The guidance contained herein is given as dose equivalent limits, as it is recognized that certair critical station / lifesaving functions may be required to be carried out under extreme radiological conditions, and that, in the context of an accident situation, these actions may require emergency workers to receive doses in excess of occupational limits. These exposures may be justifiable if it may be determined that benefits to society are being achieved, and that every reasonable effort is being made to maintain emergency workers doses as low as reasonably achievable. 1.0 Criteria for Implementation This procedure shall be implemented only under the ensuing conditions: 1.1 The need to exceed established radiation exposure limits to save a life or minimize the consequences of an incident has been identified. 1.2 A radiological survey and/or installed radiation monitor readings (airborne and area) have been utilized to provide a projected whole body dose required to complete the work. 2.0 Procedure Table 1 of this procedure summarizes the radiological dose equivalent limits for an emergency situtaion as defined in Section 1 of this procedure. 2.1 Personnel accepting emergency assignments where they may receive radiation dose equivalents in excess of occupational limits shall be volunteers of good health (preferably males over 45 years of age). 2.2 Emergency personnel volunteering for these missions shall be made broadly familiar with the potential risks associated with the projected radiation exposure. 2.3 Any such exposure under the provisions of this procedure i are to be limited to once in a lifetime. 2.4 Personnel shall not enter any area where dose rates are unknown or unmeasurable. I h
# l FORM 372 - 22 3643
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PUBLIC SERVICE COMPANY OF COLORADO ((RD: sue 2 FORT ST. VRAIN NUCLEAR GENERATING STATN)N Page 3 of 4 2.5 Personnel shall be provided high and low range pocket dosimeters suitable for measurement of anticipated exoosure levels, in addition to permanently recording film badges and any extremity monitoring devices deemed appropriate by the Senior Health Physics Representative at the Technical Support Center or a delegated Health Physics Technician at the Personnel Control Center. 3.0 Responsibilities 3.1 Personnel Control Center (PCC) Director The PCC Director is responsible to authorize volunteers selected for high exposure assignments (in excess of occupational dose equivalent limits) to receive such doses and to ascertain that documentation of such authorization is performed on Datasheet 1, provided herein. He shall confer with the most Senior Health Physics Representative at the TSC, or his designee, prior to dispatching any such volunteer personnel from the PCC with regard to proper personnel monitoring devices and protective clothing / devices required for the assignment. 3.2 Senior Health Physics Representative (TSC) The Senior Health Physics Representative at the TSC will be responsible to assess monitoring data with regards to emergency team assignments and evaluate the projected assignment dose and any requirements for stay time, personnel monitoring, and protective clothing and equipment. In conjunction with these responsiblities, the senior Health Physics representative shall also consider the need for radioprotective drugs (see RERP-THYROID). 3.3 Technical Support Center Director The TSC Director has overall responsibility for the direction of onsite emergency activities, and, as such, must be responsible for determining the need for elevated-risk assignments where occupational dose limits would be exceeded, i 1-l6* PORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO o FORT ST. VR AIN NUCLEAR GENERATING STATION Page 4 of 4 3.4 Personnel Accountability and Exposure Controller (PCC) When requested by the PCC Director, assure proper documentation of projected dese, staytimes, and protective / dosimetric equipment requirements specified by the senior Health Physics representative at the TSC. Perform job briefing and sign Datasheet 1. 4.0 References 4.1 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, U.S.E.P. A. , June 1980. 4.2 10CFR20, Code of Federal Regulations. 4.3 NCRP 42, Radiolocical Factors Affecting Decision-Making in a Nuclear Attack, National Council on Radiation Protection , and Measurements, 1974. l l 5.0 Referenced or Supoorting Procedures l 5.1 RERP-ORG, FSV Emergency Organization and Responsiblities 5.2 RERP-THYROID, Thyroid Blocking Agent Administration 5.3 RERP-DOSE, Offsite Dose Calculation Methodology 5.4 RERP-PCC, Personnel Control Center Procedure l 1 1& I &^ m FORM 372 21 3643 l
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*'c FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 2 of 3 FORMS USE REPORTIN3 SHEET l Nuclear Documents Specialist:
This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at
. The following forms have been utilized from this copy:
Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used 1 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
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COMMENTS Reported By: Date: l Nuclear Documents Specialist
- Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the 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.
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PUBLIC SERVICE COMPANY OF COLORADO $[((3 ) y'} L, - FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 L= t _ Page 1 of 2 l DATASHEET 1 JOB BRIEFING VERIFICATION SHEET
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- Volunteers Names Date Time Destination Projected Dose Complete one Job Briefing Sheet for each high exposure emergency team.
Comments I4 i9 FOMM 372 22 3643
RERP-EXP
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[h FORT ST. VR AIN NUCLE AR GENERATING STATiCN lssue 2 Page 2 of 2 1 Job Briefing - Summarize Details (Dosimetry, Protective Clothing / Equipment, Stay Time, Etc.) Name of Health Physics Representative Contacted Signature Personnel Accountability and Exposure Cont. Date Time l j l conu sn. 22.as4
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FORM 372 3643
4: PUBLIC SERvlCE COMPAN Y OF COLORADO Datasheet 1
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1 Job Briefing Verification Sheet 10 Checklist No. None N/A N/A
- FORM 372 22 3643
] , , a PUBLIC SERVICE CO3SiMMW (oW C(oL@M/AlgXol j FORT ST. VR AIN NUCLE AR GENER ATING STATION W5/05/CL lssue 2 Page 2 of 3 1 FORMS USE rep 0RTING SHEET l Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a l controlled copy of the Radiological Emergency Response Plan ! Implementing Procedures, BOOK NO. , located at l . The following forms have been utilized from this copy: Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used 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. +
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) PUBLIC SERVICE COMPANY OF COLORADO FORT ST VRAIN NUCLE AR GENERATING STATION Issue 2 (Qt ht Page 3 of 3 FORMS USE REPORTING SHEET (Continued)
COMMENTS Reported By: Date: l Nuclear Documents Specialist Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the 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 1 l 1 1 ( I FORM 372 22 3643 l
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% PUBLIC SERVICE COMPANY OF COLORADO RERP-FC'o Issue l1
. FORT ST. VRAIN NUCLE AR GENERATING STATION Page 1 of 8 i l FET ST. VII@
TITLE: FORWARD COMMAND POST PROCEDURE nnt;. CONI W LED l un:Y iSS'.'E l SU~CS VM gyENT CEhIEE rg0:TC ubi ISSUANCE A w n s., y 4 AUTHORIZED p:w 2~O3E,S BY T i W,, 4*1 J M REV Ew PORc 5 8 0 AUG 2 - 1984 EFlTE b b-TABLE OC CONTENTS Section Description Page 1.0 C ri teri a f or Impl emen tati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Procedure.......................... ......................... 3 3.0 Responsibilities ............................................ 4 4.0 References .................................................. 7 5.0 Referenced or Succorting Procedures.......................... 7 Figure 1 Location Map .......................................... 1 Figure 2 Fo rwa rd Command Po st Fl oor Pl a n . . . . . . . . . . . . . . . . . . . . . . . . 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 l' Support Equipment / Materials .................... 1 l Datasheet 1 Forward Command Post Radiological Status Board.................................... 1 l Datasheet 2 Plant Status Board.............................. 1 Checklist 1 Corporate Emergency Director's Checklist. . . . . .. 1
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f , ,g PUBLIC SERVICE COMPANY OF COLORADO RER.D-FCP FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 11 Page 2 of 8 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 N'JCLEAR DOCUMENTS SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWIWG EACH PROCEDURE. 4
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FORM 372 22 3643 S
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f , PUBLIC SERVICE COMPANY OF COLORADO h[u l- FORT ST. VR AIN NUCLEAR GENERATING STATION ' Page 3 of 8 ESTABLISHING THE FORWARD COMMAND p0ST 1.0 Criteria for Imolementation When the FSV Radiological Emergency Response Plan (RERP) requires augmentation of resources, generally for an ALERT or higher emergency 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 state / local / federal emergency response forces, and communicates with the State EOC and with the Weld County EOC (Weld County Communication Center) for l effective coordination of county forces. A senior representative of D0 DES is responsible for control and coordination of FCP emergency response activities. { l 2.2 Corporate Emergency Director (Checklist 1) i 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 l made. Refer to RERP PHONE LIST or RERP-HOME for l the FCP call list for instructions, names, and i phone numbers. 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.
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l PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VR AIN NUCLEAR GENERATING STATION [u page 4 of 8 2.3 Station Technical Liason The Station Technical Liason chall provide technical interpretation, assistance, and guidance, as requested, throughout the course of everts. 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 tecnnical cata. 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). He shall also perform core damage evaluations as required (see RERP-CORE). 3.0 Resoonsib111 ties 3.1 Corporate Emergency Director 3.1.1 The CED is responsible for direction and coordination of: a) PSC onsite and offsite emergency functions. b) Interface becween PSC and local / state / federal 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 recommended protective actions. e) Provision of administrative, technical, and logistical support to station emergency operations via the ECP. l f) Continuity of emergency organization l
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Pace 5 of S 1 i I 3.1.2 The CED provides direction to, and coordination for, the T50 Director and the Nuclear Engineering Manager (assigned to the State EOC). He will coordinate additional headquarters support via the Executive Command Post (ECP). I 3.1.3 Terminates the emergency or de-escalates the I emergency category according to the status of the l event. Deactivates the FCP wnen the emergency has
, been brought to a recovery phase. May also l deactivate upon de-escalation to an Unsual Event I category.
3.1.4 Acts as Recove ry 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) Secondary PSC Radio
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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. 3.2.4 Request location of Person'nel Control Center (PCC). 3.2.5 Communication is to be established with the Executive Command Post (ECP) and the State Emergency Operations Center (EOC). Inform the CED when accomplished. a) Appraise them of the situation as directed by the CED. b) Inform them of the location of the PCC, should it be necessary to dispatch assistance to the plant. l 1 s f FORM 372 22 360 j i
f . PUBLIC SERVICE COMPANY OF COLORADO ]
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3.2.6 Maintain communications flow between the TSC, ECP, l and State E00. ' 3.3 The FCP staff keeps an ongoing record (log) of all actions i taken. The Radiological Assessment Coordinator will i assign one of the clerical staff responsibility for i i updating the FCP status boards at approximately 30 minute l intervals. Data for adiological upcates is to be obtained f rorn, and reviewed by, the Radiological Assessment Coordinator prior to posting. Datasheet 1 is l provided as a working copy for radiological status board updates. These sheets shall be retained for record l keeping purposes. Datasheet 2 will be provided by l Technical Liaison personnel to update Plant Status Boards. 3.4 Station Technical Liaison a) Provide assistance and substantiated data on l emergency status and conditions. Provide staff l assistant copies of Datasheet 2 for use in updating l Plant Status Board. 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. 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 l information to complete Radiological Status Board l Update Sheets (Datasheet 1). 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).
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FORT ST. VR AIN NUCLEAR GENER ATING STATION Page 7 of 8 l l l l 3.6.3 Monitor radiation levels and meteorological data, and provide the Corporate Emergency Director witn estimates of the dose to the general population based or. 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 and foreseeable contingencies. 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. l Supply and review all radiological data to be posted. 3.6.6 Provide guidance to the TSC Senior Health Physics representative on matters regarding administration of thyroid blocking agent to site personnel (see RERP-THYROID). 3.6.7 Perform core damage evaluations as required (see RERP-CORE). 4.0 References 4.1 FSV Radiological Emergency Response Plan 4.2 State Radiological Emergency Response Plan 5.0 Referenced or Supporting Procedures 5.1 RERP-ORG, FSV Emergency Organization and Responsibilities 5.2 RERP-DOSE, Offsite Dose Calculations . 5.3 RERP-EXP, Emergency Exposure Guidelines 5.4 RERP-FIELD, Field Monitoring Procedure - 5.5 RERP-HOME, Home Packets for Offshift Hotifications 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 . 5.9 RERP-SURVEY, Inplant/Onsite Radiological Monitoring 5.10 Fort St. Vrain Final Safety Analysis Report + PORM 372 22 3643
R 6 PUBLIC SERVICE COMPANY OF COLORADO [ FORT ST. VRAIN NUCLEAR GEN! A ' TING STATION Page 8 of 8 5.11 RERP-SUPORG, Use and Coordination of Non-PSC Support Organizations 5.12 RERP-CORE, Core Damage Evaluation 1 E f FORM 372 72 3643 l _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . J
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FORT ST. VRAIN NUCLEAR GENERATING STATION Is'ue 11 s Page I of 1 FIGURE 6 AERIAL VIEW MAD OF PLANT U' s l g b, C* tav ,, QyFARMHOUSE (R. Russell) = ? M6.. ' .. i' 215' 'I . g ' h m" _a I ' 45* l ~ r . = WELL 4 I 8 wu .. COOLING (""" t. J N 10WER = " gl JI' ,, j\ L==. N / %g'} }"!sMA a>/ 2 270* ACitt 8 LDING 90' ~
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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)
- 4. Local government emergency plans - Weld County Plan
- 5. Evacuation time study
- 6. Maps (See RERP implementing procedures RERP-DOSE, RERP-SURVEY, and RERP-PCC.)
a) Fort St. Vrain area and environ b) Sectors c) Regional d) Health Physics Survey Maps of FSV Buildings
- 7. Public Information Plan
- 8. RERP Implementing Procedures
- 9. Office supplies a) Writing tablets b) Pe.as, pencils, and erasers
, c) Chalk d) Calculator e) Graph Paper ;
- 10. P & Is
- 11. FSAR l
- 12. E Drawings (Electrical)
- 13. I and C Drawings (Instrumentation and Control)
. 14. Technical Specificacions
- 15. Administrative Procedures Manual o
5 f FORM 372 22 3643 'I RERP-FCP PUBLIC SERVICE COMPANY OF COLOR ADO . Attachment 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 11 Page 2 cf 2 l
- 16. Emergency Procedures
- 17. Medical Emergency Plan
- 18. Calculator / Printer l l
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- 1. Fort Lupton PSC office notified of intent to occupy building.
- 2. Personnel Accountability -
a) Station Technical Liaison b) Radiological Assessment Coordinator c) Cleri;41 Assistants d) Media Relations e) Additional personnel from outside agencies.
- 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
- 4. Colorado State Patrol
- 3. Staffing recuirements met.
- 4. Communications established with TSC.
- 5. TSC informed that FCP is manned and activated.
l l 4
- PORM 372 22 3643 l
) -~ s- k PUBLIC SERVICE COMPANY OF COLORADO Cek t1 FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 11 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 ic ation of PCC.
- 12. Communication established by State EOC.
- 13. State E00 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).
1 l + 5. PORM 372 22 3643 l l , $ = f,. ' PUBLIC SERVICE COMPANY OF COLORADOfj3$fft E I FORT ST. VR AIN NUCLEAR GENER ATING STATION Issue 11 D Page 1 of 3 WORK /DATASHEET/ CHECKLIST CCNTROL LIST Worksheet No. Title Number Cooies l None N/A N/A Datasheet No. l l 1 Forward Command Post Radiological Status Board 25 1 2 Plant Status Board 25 Checklist No. 1 Corporate Emergency Director's Checklist 2 e + E
- FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO k's FORT ST. VRAIN NUCLEAR GENER ATING STATION Issue 11 Page 2 of 3 FORMS USE REPORTING SHEET Nuclear Documents Specialist: This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency Response Plan Implementing Procedures, BOOK NO. , located at . The following forms have been utilized from this copy: Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace . the noted number of forms, as well as this " Forms Use Reporting Sheet" for the affected procedure in the affected book. + d# POMM 372 22 - 3643 l I RERP-FCP PUBLIC SERVICE COIVIPANY OF COLORADO tis /DS/CL 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 11 ) Page 3 of 3 l l l FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: . _ _ Nuclear Documents Specialist
- Date Received Date Replaced Nuclear Documents Specialist will transmit this form to the originating individual / department upon completion of this form to notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.
, + E PORM 372 22 3643 l - ' - , PUBLIC SERVICE COMPANY OF COLORADO 3ERP-FIELD Assue 6 FORT ST. VRAIN NUCLEAR GENERATING STATION page 1 cf 6 gniST.VB@ TITLE: FIELD MONITORING PROCEDURE t Ort . C0tGROLLO 0N yt e ssut ST ATUS W DO Z YE TCE TE* pR10;TO USE ISSUANCE AUTHORIZED b W& y 74 + FORY M BY PORC g EFFECTIVE REVIEW m 5 8 0 Jul 311984 DATE b b* b Section Description Page General ........................................................... 2 1.0 Criteria For Imolementation................................... 2 2.0 Procedure..................... .................... .......... 2 3.0 Responsibilities ............................................. 5 4.0 References ................................................... 6 S.0 Referenced or Support.no Procedures........................... 6 Table 1 Instrument Check Source ......................... 1 Worksheet 1 In-field Sampling Data........................... 1 Datasheet 1 In-field Sampling Results ....................... 1 Datasheet 2 Field Monitoring Team Deployment................. 1 Checklist 1 Equipment Operability ........................... 1 . Work / Data sheet /Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Forms Use Reporting Sheet"......................................... 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l SrECIALIST, 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 l 4 PORM 372 22 3642 l PUBLIC SERVICE COMPANY OF COLORADO -F ELD FORT ST. VRAIN NUCLEAFi GENERATING STATION Page 2 of 6 General Emergency offsite radiological monitoring, in the event of a radiological emergency at Fort St. Vrain, will be performed by FSV monitoring teams until field monitoring teams from the Colorado Department of Health (CDH) respond to the scene. The data collected by these field teams will be relayed directly to the Technical Support Center to aid in the assessment of offsite radiological consequences. The TSC will transmit field measurement data to the Forward Command Post for use by PSC and state radiological assessment personnel. The PSC Field Monitoring Teams are deployed from the Personnel Control Center. The teams are in radio communication with the senior Health Physics representative at the TSC and report directly to him with all data. In addition, the field teams are directed by the senior Health Physics representative after initial deployment. 1.0 Criteria For Imolementation The Field Monitoring Teams are assembled at the Personnel Control Center anytime that the full FSV emergency organization is activated. The initial deployment of these teams is at the direction of the TSC Director. 2.0 Procedure The Field Monitoring Teams shall be composed of a driver and an HP Technician. There is provision for the deployment of two field teams, one with survey responsibilities near site, primarily out to the site Exclusion Area Boundary (EAB), and the other from the EAB to the outer perimeter of the plume exposure Emergency Planning Zone (EPZ), approximately a five (5) mile radius. 2.1 The decision to deploy Field Monitoring Teams is the responsibility of the TSC Director. He shall make this decision, based upon projected offsite doses, as advised by the TSC Radiological Assessment individual, and the consideration of the ability to effectively assess these dose rates in the field (lower level of detection, weather conditions, etc.) as advised by the senior Health Physics representative at the Technical Support Center. 2.2 Each field monitoring team leader shall check required survey instrumentation for operability per Checklist 1. 4 FORM 372 22 3643 , . . . . . . . . . . .......n,... .n. . . LD PUBLIC SERVICE COMPANY OF COLORADO u FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 6 2.3 The moritoring teams shall assure that all required instruments, equipment, and supplies are present in the survey vehicle prior to departure. This equipment shall include:
- RM-14 or RM-15 l
- RO 5A/D or RO 7 with RO 7-LD probe
- SAM-2 scaler
- 5 piece SAM-2 shield and detector Air sampler with Silver Zeolite cartridges and pre-filters
- Field Use Maps
- Wipes
- Pencil
- Field Radio a Copy of RERP-FIELD
- Spare Batteries 2.4 The proper selection of dosimetry and protective equipment is the responsibility of the senior Health Physics representative at the TSC. He shall utilize calculated or estimated parameters to deter:r ne potential exposure and estimated stay times (see Datasheet 2). This information shall be relayed to the PCC director for use in the briefing of the field monitoring teams.
NOTE: Two separate copies of Datasheet 2 may need to be completed if projected conditions differ for the EAB and EPZ monitoring teams. 2.5 Field Monitoring teams act under the direction of the senior Health Physics representative after their initial deployment from the PCC. The Health Physics Technician assigned to each team shall ensure that good health physics practices are employed while in the field. This is to include: l
- Keeping survey instruments (as appropriate to radiation levels) operating at all times to evaluate ambient radiation conditions and plume location; 4
FOMM 372 22 - 3643 . - . . _ _ . . ~ . . - . . _ . . . _ . . . . . . PUBLIC SERVICE COMPANY OF COLORADO ] ELD FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 6 = Wearing all protective clothing and equipment prescribed by the senior Health Physics ) representative at the TSC; ; = Spending as little time as necessary in elevated radiation exposure areas; and,
- Travelling outside of predicted plume trajectory whenever possible, to minimize exposure and spread of contamination.
2.6 The senior Health Physics representative shall communicate the sampling location designations by utilizing easily recognizable landmarks, in particular, the intersections of county roadways (e.g., Weld County Roads 19 and 38, the confluence, meteorological monitoring towers, etc.). 2.7 The Field Monitoring Teams, in the interest of dose reduction and facilitating rapid data transmission, may transmit raw field monitoring data directly to the senior Health Physics representative at the TSC, where calculations may be performed. Worksheet 1 is provided for both data collection and calculations. 2.8 The Field Monitoring teams shall collect the following data at each sampling location: Ambient Radiation Level (mrem /hr) I-131 Air Concentration (uCi/cc)
- Gross Particulate Concentration (cpm /cc) 2.9 The senior Health Physics representative at the Technical Support Center shall accumulate data on Worksheet 1 and complete all required calculations. After calculations are completed, data should be recorded on Datasheet 1, a partial scale survey map of the plume exposure EPZ. This map should be utilized in concert with dose projection results to keep the TSC Director and FCP personnel abreast of current data and dose assessment results.
2.10 Operation of Eberline SAM-2 counters is outlined below.
- Take a one minute background count and record on Worksheet 1 (or transnit to TSC via radio communication).
Collect Air Sample on Silver Zeolite Cartridge (HPP-12) and determine sample volume. t PORM 372 22 3643 PUBLIC SERVICE COMPANY OF COLORADO ]ELO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 6
- Load cartridge in detector shield and close shield door.
- Take a one minute count of air sample cartridge and record on worksheet 1 (or transmit to TSC via radio communication).
= I-131 concentration (pCi/cc or Ci/m') = uCi I-131 = (CPM3 - CPMg ) x 1.0E-10 x 15 cc V Where: CPM 3 = Gross counts per minute of sample CPMB = Counts per minute of background 1.0E-10 = Unit Conversion Factor V = Sample Volume in ft* 15 = Normal air sample volume 3 (3 ft / min x 5 min) 2.11 At the conclusion of FSV field monitoring activities, the driver shall return the vehicle, passengers, and contents to the Personnel Control Center, inform the PCC Director of the team's arrival, and request a contamination survey of the vehicle, its passengers, and its centents. Decontamination shall be handled in accordance with FSV Health Physics Procedures (HPP-10 and HPP-11) with area posting and control as required in accordance with HPP-9. 3.0 Responsibilities 3.1 Health Physics Technician (Field) Perform surveys as directed by the senior Health Physics ' representative at the TSC. Ensure that good health physics practices are employed throughout the course of field monitoring efforts. 3.2 Health Physics Technician (PCC) Perform contamination surveys as required on returning field monitoring personnel and equipment. 3.3 Senior Health Physics Representative (TSC) Assume overall responsibility for the conduct of field monitoring activities. Direct field teams to appropriate sampling locations utilizing TSC dose projections and current meteorological conditions as a basis. 4 PORM 372 22 3643 e PUBLIC SERVICE COMPANY OF COLORADO F{RD FORT ST. VhAIN NUCLEAR GENERATING STATION page 6 of 6 3.4 TSC Director Assume ultimate responsibility for all activites centered from site, including the initial dispatch of field monitoring teams. 3.5 PCC Director Brief departing monitoring teams of recommended protective actions, dosimetry, and estimated stay times as determined by senior Health Physics representative at the TSC. Ensure adequate contamination survey (and decontamination) of returning field monitoring personnel and equipment. 4.0 References 4.1 Instruction manuals for Eberline SAM-2 counting equipment. 5.0 Referenced or Supporting Procedures 5.1 RERP-EXP, Emergency Exposure Guidelines. 5.2 RERP-DOSE, Offsite Dose Calculation Methodology. 5.3 RERP-ORG, FSV Emergency Organization and Responsibility. 5.4 RERP-TSC, Technical Support Center Procedure. 5.5 RERP-PCC, Personnel Control Center Procedure. 5.6 HPP-9, Establishing and Posting Controlled Areas. 5.7 HPP-10, Area and Equipment Decontamination 5.8 HPP-11, Personnel Decontamination. 5.9 HPP-12, Portable Air Sample Collection and Analysis. 5.10 HPP-66, Operation of Portable Survey Instrumentation. 5.11 HPP-67, Calibration and Operation Procedure for the Eberline 3AM-2 Stabilized Assay Meter. l l . l l l L. PoMM 372 22 3643
- L PUBI IC SERVICE COMPANY OF COLORADO E be FORT ST. VRAIN NUCLEAR GENERATING STATION IS5ue 6 Page 1 of 1 TABLE 1 l INSTRUMENT CHECK SOURCE-I . 0A/ENG PCC CHECK SOURCE l CS-137 SCN 103 l INSTRUMENT ACCEPTABLE RANGE l RM-14/15 with HP-210 2.100 - 6,300 cpm l PIC-6A 0.5 - 1.5 mrem /hr l R0-2 0.25 - 0.75 mrem /hr l R0-5A 0.15 - 0.45 mrem /hr i E-400 0.5 - 1.5 mR/hr l E-500 0.4 - 1.2 mR/hr l TRAINING PCC CHECK SOURCE l Ba-133 SCN 107 l INSTRUMENT ACCEPTABLE RANGE l RM-14/15 with HP-210 15,000 - 45,000 cpm l PIC-6A 5.5 - 16.5 mrem /hr i R0-2 4.5 - 13.5 mrem /hr l R0-5A 3.0 - 9.0 mrem /hr l E-400 7.5 - 22.5 mR/hr l E-500 6.5 - 19.5 mR/hr l H.P. ACCESS AREA CHECK SOURCE l Cs-137 SCN 80 Cs-137 SCN 75 l INSTRUMENT ACCEPTABLE RANGE l RM-14/15 with HP-210 19,000 - 57,000 cpm l PIC-6A 3.3 - 9.8 mrem /hr l R0-2 1.3 - 3.8 mrem /hr l R0-5A 1.1 - 3.3 mrem /hr l E-400 4.5 - 13.5 mR/hr j l E-500 4.0 - 12.0 mR/hr 1 l
l NOTE: Center active detector area directly over the source. 4 PORM 372 22 3443
- RER LD PUZLIC SERVICE COMPANY OF COLORADO gcr h t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 1 of 2 l
l 1 l WORKSHEET 1, IN-FIELD SAMPLING DATA l
- 1) Date: / / l
- 2) Time: :
- 3) Field Team: ( ) EAB ( ) EPZ (CheckOne)
- 4) Sample Number:
- 5) Sample Location (describe):
- 6) Ambient Radiation Level: mrem /hr
- 7) Air Sample Data:
a) Flow Rate ft /8 min b) Collection Time minutes c) Volume Collected 7a) ft / min x 7b 8 min = ft8 d) Volume Correction Factor (VCF): 15.0 ft8 = 7c) ft*
- 8) Particulate Activity Concentration:
a) Particulate Filter Count Rate = cpm b) Background Count Rate = cpm c) Net Count Rate 8a) cpm - 8b) cpm = cpm d) Gross Beta Activity [8c) cpm x 7d) ] = pCi/cc 2.36E+11 i 4 ponu sn .22.as43
- L PUBLIC SERVICE MPANY OF COLORADO (-fk et 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 2 of 2
- 9) 131I Activity:
a) Cartridge Count Rate = cpm b) Background Count Rate = cpm c) Net Count Rate 9a) cpm - 9b) cpm = cpm d) 131I Activity 9c) cpm x 1.0E-10 x 7d) = uCi/cc l l 4._ PORM 372 22 3443 ._ , . . ~ . . . . . . . . . _ . ,_. , _ _ _ . . _ . . - _ ._. PUBLIC SERVICE COMPANY OF COLORADO $,E ED ,I FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 1 of 5 -u =,-m nw .=n= m
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j e; we - [i --g , * --L , ~~ 3 [;_ p_ m ,,',,I(t .I'., 7 V ,j- $@ws.) ' (' beh. 4 ,i i .. .W g..- % , ' [ m? [%~~~h #,g:. %,3 , . ,x . i' T ' # .Z ' .. (.. . ; i ' ,;ku . ~ c ', , ".,' A. ,, % .-' y_.[':/w ~. %' , C '. / __ s.- .G& . 3, u m_ e ...___. .~., %, .g.a y'q. 3- M E: ,, r ~ Q7 - I,; , T- . %., ,- 3. ' x.9 % .1 ~ '; ".- {s ..N (.- y,f.p- - . . .' .' -'M , y, j 'f),.,R. . -s . ~2 . ,{> ,,;. '(y,. . .. . s, s , w ~' l g, .. 3 7 7 . r.s \'._ ,, .f% Q . 9 PUBLIC SERVICE COMPANY OF COLORADO at hD I FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 5 of 5 Datasheet 1 - In-field Sampling Results l Sample l Ambient I Gross ! I-131 l Location Number i Radiation i Particulatel Air l(Use simple (See Work- I Levels i Activity l Concentra- l description) sheet No. 1)l (mR/hr) I (cpm /cc) I tion I ! ! ! (uci/ce) 1 I i l I i l I l i I I I I I I I 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l - 1 I I i l i l i I I I I I - 1 I I I I I I I I l l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I 4 PORM 372 22 3643 PUBLIC SERVICE COMPANY OF COLORAD3 HELD 2 FORT ST. VRAIN NUCLEAR GENER ATING STATION Issue 6 - Page 1 of 3 Datasheet 2 Field Monitoring Team Deployment (To be completed by senior HP representative at the TSC)
- 1) Area to be surveyed
- 2) Route to be taken
- 3) Calculated or estimated parametirs a) General Radiation Level (mrem /hr) l b) Airborne Activity Level (uct/cc)
- 4) Projected Time to complete survey (hr)
- 5) - Projected Exposure l 3)a) x 4) x 1.25 = (mrem)
- 6) Maximum Stay Time (based upon 10CFR20 limits or, wt_th the TSC Director's Concurrence, the guidelines of RERP-EXP, Emergency Exposure Guidelines)
(hr) 4 PORM 372 22 3443 . .. ~ . . . . . . . . . ~ - - , . . . PUBLIC SERVICE COMPANY OF COLORADS h,, ,E0 ,2 FORT ST. VRAIN NUCLEt0 GENERATING STATION Issue 6 Page 2 of 3
- 7) Team Members:
- 8) Dosimetry requirements: .
Pocket Dosimeter - High Range (required) Other required dosimetry (circle): Film Badge Pocket Dosimeter - Low Range
- 9) Protective Equipment requiremants (Circle required equipment):
Full Anti-C's . Shoe Covers and Gloves No Protective Clothing Required . Full-Face Respirator Scott Air Pack Thyroid Blocking Agent (see RERP-THYROID) No Respiratory Protection Required i PORM 373 33 3443 , ,. . . . . . .-..o . . . . . . . . . . . - . . . . . . . .. . . . . . . . *
- E ED PUBLIC SERVICE COMPANY OF COLCRADD ha[he 2 FORT ST VRAIN NUCLEAR GENERATING STATION Issue 6 I Page 3 of 3
- 10) Comments:
I a) Save used filters and cartridges for Radiochemistry l analysis. l b) Leave the emergency vehicle running while in the field and l upon return to avoid battery discharge. 4 P0mW 372 22e36*J D PUBLIC SERVICE COMPANY OF COLORADO I FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 1 of 2 CHECKLIST 1 EQUIPMENT OPERABILITY (To be completed by field monitoring team leader.)
- 1. RM-14 or RM-15 Verify that RM-14 or RM-15 exhibits proper response for given instrument check source (see Table 1).
l 2. R0 SA/D or RO 7 with RO 7-LD probe Verify that PIC-6A or equivalent instrument exhibits proper respon e for given instrument check source (see Table 1).
- 3. SAM-2 The SAM-2 is to be set up in the emergency vehicle, using 12V DC, and a routine performance check performed as follows:
'1) ~ Allow a two-minute instrument warmup and set switchef to settings posted on instrument cover.
- 2) Take a one-minute background count on the empty shield.
(CB) l 3) Carefully place SCN 107.00 (133 Ba check source) in the sample holder. Slide the shelf into the assembly and close the door on the lead shield.
- 4) Take a one-minute count on the source. (CS)
- 5) Obtain the net count rate of the source by subtracting CB from CS. *
- 6) Compare the net count rate with control limits established during calibration. These values are found on the instrument cover.
- 7) If instrument response is not within acceptable range, contact senior-Health Physics representative at the TSC for further action.
- 8) Leave instrument running after operability check.
^ 4 FORM 372 22 3643 i . ~ .-- - ....__.J-. -. _ . . . _ . . . _-..-._... LD . . PUBLIC SERVICE COMPANY OF COLORADO hR t1 FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 6 Page 2 of 2
- 4. Air sampler Verify that the air sampler is operable by setting it up in the emergency vehicle and running unit for approximately one minute at proper flows.
,_ _ ..__.----...._.---_...-.n_ .. _, d e 4 FORM 372 22- 3643 ) l l - 1 RE F D PUBLIC SERVICE COMPANY OF COLORADO g,3 f FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 l Page 1 of 3 i t l Work /Datasheet/ Checklist Control List Worksheet No. Title Number Copies 1 In-Field Sampling Data 15 Datasheet No. 1 In-Field Sampling Results 3 2 Field Monitoring Team Deployment 3 Checklist No. 1 Equipment Operability 3 4 FORM 372 - 22 3643 . . . . . _ , . . . - . _ - .~- - - . - . . -- ,- g + - , - - - - RE D PUBLIC SERVICE COMPANY OF COLORADO g,5 l FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 2 of 3 l FORMS USE REPORTING SHEET l l Nuclear Documents Specialist: I 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 Datasheet Numbers Copies Used Checklist Numbers Cooies 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 j 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. 4 FORM 372 22 3643 , l l . ..,,... . .. ~ n , . - -- ---.--- --- - . - - ~ ~ - - - - - - ~ - - = R F D PUBLIC SERVICE COMPANY OF COLORADO g, , FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 6 Page 3 of 3 FORMS USE REPORTING SHEET (Continued) COMMENTS , Reported By: Date: l Nuclear Documents Specialist
- Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the 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. .
e l 4 _ PORM 372 - 22 3643 1 4 RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Issue 12 FORT ST. VR AIN NUCLEAR GENERATING STATION Page 1 of 5 FCt".TST.VG:i' NUN - CONIROLLED TITLE: HOME PACKET FOR OFF-SHIFT NOTIFICATIONS ' 11- l l VER=Y tssug STATU! rra COCUMENT CENTER FNC; TO U3E ISSUANCE a,, w.. . ;. .,y 4 ' FC W rz.;;. y l AUTHORIZED BY 9%'/- 977c42r PORC EFFECTIVE l REVIEW PbRc 5 8 0 AUG2- 1984 DATE b- km ~ b Sections Descriotion Page 1.0 Criteria for Imo1ementation.................................. 3 2.0 Procedure.................................................... 3 3.0 Re s o o n s i bi l i t i e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 4.0 References .................................................. 5 5.0 Referenced or Supoorting Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . 5 Figure 1 Notification Fanout.................................. 1 Figure 2 Facility Staffing Requirements ...................... 1 Checklist 1 Management Centact Notification List for an UNUSUAL EVENT........................................ 1 Table 1 Plant Management Contacts............................ 1 Table 2 Non-Emergency Event: Four-Hour Report ............... 1 Table 3 Non-Emergency Event: One-Hour Report................ 1 Table 4 NOTIFICATION OF UNUSUAL EVENT Tabl e. . . . . . . . . . . . . . . . . . 1 Table 5 ALERT Tab 1e.................................... ..... 1 Table 6 SITE AREA EMERGENCY Tab 1e............................ 1 Table 7 GENERAL EMERGENCY Tab 1e............................... I Attachment 1 Impaired Fire Protection Notice ( ANI) . . . . . . . . . . 1 Attachment 2 Initial Notification, Non-Emergency Event . . . . . . 1 Attachment 3 NOTIFICATION OF UNUSUAL EVENT (Notification Form) ............................ 1 Attachment 4 Notification of Emergency Event ................. I FORM 313 - 33 MM3 - ~ . 6 l i t PUBLIC SERVICE COMPANY OF COLORADO issue )E"0ME 12 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 5 l Attachment 5 ECP Di rector's Call Li st. . . . . . . . . . . . . . . . . . . . . . .1 Attachment 6 FCP Di rector's (CEDs) Call Li st . . . . . . . . . . . . . . . . 1 Attachment 7 PCC Di rector's Call Li st. . . . . . . . . . . . . . . . . . . . . . . . 1 Attachment 8 State E00 Ca l l Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Attachment 9 TSC Di rector's Cal l Li st. . . . . . . . . . . . . . . . . . . . . . . . . 1 Attachment 10 Facility Directors / Alternates .................. 1 'I ? \ l 4 i f FORM 372 22 - 3643 l . 1 I 6 PUBLIC SERVICE COMPANY OF COLORADO u FORT ST VRAIN NUCLEAR GENERATING STATION Page 3 of 5 General This procedure is provided for use, at home, by plant management contacts, RERP facility directors and alternates, and by the first individual on each facility director's call list. The purpose of this procedure is: (1) To assist plant management in determining the severity of an occurrence when contacted at home by the FSV duty Shift Supervisor; (2) To provide plant management contacts with copies of notification forms to assist the the duty Shift Supervisor in their completion; (3) To provide required telephone numbers for facility activation if required; and, (4) To assure that individuals who may potentially be required to call-in individuals for off-shift emergency facility activation are clearly identified. 1.0 Criteria for Imolementation This procedure may be utilized under virtually any off-normal off-shift situation where consultation regarding reportability or activation requirements must be addressed. 2.0 Procedure 2.1 ANI Notifications , Notification to American Nuclear Insurers (ANI) is required under five (5) general categories listed below:
- Lesses believed to be near, or above, the deductible (550,000);
= Incidents where fixed fire protection systems have operated under other than test conditions;
- Incidents where prompt assistance could help prevent further loss or expense, or where assistance is otherwise desireable;
- Incidents where incendiarism or malicious mischief is suspected; or
- Emergency impairments to fire protection equipment.
Whenever the on-duty Shift Supervisor believes an occurrence matches one of these circumstances, he will contact a plant management contact for consultation (where possible). The Shift Supervisor and plant management contact will jointly complete Attachment 1 to this procedure. Additional plant management contacts may be made utilizing Table 1 for reference. i FORM 372 - 22 3643 RERP- G E
- PUBLIC SERVICE COMPANY OF COLORADO Issue 12 FORT ST. VR AIN NUCLEAR GENERATING STATION Page 4 of 5 2.2 Non-Emergency Event Notifications Notification to the NRC operations center within four (4) hours is required for events which fall under the general descriptions shown in Table 2, and within one hour for events as described in Table 5. When these events transpire, or when the on-duty Shift Supervisor believes an event may require such reporting, he may contact one of the plant management contacts listed in Table 1.
Together, where possible, they will jointly complete the "Non-Emergency Event Notification Form," Attachment 2 of this procedure. Additional plant management contacts may be made at the Shift Supervisor's discretion utilizing Table 1. 2.3 Radiological Emergency Response Plan (RERP) Notifications Notification to both offsite authorities and the NRC within fifteen (15) minutes of event classification is required when a situation has arisen that meets classification criteria set forth in Tables 4-7 of this procedure. Events classified as a NOTIFICATION OF UNUSUAL EVENT are reported to the state utilizing the notification format of Attachment 3. The plant management contact shall assist the completion of this form. If the event is an ALERT, or higher, RERP event, Attachment 4 shall be completed. The Shift Supervisor may consult with plant management regarding incident classification. 2.3.1 NOTIFICATION OF UNUSUAL EVENT For a NOTIFICATION OF UNUSUAL EVENT, where appropriate, the initial management contact shall notify other contacts per Checklist I and forward the completed form to the Technical Services Department. 2.3.2 ALERT or Higher RERP Event For an ALERT or higher RERP event, the notification fanout shown in Figure 1 of this procedure shall occur to assure prompt facility activation and staffing. Under these conditions, Facility Directors will be contacted by the PSCo Telephone Operator. The Facility Director will in turn contact his alternate. The alternate, or the next person contacted, is then responsible for performing the additional notifications specified I herein. Each facility's call list is reproduced as Attachments 5-9, herein. The Facility Director primary and alternates are shown on Attachment 10. 1 FORM Sn. 22 300 l l 1 . . PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Issue 12 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 5 3.0 Responsibilities 3.1 Duty Shift Supervisor Classify the situation, contacting a plant management contact for assistance in accordance with existirg Operations Orders, Notification Procedures, or RERP-Implementing Procedures, where possible. 3.2 Plant Manacement Contacts Assist the Shift Supervisor, as required, and perform additional notifications, as appropriate to a given situation. 4.0 References 4.1 FSV Radiological Emergency Response Plan 5.0 Referenced or Supporting Procedures 5.1 RERP-PHONE LISTS 5.2 RERP-CR, Cor. trol Room Procedure j ronu 372 22 3643 1 t i t . 8 E *' 9 l X. i u g l NOTIFICATION FANOUT E j FORT ST. VRAIN NUCLEAR GENERATING STATION ggC i CONTROL [m , ROOM "E
- i 55 m i i Pn
. NRC PSCO En REGION OPERATOR Eo WELD ? i IV COUNTY L._ PSCo ylz ! COMM FACILITY CENTER DIRECTORS j*? ii i i OR En i STATE LEAD s 52 i RERP REPS ES { FANOUT s g ALTERNATES o ' i o >-. m n STAFF i s{'s aw O., N *- * .C. . I *-' i l d 3 E n. O b h EMERGEtlCY ORGANIZATION (ALERT. SITE EMERGENCY, GEllEll AL EMEllGENCY) g 0 FORT ST. VRAlH NUCLEAR GENERAllHG STATIOl1 C CORP IHERG DIRECIOR 15C DIRECTOR phi [VQ'Q 3 R ~~O MGR stall 0N a SIAll0N TECll LIAISON N I = I TRiiilRAl / Mm PCC DIRECTOR . CONIROL ROOM OIRECTOR ADMIN SVC g, g < SCitED/510RE5f IRAINING g 5 y) 5 5UPI 0F /5HIII SUPV, [ COORD. ( SUPV OPERAll0N}l IRAltil'F's CLERICAL ASSISTANCE y I' TANT CONDlil0N ASSESS - HUCLEAR D000llitals z ~ SIAIF c PERSfMNIEL ACCOLMIABILIII - OT F.'RJIY SHIFT m ,- PtAMT CONIROL oO SECURIIY IORCL.HP IECil5 SHIFT SUPERVISOR MEDIA RilATIONS gO sCllED/0C STAFF.iRAINING DtRGENCY MAINTENAMEE g g I n - HEDIA / HEDIA >b 3 "U MINT, REPAIR. DAMAGE CMil ~ SUPI 0F / MAINI Pt ANT OPERAll0N REP l REP MAiMT / SUPv I a 35 MAINI STAFF. If,C IECll5 8 RX OPERATORS. 2/5HIIT RADIOLOGICAL A55f 55Mllii m g INST & CONIROL SUPPORT l - COORDINATOR g4 IECIWilCAL A5515tAMr.E 3 HAZARDS CONTROL SUPI NUCL / RESUlis g RADIAll0N PROIECil0N > FIRE BRIGADE BIRMT ENGRGI ENGRG SUPV TECHNICAL ADVl50R dO z *T1 RADIOLUGICAL A55ES$l1Er.1 ~ OPERAilNG STAFF SUPPORI SR. PLANT /IECH. SERV. EQPi OPERATORS & ENGR. I EfirP. M () AUXILIARY TEMIERS O I " I"I$I $ NOTE Muttl RS OF[. STAFF SUPPORT PER50NilEl I flP / HE ALIH I!! PCC Will VA".Y ACCORDING 10 Z O SUPV / PliV5tC15i SEVERiiY OF EllERGENCY AND SPECIFIC .7 Aft 1IN & LOGISTICS SUPPI SIM10HAI. MEEDS. > ~ f./ $ g DOC PRifMRY/AEIERNAIE COMPUTER SUPPORT o H 71 :n SR. COMP./ SENIOR $$d$ ,_ NLAL111 l_PROGRAl31R mgC y ' PERSONNEL CONil10L CENTER ' TECIWitCAL SUPPORI CENTER ' COMIROL ROOM ! IORWARD COMMND 11)SI *b -e. ri o , PUBLIC SERVICE COMPANY OF COLORADO 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 x Page 1 of 1 l MANAGEMENT CONTACT NOTIFICATION LIST FOR AN UNUSUAL EVENT l . The first management contact will make the following notifications, I and forward the completed form to the Technical Services Department. l l Subsequent l Date/ l l ) l Contacts i Time i Remarks l l Plant Management l l l l(Contact 1) l l l l Supt. of Oper. l l l 1218; 532-3489 I I l l Station Manager l l l l201: 442-3829 i l l lAcministrativa/ l l l l Tech. Serv. Mgr. l l l l202: 663-2363 l l l l Manager, Nuclear l l l l Production l l l l200; 833-4092 ! l l l Radiation Pro- l l l ltection Manager l l l l203; 663-1230 l l l lVice Presiaent, l l l l Production l l l l571-7305 l l l l797-4122 I I l l Media Relations l l l l Bob Burns l l l l571-8481 l l l 1759-9740 or l l 'l l l l l l Gary Reeves l l l 1571-8479 l l l l424-4958 l 1 l -l or l l l lMarily Mora l l l [571-8462 l l l l694-2369 l l l l NRC l l l lG.L. Plumlee, IIII l l l490; 776-9541; l l l l Pager: 890-2225I i
- Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange. In these cases, utilize the exchange in parentheses.
FORM 372 3643 HOME , PUBLIC SERVICE COMPANY OF COLORADO . FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 1 TABLE 1 PLANT MANAGEMENT CONTACTS
- Page Flant Home Phone kt. Phone Supt. of Operations 890-0558 218 532-3489 Station Manager 890-0698 201 442-3829 Admin./ Tech.
Serv. Manager 890-0810 202 663-2363 Mgr. Nuclear Prod. 890-0699 200 833-4092 Rad. Protection Manager 890-1775 203 663-1230 Vice Pres., Prod. N/A 797-4122, 8-571-7305 659-1180 Listed in order of preferred contact sequence. l l FORM 372 22 - 3643 RE HOME PUBLIC SERVICE COMPANY OF COLORADO , FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 12 Page 1 of 4 TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiatino Event
- 1. Any event, found while 1. Determination as result of the reactor is shut- surveillance testing of Plant down, that, had it Protective Systems (PPS) that been found while the failure of PPS modules would "
reactor was in oper- have prevented a required ation, would have re- reactor scram from occurring. suited in the plant, including its principal safety barriers, being seriously degraded or being in an unanalyzed condition that significantly compromises plant safety.
- 2. Any event or condition 2. Reactor scrams, loop shutdowns, that results in and automatic starting and manual or automatic loading of diesel generators actuation of an only.
Engineered Safety Feature, including EXCEPTIONS: the Reactor Protection System. a) Manual scram initiated at 2% during a normal shutdown. b) Only one of three channels tripped manually or auto-matically, but no final protective action takes . place, nor is required. c) Actuation of the afore-mentioned systems which result from, and are a part of, the planned sequence during surveil-lance testing or reactor operation. l FORM 372 22 3643 l t H ME PUBLIC SERVICE COMPANY OF COLORADO h,E FORT ST. VR A,lM NUCLEAR GENERATING STATION Issue 12 Page 2 of 4 TABLE 2 NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiating Event
- 3. Any event or condition 3. a) During refueling operations, that alone could have a .0 lap shutdown margin prevented the ful- is not maintained due to fillment of the safety incorrect rod removal function of structures sequence.
or systems that are needed to: b) Incorrect valve lineup which results in shut off a) shut down the reactor of secondary system decay and maintain it in heat removal sequence. a safe shutdown condition; c) Liquid waste monitor setpoints raised for liquid waste release b) remove residual heat; completed. Reactor Building sump pumps taken out of c) control the release pull-to-lock. Setpoints not of radioactive reset. material; or d) Loss of HEPA filtration. d) mitigate the con-sequences of an accident. e FORM 3M - 22 3&O . PUBLIC SERVICE COMPANY OF COLORADO HfME FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 12 page 3 of 4 TABLE 2 NON-EMERGENCi EVENTS: FOUR-HOUR REPORT Event Tyoical Indication Initiating Event
- 4. a) Any airborne radio- 4. As determined by analysis active release that and evaluation.
exceeds 2 times the applicable concentra-tions of the limits specified in Appendix B, Table II of 10CFR20 in unrestricted areas when averaged over a time period of one hour. b) Any liquid effluent release that exceeds 2 times the limiting combined MPC (see Note 1 of Appendix B of 10CFR20) at the point of entry into the receiving water (i.e., unrestricted area) for all radionuclides except tritium and dissolved noble gases, when averaged over a time period of one hour. NOTE: Immediate notifications made under this paragraph also satisfy the requirements of paragraphs (a)(2) and (b)(Z) of 10CFR20.403.
- 5. Any event requiring 5. As occurring. .
the transport of a radioactively contam-j inated persen to an 4 offsite medical facility for treatment. FORM 372 - 2,2 M43 H E r PUBLIC SERVICE COMPANY OF COLORADO h,E FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 4 TABLE 2 l NON-EMERGENCY EVENTS: FOUR-HOUR REPORT Event Typical Indication Initiatino Event
- 6. Any event or situation, 6. a) Onsite fatality for which related to the health a news release will be made.
and safety of the public or onsite personnel, or b) Inadvertent release of protection of the environ- radioactive material not ment, for which a news in excess of 10CFR20 limits release is planned or for an unrestricted area, notification to other but requiring report to government agencies has the State. been or will be made. c) Oil or chemical spill which could reach the South Platte River or St. Vrain Creek and which is therefore reportable to the EPA. t FORM 372 3643 - j - PUBLIC SERVICE COMPANY OF COLORADO 3ERP-HOME imble 3 i FORT ST. VRAIM NUCLEAR GENER ATING STATION Issue 12 I Page 1 of 3 TABLE 3 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical Initiatina Event
- 1. a) The initiation of 1. a) As occurring.
any plant shutdown required by Technical Specifications. b) Any deviation from b) Any deviation frem a Tech-Technical Specifica- nical Specification, when tions authorized the action is immediately pursuant to needed to protect the 10 CFR 50.54(x). public health and safety, and no action consistent with Technical Specifica-ions which can provide adequate or equivalent protection is inneciately apparent. (The action should be approved, as a minimum, by a senior licensed operator.) i FORM 372 22 - WM3 l RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Table 3 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 I Page 2 of 3 l l TABLE 3 NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Tyoical Initiatino Event
- 2. Any event or condition during operation that results in the condi-tion of the plant, including its principle safety barriers being seriously degraded; or results in the plant being:
a) In an unanalyzed 2. a) As determined. condition that significantly compromizes plant safety; b) In a condition b) 1. Reactor pressure in that is outside excess of design the design basis limits with failure of the plant; or to trip plant.
- 2. Winds experienced in excess of FSAR design levels.
c) In a condition c) As determined. not covered by the plant's operating and emergency procedures.
- 3. Any natural phenomenon 3. a) Toxic gas release in imme-or other external diate vicinity of plant.
condition that poses an actual threat to the b) Extremely high winds or safety of the plant or severe storm preventing j significantly hampers plant personnel from ) site personnel in the completing requisite performance of duties assignments. necessary for the safe operation of the plant. FORM 372 22 3643 ^ \ PUBLIC SERVICE COMPANY OF COLORADO (,E H E FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 j Page 3 of 3 TABLE 3 i NON-EMERGENCY EVENTS: ONE-HOUR REPORT Event Typical Initiatino Event
- 4. Any event that results 4. a) Loss of significant in a major loss of portion of Control P.com emergency assessment indication.
capability, offsite response capability, b) Loss of all offsite or communications communication systems. capability.
- 5. Any event that poses 5. a) Fire posing undue an actual threat to the personnel hazard.
safety of the plant,- or significantly hampers b) Severe chlorine release site personnel in the from chlorine cylinders. performance of duties necessary for the safe c) Accidental gaseous radio-operation of the plant, logical release resulting including fires, toxic in onsite concentrations gas releases, or 'in excess of 10 CFR 20 radioactive releases. Appendix B, Table I. FORM 372 22 300 p_-. - -m. - RE E PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 12 Page 1 of 4 TABLE 4 , 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). b) SR 5.2.11 results.
- 4. Serious fire at the 4. a) any of various alarms plant lasting more on Fire Control Alarm
- than 10 minutes Panel; which could lead to substantial b) Fire Pump 1A auto degradation of plant start; safety systems, or which could result c) verbal reports.
in the release of radiologial or toxic materials. l cow an 22. au l \ . l 1 RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO sable 4 i FORT ST. VRAIN NUCLE AR GENERATING STATION Issue 12 page 2 of 4 TABLE 4 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 5. Abnormal coolant temp- 5. Violations of eratures or core region LCO 4.1.7 or LCO 4.1.9 temperature rises for region outlet to the extent mismatch, or region requiring shutdown in AT, respectively, accordance with to the extent that Technical Speci- shutdown per Station fications. Technical Speci-fications is required (SOP 12-04).
- 6. Natural phenomenon that 6. a) Seismic Recorder may be experienced Operate; or threatened that represent risks beyond b)-d) as visually observed s normal levels: by, or reported to, a) earthquake station personnel, 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, FORM 372 22 300 -- - --g , PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Table 4 FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 4 TABLE 4 NOTIFICATION OF UNUSUAL EVENT I Event Indication 1
- 7. c) Onsite or near site plant related accidents that could result in the release of toxic material or spills of flammable materials.
- 8. Any serious radio- 8. As occurring.
logical exposure of plant personnel or the transportation to offsite facilities of contaminated personnel who may have been ~ ~~~~ injured. (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-active waste shipments.
- 10. Loss of Engineered 10. Shutdown required in Safety Feature or Fire accordance with applicable Protection System to LCOs:
the extent requiring Shutdown a) Engineered Safeguards in accordance with station Technical Spet'fications. 1) Plant ventilation-LCO 4.5.1
- 2) Steam / Water Dump System - LCO 4.3.3 FORM 372 22 M43 w
M PUBLIC SERVICE COMPANY OF COLORADO NE[,-"0, , 4 E FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 4 TABLE 4 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 10. (Cont). 3) PCRV penetration flow restriction devices - LCO 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
- 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. l NOTE: Use ELCO 8.1.1 Technical i Specification Limits as
- basis.
FORM 372 2 2- 300 -W c'e-d RE . PUBLIC SERVICE COMPANY OF COLORADO , HlME FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 12 Page 1 of 5 TABLE 5 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 and RAT undervoltage/ loss of power alarm.
- 3. Primary coolant pressure 3. PAL 9335 decay (to a value greater PAL 9347 than 100 psi less than - PAL 9359 normal pressure, and area monitor accompanied by area and or stack monitor alarm stack radiation monitor '
alarms).
- 4. High radiation levels or 4. .RT'7312 high airborne contamination CAM (s) alarm
.which indicates severe RT 6212 , degradation in control of RT 6213 , radioactive materials. RT 93252-12 . (Increase by factor Area Monitors 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 I monitors. / FORM 372 22 300 RERP-HOM:' PUBLIC SERVICE COMPANY 3F COLORADO Table 5 , FORT ST. VRAIN NUCLEAR GENERx.'ING STATION Issue 12 Page 2 of 5 TABLE 5 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 undervoltage 480V bus under-voltage, and Diesel Trouble al a rms.
- 6. Loss of all vital 6. DC bus 1 < 10 volts and DC power for up to DC bus 2 < 10 volts 30 minutes.
- 7. Loss of primary coolant 7. All He flow indicators read forced circulation for zero.
between 2 and 5 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 suberitical condition by scram of the control b) neutron rods. count rate not decreasing.
- 10. Serious fire which could 10. a) any of various alarms on lead to substantial Fire Control Alarm Panel degradation of plant safety systems, b) Fire Pump 1A auto start c) verbal reports These times are LOFC from 100% power. Times may be I correspondingly longer for lower power levels (See LCO 4.2.18).
l l PORM 372 22 M43 . l l R PUBLIC SERVICE COMPANY OF COLORADO a FORT ST. VRAIN NUCLEAR GENERATING STATION 1ssue 12 Page 3 of 5 TABLE 5 ALERT Event Indication
- 11. Radiological effluents 11. a) RT 7324-1 indicating exceed 10 times technical 22.5 x 10 8 pCi/cc specifications instan-tenous limits. b) RT /324-2 indicating 22.5 x 10 8 pCi/cc c) RT 7325-1 indiccting
~ 27.0 x 10 ' pCi/cc d) RT 7325-2 indicating 27.0 x 10 pCi/cc e) RT 73437-1 indicating 27.0 x 10 ' pCi/cc I-131. f) RT 4802 indicating ~ 2 7.0 x 10 ' pCi/cc I-131. g) RT 4803 indicating 2 2.5 x 10 8 pC1/cc Utilize reading from above instruments and calculate dose rate per procedures
- 12. Ongoing security 12. As observed or reported.
compromise. PORM 3M 22 SE43 o . _ PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Table 5 s / FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 5 TABLE 5 ' ALERT Event _ Indication
- 13. Severe natural phenom- 13. a) Seismic recorder operate enon being experienced or (2.05 g)
or projected, such as: b) As Reported a) earthquake exceeding Operating Basis c) As Reported Earthquake levels; b) flood near design level; or, c) tornado striking facility.
- 14. Other hazards being 14. As reported by, or to, experienced or projected station personnel.
such as: x a) aircraft crash oil 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)
- 15. Evacuation of control 15. As deemed necessary by room anticipated or Shift Supervisor required, with control of l shutdown systems established l from local stations.
(Control room integrity l l breached). FORM 372 22 - 3643 ~ -HOME PUBLIC SERVICE COMPANY OF COLORADO (E FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 12 Page 5 of 5 s TABLE 5 ALERT Event Indication
- 16. All alarms 16. Control room observation.
(annunciators) lost for more than 15 minutes and reactor is not siiutdown; or, plant transient experienced while all alarms lost. (Parameter indication still functional.)
- 17. Other plant conditions 17. As deemed necessary by warranting precautionary Shift Supervisor.
activation of the PCC, TSC, and FCP. l PORM 372 - 22 3643 1 ' RERP-HOM': PUBLIC SERVICE COMPANY OF COLORADO Table 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 4 TABLE 6 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. 1 See LCO 4.2.18.)
- 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 open. decreasing Reactor pressure.
- 4. Determination of inability 4. 230 KV OCB trips and RAT to restore onsite AC undervoltage/ loss of power power. alarm accompanied by 4Ky 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 .01Ap at 220 F.
- 6. Major damage to spent 6. a) Visual observation.
l fuel due to severe cask damage resulting in release b) area radiation monitor of radioactivity to plant alarms. environs. I FORM 372 22 ;M43 PUBLIC SERVICE COMPANY OF COLORADO "" (b FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 4 TABLE 6 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 greater than 50 mrem / on:
hr,or greater than 500 mrem /hr a) RT 73437-1, RT 4802, whole body for two and RT 7325-1, 2 minutes at the ~ site boundary under 26.7 x 10 5 pCi/cc adverse meteorology I-131; or, (or levels 5 times the above for thyroid b) RT 7324-1, 2, dose rate). and RT 4803 ~ >6.6 x 10 2 pCi/cc 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 to security breach. (Response detailed in Station Security Plan.) FORM 372 - 22 3443 PUBLIC SERVICE COMPANY OF COLORADO ]ME FORT ST. VRAIN NUCLEAR GENERATlh!G STATION Issue 12 Page 3 of 4 1 TABLE 6 SITE AREA EMERGENCY Event Indication
- 10. Severe natural phenomenon 10.
being experienced or projected (with plant not in cold shutdown), such as; a) earthouake greater a) Seismic Recorder Operate than Safe Shutdown alarm with indication of Earthquake ground motion greater than 0.10g horizontal- or greater than 0.067g vertical. b) flood greater than b) As reported or observed. design levels c) winds in excess of c) average wind velocity design levels greater than 90 mph 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.
FORM 372 22 MM3 RERP-HOM': PUBLIC SERVICE COMPANY OF COLORADO Table 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 4 TABLE 6 SITE AREA EMERGENCY Event Indication
- 13. Evacuation of control 13. Remote shutdown 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 notification. 1 i FORM 372 22 3643 PUBLIC SERVICE COMPANY OF COLORADO y,E$HfE FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 I Page 1 of 1 l TABLE 7 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, c- are measured 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 possible. l FORM 372 - 22 3643 l l 1
- RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Attachment 1
^ FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 12 l Page 1 of 4 ATTACHMENT I IMDAIRED FIRE PROTECTION NOTICE Report No. - Year Sequence No. NOTE: It is important that the time of all calls and names of people contacted be logged. Any futher followup calls received or made should be logged as to time and identity of persons involved and the information transmitted or received shall also be logged. GIVE THIS INFORMATION AS SHOWN
- 1. Facility Name: Public Service Company of Colorado Unit No. One
- 2. Location: Fort St. Vrain, Platteville, Colorado Below Is the Information Which Will Be Requested Of The Caller
- 3. Caller's Name: Phone:
- 4. Cate and time of occurrence:
- 5. Details and extent of impairment:
- 6. Did impairment result from a loss? l(([*Yes (([lNo If yes, i details:
- Loss would be a fire, accidental system operation, windstorm damage, etc.
- 7. Restoration (of system) begun? l((lYes l((lNo Restoration work to be continuous? l((IYes l][lNo
- 8. Impaired area or equipment operable? l(( lyes ((((No Estimated restoration time: l l
FORM 372 Z2 3443 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN HUCLEAR GENERATING STATION [ Issue 12 nt 1 Page 2 of 4
- 9. Precautions: l[lValvestaggedout l((Discontinuedwelding, cutting,andhotwork l[IDiscontinuedsmoking l[lNotifyControlRoom(Shift) Supervisor,or other applicable management.
l[] Notify Fire Department / Fire Brigade l[lIncreasedwatchmanserviceto hourly (([Extraextinguishers/firehoseinarea Other:
- 10. Contacts made by Shift Supervisor:
a) Name of ANI contact: b) Time of ANI contact: Management
Contact:
a) Name of management contact: b) Time of management contact:
- 11. Additional contacts made/ received:
a) Per attached call sheet log. l l l12. RESTORED l l l l a) Repeat Steps I and 2 above l l l l b) Caller's Name: l l l l c) Date and time of restoration: l 1 l l d) Name of ANI contact: l 1 1 I e) Time of ANI contact: l l l l
- 13. The Shift Supervisor shall send the completed copies of the completed forms directly to Technical Services.
FORM 372 22 3643 l
RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Attachment 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 4
- 14. If Notification was a Fire /All-Risk Emergency, Technical Services will:
a) Determine if a Reportable Occurrence is required, and prepare a facsimile copy if a 14 day report is indicated. b) Assign a sequential number and send a copy to the Superintendent, Operations and a copy to PORC. 1 l 1 l FORM 372- 22 3643
l PUBLIC SERVICE COMPANY OF COLORADO ((l, ,, 1
, FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 4 j
l l l l l l l CALL I TIME I DATE I CONTACT (NAME) l COMMENTS / REMARKS I I I l i l l I I I i i l I I I I I I I I I I I I I I i i i l l I i i l ! I i i I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 I I I I I I I I I I I I I I I I I I I I I I I I i l I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I i 1 I I I I I I I I I I I I I I I I l 1 I I I I I I l l 1 l l l l l 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l l I I I I I I I I I I I I I l l PORM 372 22 3643 I
RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Attachment 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 4 Initial Notification, Non-Emergency Event Report No. - Year Sequence No. IMPORTANT: It is imoortant that the time of all calls and names of people contacted be logged. Any further follow-up calls received or made should be logged as to time and identity of persons involved and the information transmitted or received shall also be logged.
- 1. Name and Identity of Caller:
- 2. Date of Event: Time of Event:
- 3. This notification appears to be required pursuant to 10CFR 50.72, paragraph ((b)(1), "One-Hour Report"; or (b)(2),
"Four-Hour Report") (circle one).
- 4. Description of Event:
Reactor power prior to event: Loop Shutdown? Scram? Initiating signal (s): Was event result of an LCO Action Statement? Other pertinent information:
- 5. Actions Taken:
l PORM 372 22 3643
1 PUZLIC SERVICE COMPANY OF COLORADO ht c t2 FORT ST. VR AJN NUCLEAR GENERATING STATION Issue 12 page 2 of 4 I l t
- 6. Status:
i Reactor power at time of report: Under control by on-site staff, no off-site assistance anticipated. Final report. Under control by on-site staff. Will keep NRC advised. Off-site assistance may be required. Will advise. (See Item #7) Off-site assistance required. (See Item #7)
- 7. If off-site assistance is anticipated or required.. describe assistance that has been or may be requested:
- 8. Does the event involve off-site releases of the potential for off-site release that would affeact the general health and safety of the public as the result of Fort St. Vrain conditions?
Yes No
- 9. If yes, provide a good description:
- 10. Contacts made by Shift Supervisor:
a) Name of NRC contact: b) Time of NRC contact: PORM 372 22 3643
RERP-HME PUBLIC SERVICE COMPANY OF COLORADO Attachment 2 FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 12 Page 3 of 4 Management Contact a) Name of management contact: b) Time of management contact:
- 11. Contacts made by management:
a) Per attached call sheet log.
- 12. The Shift Supervisor and Management Contact shall send their copies of the completed forms directly to Technical Services who will:
a) Determine if a reportable occurrence is required and prepare a facsimile copy if a 14 day report is indicated. b) Send a copy to the Superintendent, Operations. c) Send a copy to PORC. FORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO hR 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 4 of 4 I I I I I I l CALL 1 TIME I DATE I CONTACT (NAME) I COMMENTS / REMARKS I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I l l 1 1 I l 1 I I I I I I I I I I i l i I I I i l l I I I I I I I I I I I I I I I I I I I I I i 1 1 1 I I I I I I I I I I I I I I I I l l l 1 l l l l 1 1 I I I l l 1 I I I I I I I I I I I I I I I l l l l l 1 I I I I I I I I I l l l l l l I I l l l l l l l l l 1 I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I .I I I I I I I I FORM 372 22 3643
l RERP-HOME
. PUBLIC SERVICE COMPANY OF COLORADO Attachm:nt 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 3 NOTIFICATION OF UNU5UAL EVENT A. The Emergency Coordinator and first management contact will complete the following information jointly:
- 1. Name and identity of caller
- 2. Date of Event Time of Event
- 3. General Category of Event Unplanned Radiological Release to Reactor Building Fuel Failure Fire Natural Phenomenon (circle one)
Earthquake Flood Tornado Winds Unusual Hazards (circle one) Aircraft Explosion Toric Material Other (Specify) Spent Fuel Incident 4 Description of Event
- 5. Actions Taken
- 6. Status:
Under control by onsite staff, no offsite assistance anticipated. Under control by onsite staff. Will keep State and NRC advised. Offsite assistance may be required. Will advise. (See Item 7.) Offsite assistance required. (See Item 7.) FORM 372 22 M43
PUBLIC SERVICE COMPANY OF COLORADO 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 3
- 7. If offsite assistance is anticipated or required, describe assistance that has been or may be required:
- 8. At the present time, the event does not involve offsite release or the potential for offsite releases that would affect the general health and safety of the public.
B. The Emergency Coordinator will make notifications as follows: I Contact with State EOC (279-8855) and Governor's Office (866-2471)l l orMansion(837-8350) l l l
- 1. READ the following statement verbatim:
"THIS IS A NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION. THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF EMERGENCY RESPONSE CENTERS. THIS NOTIFICATION REQUIRES VERIFICATION OF RECEIPT BY THE STATE. VERIFY BY CALLING 571-7436 or 785-2223."
- 2. READ all the information recorded in Step A (Page 1 of this ATTACHMENT).
PORM 372 22 M43 I l
R PUBLIC SERVICE COMPANY OF COLORADO ffga t3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 3 1
- 3. RECORD the following information:
Name of State E0C contact Date/ Time Name of Governor's Office / Mansion Contact Date/ Time Call back verification from State EOC, Date/ Time Call back verification from Governor's Office / Mansion Date/ Time l I l Contact with NRC Operations Center (Hot Line or 202-951-0550) l I I (Alternate means of notification are described in Attachment 1 of RERP-CR.)
- 1. READ the following statement verbatim:
"THIS IS NOTIFICATION OF AN UNUSUAL EVENT AT THE FORT ST. VRAIN NUCLEAR GENERATING STATION AT PLATTEVILLE, COLORADO. THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO 10CFR50.72, PARAGRAPH (a)(3). THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE ORGANIZATIONS."
- 2. READ the NRC Operations Center all of the information recorded in Step A (Page 1 of this Attachement).
- 3. RECORD the following information:
Name of NRC Contact Date/ Time ! PORM 372 22 3643 l i e
- 1 RERP-HOM: I PU.~:LIC SERVICE COMPANY OF COLORADO Attacnment 4 i FORT ST. VRAIN NUCLEAR GENERATING STATl10N Issue 12 Page 1 of 5 l
NOTIFICATION OF EMERGENCY EVENT A. The Emergency Coordinator will complete Pages 1 and 2 of this attachment with the assistance of the first management contact. I I l Required Information l l 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, an3 no special protective actions are recommended at this time.
93 l b) A small radioactive release IS taking place, but Ng l protective actions are recommended at this time and l are not anticipated to be. 93 l c) A radioactive release IS, repeat IS, taking place, and we recommend that people in areas remain indoors with windows and doors closed. 93 l d) A radioactive release IS, repeat IS, taking place,' and we recommend that evacuation of areas be considered.
- 4. Personnel Control Center to be located
- 5. Further information on incident conditions will be provided in followup messages.
FORM 372 22 36MI
PljBLIC SERVICE COMPANY OF COLORADO Rf.
. ftg FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 5 l l
[ SUPPLEMENTAL INFORMATICN l 1 I NOTE: This information is to be supplied to the NRC and the Colorado Department of Health wher, requested. The radiological data can be determined as specified in RERP-DOSE.
- 1. Date and Time of Incident
- 2. Class of emergency (ALERT)(SITE AREA EMERGENCY)
(GENERAL EMERGENCY)
- 3. Type of release (airborne, waterborne, surface)
- 4. Estimated duration of release (Hours)
- 5. Current release rate:
Noble Gas Ci/sec; Iodine Ci/sec
- 6. Estimated curies released:
Noble Gas Ci; Iodine Ci
- 7. Wind Velocity MPH, from degrees.
to degrees, Air Temp 'F
- 8. Stability Category . Form of Precip.
- 9. Dose rate at EAB: WB rem /hr; Thyroid rem /hr 2 Miles: WB rem /hr; Thyroid rem /hr 5 Miles: WB rem /hr; Thyroid rem /hr
- 10. Projected dose at EAB: WB rem; Thyroid rem 2 Miles: WB rem; Thyroid rem 5 Miles: WB rem; Thyroid rem
- 11. Estimated accumulated dose at EAB:
WB rem; Thyroid rem FORM 372 22 3643
RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO At:9thment 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 3 of 5
- 12. Areas expected to be impacted by release
- 13. Estimate of any surface radioactive contamination
- 14. On-site response actions under way
- 15. Recommended Protective Action based on the projected dose at the EAB (Read appropriate Protective Actions)
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.
- 16. Prognosis for worsening of event
- 17. Date and time of report
- 18. Name of person providing report
- 19. Telephone number for call back l
l l PORM 372 22 M43
- RERP-HOM:
PUBLIC SERVICE COMPANY OF COLORADO Atta::hment 4 FORT ST. VRAIN WUCLEAR GENERATING STATION lssue 12 l Page 4 of 5 l l l
- 20. Description of any requested off-site assistance B. The Emergency Coordinator will make notifications in sequence as follows:
l l l l PSC Company Operator 8-571-4591 l l or 8-571-0111 l l l
- 1. INSTRUCT the Operato.' to initiate the " Fort St. Vrain Radiological Emergency Call List."
- 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 I l Weld County (911 Using Greeley Line) l 1 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 i l l PORM 372 22 340
PUBLIC SERVICE COMPANY OF COLORADO [.];,ft4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 5 of 5 l l l NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l l l (Alternate means of notification are described in Attachment 1 of RERP-CR.)
- 1. READ Items 1) through 4) from Part A.
- 2. READ the following sentences verbatim. "THIS EVENT IS BEING REPORTED PURSUANT TO 10CFR50.72, PARAGRAPH (a)(3).
WE ARE PRESENTLY ACTIVATING STATE AND LOCAL EMERGENCY RESPONSE CENTERS."
- 3. READ the supplemental information (Page 2 of this attachment).
- 4. RECORD the following information:
NAME of NRC Contact TIME of NRC Contact l PORM 372 22 3643
PUILIC SERVICE COMPANY OF COLORADO fta z5 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 2 l ECP DIRECTOR'S CALL LIST INTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the response center / post Director:
- a. Call your response center / post Alternate Director (the alternate will complete the calls on the attached list).
- b. If you cannot contact your Alternate Director, call the first person on the attached list a_nd inform him to complete the call list.
- 2. If you are the response center / post Alternate Director and are contacted by the Director:
- a. Complete the attached call list.
- 3. If you are the response center / post Alternate Director and are contacted by the PSC Operator:
- a. Call the first person on the attached list and inform him to complete the call list.
PORM 372 22 3643
E PUl:LIC SERVICE COMPANY OF COLORADO k*af m nt 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 l Page 2 of 2 l ECP DIRECTOR'S CALL LIST First call all primaries, then call all alternates. PSC Extension Home Time Manager - Technical Succort .
] Primary - M. E. Niehoff 785-1403 690-3879 Alternate - Mike Holmes 571-8409 988-4522 Manager - Media Relations Primary - R. T. Person, Jr. 571-7323 753-9292 Alt. - W. O. Fitzmaurice 571-7158 424-8053 Manager - Resources Primary - D. D. Hock ' 571-7211 394-3063 l Alternate - J. Bumpus 571-7821 388-7645 Manager - Security Primary - E. O'Neal 571-7709 757-0038 -
l Alternate - E. Lane 571-8533 321-4016 PORM 372 22 364
PUBLIC SERVICE COMPANY OF COLORADO E FORT ST. VRAIN NUCLEAR GENERATING STATION ftt nt 6 Issue 12 Page 1 of 2 CORPORATE EMERGENCY DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the response center / post Director:
- a. Call your response center / post Alternate Director.
- b. If you cannot contact your Alternate Director, call the first person on the attached list a_nd inform him to complete the call list.
- 2. If you are the response center / post Alternate Director and are contacted by the PSC Operator or the center / post Director:
- a. Call the first person on the attached list d inform him to complete the call list.
- 3. If you are the first person on the attached list and are contacted by the Alternate Director or the Director:
- a. Complete the attached list.
l l PonM 373 22 3643
l PUBLIC SERVICE COMPANY OF COLORADS ya m]t 6 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 2 of 2 CORPORATE EMERGENCY DIRECTOR'S CALL LIST (FCP) First contact all primaries,.then call all alternates. Extension Home Time i' stgion Technical Listson (Ose of the Station Technical Liaisons is also contacted by the
, PSC Operator.)
Primafy - C..H. Fuller .785-1202 663-2363 ~~ Altprnate - J. W.,Gahm 785-1350 452-0507 d Radiological _A+.sesse g Petr.ary - T. Borst 785-1203 663-1230 (Pager) 890-1775 Clerical Assistance Primary D. Merritt 785-1271 737-2339 Primary - D. Heath 785-1272 223-5121 Alternate - S. Katcher 785-1212 356-0351 Media Relations Primary - M. Mora 571-8462 694-2369 Alternate - S. Volsted 571-7242 755-5164 e
,L m.n.yu e
R PUBLIC SERVICE COMPANY OF CELORADO Rfgc nt 7 FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 3 PCC DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the response center / post Director:
- a. Call your response center / post Alternate Director (the alternate will complete the calls on the attached list),
- b. If you cannot contact your Alternate Director, call the first person on the attached list and him to complete the call list.
--- inform
- 2. If you are the response center / post Alternate Director and are contacted by the Director:
- a. Contact persons to set up the facility by calling those individuals with asterisks (*) after their names and by notifying four (4) Health Physics Technicians listed. Inform all persons of the l location of the PCC. Call the remainder of personnel upon arrival at the PCC. (This responsibility may be delegated.) '
- 3. If you are the response center / post Alternate Director and are contacted by the PSC Operator:
- a. Call the first person on the attached list and inform him to complete the call list as specifie3 in 2.a. above.
90nk 313
- 33
- M43
l
. PUBLIC SERVICE COMPANY OF COLORADO h* nt 7 FORT ST. VR AIN NUCLEAR GENERATING STATION lssue 12 Page 2 of 3 i
PCC DIRECTOR'S CALL LIST l I Plant Extension Home Time ; Personrel Accountability anc ! & C Technicians G. Redmond* 251 9-339-3152 T. Bashline 262 8-303-686-9763 P. Bearly 455 8-303-669-6636 M. Benedict 313 9-353-7209 M. Blosson* 261 9-785-6302 R. Dickerson 273 8-303-287-6089 T. Dillen 262 9-356-3370 R. Erwin 315 9-330-7178 D. Frye 276 9-587-4768 R. Hamblin 254 8-303-567-1703 C. Harding 311 9-785-2398 l K. Hays 319 8-303-778-7702 J. Hohn 260 9-785-6322 W. Holcomb 312 9-330-2068 R. Hooper 458 8-303-452-3614 D. Horihan 250 78-776-7976 S. Lehr* 451 8-303-422-1280 G. McAfee 260 8-303-857-6498 l R. Moler 456 78-772-9357 G. Murphy
- 254 9-785-2542 l M. Murphy 454 8-303-279-6762 G. Powers 252 8-303-426-1623 D. Reed
- 314 9-785-2159 l Rivera 453 E-303-667-1906
. Shafer* 457 9-587-4061
.. Stieff* 209 9-587-2500 J. Switzer 452 9-587-4134 P.. Teel 261 8-303-288-1959 R. Wyatt 262 8-303-493-3649 Maintenance, Reoair. and Damage Control R. Webb* 229 78-776-8219 (Pager) 855-7257 R. Lamb
- 336 78-772-0757 D. Nelson
- 246 9-587-4189 s
FORM 372 22 300
RE
. PUBLIC SERVICE COMPANY OF COLORADO , j y FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 12 Page 3 of 3 Monitoring Teams - Health Physics (Notify four of the following initially.)
J. Brown 245, 9-339-3972 P. Glahn 245 8-303-450-5292 L. Hutchins 245 9-330-7187 l G. Madison 245 8-303-833-2278 K. Morse 245 9-353-6163 K. Nasveschuk 245 78-651-6254 1 E. J. O'Donoghue 245 8-303-452-3514 S. Sherrow 245 9-353-1338 l S. Sieg 245 8-303-663-3468 l G. Valentine 245 8-303-532-4861 Radiochemistry V. McGaffic (P)* 278 9-587-2752 D. Miller (A)* 279 8-303-663-3595 S. Poet (A) 279 78-652-2297 M. Prochownik (A) 279 9-785-6010 S. Rima (A) 279 78-772-4068 Operating Staff Support As Required - See RERP Phone Lists. Maintenance (Electrical, Mechanical) As required at the discretion of the PCC Director - Refer to RERP Phone Lists. Hazards Control Team Fire Brigade Members I l FORM 372 22 M43
RERP-HOME i .
~
PUBLIC SERVICE COMPANY OF COLORADO Attachment 8 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 Page 1 of 2 STATE EOC CALL LIST INSTRUCTIONS (For Contacts cy P'$C) In the event you are notified by the PSC operator that a Radiological ALERT or higher classification event has occurred at Fort St. Vrain, complete the following telephone calls:
- 1. If you are the PSC primary contact:
- a. Call the PSC alternate contact and instruct him to complete the call list.
- b. If you cannot reach the PSC alternate contact, call the first person on the attached list and inform him to complete the call list.
- 2. If you are the PSC alternate contact and are notified by the PSC primary contact:
- a. Complete the attached call list.
- 3. If you are the PSC alternate contact and are notified by -
the PSC operator:
- a. Call the first person on the attached list g d inform him to complete the call list.
FORM 372 - 22 3643
R PUBLIC SERVICE. COMPANY OF COLORADO
. , ffga t8 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 12 i Page 2 of 2 STATE EOC CALL LIST (For Contacts by PSC) I Extension Home Time Technical Assistance H. L. Brey (Primary) 571-8404 469-4238 l J. R. Reesy (Alt.) 571-8406 755-1720 Radiological Consultant Janet Johnson 491-5930 482-3029 Media Relations R. A. Burns (Primary) 571-8481 759-9740 - - - - -
G. Reeves (Alt.) 571-8479 424-4958 l l FORM 372 22 - 3643
' RERP-HOME PUBLIC SERVICE COMPANY OF COLORADO Attachment 9 l
FORT ST VRAIN NUCLEAR GENERATING STATION Issue I2 Page I of 3 l TSC DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the PSC operator that a l Radiological ALERT or higher classification event has occurred at i Fort St. Vrain, complete the following telephone calls: I. If you are the response center / post Director:
- a. Call your response center / post Alternate Director (the alternate will complete the calls on the attached list).
- b. If you cannot contact you Alternate Director, call the first person on the attached list and inform him to complete the call list.
- 2. If you are the response center / post Alternate Director and are contacted by the Director:
- a. Complete the attached call list.
- 3. If you are the response center / post Alternate Director and are contacted by the PSC Operator:
- a. Call the first person on the attached list and~~~
inform him to complete the call list. FORM 372 22 300
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.' PUBLIC SERVICE COMPANY OF COLORADO g FORT ST. VRAIN NUCLEAR GENERATING STATION lssue 12 Page 2 of 3 TSC DIRECTOR'S CALL LIST First call all primaries, then call all alternates.
Plant Reactor Physics Extension Home Time Primary - F. Novachek 270 457-8034 (Pager) 890-1941 Alternate - R. Heller 284 772-1093 Radiological Assessment l Primary - J. Sills 265 221-5059 l (Pager) 890-2223 Alternate - S. Johnson 267 663-1431 Plant Condition Assessment Call two off-duty Shift Supervisors M. Deniston 219 776-3776 D. Evans 219 776-9672 J. Hak 219 776-1904 l D. Hood
- 219 or 347 776-1843 l J. Hunter 219 330-1411 H. O'Hagan 219 776-8232 G. Reigel 219 330-4235 J. Vandyke 219 or 346 772-2476 Emergency Maintenance Primary - W. Craine 222 667-5427 Alternate - J. Petera 233 427-6273 Instrument and Cectrol Primary - B. Burchfield 249 351-0373 Alternate - J. McCauley 248 667-0635 Health Physics / Health ?hysicist Primary - T. Schleiger 242 785-5314 l Alternate - B. Woodard 244 678-0818
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[* Also contacted as alternate to Control Room Director by PSC l operator. 1 i ! l FORM 3 2 300
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. PUBLIC SERVICE COMPANY OF COLORADO f. 9 FORT ST. V,R AIN NUCLE AR GENERATING STATION
, Issue 12 Page 3 of 3 Administration / Logistics Primary - A. Kitzman 206 737-2578 ,
Alternate - P. Collins 207 587-2172 Alternate - P. Bollig 204 339-3972 , Alternate - D. Connelly 210 353-4575 Telechone Console Ooerators -
)
Primary - D. Edwards 217 669-1680 Alternate - D. Libal 213 651-1404 Computer Support
- Primary - D. Klaus 437 466-5046
- Alternate - D. Bilstein 333 532-2546 l
- Alternate - D. Haloin 376 353-1993
- Computer Services Page Number: 855-3234 FORM 372 - 22 3643 l
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GENERATING STATION Page 9 of 12
- Dispatches personnel to notify any individuals living in the owner controlled area who were unable to be contacted by telephone; l
- Coordinates medical transport for injured l personnel; '
- Coordinates access for personnel arriving from '
outside the plant with Weld County Sheriff's I Department;
- Coordinates entry /re-entry of required persor.nel with the Lead Security Officer;
- Relocates the PCC to an alternate onsite or offsite location, as required;
- With the concurrence of the TSC Director, authorizes volunteer emergency workers to receive doses in excess of 10 CFR 20 limits (see RERP-EXP); and, a Receives reports of accidental or emergency exposure in excess of occupational limits, and inforrrs the TSC Director of these occurrences; and,
* 'iefers any rec;uests for cutside assistance to the TSC Director.
2.5.2 Personnel Accountability Pemonnel Accountability personnel are responsible for maintainino continued personnel accountability and exposurc estirhates, handling search and rescue assignmer.ts, pcrforming first aid and personnel l decontamination, and assisting in the medical transport of injury victims. 2.5.3 Maintenance, Rerair, and Damage Control Perform mechanical and electrical repair / damage control, emergency maintenance, and temporary modifications. 2.5.4 Hazards Control Extinguish fires, purge hazardous gases, and combat natural emergencies. A PORM 372 22 3643
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. PUBLIC SERVICE COMPANY OF COLORADO ,6 FORT ST. VR AIN NUCLEAR GENERATING STATION Page 10 of 12 2.6 Executive Command Post The Executive Command Post (ECP) is manned by senior corporate personnel with the authority to activate corporate personnel, facilities, equipment, and financial resources in an emergency situation (see Figure 3). The ECP supports PSC personnel stationed at onsite and offsite emergency response centers.
2.6.1 ECP Director The ECP Director will assume overall responsiblity for providing the Corporate Emergency Director with the counsel, expertise, and resources available within the PSC organization. He coordinates emergency assistance, provides re-entry and recovery support, station and site modifications review by the Nuclear Facilities Safety Committee. 2.6.2 Manager of Technical Support The Manager of Technical Support will provide the Corporate Emergency Director and onsite emergency operations with technical advice in nuclear, mechanical, civil, and electrical engineering. -He provides engineering support, technical experts, and consultants, as requested. 2.6.3 Manager of Media P.21ations The Manager of Media Relations will coordinate communications between the ECP and other emergency facilities, and will assist the ECP Director and PSC medis relations personnel in preparation of press releases, annouacements, and interviews. 2.6.4 Manager of Resources The Manager of Resources will coordinate provision of manoower and equipment from within PSC, and from consultants / contractors to support onsite emergency operations. He provides requested technical and craft support; personnel or consultants for engineering / design and construction reviews; temporary housing, office transportation, and construction equipment; purchasing, financial, legal, and general office support; and, food deliveries and related logistics support to l designated emergency operations. l l o I O l FORM 372 22 3643 l
1 l Y' RERD-ORG l q PUBLIC SERVICE COMPANY OF COLORADO Issue 6 FORT ST. VR AIN NUCLEAR GENERATING STATION Page 11 of 12 2.6.5 Manager of Security The Manager of Security will coordinate PSC security operations with public law enforcement agencies. He acquires additional security manpower hardware, and equipment, as requested. 2.7 State Emergency Operations Center The State Emergency Operations Center (State EOC) is the primary point thrcugh which the Governor, or his designee, exercises overall control and coordination of emergency response operations through the Colorado Division of Disaster Emergency Services. 2.7.1 Vice President of Governmental Affairs or the Manager of Nuclear Engineering This individual is responsible to coordinate PSC emergency response activities with those of state / local / federal agencies. 2.7.2 Media Relations Manager or News Director This individual is responsible for providing up-to-date site information to the Public Information Coordination Team (PICT) Chief (Governor s Office representative) and assisting the PICT i r, preparation of mutually acceptable news releases, fact sheets, background material media releases, and runor control in accordance with the "PSC RERP Public Ir. formation Plan." 2.7.3 Radiation Specialist I The Radiation Specialist is responsible for providing assistance and substantiated data regarding the site's emergency status and plant conditions to state / local / federal emergency response agencies assigned to the State EOC. 3.0 Responsibilities This procedure will be implemented whenever the Shift Supervisor declares an ALERT, or higher, emergency classification. Individual responsibilities are specified in Section 2.0 of this procedure. FORM 372 22 3643
k RERP-ORG
, PUBLIC SERVICE COMPANY OF COLORADO Issue 6 FORT ST. VR AIN NUCLE AR GENERATING STATION Page 12 of 12 l
l I 4.0 References 4.1 Fort St. Vrain Nuclear Generating Station Radiological Emergency Response Plan l 4.2 PSC RERP Pu'elic Information Plan 5.0 Procedures Referenced l 5.1 RERP-CR, Control Room Procedure 5.2 RERP-ECP, Executive Command Post Procedure 5.3 RERP-FCP, Forward Command Post Procedure 5.4 RERP-PCC, Personnel Control Center Procedure 5.5 RERP-SEOC, State Emergency Operations Center Procedure 5.6 RERP-TSC, Technical Support Center Procedure 5.7 RERP-EXP, Emergency Exposure Guidelines 5.8 RERP-SUPORG, Use and Coordination of Non-PSC Support Organizations I t (3 FORM 372 3643
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. . , PUBLIC SERVICE COMPANY OF COLORADO he 7 FORT ST. VRAIN NUCLEAR GENERATING STATION Is' sue 6 Page 1 of 1 FIGURE 1 ONSITE-OFFSITE EMERGENCY ORGANIZATION Fort St. Vrain Nuclear Generating Station l TECHNICAL SUPPORT CENTER 1 I I I
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- TECIINICAL ASSISTANCE
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RERP-PAG k, < PUBLIC SERVICE COMPANY OF COLORADO Issue 3 V FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 5 [ ORT ST.VEN TITLE: PROTECTIVE ACTION GUIDELINE RECOMMENDATIONS HON - CONTROLLED COPY ytg$yISSUE ST ATUS wlTH C000ptsi CENTER pqio9 TO USE ISSUANCE L2, W ,L.o. f 47 gqv 3n.n.3W AUTHORIZED BY 77]'l/912J PORC ' EFFECTIVE REVIEW PORc 5 8 0 AUG 2 - 1984 oATe 8-k 84 Section Description Page General...........................................................2 1.0 Cri teri a for Impl ementati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2.0 Procedure..................................................... 2 3.0 Re s po n s i b i l i ti e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 4.0 References ................................................... 5 5.0 R?ferenced or Supporting Procedures........................... 5 Table 1 Protective Action Guidelines ........................... 1 Table 2 Estimated Evacuatien Tirie cf the Perreanent Population Within the Plume Exposure and Emt gucy Plar.ning Zone. ..... .. .... ........ .... .. 1 Figure 1 Pcpulation Distribution Summari......... ............... 1 Datasheet 1 ..... .. ........... ...................... ......... 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 l WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTICN FOLLOWING EACH PROCEDURE. 4 3 FORM 372 22 3642 1
PUBLIC SERVICE COMPANY OF COLORADO (,
- FORT ST, VRA!N NUCLEAR GENERATING STATION Page 2~of 5 General This procedure discusses the mechanism for making recommendations of offsite protective actions to state authorities during a radiological emergency at Fort St. Vrain. This procedure also discusses the mechanism for decision-making regarding protective action recommendations.
The decision as to the appropriate protective actions to recommend rests, initially, with the Emergency Coordinator and, after facility activation, with the Corporate Emergency Director. The Corporate Emergency Director is assisted in this task by the Radiological Assessment Coordinator and the Technical Support Center Director. The decision should be based upon dose projections, field monitoring results, plant system parameters, expected duration of release, weather conditions, and, most importantly, dose avoidance. 1.0 Criteria For In.slementation This procedure is intended for use by the Emergency Ccordinator or by Radiological Assessment personnel at the Technical Support Center (TSC) and the Forward Command Post (FCP) for determination of the most practical method of protecting the general public. This information shall be relayed to the TSC Director and the Corporate Emergency Director. Additionally, this procedure may be used for reference information by the TSC Director and the Corporate Emergency Director to assist in decision making. This procedure is to be implemented whenever there is an ALERT or higher emergency class event in progress. 2.0 Procedure Protective action recommendations are te be based upon the U.S. EPA Protective Action Guidelines. These Protective Action Guides (PAGs) tre summarized in Table 1 of this procedure. The PAGs presented in Table I refer to avoidable doses, not simply to projected doses. In other words, for a protective action to provide any benefit, a substantial dose avoidance mJst be realized. The PAG values in no way imply an acceptable dose; they are simply values of dose avoidance where the benefit of taking a protective action is highly likely to exceed the risks associated with taking that action. Utilize Table 1 as the basis for making protective action recommendations. The following subsections of this procedure describe the various factors to consider in making a protective action. recommendation. Datasheet 1 is provided as a central place to record the appropriate data.
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- RERP-PAG i PUBLIC SERVICE COMPANY OF COLORADO 1ssue 3 EORT ST VRAIN NUCLEAR GENERATING STATION Page 3 of 5 2.1 Evacuation effectiveness The effectiveness of evacuation in limiting the radiation dose received is a function of the time available to complete evacuation prior to plume arrival. If the oublic can be evacuated prior to the plume's arrival, then the evacuation is totally effective in dose avoidance. The
" Evacuation Time Study of the 10-Mile Radius Area About the Fort St. Vrain Nuclear Generating Station," April 1981, states that the entire two mile radial area around the plant can be evacuated in approximately one (1) hour after notification, and that the entire plume exposure Emergency Planning Zone (EPZ) can be evacuated within 2.75 hours. These numbers are good weather estimates based upon notification by Weld County Sheriff's personnel.
More detailed estimates, including adverse weather estimates and credit for use of the Early Warning Alert (EWA) system, are available in Table 2 for reference purposes. Figure I provides a reference map showing sector boundaries and summarizes the population distribution around the plant. The above stated values should be utilized in conjunction with a stated value for plume arrival delay, in order to assess the effectiveness of an evacuation in dose avoidance. Simply stated, plume arrival delay (TA ) is the sum cf the time available before a projected release begins (TB ) and the time projected for plume travel (TT ) for a given windspeeri and downward distance once the release has begun. TA (hours) = TB+TT 2.2 Sheltering Effectiveness Sheltering wili always provide a measure of protection to the public, whenever carried out as instructed. It is extremely difficult, however, to quantify any specific protection factor that this will provide for all members of the public in all types of structures. Sheltering should be advised in any case where a definite hazard exists, but there are constraints against evacuation. Sheltering as a protective action includes the following actions: (1) Seeking shelter indoors near the center of the lowest floor of the structure; 1 (2) Securing all intake / exhaust ventilation to the ! structure during passage of the cloud; I O FORM 372 22 - 3643 l
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-r PUGLIC- SERVICE -COMPANY OF COLORADO u FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5
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i (3) Sealing fete cracks and window ledges with wet towels c'r rags; J (4) Cove <'ing ' mouth and nose with moistened handkerchief or cloth; and
. . . . /'
(5)_ , Restoring structure- ventilation as quickly as
. "possible after passage of the cloud.
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3 <0 Resoonsibilities , 3.1 Corporate Er.ergency Difector ,
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After the ' full activation of the FSV emergency organization, the Corporate Emergency Director has the authority and responsibility to make all protective action recommendations. The Corporate Emergency Director should 2onfer with the Radiological Assessment Coordinator and the Technical Support Center Director in this decision. 3.? Radiological _ Assessment Coerdinator After ~ activation--of the FSV emergency organization, make assessments of protective action needs based upon the current radiological conditions and the considerations conta Ged herein. Inform the Corporate Emergency Director of the results of this appraisal and submit an assessment of recommended protective actions.
, 3lJEmergancy Coordinator
, Prior to the activation of the FSV emergency organization,
, tne Shift Supervisor, in the role of Emergency Coordinator, has the authority and responsibility to recommend protective actions to offsite authoritics.
3.4 Technical Support Center Director Confer , with the Corporate Emergency Director, as recuested,,with respr.ct to current plant conditions and the need for offsits protective actions. 3.5 Radiological Assesraent (TSC). Assist the TSC Director and Radiological Assessment Coordinator witn this evaluation as requested. Confer
, with the Ra'diological Ass?ssment Coordinator regarding persistance or prospect of conditions worsening.
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l PUBLIC SERVICE COMPANY OF COLORADO $U FORT ST. VRAIN NUCLEAR .'.ENERATING STATION Pagt S of 5 4.0 References 4.1 Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, U.S.E.P. A. , June,1980. 4.2 Reactor Safety Study, Appendix VI, WASH-1400, October 1975. 4.3 Examination of Offsite Radioloeical Emercency Prote:tive Measures for Nuclear Reactor Accicents Invo'/ino Core Melt, NUREG/CR-1131, D. C. Aldrich, P. McGrath, N. C. Rasmussen, October, 1979. 4.4 " Evacuation Time Study of the 10-Mile Radius Area About the Fort St. Vrain Nuclear Generating Station," Public Service Company of Colorado, April, 1981. 5.0 Referenced or Supportino Procedures 5.1 RERP-DOSE, Offsite Dose Calculation Methodology. l 5.2 RERP-CR, Control Room Procedure 5.3 RERP-ORG, FSV Emergency Organization and Responsibilities 5.4 RERP-FIELD, Ficid Monitoring Procedure + FORM 372 - 22 3643 l l
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'l' PROIECilVE ACil0N._GUj.l R [Nrj '/ -
,- Recommended protectiva actions to reduce whole body and thyroid dose from exposure to a gasentes pitmio ,
Projected'. Dose (Rem) _t.o_Jh_e Popu_1_a1Lon Recommended Actigns ia1 Cgem ses. < Whole Body less than 1 No planned protective actions Previously recommended (b). State may issue an protective actions may Thyroid less than 5 . advisory to seek shelter and be reconsidered or , avait rurther instructions. terminated.
^
Moni to r env i ronmenta l radia tion levels. - , Whole Body I to 5 seek shelter as a minimum. Ir constraints exist, Consider evacua tiori. Evacuate special consideration Thyroid 5 to 25 unless constraints make snotild be given for j , i t' impractica l, evacuatiori or children J Moni tor envi ronmenta l and prtgnant women. , radiation levels. Control , access. '/ Whole body 5 nnd above Conduct mandatory evacuation. Seeking sliel ter.would be - Monitor environmental an alternative if thyroid 25 and above radiation levels evacuation were not and adjust area ror immediately possible. mandatory evacuation based on these levels. Control access.
<s (a) These actions a re recommended for planning purposes. Protective action decisions at the time or the incident must take existing conditions into consideration.
(b) At the tipo of the incident, orricials may implement low-impact protective actions in keeping with the principle or maintaining radiation exposures as low as reasonably achievable. j
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It rit P- pan Tablo 2 lasuo 3 Page 1 of 1 TABLE 2* ESTitMED EVACUAil0J_RM_rJr TIIE PERMAl(MT POPULATION WITil.Jf(EC._flutiE EXPOSURflMERCENCY 81ANNINC 20N(_(EP/,1 Estimated Estimated Estimated Estimated [stimated Estimatori 1980 NotIricatIon Evacuation Adverso Evacuation Ailverso Zone Resident ilme*Dy T ime for Wea tfie r I l mo f o r - Weather Population Sheriff's Good Wea the r - Evacuation Good Wea thor - Evacuation Department Sherirr's Time - FWA Notirica- Ilmo - IWA rur Good Department Notification tion Notification Wonther ( flou rs ) { llours ) { ifou rs ) { llou rs ) (llou rs) g-2 MiIes gl6
- Q,.2 LR LD 0.75 L!d I 140 0.5 1.0 3.0 0.75 1.55 11 76 0.3 0.75 1.75 0.70 1.40 0-5 MI1es J116 gJ g 12 12.0 LD LJ2 i&V 711 0.9 1.5 5.5 0.85 1.15 ,
I & VI 502 0.9 1.25 5.25 0.60 1.70 11 & Ill 363 06 1.0 3.75 0.65 1.70 II & IV 1816 0.5 1.25 3.25 1.0 1.70
- Based upon April 1981, "Evacua tion Time Study or the 10-Milo Radius Area About the fort St. Vrain Nuclear Cenorating Station,"
and a stated 15 minute notification utilizing the Early Warning Alert (EWA) system. s
i L l RERP-PA^" l PUBLIC SERVICE COMPANY OF COLORADO rigure 1 1
.. -. FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 1 l FIGURE 1 Pooulation Distribution Summary
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, PUBLIC SERVICE COMPANY OF COLORADO RgRP-PAG Da. asheet 1 1
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FODT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 I 4 Page 1 of 1 I i Datasheet 1 - Protective Action Recommendations Date / / Time : Initials Response Center Comments l 4 l l l l l 1 1 l
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~ $ i Page 1 of 3 Worksheet No. Title Number Ccoies None N/A N/A Datasheet No.
1 Protective Action Recommendations 20 Checklist No. None N/A N/A S FORM 372 22 3643
I' RERP-DAG
, , PUBLIC SERVICE COMPANY OF COLORADO WS/DS/CL , i FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 3 Page 2 of 3 FORMS USE rep 0RTING SHEET l Nuclear Documents Specialist:
This sheet is being transmitted to report use of forms from a controllec copy of the Emergency Plan Implementing Procedures, BOOK NO. , located at . The following forms have been utilized from this copy: Worksheet Numbers Copies Used Datasheet Numbers . Copies Used Checklist Numbers Copies Used The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting form. When this form is received, it will be necessary to replace the noted number of forms, as well as this " Forms Use Reporting
. Sneet" for the affected procedure in the affected book. +
4# FORM 372 22 3643
k RERP-DA*
. . PUBLIC SERVICE COMPANY OF COLORADO WS/DS/C[
. FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Fage 3 of 3 FORMS USE REPORTING SHEET (Continued)
COMMENTS Reported By: Date: l Nuclear Documents Specialist
- Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the 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.
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PORM 372 22 3643
I , . PUBLIC SERVICE COMPANY OF COLORADO h,y,[fg3 FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 3 Page 1 of I Datasheet 1 - Protective Action Recommendations Date / / Time : 4 Initials Response Center Comments ! + 2 FORM 372 22 3643 l l
I , PUBLIC SERVICE COMPANY OF COLORADO $- t1 FORT ST. VR AIN NUCLE AR GENERATING STATION lssue 3 Page 1 of 1 Datasheet 1 - Protective Action Recommendations Date / / Time : Initials Response Center Comments I 1 1 1 i f l k 1 + pomM 372 22 3643 l l
$ -' , -7 PUBLIC SERVICE COMPANY OF~ COLORADO Datasneet 1-FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 3
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g WS/DS/CL e'l .I FORT ST. VR AIN NUCLE AR GENE R ATING STATION Issue 3 e J j Page 2 of 3 4 FORMS USE REPORTING SHEET ,
'l Nuclear Documents Specialist:
This sheet is being transmitted to report use of forms from a controlled co;:y of the Emergency Plan Implementing Procedures, BOOK NO. , located at . The following forms have oeen utilized from this copy: Worksheet Numbers Copies Used Datasheet Numbers Copies Used Checklist Numbers Copies Used
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The procedure affected by this sheet is shown in the header to this page, unless otherwise noted below in the comments to this reporting l form. When this form is received, it will be necessary to replace I the noted number of forms, as well as this " Forms Use Reporting Sheet" for.th'e affected procedure in the affected book. l
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P A' f 1 PUBLIC SERVICE COMPANY OF COLORADO S g,f r-.j,.) FORT ST VRAIN NUCLE AR GENERATING STATION Issue 3 c TA :d Page 3 of 3 FORMS USE REPORTING SHEET (Continued) COMMENTS Reported By: Date: [ Nuclear Documents Specialist _ Date Received Date Replaced l* Nuclear Documents Specialist will transmit this form to the origin-ting individual / department upon completion of +his form to notity users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies. L l 4 F OmM 372 22- 3643 1
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PUBLIC SERVICE COMPANY OF COLORADO pR - C t assue IE A FORT ST. VR AIN NUCLEAR GENERATING STATION Page 1 of 14 y :. gy N. TITLE: PERSONNEL CONTROL CENTER PROCEDURE ggM - C0(.R0' S v0. . vEn g issue ciATUS N D pohut/EKT CENTER pq:ogTOUSE ISSUANCE g g, 4/ AUTHORIZED pcRV 372-22-3%, BY 4D/M4d " PORC - EFFECTIVE REVIEW 2DRC 5 8 0 AUG 2 - 1984 DATE h- b. b TABLE OF CONTENTS Section Description Pace 1.0 Cri te ri a f o r Imol ementati on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 2.0 Procedure.................................................... 3 3.0 Responsibilities ............................................ 11 4.0 References ........... ............. ........................ 13 5.0 Referenced or Supportino Procedures. . . . . . . . . . . . . . . . . . . . . . . . . . 13 Figure 1 Training Center Floor Plan ............................ 1 Figure 2 QA/ Engineering Complex Floor Plan. . . . . . . . . . . . . . . . . . . . . . 1 Figure 3 Route to Johnstown County Shops........................ 1 Figure 4 Route to Platteville VFD .............................. 1 Figure 5 Route to Longmont Service Center ...................... 1 Figure 6 Sector Map ............................................ 1 l Figure 7 Site Map .............................................. 1 l Figure 8 Exclusion Area Map .................................... 1 l Figure 9 Emergency Planning Zone (5-Mile) ...................... 1 l Figure 10 Emergency Organization ................................ 1 Datasheet 1 Personnel Accountability and Exposure .............. 1 l Datasheet 2 Briefing Sheet for Field Monitoring Teams .......... 1 l Datasheet 3 Briefing Sheet for Inplant Monitoring Teams ........ 1 l Datasheet 4 Briefing Sheet for Emergency Teart ................ 1
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POR M 372 22 - 3t:42
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RERFPCC l - g PUBLIC SERVICE COMPANY OF COLORADO Issue 14 FORT ST. VR AIN NUCLEAR GENERATING STATU3N page 2 of 14
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Checklist 1 PCC Director's Checklist. ..... ...... ......... .. 1 Checklist 2 Recorder PCC Closecut Checklist . . . . . . . . . . . . . . . . . . . . 1 Attachment 1 Recorder............................................ 1 Attachment 2 Communications...................................... 1 Attachment 3 Decontamination ............. ...................... 1 Attachment 4 Fort St. Vrain Security Department................... 1 Attachment 5 Drivers ............................................ 1 Attachment 6 First Aid .......................................... 1 Attachment 7 Instrument Accountability and Repair................ 1 Work /Datasheet/Checkli st Control Li st . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Fo rm s U s e Re p o rti n g S he et* . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED [ WORKSHEET SECTION AND FORWARD IT TO THE NUCLEAR DOCUMENTS l SPECIALIST, FORT ST. VRAIN. DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABSED SECTION FOLLOWING EACH PROCEDURE. I l l
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FORM 372 22 3643
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. . . PUBLIC SERVICE COMPANY OF COLORADO u y t FORT ST. VR AIN NUCLEAR GENERATING STATION pgge 3 of 14 1.0 Criteria for Implementation When the FSV Radiological Emergency Response Plan (RERP) l requires augmentation of onsite resources, the Personnel Control i Center (PCC) shall be activated. I l
2.0 Procedure l The PCC shall be activated by the Personnel Control Center i l Director at the direction of the Shift Supervisor (see RERP-CR). The Shift Supervisor prior to ordering PCC activation, shall i determine the PCC location. There are two designated onsite PCC locations, and three designated offsite PCC locations. The preferred location is the Training Center and the preferred alternate location is the Engineering /QA Complex. Facility locations are as follows: a) Onsite (in order of preference) (1) Training Center; (2) Engineering /QA Complex; b) Offsite (in order of preference) (1) Johnstown County Shops; (2) Platteville Volunteer Fire Departments; (3) Longmont Pt.blic Service Company Service Center. The decision of PCC location will be made based upon prevailing wind conditions and site accesibility to offsite respondants. 2.1 In the event that the PCC must be established offsite, the PCC Director is responsible for the transport of emergency equipment, including decontamination supplies, necessary to establish the offsite PCC. a) Emergency kits are stored at both the Training Center and the Engineering /QA Ceraplex (see HPP-37). The kits include:
- 1) Emergency radiological monitoring equipment
- 2) First-aid anc decontamination equipment
- 3) Protective clothing
- 4) Communications equipment
- 5) Portable lighting
- 6) Protective breathing apparatus
+ F ORM 372 3643
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- P PUBLIC SERVICE COMPANY OF COLORADO s FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 14 2.2 The PCC Director shall perform personnel accountability to assure that the initial manning requirements of the PCC can be met.
If not during normal working hours, those personnel required to man the PCC are notified by telephone (see RERP-HOME). 'It is the responsibility of the PCC Alternate Director, or the first individual contacted by the Director, to ensure that the notifications are made. l 2.3 The PCC Director shall establish initial communications with the Technical Support Center (TSC) and verify that primary and secondary communication links are available. I Communications personnel should be assigned to maintain I constant communication with the TSC. 2.4 Personnel reporting to the PCC
= Individuals assigned to the PCC must enter at the '
entrances designated on Figure 1 (Training Center) or Figure 2 (Engineering /QA Complex); remain in the FRISKING (or waiting) area until monitored for contamination.
- If contamination is found, proceed to the decontamination area as directed and initiate decontamination procedures (see HPP-11).
If cc.ntamination is not found, proceed to a clean arer c" the PCC as directed. 2.5 PCC Habitability Initially, and throughout the period that the PCC is activated, the PCC director is responsible for assurance cf facility habitability. The PCC director shall request that Health Physics periodically monitor the area (approximately every 15-20 minutes). Habitability is determined using an RM 14/15 set to alarm at 500 cpm, or if radiation levels are greater, by periodic air sampling. The HP Technician performing habitability checks shall inform the PCC Director of each survey's results, and assure that the Recorder enters results in PCC Log. 2.6 Personnel Accountability and Exposure Control After initial personnel accountability is completed at emergency stations (see G-5, Personnel Emergency Response), each facility director assumes responsibility for continued personnel accountability of the personnel
. assigned to him. This task is most challenging at the PCC, where repair / damage control teams, survey teams, k'
FORM 372 22 3643
P PUBLIC SERVICE COMPANY OF COLORADO
- FORT ST. VR AIN NUCLEAR GENER ATING STATHDN Page 5 of 14
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l l PCC, where repair / damage control teams, survey teams, reserve operating staff, and search and rescue teams are assembled and dispatched into the plant. The PCC Director shall assign a member of the PCC staff proximate responsibility for maintaining records of personnel accountability and personnel exposure records for those individuals assigned to the PCC. This individual, the Personnel Accountability and Exposure Controller, reports directly to the FCC Director, who maintains ultimate responsibility for continued Personnel Accountability. Additionally, the PCC Director has the responsibility for authorization of selected volunteers to receive emergency exposures in excess of occupational limits (only with joint concurrence of TSC Director and the senior Health Physics representative at the TSC). These responsibilities are described in detail in RERP-EXP, and include specific requirements for record keeping and job briefings. Responsibility for record keeping of personnel accountability and exposure is assigned to the Personnel Accountability and Exposure Controller. He is provided Datasheet 1 to assist him in maintaining the required records. 2.7 Personnel Assignments After activation of the PCC, the PCC Director shall assign one memb2r of his staff responsibility for maintaining control over personnel assignments to teams or tasks. This individual is the Personnel Assignment Controller, and his responsibilities are summarized below. NOTE: The senior Health Physics representative at the Technical Support Center and the TSC Director shall be
. consulted prior to dispatching any personnel from the personnel Control Center.
l l l l 1 + A l FORM 372 22 3643
RERP-PCC PUBLIC SERVICE COMPANY OF COLORADO Issue 14 FORT ST. VRAIN NUCLEAR GENERATING STATION page 6 of 14
'.4 2.7.1 Distribute equipment and appropriate Attachments or Datasheets of the PCC Procedure and record on the assignment board as personnel arrive and are available.
a) Recorder Attachment 1 Checklist 2 b) Communication Attachment 2 c) Personnel Accountability and Exposure Controller Datasheet I d) Decontamination Attachment 3 e) Security Attachment 4 f) Drivers Attachment 5 g) First Aid Attachment 6 h) Instrument Repair and Accountability Attachment 7 i) Assign first supervisor to arrive at the PCC the duty of directing additional personnel to their areas and retrieving them as necessary. j) Additional Personnel 2.7.2 Make every effort to ensure all arriving persons are assigned to each group in accordance with individual qualifications or, if not immediately assigned, assembled in an out-of-the-way place for further instructions. 2.7.3 Provide each. group with additional manpower as required. 2.7.4 With the assistance of the Personnel Accountability and Exposure Controller, contact or account for all personnel onsite and at the PCC. 2.7.5 Record all data for the master log. 2.7.6 Li st all available personnel on the control board from the Emergency Kit so that, if additional assistance is needed, personnel can be called in. 2.7.7 Keep records of additional personnel assignments . for master log. $ l FORM 372 22 - 3643
t PUBLIC SERVICE COMPANY OF COLORADO Ph l FORT ST. VRAIN NUCLEAR GENERATING STATION page 7 of 14 2.8 Radiological Monitoring Teams Radiological monitoring teams are dispatched from the PCC upon approval of the TSC Director, and under the overall direction of the senior Health Physics representative at the TSC. Protective clothing and aquipment requirements along with maximum stay times, are determined by the senior Health Physics representative at the TSC and relayed to the PCC Director for use in the briefing of the i monitoring teams (see Datasheets 2 and 3). 2.8.1 Field Survey Teams Field Survey Teams to survey both the Exclusion Area Boundary (EAB) and the plume exposure Emergency Planning Zone (EPZ) are dispatched as required (see RERP-FIELD). Field Teams consist of a Health Physics Technician and a Driver. Keys for the two site assigned Emergency Response vehicles and for two site assigned vehicles generally located at the Engineering /QA complex are stored in the PCC Emergency Kits. 2.8.2 Inplant/Onsite Monitoring Teams Monitoring teams to survey the plant and protected areas consisting of at least a Health Physics Technician and an assistant shall be dispatched as required (see RERP-SURVEY). 2.9 Notification of Persons Living on Plant Property The PCC Director is responsible to assure prompt (within 30 minutes of activation) notification of individuals living on plant property. This may be done by telephone (see Attachment 2) or by personal contact. 2.10 Medical Transport Transport of injured or contaminated individuals is to be performed "in accordance with the FSV Medical Emergency Plan. The TSC Director shall be notified of all such transport. l 1
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A FORM 372 3643
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. PUBLIC SERVICE COMPANY OF COLORADO Ph FORT ST VRAIN NUCLE AR GENERATING STATION page 8 of 14 2.11 Site Access Control / Security 2.11.1 PCC Guard Upon notification to activate the PCC, the Lead Security Officer (LS0) shall dispatch one security guard to the PCC. Security responsibilities at the PCC are as follows:
= Assist in gate control of authorized personnel and vehicles at the PCC (if Engineering /QA Complex selected).
- Ensure that the outer perimeter gate is secured and that non-PCC personnel are not admitted to the PCC without proper authorization.
- Assist with radio communications and access authorizations in cooperation with the LSO.
2.11.2 Site Response Guards After activation of the Personnel Control Center the PCC Director will coordinate access of personnel and vehicles into the protected area or vital areas with the LSO. Site response security personnel will: Check all site visitors out through the Search and Identification Facility.
- Facilitate the exit of onsite personnel reporting to the PCC.
- Assist in personnel accountability (in particular the Central Alarm Station as specified in Procedure G-5).
- Assist with p,ersonnel and vehicle ingress / egress to and from protected and vital areas.
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4' FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENER ATING STATION Page 9 of 14 2.12 Locating or Relocating the Personnel Control Center Offsite In t.he evaa. that the Personnel Control Center must be located or relocated offsite, one of the three locations listed below, in order of preference, will be used. An Emergency Kit and Instructions from a site facility will be utilized and must be transported to the alternate PCC. It is the PCC Director's responsibility to assure transport of Emergency Kit supplies. Privately owned vehicles will be used for transportation. 2.12.1 Johnstown County Shop The Johnstown County Shop keys are located with the Emergency supplies in the PCC Emergency Kit. During business hours, the county should be notified of an anticipated use of the facility (See RERP PHONE LIST). During non-business hours, the County shall be notified by calling one of the individuals listed in RERP PHONE LIST, at home. The physical location of the Johnstown County Shop is shown on Figure 3. 2.12.2 Platteville Volunteer Fire Department The Platteville Fire department should be notified of an anticipated use of the facility (See RERP PHONE LIST). Location of the facility is shown on Figure 4. 2.12.3 Longmont PSCo Service Center The Longmont Service Center should be notified of an anticipated use of the facility (See RERP PHONE LIST). Keys (two) to the gate and side door of ,the Service Center are located with the emergency supplies. Access to the building shall be via the east side door. One key opens the yard gate and , the other key opens the building door. Light l switches are located on the east wall, just south of the overhead door, and on the north wall by the entrance. Physical location of the facility is i shown on Figure 5. l
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FORM 372 22 - 3643
E RERhPCC PUBLIC SERVICE COMPANY OF COLORADO Issue 14 t FORT ST. VRAIN NUCLEAR GENER ATING STATION page 10 of 14 2.13 Decontamination / Controlled Areas Areas for the decontamination of site personnel and for control of radiologically contaminated equipment shall be established on an as-needed basis in accordance with existing Health Physics Procedures (see HPP-9, Establishing and Posting Controlled Areas; HPP-10, Area and Equipment Decontamination; HPP-11, Personnel Decontamination; and, HPP-21; Surface Radioact.ve Contamination Surveys). 2.14 Re-entry and Egress It is the responsibility of the PCC Director to coordinate re-entry into the plant for support plant operations personnel, emergency teams, or corporate resources personnel when directed to do so by the TSC Director. PCC Director will coordinate access to the plant site with the Weld County Sheriff's Department if PCC is to be established onsite. The PCC Director is also responsible for accountability of personnel leaving the plant after re-entry or being relieved. 2.14.1 Re-entry Guidelines For support plant operations personnel, and corporate resources personnel the PCC Director shall: a) Conduct briefings for the personnel to appraise them of personnel protective equipment requirements as advised by the senior Health Physics representative at the TSC and the TSC Director. b) Have the Personnel Accountability and Exoosure Controller record accountability and , exposure information. c) Have the LSO inform security of the personnel arriving and prepare to clear them through security.
+
A FOR M 372 - 22 3643
E RERP-PCC
.j PUBLIC SERVICE COMPANY OF COLORADO Issue 14 4
7 FORT ST. VR AIN NUCLEAR GENERATING STATION page 11 of 14 I 2.14.2 Emergency Teams (see RERP-TEAMS) a) The PCC Director will select individuals with the appropriate qualifications in Health Physics, First Aid, Operations, or Maintenance to make up a re-entry team and appoint a team leader. b) Conduct a briefing of the personnel to appraise them of conditions affecting them and personnel protective equipment requirements as advised oy the senior Health l Physics representative at the TSC. (See l Datasheet 4). Tht: PCC Director must clear all Emeroency Team re-entry with the senior Health Physics representative at the TSC, and request assessment of protective equipment, clothing requirements, thyroid prophylaxis needs, and any Emergency Exposure limitations as specified by RERP-EXP. c) Furnish team leaders with communication equipment and have the Personnel Accountability and Exposure Controller record information. d) Have the LSO inform Security of the pcrsonnel arriving and prepare to clear them through Security. e) The re-entry team will enter the area, establish communication with the TSC, perform the duties in the most safe and efficient manner possible, and inform the TSC of completion of duties and intent to leave the
. area.
f) Once their ~ operations have been completed, i the team personnel will follow self- l monitoring and personnel decontamination l procedures as specified by the team leader. l g) Return to the PCC to be screened through the Personnel Accountability and Exposure Controller and report to the PCC Director. h) The PCC Director will inform the TSC of the j return of the emergency team. l l lY ,ow m.u.=u
t y PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENER ATING STATION
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page 12 of 14 1 2.14.3 Personnel Leaving the Plant After Re-Entry or Being Relieved a) Report to the PCC for accountability. b) The PCC Director informs the TSC. 3.0 Resoonsibilities The Personnel Control Center (PCC) serves as manpower marshalling location to provide a pool of personnel available for emergency assignment. Personnel are assigned to perform functions consistent with their routine job classification. 3.1 Personnel Control Center Director The PCC Director is responsible for continued personnel accountability, assembling personnel for repair / damage control or radiological survey teams, search and rescue teams, reserve operating staff, and establishing radiological control areas as directed. In particular, his responsiblities inclede the following: Continued personnel accountability; Assuring that all emergency workers at-risk are evaluated by the Senior Health Physics representative at the TSC with regard to a need for thyroid blocking;
- Coordinates with Security personnel to control l access to the owner controlled area (Shift l Supervisor, in the capacity of Emergency l Coordinator, may perform before PCC activation);
- Dispatches personnel to notify any individuals living in the owner controlled area who were unable to be contacted by telephone;
- Coordinates medical transport for injured personnel; i
Coordinates access for personnel arriving from l outside the plant with Weld County Sheriff's Department; Coordinates entry /re-entry of required personnel with the Lead Security Officer; l
- Relocates the PCC to an alternate onsite or offsite location, as required;
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FORM 372 - 22 3643
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.7 PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Page 13 of 14
- Vith the concurrence of the TSC Director, authorizes volunteer emergency workers to receive doses in excess of 10 CFR 20 limits (see RERP-EXP);
- Receives reports of accidental or emergency exposure in excess of occupational limits, and informs the TSC Director of thesa occurrences; and,
- Refers any requests for outside assistance to the TSC Director.
3.2 Senior Hetith Physics Representative (TSC) The senior Health Physics representative at the TSC is responsible for the direction of radiological monitoring teams dispatched from the PCC. He is also responsible for assessment of protective clothing, dosimetry, and equipment requirements and maximum stay times for the teams. 3.3 Personnel Accountability and Exposure Control Personnel Accountability personnel are responsible for maintaining continued personnel accountability and exposure estimates, handling search and rescue assignments, performing first aid and personnel decontamination, and assisting in the medical transport of injury victims. The initial personnel accountability assessment prior to activation of the PCC shall be handled in accordance with Administrative Procedure G-5 and Security Instruction 6.10. 3.4 Maintenance, Repair, and Damage Control Perform mechanical and electrical repair / damage control, emergency maintenance, and temporary modifications. 3.5 Hazards Control Extinguish fires, purge hazardous gases, and combat natural emergencies. 3.6 Other Personnel l Detailed responsibilities of personnel assigned functions of Recorder, Communications, Decontamination, Security,
. Drivers, First Aid, and Instrument Repair / Accountability may be found in the Attachments to this procedure. +
FORM 372 22 - 3643
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PUBLIC SERVICE COMPANY OF COLORADO Eh FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1/ of 14 I l 4.0 References 4.1 FSV Radiological Emergency Response Plan 4.2 State Radiological Emergency Response Plan 4.3 PPC-83-1336 5.0 Referenced or Succortine Procedures 5.1 RERP-ORG, FSV Emergency Organization and Responsibilities 5.2 RERP-FIELD, Field Monitoring Procedure 5.3 RERP-SURVEY, Inplant/Onsite Monitoring Teams 5.4 RERP-THYROID, Thyroid Blocking Agent Administration 5.5 RERP-EXP, Emergency Exposure Guidelines 5.6 RERP-TSC, Technical Support Center Procedure 1 5.7 RERP-CR, Control Room Frocedure 5.8 RERP-HOME, Home Packet for Off-shift Notifications 5.9 RERP-PHONE LIST 5.10 RERP-SUPORG, Use and Coordination of Non-PSC Support Organizations 5.11 MEP, FSV Medical Emergency Plan 5.12 HPP-9, Establishing and Posting Controlled Areas 5.13 HPP-10, Area and Equipment Decontamination 5.14 HPP-11, Personnel Decontamination - 5.15 HPP-12, Portable Air Sample Collection and Analysis 5.16 HPP-21, Surface Radioactive Contamination Surveys 5.17 HPP-37, RERP Inventory List 5.18 HPP-57, Radiation and Airborne Radioactivity Monitoring During Abnormal Releases in the Plant 5.19 Security Instructions, Section 6.10, Personnel Accountability for Station Emergencies 5.20 G-5, Personnel Emergency Response + FORM 372 22 - 3643
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