ML20071E015
| ML20071E015 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/21/1983 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | |
| Shared Package | |
| ML20071D979 | List: |
| References | |
| PROC-830121-01, NUDOCS 8303100030 | |
| Download: ML20071E015 (301) | |
Text
N/2C"T PUBLIC SERVICE COMPANY OF CHLORADO
{(gghU%
FORT ST. VRAIN NUCLEAR GENERATING STATION 1/21/83 b
NON CONTROLLED COPY RADIOLOGICAL. EMERGENCY RESPONSE PLAN - STATION ISSUE EFFECTIVE NO.
SUBJECT NUMBER DATE RERP-ECP Executive Command Post Procedure 6
01-03-83 RERP-EXP Emergency Exposure Guidelines 1
08-02-82 RERP-FCP Forward Command Post Procedure 8
01-03-83 RERP-FIELD Field Monitoring Procedure 2
09-01-82 l RERP-HOME Home Packet for Off-Shift l
Notifications 3
01-21-83 RERP-ORG FSV Emergency Organization and Responsibilities 3
01-03-83 RERP-PAG Protective Action Guideline Recommendations 1
08-02-82 RERP-PCC Personnel Control Center Procedure 8
12-20-82 RERP-SEOC State Emergen:y Operations Center Procedure 5
01-03-83 RERP-SURVEY Inplant/Onsite Radiological Monitoring 1
09-09-82 RERP-THYROID Thyroid Blocking Agent Administration 2
12-03-82 O
FORM 372 22 3643 l
9303100030 830302 PDR ADOCK 05000267
(
F PDR
~
~
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION
. Issue 3 Page 1 of 5 g)
- v 1
TITLE:
HOME PACKET FOR OFF-SHIFT NOTIFICATIONS ISSUANCE
/ N-#
AUTHORIZED d #w M BY P")RC g
EFFECTIVE I-AI-N
$ ggg,ggy39,9,m, DATE H EVIEW 333 Sections Description Pace 1.0 Cri teri a f or Impl ementat ion.................................. 3 2.0 Procedure....................................................
3 3.0 Responsibilities.......................................... 5 4.0 References.................................................
5 5.0 Referenced or Supporti ng Procedures.......................... 5 f]
Figure 1 Notification Fanout..............
.................... 1 Figure 2 Facili ty Staf fi ng Requi rements.....................
1 l Checklist 1 Management Contact Notification List for an i
UNUSUAL EVENT.......................................
1 Table 1 Plant Management Contacts.............
1 Table 2 Significant Event Table............................
1 Table 3 NOTIFICATION OF UNUSUAL EVENT Table.................
1 Table 4 ALERT Table.
1 Table 5 SITE AREA EMERGENCY Table..
1 Table 6 GENERAL EMERGENCY Table.........
1 Impaired Fire Protection Notice (ANI)..........
1 Attactment 2 Initial Notification, Significant Event......... 1 NOTIFICATION OF UNUSUAL EVENT (Notification Form)
.1 Notification to Activate State Emergency
)
g I
e nw ass. ss. sus
\\..
PU LIC SERVICE COMPANY OF COLORADO RERP-HOME Issue 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 5
+
O ECP Di re cto r ' s Cal l Li st......................... 1 Attachmca+ 6 FCP Director's (CEDs) Call List...............
1 PCC Director's Call List........................
1 S ta te EOC C a l l Li s t............................
1 TSC Di rector's Call Li st.......................
1 0 Facility Directors / Alternates..................
1 O
l l
O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORAD3 RERP-HOME Iss u 3 FORT ST. VRAIN NUOLEAR GENERATING STATION Page 3 of 5 m
b 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 occt.rrence 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) Te assure that individuals who may potentially be required to call-in individu;is for off-shift emergency facility activation are clearly identified.
1.0 Criteria for Implementation 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 O
"ot4r4cetio#
to Amer 4ce" " cieer tas#rers
<^"t) is required under five (5) general categories listed below:
Losses 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. Additiona' plant management contacts may be made utilizing Table 1 for reference.
l l
\\
V l
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADD RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION 4 of 5
/ ;
V 2.2 "Significant Event" Notifications Notification to the NRC operations center within one (1) hour is required for events which fall under the general descriptions shown in Table 2.
When
- e events
+
e believes transpire, or when the on-duty Shift Supe' an event may require such reporting, he contact one of the plant management contacts l'
in Table 1.
Together, where possible, they 1*
sy complete the "Significant Event Notificatt of this procedure. Additioral r gement contacts may be made as necessary, utilizi t.
2.3 Radiological Emergenc.
a-
.. (RERP) Not'fications Notification to bote authorities and the NRC within fifteen (15) r<
of event classification is required when a situation has arisen that meets classification criteria set forth in Tables 3-6 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 g
aointly completed.
2,3.1 NOTIFICATION OF UNUSUAL EVENT l
For a NOTIFICATIO9 OF UNUSUAL EVENT, the initial l
management contact shall notify other contacts per l
Checklist 1 and forward the completed form to the l
Technical Services Department.
2.3.2 ALERT or Higher RERP Event Fo 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 herein.
Each facility's cali list is reproduced as Attachments 5-9, herein.
The Facility Director primary and alternates are shown on Attachment 10.
FORM 372 22 - 3643
l PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Issua 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 5
)
O 3.0 Responsibilities 3.1 Duty Shift Supervisor Contact a plant management contact in accordance with existing Operations Orders, Notification Procedures, or RERP-Implementing Procedures, where possible.
3.2 Plant Management 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 4.2 PT-80-177,
Subject:
Fire /All-Risk Emergency fiotification to the NRC; March 26, 1980 4.3 PT-80-177,
Subject:
Fire /All-Risk Emergency Notification to the NRC; October 13, 1980 O
s o aerere#ced er svanort<ma eroced"res 5.1 RERD PHONE LISTS 5.2 CR-UE, Control Room UNUSUAL EVENT Procedure 5.3 CR-ALERT, Control Room ALERT, SITE EMEFiGENCY, GENERAL EMERGENCY Procedure.
()
FORM 372 22 3643
O O
O 2
e c=
85 4
m u,am
'$x<
HOTIFICATION FANOUT FORT CT. VR AIN NUCLEAR GENERATING STATION 2O CONTROL z
ROOM 80 i
EO lE a
3 NRC PSCo REGION OPERATOR gz g*
IV WELD I
COUNTY PSCo Ro COMM FACILITY Em CENTER DIRECTORS yn i
- O FANOUT i
ALTERNATES O
O STAFF JX2k 2 E'2 -k 8%
O.,
W m
w
i RERP-HOME j
PUBLIC SERVICE COMPANY OF COLORADO Figure 2 1
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 1 OV i-e 51, I
i a
i
- n 5
s' 1
=
3 hg*:l*
[ii I
l55 O,*
se w 2 c
3 gg s
!5
=
1 3
i '
5 "i
- $3 I
223 n
jg3 ye$
O hI
- : -s 4
e 2
a s
!!)
!ih 3
i
- I!
i "g g g g
g g
ar-V a-s a
m W
(>
3,323s I
gg
",ls i I
I I
I
<z II I y I
E C
$$i"!!
$5 3
g Ei eIE 55
! l
- ;5 1
g u
1 l g
2s
1 2
=
s 11335 f O
E na O
1 a
a g
-i 15 1
8 i
5E
-I ~
n e<
3 I
E g
ec l a=
z.
e
=
=
o O-n=W:
- ::s
=
i
=
a n
e
- We t
_ _ _ __ _ a m#<
C W
3
- 4
- s g
-l1 2
ogo eg
"=E is 5:
5 8. I I
-[is g
si s i: I gl i
5 g
g ra i s,
- g a
nz m is n =]aj 5 :s g
s:
i a
s ua !
55 i
g e
- s ed
= ~
a a s
= g
.n
-gr -l i t
- s s.
s g
s s
t s
=-
- i. !
N<.
a l
- . =.
g:;-
y a
I s>
o c-a ma r
a ez
{es' -! !!
1 1,,
g 6
i 1
a n
15!,l
!s i N
g Ea is
<a 6
6 6
I I
6 1
Og m
C i
t I
E g* t y
O h
~ sl 52 e
g.;
a
=
1 a s 1
I LE I"5 3
"t s 1*' G.
W T
a g' -3 a
3 c
m u
-=
kh b
sti
- = u, 5 e
'i " d I y$tII 5I
{
m W
IE ='
3 I
i l
=i:i 8
g5 e
c ta tj E
E Em r sa O
1 FORM 372 22 3643 i
p.
PUBLIC SERVICE COMPANY OF COLORADO RERP-Home FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 1 l
i l
MANAGEMENT CONTACT NOTIFICATION LIST 1
I i
FOR AN UNUSUAL EVENT i
l The first management contact will make the following notifications, l and forward the completed form to the Technical Services Department.
ll l Subsequent l
Date/
l l
l l Contacts l
Time l
Remarks l
l l Plant Management l l
l l l(Contact 1) l l
l l lSuot. of Ooer.
l l
l lim I
I I
l l Station Manager l l
l l :_ (
l i
I lAdm1~istrative/ l l
l l
n l ITech. Serv. Mgr. l l
l l'i__.
'l l
l l l Manager, Nuclear l l
l l l Production l
l l
1, _.
-1 I
l l l Radiation Pro-l l
l l ltection Manager l l
l l
l l
I l lVice President, l
l l
l l Production l
l l
l l
l l
8 I
l l
l l Media Relations l l
l l IRnh Rurns l
l l
l I
I I
I I
l l l or l
l l
l IGary Reeves l
l l
1 I
i l
1 1
I I
or l
l l
l 1 l'IMarily McAdams l
l l
l l
l l
l 1
l l
l l NRC l
l l
l l Bill Dickerson l
l l
l I
I l
l l
~ or I
I l
l IG.L. Plumlee, III]
l l
l
-l l
l l
require use of a different telephone exchange.
In these cases, s
l utilize the exchange in parentheses.
I
)
FOMM 372-22 3643
4 PUBLIC SERVICE COhlPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION g
- '~-
Page 1 of 1
' l TABLE 1 PLANT MANAGEMENT CONTACTS
- Page Plant Home Phone Ext.
Phone
\\
i Supt. of Operations Station Manger Admin./ Tech.
Serv. Manager Mgr. Nuclear Prod.
Rad. Protection Manager l
Vice Pres., Prod.
I
_.i Listed in order of preferred contact sequence.
l
]
1 FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORAD3 RERP-HOME Table 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 6 v
TABLE 2 SIGNIFICANT EVEN1 TABLE 2 Event (NRC Description)
Typical Initiating Events :
1.
Any event requiring initi-1.
a) Initiation of ',he Radiclogi-ation of the licensee's cal Emergency Response Plan emergency plan or any (RERP) as descrived in section of that plar..
Tables 4.1-1 through 4.1-4 of the Plant RERP.
b) Abnormal coolant temperature and/or pressure or abnormal fuel temperatures.
c) Loss of engineered safety feature or fire protection system function requiring shutdown by Technical Speci-fications (e.g., because of malfunction, personnel errer, or procedural O
in deauecv).
2.
The exceeding of any Tech-2.
a) Exceeding limits of SL 3.1, nical Specification Safety Eeactor Core Safety Limit.
Limit b) Exceeding limits of SL 3.2, Reactor Vessel Pressure Safety Limit NOTE: Action to be taken specified in AC 7.2.
3.
Any eve it that results in 3.
a) Reactor pressure exceeds the nuclear power plant limiting safety system set-not being in a controlled ting (LSSS 3.3) without or expected condition automatic trip.
while operating or shut-down.
b) Inability to trip and insert sufficient rods to achieve Technical Specification shutcown margin.
O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 6
(~))
TABLE 2 SIGNIFICANT EVENT TABLE 2 2
Event (NRC Description)
Typical Initiating Events 3.
(Cont.)
c) Failure of the PPS ti com-plete a required pro ective action once initiatec.
dj Failure of a system other than the systems subject to limiting safety system set-tings to actuate, or actua-tion of a limiting safety system at a monitored para-meter value less conserva-tive than listed in the sys-tem's Technical Specifica-tions.
e) Operation with unacceptable PCRV penetrat!on interspace C
leak rate test results.
f) Reactivity anomalies in-volving disagreement with the predicted value of reac-tivity balance under steady state conditions power oper-ation 2.01aK/K; a calculated shutdown margin less con-servative than Technical Specifications; short term reactivity increases that correspond to a reactor period of less than 5 sec-onds, or if suberitical, an unplanned reactivity inser-tion of >.005AK/K; or any un-planned criticality.
g) Upsets resulting in reactor pressure and flux transients that peak at values higher than analy::ed.
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLERADS RERP-HOME 2
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 6 G
TABLE 2 SIGNIFICANT EVENT TABLE "
2 Event (NRC Description)
Typical Initiating Events
- 3. -(Cont.)
h) Failure of a PCRV safety /
relief valve to close after pressure has reduced below the required reseat value.
4.
Any act that threatens the 4.
a) Threatened civil dis-safety of the nuclear turbances that result in power plant or site per-initiation of the Security sonnel, or the security Contingency Plan.
of special nuclear material (SNM) including b) Evidence of unauthorized instances of sabotage or access to Fuel Storage attempted sabotage.
Building or Fuel Storage Wells.
c) Notification by fuel ship-ping carrier of theft or
()
attempted theft of fuel.
.=
d) Actual incidents of sabotage or threatened sabotage.
5.
Any event requiting 5.
a) ACM generator breaker initiation of shutdown of tripped after 20 minutes the nuclear power plant in during test; tripped unit accordance with Technical found to be defective, de-Specification Conditions clared inoperable.
for operation.
b) One of two centrifugal turbine water removal pumps inoperable due to faulty bearing; redundant pump inoperable.
NOTE:
In the two examples listed above, re-pair (s) cannot be implemented.within LCO time limits.
O PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADD RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 6 i
(3
\\J TABLE 2 SIGNIFICANT EVENT TABLE 2 8
Event (NRC Descriotion)
Typical Initiating Events 6.
Personnel error or pro-6.
a) Durine refueling operations, cedural inadequacy which, a.01Ap shutdown margin during normal operations, is not maintained due to anticipated operational incerrect rod removal occurrences, or accident sequence.
conditions, prevents, or could prevent by itself, b) Incorrect valve lineup the fulfillment of the which results in shut off safety function of those of secondary systcm decay structures, systems, and heat removal sequence.
components that are needed to c) Error in analysis of waste tank results in release
- 1) shutdown the reactor which exceeds acceptable safely and maintain limits.
it in a safe condi-tion; or, d) Liquid waste monitor set-gQ points raised for liquid
- 11) remove resiaual heat waste release completed.
following reactor Reactor Building sump pumps shut &wn; or, taken out of pull-to-lock.
Setpoints not reset.
iii) limit the release of radioactive material to acceptable levels or reduce the poten-tial for such release.
7.
Any event resulting in 7.
EXCEPTIONS:
manual or automatic actu-ation of Engineered Safety a) Manual scram initiated at Features, including the 52% during a normal Reactor Protection System shutdown.
(scrams and loop shutdown only).
l l
FORM 372 22 3643
PUZLIC SERVICE COMPANY CF COLORAD3 RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 6 TABLE 2 SIGNIFICANT EVENT TABLE 2 Event (NRC Description)
Typical Initiating Events
- 7.
(Cont.)
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 foremen-tioned systems which result from, and are a part of, the planned sequence during sur-veillance testing.
8.
Any accidental, unplanned 8.
a) Initiation of EP H-3, "High or uncontrolled radioac-Activity in the Plant."
tive release.
(Normal or expected releases from b) Burst of gas waste tank maintenance or other oper-rupture disk.
h, ational activities are not included).
9.
Any fatality or serious 9.
A serious injury is considered injury occuring on-site to be an injury which in the and requiring off-site judgment of the licensee repre-medical facility for sentative will require hos-treatment.
pitalizat.cn for an extended period of time (greater than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />).
- 10. Any serious personnel 10.
Decontamination process re-radioactive contamination quiring use of agents other requiring on-site or off-than soap and water.
site decontamination.
4 l
nU FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRADO RERP-HOME a
2 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 6 g
G' TABLE 2 SIGNIFICANT EVENT TABLE 2 2
Event (NRC Description)
Tyoica; Initiating Events
- 11. Any event meeting the cri-11.
a) Exposure of the whole body teria of 10CFR20.403 for of any individual to 25 rem one hour notification.
or more of radiation; ex-posure of the skin of the whole body of any individual to 150 rem or more of radia-tion; or exposure of the feet, hands, or forearms of any individual to 375 rem or more of radiation.
b) A loss of one working week or more of the operation of any facilities affected.
c) The release of radioactive material in concentrations A
which, averaged, over a per-U of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exceed 5000 times the limits speci-fied for such materials in 10CFR20, Appendix B, Table II.
d) Damage to property in excess of S200,000.
- 12. Strikes of operating em-
- 12. Situation evident.
ployees or for security guards, or honoring of picket lines by these employees.
NOTE 1: Many of the events contained in this table are duplicated in the RERP, Tables 4.1-1 through 4.1-4.
For those cases it is imperative that RERP actions are carried out in addition to reporting requirements contained in this section.
RERP actions take precedence whenever doubt or time is a factor.
Tables in Section 2 will classify operating events at their highest level of response wherever duplication of events exists.
NOTE 2:
This table lists only typical initiating events that fit the Nuclear Regulatory Commission event descriptions. This column does not list all initiating events that are conceivable for a particular fsy Nuclear Regulatcry Commission event description.
For4M 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Table 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 4 O,,
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 result!ng 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.
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 c.ould 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.
O v
FORM 372 3643
PUBLIC SERVICE COMPANY OF COLSRADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Table 3 J
Issue 3 Page 2 of 4
,m L,]
TABLE 3 NOTIFICATION OF UNUSUAL EVENT Event Indication 5.
Abnormal coolant temp-5.
Violations of eratures or core region LC0 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 (50P 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, O
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 l
or near site i
explosions that may be subject to public concern because of possible detrirrental l
effect on the plant; or, F OR M 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME Table 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 3 of 4 OV TABLE 3 NOTIFICATION OF UNUSUAL EVENT Eyent 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
(_s) injured.
s (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:
I the extent requiring Shutdown a)
Engineered Safeguards in accordance with station Technical Specifications.
- 1) Plant ventilation-LCC 4.5.1 (3
- 2) Steam / Water Dump U
System - LCO 4.3.3 FORM 372 22 36E3
PUDLIC SERVICE COMPANY OF COLORADO RERP-HOME A
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4
('M V
TABLE 3 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 -
- 5) PCRV Safety Valves -
LCO 4.2.8 SL 3.2 LSSS 3.3.2.c b)
Fire Protection System -
- 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)
NOTE: Use LCO 4.8.1 Technical Specification Limits as basis.
O FORH 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRAD3 RERP-HOME -
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 5 o
O 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 failae of 2.
Loop 1 Hot Reheat Header (HRH) one steam generator reheat activity high (5 mrem /hr);
section with loss of or, Loop 2 HRH activity offsite power.
high (5 mrem /hr) accompanied by 230 Kv OCB trips O
am RAT undervoite9eeloss of power alarm.
3.
Primary coolant pressure 3.
PAL 9335 decay (to a value graater PAL 9347 than 100 psi less than PAL 9359 normal pressure, a_nd area monitor n
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 radicactive 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.
F ORM 3 72 - 22 3643
PUBLIC SERVICE COMPANY CF COLORADZ)
RERP-HOME able 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 2 of 5 g(_/
TABLE 4 ALERT Event Indication 5.
Loss of offsite power and 6.
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 alarms.
6.
Loss of all vital 6.
DC bus 1 < 10 volts and DC power for up to DC bus 2 < 10 volts 30 minutes.
7.
Loss of primary coolant 7.
All He flow indicators read forced circulation for zero.
between 2 a-d 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.*
8.
Loss of secondary coolant 8.
All secondary coolant flow functions needed for indicators read zero.
(.s) 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 substant'al Fire Control Alarm Panel degradation of plant safety systems, b)
Fire Pump 1A auto start c) verbal reports These times are LOFC from 100*4 power.
Times may be correspondingly longer for lower power levels (CMG-4).
FORM 372 22 36A3 l
PUBLIC SERVICE COMPANY OF COLORADO RERP-HCME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 5 O
v TABLE 4 ALERT Event Indication
- 11. Radiciogical 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 pC1/cc c)
RT 7325-1 indicating 27.0 x 10 ' uCi/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 2 pC1/cc Utilize reading from above instruments and calculate dose rate per procedures
- 12. Ongoing security 12.
a)
As observed or reported; compromise.
b)
Guard Station Trouble alarm; or, c)
Guard Station Acknowledge alarm.
O l
PORM 372 22 - Wi43
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 5 O
'J TABLE 4 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, experienceJ or projected station personnel.
such as:
O e) eircreft cress on feciiitv:
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 rystems established from local stations.
(Control room integrity breached).
(%
FORM 373 - 22 3643
RERP-HOM'C PUBL!C SERVICE COMPANY OF COLORADO Table 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Pace 5 of 5 O
v TABLE 4 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.
O O
F ORM 372 22 3643
PUBl.IC SERVICE COMPANY OF COLORADO RERP-HOME Table 5 FORT f.T. VRAIN #4UCLEAR GENERATING STATION Issue 3 Page 1 of 4 o
.s' TABLE 5 SITE AREA EMERGENCY Event Ir.dication 1.
Loss af primary coolant 1.
All He flow indicators read forced circulation for zero.
over 5 hr. f rom 100*. power.
(Lower power levels preceeding LOFC extends time available before core damage is incurred.
See CMG-4.)
2.
Non-isolable primary 2.
Loop 1 or 2 HRH activity coolant leakage through a alarm-high with Shift steam generator reheat Supervisor determination sec' ion.
that leakage is non-isolable.
3.
PCRV relief valve remains 3.
Rf 93252-12 alarm and rapidly s
s,)
- 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 4Kv bus undervoltage, 480v bus undervoltage, and Diesel Trouble alarms. Standby Diesel Fail to Start.
5.
Loss of ' unctions needed 5.
Inability to insert for plant hot shutdown.
suf ficient control rods accompanied by failure of emergency reserve shutdown system - resulting in inability to maintain
.0 lap 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 clicactivity to plant alarms.
environs.
Ov FORM 372 22 364
PUBLIC SERVICE COMPANY OF COLORAD3 RERP-HOME Table 5 FORT ST. VR A,tN NUCLEAR GENERATING STATION Issue 3
~
~
Page 2 of 4 ss 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 to affected safety system.
d)
Shift Supervisor determines fire beyond capability of station staff.
8.
a)
Effluent monitors 8.
Stack monitor alarm with r3 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 l
minutes at the
~
site boundary under 26.7 x 10 ' uti/cc adverse meteorology I-131; or, (or levels 5 times the above for thyroid b)
RT 7324-1, 2, dose rata).
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 catailed in Station Security Plan.)
i 1
\\
%E i
PORM 372 22. M43
PUBLIC SERVICE COMPANY OF COLORAD'3 RERP-HOME Table 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 3 of 4 OL.)
TABLE 5 SITE s,REA EMERGENCY Event Indication
- 10. Severe natural nhenomenon 10.
being experienced or projected (with plant not in cold ihutdown), such as; a) earthquake greater a)
Seismic Recorder Operate than Safe Shutdowa alarm with indication of Earthquake ground motion greater than 0.10g horizontal or greater than 0.0679 vertical.
b) flood greater than b)
As reported or observed.
design levels O
c) 4"es '" excess or c) ever se
'#d veioc'tv 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 louve.s 12.
a)
Louvers Open Alarm open due to building (3 inches water) being everpressurized N
by primary coolant.
b)
Reactor building u)
(DBA #2) radiation alarms.
l-FORM 372 22 3643
~-
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 TABLE 5 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.
O O
F O R M 3 72 22 3643
RE H E PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 1 OV 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.
actual meteoro-logical conditions.
b)
These dose rates are projected based on other plant para meters, or are measured CI 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 lcrge amounts of radioactivity possible.
PORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLOR AD;)
RERP-HOME c ent 1 FORT ST. VRAIN NUCLEAR GENERATING STATION s
Page 1 of 4
,ey
_f ATTACHMENT I IMPAIRED FIRE PROTECTION NOTICE Report No.
Year Sequence No.
ATTACHMENT I IMPAIRED FIRE PROTECTION NOTICE 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 shali al:,o be logged.
GIVE THIS INFORMATION AS SHOWW v) 1.
Facility Name: Public Service Company of Colorado Unit No. On_e 2.
Location: Fort St. Vrain, Platteville, Colorado Below Is the Information Which Will Be Requested Of The Caller 3.
Caller's Name:
Phone:
4.
Date and time of occurrence:
5.
Details and extent of impairment:
6.
Did impairment result from a loss?
l[l*Yes
((j No If yes, details:
O V'
- Loss would be a fire, accidental system operation, windstorm damage, etc.
ronu s n.22.as<s
PUBLIC SERVICE COMPANY OF COLORADS RERP-HOME ent 1 FORT ST. VRAIN NUCLEAFi GENERATING STATION Page 2 of 4 C'i
\\s' 7.
Restoration (of system) begun? l[lfes l[]No Restoration work to be continuous?
l[l Yes l[] No 8.
Impaired area or equipment operable? l[]Yes l[]No Estimated restoration time:
9.
Preceutions:
l[IValvestaggedout l[IDiscontinuedwelding, cutting,andhotwork l((Discontinuedsmoking l[l Notify Control Room (Shift) Supervisor, or other applicable management.
l[lNotifyFireDepartment/FireBrigade l[lIncreasedwatchmanserviceto hourly
-l-l Extra extinguishers /firehose in area
/]
Other:
10.
Contacts made by Shift Supervisor:
a) Nan.e of ANI contact:
b) Time of ANI contact:
Management
Contact:
a) Name of management contact; b) Time of management contact:
11.
Additional contacts mode / received:
a) Per attached call sheet log.
M i
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 4 U
l l
l12.
RESTORED l
l l
l a) Repeat Steps 1 and 2 above l
I I
l b) Caller's Name:
l I
l I
c) Date and time of restoration:
l I
l l
d) Name of ANI contact:
i l
l l
e) Time of ANI contact: _
l l
1 13.
The Shift Supervisor shall send the completed copies of the completed forms directly to Technical Services.
14.
If Notification was a Fire /All-Risk Emergency, Technical Servicer, will:
a) Determine if a Repoitable Occurrence is required, and prepare a facsimile copy st a 14 day report is indicated.
b) Assign a sequential number and send a copy to the Superintendent, Operations and a copy to PORC.
b FORM 372 - 22 3643
PUBLIC SERVICE COMPAN's OF COLORADO RERP-HOME FORT ST, VRAIN NUCLEAR GENERATING STATION
$3 Page 4 of 4 v
O I
i i
i I
l l
CALL I TIME I DATE I CONTACT (NAME)
I COMMENTS / REMARKS l
l l
l l
l 1
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 l
l l
1 1
I I
I I
I I
I I
I I
I I
I i
i I
I I
I i
I i
l 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 l-1 I
I I
I I
I i
l I
I I
I I
I I
I I
I i
l i
l l
I I
I I
I O
i i
i i
i 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 1
I I
I I
l
,1 I
I I
I I
i l
l l
l 1
1 I
I I
I I
I I
I I
i i
I I
I I
I I
l l
l l
l l
l 1
I I
I I
I
~l l
I i
i l
l I
I i
1 I
I I
I I
I I
I I
I I
I l
I I
I I
I I
I I
i i
l i
I I
I l
i I
I I
I I
1 I
I I
I I
I I
I I
I I
I O
FORM 372 22 3543
PUBLIC SERVICE COMPANY OF COLORAD3 RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Fage 1 of 4
,_U Initial Notification, Significant Event Notification Report No. _
Year Sequence No.
IMPORTANT:
It is important that the time of all calls and names of people contacted be logged. Any further follow-up calls received or made s'1ould 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, Item number (1-12).
4.
Description of Event:
nN]
~
5.
Actions Taken:
6.
Status:
Under control by on-site staff, no off-site assistance anticipated. Final report.
Under control by on-site staff. Will keep NRC advised.
A Off-site assistance nay be required.
Will advise.
(See Item #7)
FORM 372 22 36M
PUBLIC CERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VR AIN NUCLEAR GEf4ERATit+G STATION Issue 3,
Page 2 of 4 O(-
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:
b) u.
- 10. Contacts made by Shift Supervisor:
a) Name of NRC contact:
b) Time of NRC contact:
Management Contact a) Name of management contact:
b) Time of management contert:
- 11. Contacts made by management:
a) Per attached call sheet log.
(3
%)
FORM 37? 22 - 36&3
i PUBLIC SERVICE COMPANY OF COLORADO RERP-HONE 4
FORT ST. VRAIN NUCLEAR GENERATING STATION 3u Page 3 of 4 v
O 1
- 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 renort is indicated.
b) Send a copy to the Superintencent, Operations.
c) Send a copy to PORC.
O 1
O F ORM 3 72 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME achment 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 (3
'J l
l l
1 i
l l_ CALL 1 TIME I DATE !
CONTACT (NAME) l COMMENTS / REMARKS l
1 1
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
I I
I I
I I
I I
I I
I l
1 I
I I
l l
O i
i i
i i
i i
I i
l I
I I
I I
I I
I I
I I
I i
l l
l 1
l I
I I
I I
I I
l l
l l
l 1
1 I
i l
l 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
l 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
l 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 1
I I
I I
I i
i l
l I
I I
I I
I I
I I
l __
l l
l O
D F OR M 3 72 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADT)
RERP-HOME hment 3 FORT ST. VRAIN NUCLEAR GENERATING STATICN Page 1 of 3 O
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 cae)
Earthquake Flood Tornado Winds Unusual Hazards (circle one) h, Aircraft Explosion Toxic Material Other (Specify)
Spent ruel Incident 4.
Description of Event 5.
Actions ken 6.
Status:
Under control by onsite staff, no offsite assistance anticipated.
Under control by onsite staff. Will keep State and NRC advised.
7.
At the present time, the eventdoesnotinvo[veoffsite release or the potential for offsite releases that would affect the general health and safety of the public.
PUBLIC SERVICE COMPANY OF COLORADO t3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 2 of 3 s
B.
The Emergency Coordinator will make notifications as follows:
l Contact with State EOC,
, and Governor's Office
~JT s
l or Mansion,
1 1
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 ACTIVATION OF EMERGENCY
RESPONSE
CENTERS.
THIS E0TIFICATION REQUIRES VERIFICATION OF RFCEIPT' BY THE STATE.
VERIFY BY CALLING.
2.
READ all the information recorded in Step A (Page 1 of this ATTACHMENT).
3.
RECORD the following information:
Name of State E0C contact Date/ Time Name of Governor's Office / Mansion Cont. int Date/ Time Call back verification from State E0C, Date/ Time Call back verification from Governor's Office / Mansion Date/ Time i
I l Contact with NRC Operations Center (Hot Line or
,I I
l (If NRC Hot Line and Land Line are inoperative, use HP Network line.)
1.
READ the following statement verbatim:
"THIS IS NOTIFICATION OF A SIGNIFICANT EVENT AT THE FORT ST.
VRAIN NUCLEAR GENERATING STATION AT PLATTEVILLE, COLORADO. THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO 10CFR50.7?, ITEM NUMBER 1.
THIS NOTIFICATION 00ES NOT REQUIRE ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE ORGANIZATIONS."
FORM 372 22 36A3
PU LIC SERVICE COMPANY OF COLORADO RERP-HOME C ent 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 3 O
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 O
l O
F OR M 3 72 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 4 NOTIFICATION TO ACTIVATE STATE EMERGENC. RESPONSE CENTERS l
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
_Clame)
, Shift Supervisor at the Fort St.
Vrain Station.
2.
At (Time) we experienced an (ALERT, SITE AREA EMERGENCY, GENERAL EMERGENCY) Class incident.
3.
a)
There is NO, repeat NO, radioactive release taking place, and no special protective actions are recommended at this time.
OR O'
b)
A radioactive release IS, repeat I_S, taking place, and we recommend that people in areas remain indoors with windows and doors closed.
A radioactive release I_S, repeat IS, taking place, and we recommend that evacuation of areas be considered.
4.
Further information on incident conditions will be provided in followup messages.
O FORM 372 22 + 3643
1 PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAd GENERATifJG STATICN e
Page 2 of 4
,~
%)
SUPPLEMENTAL INFORMATION NOTE: This information is to 60 wpplied to the NRC and the Colorado Departn:ent of Health when requested.
The radiological data can be determined as specified in Section 2.2.1.2 of this procedure.
1.
Date and Time of Incident 2.
Class of emergency (ALERT)(SITE AREA EMERGENCY)
(GENERAL EMERGENCY) 3.
Type of release (airborne, waterborne, surface) 4.
Current release rate:
Noble Gas,
Ci/sec lodine C1/sec 5.
Estimated curies
'aased Noble Gas Ci Iodine Ci 6.
Wind Velocity MPH, from degrees. Air Temp.
- F.
O-7.
Stability Category
, Form of Precip.
8.
Dose rate at EAB - WB rem /hr Thyroid rem /hr 9.
Projected dose at EAB - WB rem Thyroid rem 10.
Estimated accumulated dose at EAB-WB rem Thyroid rem 11.
Estimate of any surface radioactive contamination 12.
On-site response actions urder way U
FORM 372 22 3643
o o
PUBLIC SERVICE COhlPANY OF COLCRADO
, RERD-:10ME ttachment 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3
~
Page 3 of 4
')
13.
Recommended Protective Action based on the projected dose at the EAB (NOTE:
Refer to RERP-PAG):
Circle Appropriate Protective Actions and Read Aloud Projected Dose Recommended (rem)
Protective Action Whole Body <1 No planned protective actions.
State Thyrcid <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.
Vhole Body 5 and above Conduct mandatory evacuation. Monitor Thyroid 25 and above radiation levels and adjust area for mandatory evacuation based on these levels Control Access.
14.
Prognosis for worsening of event 15.
Date and time of report B.
The Emergency Coo-dinator will make notifications in sequence as follows:
1 I
l PSC Company Operator l
or l
/l 1)
INSTRUCT the Operator to initiate the " Fort St.
Vrain Radiological Emergency Call List."
2)
REAU verbatim the information recorded in Part A (Page 1 of this attachment).
3)
RECORD the fol!owing information:
Time PSC Operator Hotified Time Operator Callback Received i
)
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION sue Page 4 of 4 v
(3
%J l
l l Weld County (911 Using Greeley Line) l I
i 1)
READ verbatim the information recorded in Part A (Page 1 of thfs attachment).
2)
RECORD the following information:
Time Weld County Notified Time Weld County Callback Received I
l l NRC OPERATIONS CENTER (HOT LINE OR (202) 951-0550) l l
l (Use HP Network Line if NRC Hot Line and Land Line are inoperable.)
1)
READ Items 1) through 4) from Part A.
O 2)
READ the following sentences verbatim. "THIS EVENT IS BEING REPORTED PURSUANT TO 10-CFR50.72, ITEM NUMBER 1.
WE ARE PRESENTLY ACTIVATING STATE AND LOCAL EMERGENCY RESPONSE CENTERS."
3)
READ the supplemental informatton (Paga 2 of this attachment).
4)
RECORD the following information:
NAME of NRC Contact TIME of NRC Contact
~. -
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME
+achment 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 2 A
%,.)
ECP DIRECTCR'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 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
^t) are contacted by the PSC Operator:
x a.
Call the first person on the attached list ad inform him to conplete the call list.
%)
I FORM 372 22 3643 l
PUBLIC SERVICE COhlPANY OF COLORADO RERP-HOME
'~
ent 5 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 2
)
ECP DIRECTOR'S CALL LIST First call all primaries, then call all alternates.
PSC Extension Home Time Manager - Technical Suocort Primary - J. R. Reesy
{
Alternate - Mike Holmes l
Manager - Media Relations Primary - R. T. Person, Jr.
Alt. - W. D. Fitzmaurice Manager - Resources Primary - D. D. Hock Alternate - J. Bumpus l
Manager - Security Primary - E. O'Neal I
Alternate - toonard Johnson "Tc call these numbers from other than a PSC telephone, the correct prefix is
{
9 i
FOMM 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 2 (D
%j CORP 0 RATE EMERGENCY DIRECyft'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 inform him to complete the call list.
2.
If you are the response center / post Alternate Director and art contacted by the Director:
a.
Complete the attached list.
3.
If you are the response center / post Alternate Director and are contacted by the PSC Operator:
a.
Call the first perso on the attached list af inform him to complete the call list.
O u
FORM 372 - 22 3643
~
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME FORT ST VRA,1N NUCLEAR GENERATING STATION Page 2 of 2 CORPORATE EMERGENCY DIRECTOR'S CALL LIST (FCP)
First contact all primaries, then call all alternates.
Extension Home Time Station Technical Liaison Primary - L. M. McBride l
Alternate - J. W. Gahm L_
Radiological Assessment f
Primary - T. Borst t
I Clerical Assistance l
Primary - C. Stroh Alternate - Sue Katcher i
1 2nd Alt. - Laurie Banagas j
I M__e_d_i_a Re l a t i on s i
Primary - M. McAdams l
Alternate - S. Volsted 1
1 FORM 372 22 3643
RERP-HOMC PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 3
(')
8J PCC DIRECTOR'S CALL LIST INSTRUCTIONS In the event that you are notified by the FSC 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 resoonse 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.
O F ORM 372 3643
PUBLIC SERVICE COkiPANY OF COLORADO RERP-HOME achmen?. 7 FORT ST VRAIN NUCLEAR GENERATING STATION Page 2 of 3 T
PCC DIRECTOR'S CALL LIST Plant Extension Home Time Personnel Accountability and I & C Technicians T. Bashline P. Bearly M. Benedict M. Bicssom i
P. Bollig l
S. Caines
[
R. Erwin G. Fisher M. Gale C. Harding K. Hays W. Holcomb T. McElwaine G. Murphy
~
M. Murphy i
D. Nelson i
G. Powers G. Redmond l
R. Rivera i
C. Stieff J. Switzer
?
L. Walker S. W111 ford Maintenance, Repair, and Damage Control As Required - See RERP Phone Roster at end of procedure.
Hazards Control Team D. Brown C. Schmidt FORM 372 22 36&3
PUBLIC SERVICE COMPANY OF COLORADO RERP-HOME e -
FORT ST VRAIN NUCLEAR GENERATING STATION ue Page 3 of 3
^
Monitoring Teams - Health Physic::
R. Hooper
,\\
K. Latimer i
P. Morris E. J. O'Donoghue S. Rima D. Rozell S. Scruggs E. Stroud Radiochemistry
}
V. McGaffic (P)
O. Millor(A)
S. Poet (A)
M. Prochownik (A)
Operating Staff Support As Required - See RERP Phone Roster Telephone Console Operators
\\
D. Edwards (P)
S. Rozell (A)
Maintenance (Electrical, Mechanical)
As required at the discretion of the PCC Director - Refer to RERP Phone Lists.
e e
FORM 372 22 364J
PUBLIC SERVICE COMPANY CF COLERAD3 RERP-HOME FORT ST VRAIN NUCLEAR GENERATING STATION 3
Page 1 of 2 gb STATF. 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 followfng 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 attact.ed call list.
Q 3.
If you are the PSC alternate contact and are notified by the PSC operator:
a Call the first person on the attached list a_rtd inform him to complete the call list.
e FORM 372 - 22 3643
SERVICE COhlPANY OF COLORADO RERP-HOME B PUBLIC FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 2 of 2 b
STATE _EOC CALL LIST (For Contac+e by PSC)
Extension Home Time Radiological Cor.sultant K. Schlager Media Relations R. A. Burns (Primary)
G. Reeves (Alt.)
e i
e
'N
)
FORM 372 22 36&3 4
PUBLIC SERVICE COMPANY OF COLCRAD9
[ga h R
t9 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 3 Page 1 of 3 v
TSC 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 yor are the response center / post Director:
a.
Call your response center / post Alternate Director (the alternate wi'l 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 nim to complete the call list.
2.
If you are the response center / post Alternate Director and are contacted by the Director:
a.
Complete the.ittached 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.
i FORM 372 - 22 36E3
PUZLIC SERVICE CONIPANY OF COLORADS RERP-HCME ent 9 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 3 TSC DIRECTOR'S CALL LIST First call all primaries, then call all alternates.
Plant Reactor Physics Extension Home Time Primary - C. Fuller
\\'
Alternate - R. Heller
-\\
Alternate - F. Novachek t
Radiological Assessment Primary - J. Sills Plant Condition Assessment Call two off-duty Shift Supervisors M. Deniston D. Evans W. Franklin J. Hak D. Hood H. O'Hagan G. Reigel J. Vandyke Emergency Maintenance Primary - W, Craine l
Alternate - J. I.iebelt Instrument and Control Primary - B. Burchfield Alternate - J. Weller Health Physics / Health Physicist Primary - T. Schleiger Alternate - B. Woodard Administration / Logistics Primary - A. Kitzman Alternate - P. Collins Alternate - D. Merritt
~f g
\\
~
'"w-
/
FORM 372 L 3643
PUBLIC SERVICE COhlPANY OF COLORADO RERP-HOME FORT ST. VRAIN NUCLEAR GENERATING STATION e
Page 3 of 3 Computer Sucoort
\\
Primary - D. Klaus
\\
Alterrate - D. Blistein
's l
s l
l l
l FORM 372 22 3643
1 o?
a O
m 0
1 1
t En f
Me o Om3 lh I
- ce Paue Rtsg Etsa RAIP em i
T
,1' If Il6 se t
a n
r e e n D
l fo t
1 A i
/
T s
N r
.i i E
o l
M 11 tc n
d C e kn n
n l
A r T
D y icw t
nw e
n e
o n
oo rl o
T i
i rt o
tt eg tr rr rr A
t es m
hs dh he ee em y
dn g
gn lur t
gv vv vo i
t C
eh n
iro oo re ee er n
nn no h
i ro o
i i
FJ L
ca F
gg, i.
sne tx N
E
\\
\\
i A!
jI
(.
r e
t g
n r
e u
r r
l o
s e
o e
l C
bi a
dm t
l re s
y nl k
.d ih c
l en gse r
el c
I a
r a e
u kn ai r e
ri o
e, W
BC I
e_.
r eF o
JlB l
t s
c t lad (l
t a
l M
I 'O n
W.
r B n
s.
a_ e.
D s
4 l
W.
c Lo Cl i
W
.K
.D o
e e
aE o
r,f L l
e y
P t
.n C
s F.
gc.
C o
H c R.
pM
.N
.R
.J a
.J l
P d
.B O_.
.E H
t e
o n
n r
r o
D i
M I
J' d
L q O a
R yD m
c :
g D
L.
n r
o a
o e
o m
n e
n e
e si n
- t m
- t o
- t m
- t m
- t o
- t e:t S
ya o
ya C
ya m ya I
ya C
ya gya
\\V l
ar R
ar l
ar C ar o
ar e
ar qar rn o
rn rn o rn rn rn grn a
me tt rl n
rt r
rl r
rl i
it me e
mo me J me v
me mme c
it it n
it d i t n
it Jit rl t
rf rl i
s v
p c.
M.
h r
r r
e c
o 3
L e
o y
e T
a C b P c f d G e f.
r Ig L
PUBLIC SERVICE COMPANY OF COLORADO FORT ST. VRAIN NUCLEAR GENERATING STATION hb 1/21/83 NON. CONTROLLED COPY RADIOLOGICAL EMERGENCY RESPONSE PLAN - STATI0i4 l
ISSUE EFFECTIVE l
NO.
SUBJECT NUM5ER DATE 1
1 1
RERP-TSC Technical Support Center Procedure 11 01-03-83 l
l l RERP CR-UE Control Room Unusual Event l
Procedure 17 01-21-83 l RERP-VC Visitors Center Procedure 2
01-21-83 RERP-PHONE LISTS 14 10-26-82 O
O F OR M 3 72 22 3643
1 PUBLIC SERVICE COMPANY OF COLORADO RERP-VC FORT ST. VRdlN NUCLEAR GENERATING STATION Issue 2 Page 1 of 3 O
TITLE:
VISITOR'S CENTER PROCEDURE ISSUANCE AUTHORIZED
/W 'O BY l
Wsutsdm PORC ef EFFECTIVE EDRC 5 0 0JAN 171983 {
DATE l-AI-83 REVIEW Sections Description
_Page 1.0 Criteria for Implementation......
........................ 1 2.0 Procedure......
................................... 1 3.0 Responsibilities..........
............................... 3 4.0 References............................................... 3 5.0 Referenced or 'iupportino Procedures........................ 3 Figure 1 Visitor's Center Evacuation Routes.................... 1 O
Postu 272 22 3M2 l
i
PUBLIC SERVICE COMPANY OF COLORAD3 RERP-VC FORT ST. VRAIN NUCLEAR GENERATING STATION Iss'e 2 Page 2 of 3 1.0 Criteria for Imolementation The purpose of this procedure is to provide guidance to the PSC Visitor's Center representative in the event of a radiological emergency at Fort St.
Vrain requiring activation of the FSV Radiological Emergency Response Plan (RERP).
The RERP is generally activated for an ALERT, or higher, emergency classification.
2.0 Procedure This procedure will be initiated by notification via the plant public address system or by telephone call to the PSC representative at the Visitor's Center.
2.1 When notified that the Radiological Emergency Response Plan (RERP) is being activated, instru;t all non-station occupants to proceed to the Fort Lupton Fire Station using the route specified.
The Personnel Control Center (PCC) will inform the Fort Lupton Fire Station to anticipate persons arriving.
2.1.1 Load occupants into buses and cars, and transport to the fire station in caravan style.
(q Route #1 - through Platteville to U.S. 85 to
=
_j Fort Lupton, 1 on attached map (Figure 1).
Route #2 - South to Colorado 66 West to I-25 east, Colorado 52 to Fort Lupton, 2
on attached map (Figure 1).
Route #3 - 'lorth to Johnstown to Colorado 60 east to U.S. 85 south to Fort Lupton, 3
on attached map (Figure 1).
2.1.2 Do not attempt to detain any visitors who will not cooperatt in the evacuation of the Visitor's Center.
If a visitor will not cooperate in the evacuation, obtain whatever identifying information that is possible (name, description, vehicle license plate, etc.), and notify the Central Alarm Station (Extensicn 300 or page) of the situation.
2.1.3 Attempt to obtain names and applicable information from visitors prior to their departure to the Eva:uation Center.
This i n f ormati.on should be available from the guest log.
2.1.4 Take the Visitor's Center Log Book and any applicable notes when leaving.
e ~s FORM 372 22 M43
PUBLIC SERVICE CONIFA.NY OF COLORADO RERP-VC FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 2 Page 3 of 3
)
2.2 Wnen the evacuation of visitors from the Visitor's Center has been completed, the PSC Visitor's Center representative shall contact either the Shift Supervisor (Extension (or page) or the Central Alarm Station (Extention iorpage).
2.3 Upon arrival at the Fort Lupton Fire Station, personnel will be monitored and sent home.
2.3.1 Acccunt for occupants of Visitor's Center by checking names againsi, the Log Book or name list.
2.3.2 Call the Personnel Control Center s
and report accountability for Fort St.
Vrain employees only (if required).
2.3.3 Notify the State Health Department of any visitors who did not cooperate in the evacuation, and furnish any applicable information available regarding their identity.
i 3.0 Responsibilities l
The PSC representative at the Visitor's Center is responsible to notify visitors and building occupants of the situation and any instructions received from the Lead Security Officer or Shift i
Supervisor. The PSC representative shall attempt to evacuate the building, as o!rected, but is not responsible for the i
actions of uncooperative visitors.
In the event of an uncooperative visitor, the PSC representative shall notify FSV i
s(curity of the situation. Upon completion of the Visitor's Center evacuation of visitors, the PSC representative shall 3
notiry the Shift Supervisor or Central Alarm Station of l
evacuation completion.
4.0 References 4.1 FSV Radiological Emergency Respanse Plah (RERP) 5.0 Referenced or Supporting Procedures 5.1 RERP-PCC, Personnel Control Center Procedure 5.2 AFM G-5, Personnel Emergency Response FORM 372 22-36 0
PUBLIC SERVICE COMPANY OF COLORADO RERP-VC FORT ST. VRAIN NUCLEAR GENERATING STATION Figure 1 Issue 2 Page 1 of 1 Ov 03 I
colorado M. 60
\\ ohnstown 0
J Milliken 3
t Iu 3
i
/
d g Fort St.
visitor's Center ID Train
. ?
T C i
ceterado M. 66 Platteville N
O I
colorado www. 92
\\
7 Fort L@ ton Exit g
( Fort Lupton ath St.
- 9 Fort Lupton Municipal Bldg.
M, 6
(618 4th St.)
=
l r
O l
FORM J F2 22 3643
~
PUBLIO SERVICE COMPANY OF COLORADD CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 1 of 9 O
v TITLE:
CONTROL ROOM UNUSUAL EVENT PROCEDUR,E ISSUANCE AUTHORIZED
/-//D BY h 171nb PORC EFFECTIVE p 5 0 0'JAN 171983 DATE I N REVIEW TABLE OF CONTENTS Section Description Page 1.0 Criteria for Implementation....
.... 3 2.0 Procedure.................
3 3.0 Responsibilities.....
....................... 10 4.0 References................................................. 11 5.0 Referenced or Supporting Procedures....................... 11 Figure 1 Response Center Manning Requirements.................
1 Figure 2 Visitor's Center Evacuation Rottes...................
1 Figure 3 Site Sector Map.....................................
1 Table 1 NOTIFICATION OF UNUSUAL EVENT........................
1 Table 2 ALERT............
1 Table 3 SITE AREA EMERGENCY....................................
1 Table 4 GENERAL EMERGENCY........
1 Table 5 Fort St. Vrain Atmospheric Stability Categories........
1 Table ti Dose Conversion Factors (DCFs)..
1 Notification of Unusual Event...
.1 Local Determination of Stack Concentration.....1 Dispersion Factors..
1-Datasheet 1 Catalogger Monitored Release..
.1 Datasheet 2 Datalogger Unmonitorec Release..
1 FnRM 372 - 72 3M2
PUBLIC SERVICE COMPANY CF COLORAD3 CR-UE s e FORT ST. VRAIN NUCLEAR GENERATING STATION V
Datasheet 3 Preliminary Assessment of Plant Conditions....... I Checklist 1 Emergency Coordinator / Control Room Director Checklist.............................
1 Checklist 2 Datalogger Monitored Release....................
1 Checklist 3 Management Contact Notification List.............
1 Worksheet 1 Monitored Release Calculations (Manua',).......
1 Worksheet 2 Monitored Release Calculations (TI-59)..........
1 Worksheet 3 Unmonitored Release Calculations (Manual)....... I Worksheet 4 Unmonitored Release Calculations (TI-59)........
1 Work /Datasheet/ Checklist Control List.........................
1 Forms Use Reporting Sheet *....................................... 2 ANYTIME A WORKSHEET, DATASHEET, OR CHECKLIST HAS BEEN WRITTEN ON, COMPLETE THE REPORTING SHEET ATTACHED IN THE TABBED WORKSHEET SECTION AND FORWARD IT TO THE TECHNICAL CLERK AND gQ RECORDER, FORT ST. VRAIN.
DO NOT WRITE ON ANY WORKSHEETS, DATASHEETS, CHECKLISTS, OR REPORTING SHEETS IN THE PROCEDURE ITSELF. ALL WORKSHEETS/DATASHEETS/ CHECKLISTS ARE TO BE TAKEN FROM THE TABBED SECTION FOLLOWING EACH PROCEDURE.
O FORM 372 22 3643
PUBLIC SERVICE COMPANY EF COLORAD3 CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION g
g V
1.0 C iteria for Implementation This procedure is provided for use by Control Room personnel in the event of an occurrence which is classified as a NOTIFICATION OF UNUSUAL EVENT, as specified in the FSV Radiological Emergency Response Plan (RERP).
A summary of initiating event categories and respective Emergency Action Levels (EALs) are summarized for the four levels of emergency classification in Tables 1-4 of this procedure.
In addition, the classification process is described in greater detail in Emergency Procedure EP-CLASS, Event and Emergency Classification Overview.
Initial eur.t classification is the responsibility of the Shift Supervisor.
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 RERP is required whenever any of the Initiating Events of Tables 1 through 4 of (V]
this procedure occurs.
Additional guidance on accident classification is cuntained 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 Checklist 1 is for use by the CR Director and/or the Emergency Coordinator. This check list is a brief summary of actions, and is to be used for guidance purposes to assist in verifying execution of required responses.
\\j I
I FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADS CR-Ut Issue 17 FORT !.T. VFtAIN NUCLEAR GENERATING STATION Page 4 of 9
\\.)
~
2.1.4 During non-working hours, PSC personnel required to man the response centees (Figure 1) are notified by telephone.
It is the responsibility of the individual response center Alternate Directors (or, the first individual contacted by the director) to ensure these notifications are n.ade (see RERP-HOME).
Refer to the RERP PHONE LIST for instru;tions and personnel names and numbers.
Under most circumstances, an occurrence classified as a NOTIFICATION OF UNUSUAL EVENT does not warrant activation of the FSV Emergency
Response
Organization and Facilities.
A precautionary activation of FSV Emergency Response Organization and Facilities would constitute an ALERT emergency classification.
2.1 Initial Required Responses For Unusual Event In the event of an occurrence believed to be defined by any of the events listed in Table 4.1-1 of the RERP (included as Table 1 of this procedure), the following actions shall be taken:
2.2.1 On-Shift Control Room Personnel:
/x
\\_,)
2.2.1.1 Implement Emergency Procedure actions required to limit the consequences of the event and return the plant to a safe and stable condition.
2.2.1.2 If a radiological release is involved, make a preliminary assessment of the release. Actions.to perform offsite dose calculations are described in implementing procedure RERP-DOSE.
RERP-DOSE should be utilized as a
reference in any cases where questions as to the specifics of dose calculation procedures arise.
Worksheets, Datasheets, and a Checklist for dose calculations are contained herein, 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 Release - Datalogger Datasheet 2 Unmonitored Release - Datalogger Checklist 2 Monitored Datalogger
(~}
Datalogger calculation is the most rapid means of assessing offsite consequences, FORM 372 22 36 4
SERVICE CO51PANY OF COLORADO CR-UE E' PUBLIC lssue 17 FCAT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 9
'i provided that the user is familiar with proper program utilization.
It is the Shift Supervisor's responsibility to assure that offsite consequence assessments are performed, as required.
This activity vill become the responsibility of the Technical Support Center after full emergency facility activation.
2.2.1.3 As soon as possible, inform the Emergency Coordinator of the results of the preliminary radiological assessment.
2.2.2 Shift Supervisor (Emergency Coordinator Checklist 1) 2.2.2.1 Assume the position of the Emergency Coordinator until relieved by the Superintendent of Operations.
2.2.2.2 As Emergency Coordinator, direct onsite emergency response and initiate any required corrective actions.
2.2.2.3 Notify the on-duty Technical Advisor Page Plant Home Phone Ext.
Phone l
F. Novachek l
J. Sills l
J. Eggebraten 2.2.?.4 If a radiological release or potential radiological release is
- involved, delegate the preliminary assessment of the release to a Reactor Operator and obtain assessment results.
2.2.2.5 Initiate radiological protective actions for station personnel.
2.2.2.6 Contact one member of plant management listed below in order of preference (see Checklist 3):
PORM 372 22 3643
PUBLIC SERVICE CO51PANY OF COLORADO CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page C of 9 c ')
Page Plant Home Phone Ext.
Phone Supt. of Operations Station fianager Admin./ Tech.
Services Mgr.
Mgr. Nuclear Prod Radiation Protection Manager Vice Pres, Prod.
2.2.2.7 Based on preliminary plant and radiological assessments, the Shift Supervisor (Emergency Coordinator) shall confirm the classification of the emergency as a NOTIFICATION OF UNUSUAL EVENT with the first management contact.
If the classification of the emergency is deemed an ALERT, SITE AREA EMERGENCY, or GENERAL EMERGENCY, go to section 2.7 of
" Control Room
- ALERT, SITE EMERGENCY, GENERAL EMERGENCY Procedure (CR-ALERT)."
NOTE:
In the event that no management person listed above can be contacted, it is the responsibility of the Shift Supervisce to classify the emergency and make the appropriate notifications of 2.2.2.8 below.
2.2.2.8 NOTIFICATION OF UNUSUAL EVENT a)
The Shift Seoervi3cr (Emerge.cy Coordinator) and the first management contact shall jointly complete the
[
" NOTIFICATION OF UNUSUAL EVENT" Form l
(Attachment 1).
Both the management l
contact and the Shift Supervisor l
(Emergency Coordinator) shall fill i
out the Nctification Form to ensure both have the same information.
")
4 FORM 313 33 36M
PUBLIC SERVICE COMPANY OF COLORADO CR-UE ss e 17 FORT ST. VR A,1N NUCLEAR GENERATING STATION
)
J b)
The Shift Supervisor (Emergency Coordinator) shall then noti fy the State of Colorado and the NRC Operations Center by making the following telephone calls as per, Page 2.
State Emergency Operations Center Governor's Office or Governor's Mansion NRC Operations ' Center " Hot Line" or Shift Technical Advisor (as required)
Back-up Emergency Numbers For NRC Notification:
\\
\\
[onHPNsystem(locatedinH.P.
Supervisor's office and the Technical Support Centei-)
The information on the " Notification of Unusual Event" Form will be read to the above contacts.
c)
The management contact will contact the remainder of the managemen; personnel listed in 2.2.2.6 above, and one of the Res4Jent N?C Inspectors (Checklist 3):
Plant Ext.
Office Home B. Dickerson G. L. Plumlee, III d)
No further action is required unless the event escalates to a higher RERP emergency classification as shown in Tables 2-4 of this prucedure.
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRADO CR-UE Issuo 17 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 9
'v 3.0 Responsibilities 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, epon activation of the FSV Emergency Organization (see Figure 1). The Emergency Coordinator is responsible for:
Initial accident classification; Reccamending protective actior.2:
Initiating emergency actions to mitigate the accident; Notifying offsite authorities; Diagnosing accident conditions; Estimating radiological exposures; and s
d Establishing communications with the TSC.
Responsibility for the decision for offsite r.stification and protective action recommendation may not be delegated.
3.2 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.
3.3 Plant Control and Plant Operations 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 Respoase Plan 4.2 State Radiological Emergency Response Plan n
l l
ronu 372 22. asas l
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Ssue 1 FORT ST. VRAIN NUCLEAR GENERATING STATION nU 5.0 Referenced or Supporting Procedure
5.1 CR-ALERT
Control Room ALERT, SITE EMERGENCY, GENERAL EMERGENCY Procedure 5.2 RERP-DOSE, Offsite Dose Calculations 5.3 EP-CLA53 Event and Errergency Classification Overview 5.4 RERP-ORG, FSV Emergency Organization and Responsibilities 5.5 RERP-PAG, Protective Action Guideline Recommendations 5.6 RERP-Phone List 5.7 RERP-liOME, Home Pteket for Off-Shift Notifications i
l O
l l
O P ORM 372 - 22 + 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UF FORT ST. VRAIN NUCLEAR GENERATING STATION Figure 1 Issue 17 6
Page 1 of 1 l
1 Ia 3
2
=
=
p.*
n d!s I
i
.g 5
=
=
f I
w=-
I
=c Is j.
88 !!=
3 3
2 c
4 h
,e~. !-
=
s_
g:3.la W
I 2'= =
!E i
2 e!
i s
n 4
i,. =f U
5 g
-jl g
5g s
E*
EY 2
2
%l=ana 3
g1 h
w J
l l
l l
I II 5y. 1
<g 2
12 Eo
=53 I
$P sin")ai 3
l si 5
w<
g
=:
s i
i i i i as I !e i
a
! i a===5 e jal !
3 N-a g
l C
5 l em j I i
r e<
8 e
e 3
ww 3;
a t
O ni l ii
=
dE=
i __ _ _ _ _ _.i m
e w
- s - a cuo
.a
=
g l !
5 I i I
~<
- 5l "i
a I gs E
n t
5
=1 42 3
=
-u
=
-l 8
s i a=
5
=
1 E s 3
Y.:.5 %,,. ! D N
N a s 3
3 2
-I
-l
,2 Isg o>
3 w
=
5 M
s I l u
a a
'I "g Sa g 3
[
- s g*
w
= 25 s'! !
1 i s.I
- 15!
3 3
,I N*
O I
E 8
"3 5
is i
=$
is 1 8s e
yo T--
i i
i i
u-g o
e i
i i
=
l 8 E' d' f
3 o
E
-E
{ at w
=
=>
I s -5 L,fl ;;
a
=
a
! :*=
a. I "=
i.
w l '. 3"'1.
u a
e a
43 s
s zi.=
e
=
b h $5
'?
E 3 h z' I
",!'::s. 33,f I 31 g sii!
E W
3
,1 jj -1 i
2l j E l =1 ~
ii'l i; ' '
- - 2
'; I E
i aj!;
I I
53
$iis I
Gb FORM 372 22 3643 I
PU LIC SERVICE COMPANY OF COLORADO CR-UE FORT ST. VRAIN NUCLEAR GENEPATING STATION Figure 2 Issue 17 Page 1 of 1 0-FIGURE 2 VISITORS CENTER EVACUATION ROU_T_E.E5 03 i
Colorado Hwv. 60 Johnstown Milliken E
as k
O 3
E a6 Fort St.
Visitor's
> m Center g ;
Vrain f 3 1
5 o
,)
Colorado Hw. 66 g
Platteville C
3 3
Colorado Hvv. 52 s" Fort Lupton Exit Fort Lupton E.'.
- j an r
l
-th St.
E E
)l Fort Lupton j
g Municipal Bldg.
9.
6 (618 4th St.)
O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRADO CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION 9#
Issue,..
Page 1 of 1 O
FIGURE 3 SITE SECTOR MAP e-m-m,-n-,
m-m 1
=
m @ m_ m_ e s e s__ e m @ @ @
g.,_
9, J'l
'27 l
F.N"P !@
pp..
1
~
l'i I
.\\;-!M/
,3 m
... -. ~ m. gjS !
I g
i
>.j i
I a
i l ;g
.. u. -.
g1$xg t xn w.
@t 3 m m m m e i1 %. q,c A l r
g I
g
,g I "X ' *.4 MLn.Dr.qd4M';b~ 4 6/kg 1 x,x?iiNj
.\\%,TMFWI IM Y N A i\\ 'g 2X' iffN /lM 1 Ii i # E :f t
3 G
j
^ I"' *H ' ^ *# 'N N *
~
^
- W -
N"" 'V "
~"'
O e
3
~/C l \\ 'A l '-
! ~'
J\\
~
g g_
ci i c V'e\\ +]
E
-^ g\\
i\\X i l
F l
j G vv oc o
3
- -j 4
i1,II
. //
I4 Cr4M M i
! \\ 1 11 !
3 I
III Vi5pl i(
'.. f r jll c
i 1 i
ij 1 y y;."~f.
6, a"t
.e-.\\ /,g g K*-,
i UU
. FF,
e E
_ - m y,. y.,
i 1
g
,\\!N!k(
Nll' 'l"{ O7l N)
% %i=c i4 4N,1L*1 i N / 1 I/ P 4.L!
@ T'm p fj l j ; l\\f y\\ J!
/
O-
. u. N M
Z 3
l Y:
iN,E E N s
- TTGQ,7 j
l,,]__' g
.44
- /l q
IV N j l
! l.;
j C, M B ()
YAAl Lg 2,,
wx R R.s --
j,
\\
M PP 00 5
i
i e,
g p
t V
. /.* (.A V
y \\
l 2
1'
' "7*
l ' ' '
[
n
't
- C7
- i ei j
- 4 5r l;
l i
e j
m-/
- 1 o
i-i l
fi 1
D
- ""*j I M i s'
3q-I y;.
l W W D d 6 W $ b d b $ $ 'b h h b
h O
l ItORM 372 - 22 3643
~
PUBLIC SERVICE COMPANY OF CHLORAD3 CR-UE IADI' 1 FORT ST VRAIN NUCLEAFt GENERATING STATION Issue 17 Page 1 of 4 V
TABLE 1 NOTIFICATION OF UNUSUAL EVENT Event Indication 1.
Any unplanned radio-1.
Alarms on:
logical release to RT 7312 the Reactor Building CAM (s) or its ventilation RT 7324-1 system.
kT 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 on 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.
O 3.
Indication of minor 3.
a) 25% increase in fuel damage detected circulat.ing activity in primary coolant.
from previous equilibrium cond-itions at the same power level.
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 raports.
in the release of radiologici or toxic materials.
A)
't FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADD CR-UE IADIO 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 2 of 4 C,y TABLE 1 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, accordanct with to the extent that Technical Spect-shutdown per Station fications.
Technical Speci-fications is required (SOP 12-04).
6.
Natural phenomenon that 6.
a)
Seismic Recorder may be experienced Operats; or threatened that represent risks beyond b)-d) as visually observed normal levels:
ty, or reported to, a) earthquake station personnel.
7_s
(,)
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 l
plant; or, I
IU FORM 372 22 3643
PUBLIC SERVICE COMPANY CF COLORAD3 CR-UE Table 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 3 of 4 pO TABLE 1 NOTIFICATION OF UNUSUAL EVENT Event Indication 7.
c)
Onsite or near site plant related accidents that could result in the release of toxic material or spills of flammable materials.
8.
Any serious radio-S.
As occurring.
logical exposure of plant personnel or the transportation to offsite facilities of contaminated personnel who may ha/s 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 extcnt requiring Shutdown a)
Engineered Safeguards in accordance with l
station Technical l
Specifications.
- 1) Plant ventilation-LCO 4.5.1
- 2) Steam / Water Dump System - LCO 4.3.3 s
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-VE 1
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 4 O
TABLE 1 NOTIFICATION OF UNUSUAL EVENT Event Indication
- 10. (Cont).
- 3) PCRV penetration flow rostriction devices - LC0 4.2.7 and LCO 4.2.9
- 4) PCRV penetration secondary closures -
- 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 ag RT 4803; or b)
RT 7325-1, 2, RT 4302, ap RT 73437-1; or c)
NOTE:
Use LCO 4.8.1 Technical Specification Limits as basis.
I O
l l
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADS CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 4 Ob TABLE 2 ALERT Event Incication 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 (Smrem/hr) accompanied by 230 Ky OCB trips and RAT undervoltage/ loss O
or *er
'er=-
a 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 moniter alarms).
4.
High radiation levels or 4.
RT 7312 high airborne contaminatioa 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 pr'ocess monitors.
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Table 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 2 of 4 m
TABLE 2 ALERT Event Indication 5.
Loss of offsite power aj 5.
230 KV OCB trips a_nd RAT n
vital onsite AC power undervoltage/ loss of power alarm for up to 30 minutes.
accompanied by 4 KV bus undervoltage 480V bus under-volta,ge, a_nd Diesel Trouble alarms.
6.
Loss of all vital 6.
DC bus 1 < 10 volts and DC power for up to DC bus 2 < 10 volts 30 minutes.
7.
Loss of primary coolant 7.
All He flow indicators read forced circulation for
- zero, between 2 and 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.*
8.
Loss of secondary coolant 8.
All secondary coolant flow functions needed for indicators read zero.
i removing residual heat.
1 O
V 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 tir2s are LOFC from 100". power.
Times may be corresponding longer fo lowe. power levels (CMG-4).
j W
O FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE FOPT ST. VRAIN NUCLEAR GENERATING STATION 7
Page 3 of 4 rh O
TABLE 2 ALERT Event Indication
- 11. Radiological effluents
- 11. a)
RT 7324-1 indicating exceed 10 times technical 22.5 x 10 2 uCi/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 ' uCi/cc d)
RT 7325-2 indicating
~
27.0 x 10 ' pCi/cc e)
RT 73437-1 indicating 27.0 x 10 ' 2Ci/cc I-131.
r3 f)
RT 4802 indicating U
2 7.0 x 10
- uCi/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
- 12. Ongeing security 12.
a)
As observed or reported; compromise, b)
Guard Station Trouble alarm; or, c)
Guard Station Ack owledge alarm.
- 13. Severe natural phenom-13.
a)
Seismic recorder operate enon b ing 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 3(d level; or, c) tornado striking f acility.
FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADD CR-UE Idbl' 2
~
FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 l
Page 4 of 4 l')
G TABLE 2 i
ALERT Event Indication
- 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 coctrol
- 15. As deemed necessary by O;
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 sisutdown; 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.
e.
O l
P ORM 372 22 3643
PUBLIC CERVICE COMPANY CF COLCRADD CR-UE Table 3 FORT ST. '/SAIN NUCLEAR GENERATING STATION Issue 17 Page 1 of 4 O
v TABLE 3 SITE AREA EMERGENCY Event Indication 1.
Loss of primary coolant 1.
All He flow indicators read forced circulation for zero.
over 5 hr. from 100% power.
(Lower power levels preceeding LOFC extends time available before core damage is incurred.
See CMG-4.)
4 2.
Non-isolable primary 2.
Loop 1 or 2 HRH activity coolant leakage through a alarm-high with Shift steam generator reheat Superviscr determination section.
that leakage is non-isolable.
3.
PCRV relief valve remains 3.
RT 93252-12 alarm and rapidly open.
decreasing Reacter pressure.
O
\\-
4.
Determinatior, of !nability 4.
230 KV OCB trips and RAT to restore onsite AC undervoltage/ loss of power
- power, alarm accompanied by 4Kv 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 emergetcy reserve shutdown system - resulting in inability to maintain
.0 lap at 220 F.
6.
Major damage to spent 6.
a)
Visual observation.
fuel due to severe cast damage resulting in release b) area radiation monitor of radioactivity to plant alarms.
l environs.
FORM 372 22 - 36E3
7 PUBLIC SERVICE COMPANY OF COLORADO CR-VE 8
FORT ST. VRAIN NUCLEAR GENERATING STATION Y
Page 2 of 4 3
(G TABLE 3 SITE AREA EMERGENCY Event Iridication 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 'ayond 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 l
minutes at the site boundary under 26.7 x 10 uCi/cc adverse meteorology (or levels b times I-131; or' the above for tnyroid dose rage).
b)
RT 7324-1 2*
andRT4853
>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.
l (Response detailed in Station Security Plan.)
F ORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADD CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Table 3 Issue 17 Page 3 of 4 nU TABLE 3 SITE AREA EMERGENCY Event Indication
- 10. Severe natural phenomenon 10.
being experienced or projected (with plant not in cold shutdown), such as; a) earthquake greater a)
Seismic Recorder Operate than Safe Shutdown alarm with indication of Earthquake ground motion greater than 0.10g horizontal or greater than 0.067g vertical.
b) flood greater than b)
As reported or observed.
design levels c) winds in excess of c) average wind velocity design levels greater than 90 mph s
s s,/
ar 10 second gusts exceeding 99 mph.
d) tornado in excess of d) horizontal wind design levels velocity greater then 202 mph.
- 11. Other hazards being
- 11. As observed by or experienced or projected reported ta, 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 prinary cocian.
b)
Reacter buildinp (CBA #2) radiation alarms.
l FORM 372 22 3643 b
PUZLIC SERVICE COMPANY OF COLORADO CR-UE Table 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 4 of 4 TABLE 3 SITE AREA EMERGENCY Event Indication
- 13. Evacuation of control 13.
Remote shutdown room accompanied by instrumentation indications inabi'lity 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.
O O
F ORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO CR-UE able 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 1 of 1 O
TABLE 4 GENERAL EMERGENCY Event Indication 1.
a)
Effluent monitors 1.
Stack monitor RT-7324-1, 2 detect levels alarm, or corresponding to Corresponding dose 1 rem /hr. whole rates determined with body (or 5 rem /hr E-500 or cutie pie thyroid) at the detector per exclusion area procedure HPP-56 and boundary under associated graphs.
actual meteoro-logical conditions.
b)
Thess dose rates are projected based on l
other plant para i
meters or are in the environs.
gJ 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.
i l
l l
FORM 372 22 3643
PUZLIC SERVICE COMPANY OF COLORADO CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Table 5 j
Issue 17 i
Page 1 of 1 TABLE 5 FORT ST. VRAIN ATMOSPHERIC STABILITY CATEGORIES
- ai (*F)
AT ('F) from frem Reactor Pasquill Stability ce**
60, tower Evildino Cateco-ies Classift:ation (Decrees) s-1.7 s-1.5 A
Extremely Unstable 222.5
>-1.7 to s-1.5
>-1.5 to s-1.3 S
Moderate'y unstacle <22.5 to 217.5
>-1.5 to s-1.3
>-1,3 to s
.2 C
Slightly Unstable
<17.5 to 212.5
>-1.3 to s-0.4
>-1.2 to 5-0.4 0
Neutral
<!2.5 to 27.5
>-0.4 to s+1.3
>-0.4 to s+1.2 E
Slightly Stable
<7.5 to 23.8
>+1.3 to s+3.5
>+1.2 to s+3.1 F
Mocerately Stanle
<3.S to 22.1
- 3.5
>+3.1 G
Extremely Stable
<2.1
(%
O per Proposed Revision 1 to Regulatory Guide 1.23, September 1980.
For utilizing other than Reactor Building Instrurnents (AT), utilize NRC Regulatory Guide 1.23, proposed Revisio,.
as a reference for stability classification.
Standard deviation of horizontal wind direction fluctuation (plume meander) over a period of 15 minutes to I hour.
l O
F ORM 372 3643
PUBLIC SERVICE COMPANY OF COLCRAD3 CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 1 TAF.LE 6 DOSE CONVERSION FACTORS (DCF'S)
Fadionuclide rem /hr DCF(C1/m )*
3 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 (based on 879 Mw(t) design inventory)
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 l l (based on 879 Mw(t) design inventory) l l
l
- DCF's for noble gases from "The EXREM III Computer Code for Estimating External Radiation Doses to Populations from Environmental Releases," ORil-TM-4332, with the exception of DCF's for Kr-89 and Kr-90, which are from " Final Environmental Statement, Light Water Breeder Reactor Program," Volume 3 of 5,
" Commercial Application of LWBR Technology," ERDA-1541.
DCF's for radiciodines from "INREM 11:
A. Computer Implementation of Recent Models for Estimating the Dose Equivalent to Organs of Man from an Inhaled or Ingested Radionuclide," ORNL/NUREG/TM-34 FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE ah 1 FORT ST VRAIN NUCLEAR GENERATING STATION 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 Unp'.anned Radiological Release to Reactor Buildt,'g 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 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.
7.
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 thi public.
l n
a FORM 372 22 3643 l
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Attach. 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 3
~
8.
The Er.ergency Coordinator will make notifications as follows:
l Contact with State EOC (
, and Gnvernor's Office,
l or Mansion,
1-
~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 ACTIVATION OF EMERGENCY RESPONSE CENTERS.
THIS NOTIFICATION REQUIRES VERIFICATION nF RFCEIPT BY THE STATE.
VERIFY BY CALLING 2.
READ all the information recorded in Step A (Page 1 of this ATTACHMENT).
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
I l Contact with NRC Operations Center (Hot Line or I
l' (If NRC Hot Line and Land Line are inoperative, use HP Network line.)
1.
READ the following statement verbttim:
"THIS IS NOTIFICATION OF A SIGNIFICANT EVENT AT THE FORT ST.
VRAIN NUCLEAR GENERATING STATION AT PLATTEVILLE, COLORADO.
THIS NOTIFICATION APPEARS TO BE REQUIRED PURSUANT TO 10CFRSO.72, ITEM NUMBER 1.
THIS NOTIFICATION DOES NOT REQUIRE ACTIVATION OF FEDERAL OR STATE EMERGENCY RESPONSE ORGANIZATIONS."
T FORM 372 22-3643 s
7 PUZLIC SERVICE COMPANY OF COLORADO CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION i
7 Page 3 of 3 0
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 O
O 1
l l
FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Attach. 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 1 of 1 O
v LOCAL DETERMINATION OF STACK CONCENTRATION This procedure should be performed by a person familiar with the instrumentation used to make a local determination of the stack concentration.
I i
l Dosimeter will be worn when performing this procedure. Exposure l l time will be kept to a minimum.
l l
1 1.
Proceed to the survey area at the exhaust stack on level 10, Turbine Building.
2.
Insert instrument probe in shielded box at the exhaust stack and note reading (mR/hr).
3.
Leave area immediately. Report the instrument used and reading (mR/hr) to the Control Room via the Gai-tronics.
s s
4.
Return to Control Room and verify proper instrument reading (mR/hr) conversion to concentration (pCi/cc) via conversion graph posted in Control Room.
NOTE: Utilize HPP-56, " Manual Release Rate Determination" as a reference, if required.
O FORM 372 22 36CB
- - _. ~
._ _ _ - _.. ~.
O O
O CR-UE Attach. 3 issue 17 Page 1 or 14 4
TABLE 1A 3
X/Q VALUES (X10 5 sec/m ) AT Tile EXCLUSION AREA BOUNDARY (590m)
FOR AN ANEMOHETER LOCATED AT A HEICIIT OF 10 METERS i-4 ACCORDING TO THE EQUATIONS OF NRC REG CulDE 1.145 i
WINDSPEED AT 10 METERS (MPH)
Stability A
Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 A
3.469 1.735 1.156 0.694 0.496 0.386 0.289 0.231 0.174 0.116 0.069 8
11.890 5.746 3.830 2.298 1.642 1.277 0.958 0.766 0.575 0.383 0.230 4
I i
c 23.250 11.630 7.751 4.650 3.22 2.584 1.938 1.550 1.163 0.775' O.465 0
36.56 18.28 12.19 7.844 6.9?8 5.988 4.491 3.593
'2.695 1.196 1.078' E
48.86 24.23 16.15 10.83 10.83 9.449 7.089 5.670 4.252 2.835 1.701 8
F 88.42 is 4. 21 29.47 20.35 18.54 14.42 10.81 8.650 6.8488 4.'325 2.595 c
140.20 70.11 46.74 33.62 40.06 31.16 23.37 18.70 14.02 9.348 5.609 I
CR-UE Att3 Cil. 3 Issue 17 Page 2 of 14
=.
=in_ -- - _
- a FIGURE 1.A.
1
~~~
- = DISPERSION FAC"*OR R!Q) vs.WINDSPEED FOR THE EXC:.,USION C~ - "
-"3
~ AREA BOUNDARY (590 METERS), ACCDRDING TO THE EOUATIONS OF NRO REG. GUIDE 1.145. WINCSPEEDS SHOWN ARE THE INDICATION.
FOR AN ANEMOMETER 1,0CATED AT A HEIGHT OF 10 METEPJ.
1
-;es
~
-....-... -... ~
-~-;~K -' M- ' - -
- ; tv - vc^7-~ _ ;-rTX
- Wh.&g =#rg -~ E W_= 5.--) i1 --=JI w"w = N.U-e:---TR-V4 U-%
. x --- p-yW - :p r. :. -
g
.m Wig =2
,. =: w
- 1. ;.L.- -
_,__ _.____m... f_ _ C_____ T___ _T.
_A_
h_i __ ___
-~M_
't-
_.NC, _- Z_ _ _.
2 7
.-i*
.y.
_ G X x ne.
~
~
l f
vs F.s C
( _ C..
,m s".,,
s.
t
~=
I
- w l
l 5
se 4,
y g,
a I
/
- ,t d g
g a
s q:
o! ;4 C-----
p.
=-
3.*
4 y..
w-aii s
- z. := = _.
\\
L
~ %,,m "4
I., :e =
y_
e.
pJ
^
c..-
W.
I A num-m =w e.
-l a _
- _ - - -m W
c
. w u_ _.. _ _ _ _ _
w 4 % +.m.-e m--
N
--m
, yq z wx~3 - "
.p=_-'
-~*--M
"_"r~
M sv..y-
'~
~a
~"
]
1I
._ ~._ -- - -. - _. _
s e
E tr7 E
2 80 K,
10
~WINDSPEED INDICATION (di
.. ~ -
O O
D:
Cit-UE :
Attach. 3.
Issue 17 Pago 3 or 14 TABLE 2A r
X/Q VALUES (X10 6 3,cf,3 AT A DOWNWIND DISTANCE OF 2 MILES 3
4 IOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 MET [RS
~
i ACCORDING TO THE EQUATIONS OF NRC REC CUIDE 1.145 f:
WINDSPEED AT 10 METERS (MPH)
Stability Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0 30.0 50.0 1
4 A
0.124 0.062 0.041 0.025 0.018 0.014 0.010 0.008 0.006 0.004 0.002
- i il 1.T51 0.876 0.584 0.350 0.250 0.195 0.146
-0.117 0.088 0.058 0.035 C
12.97 6.483 4.322 2.593 1.852 1.441 1.081 0.865 0.648 0.432 0.259 D
38.13 19.07 12.71 7.859 6.104 5.019 3.972 3.177 2.383 1.589 0.953 j.
E 64.89 32.44 21.63 13.74 11.46 9.821 7.961 6.369 4.776 3.184 1.911
- )
I 130.4 65.18 43.45 28.33 25.27 22.53 17.91 14.33 10.74
(.163 4.2911 ll i
C 250.1 125.0 83.35 56.60 56.14
- 51. 2 38.79 31.03
'23.28 15.52 9.310 t
i-
+
i t
4 i
i
CR-UE Attach, 3 l
Issue 17 l
Page 4 of 14 l
._ 1F3
~
-7.,..-.
s i
e FIGURE 2.A.
' Dl5PER$10N FACTOR pt/Q) vs. WIND 5 PEED POR A DOWNWIND
,es DISTANCE OF 2 Mll.ES, ACCDRDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEED5 SHOWN ARE THE INDICATIONS 8
FOR AN ANEMOMETER I.DCATED AT A HEIGHT OF 10 METERS.
t i
s I
i
?
?
'. \\
i i
1 l
i s
l l
?
i i
e{
i a
a x
\\ \\
x nx x
il\\\\ 6N i
i i
I i,,, i( (!NTF i i
i i
1
~
g N
5 5
~
i N
r s.
.x e
l
\\
IN I i
1.
I j,, \\!
.l..l'T M Di h
w 1
=
s.
.C
(\\l i
i l
i t
1.
.I
.., i i
j
.!'f j
I 8 ' t l l.i ;,
- l.
l l
t ?:
,g.
irr
~
~
B
~
A s.
l'
.\\.
i i
t, I
i i
l'!.!'l' !!.!!!I'l,l l
l t
t i
l l
l l
k i
hi l
I i
.m to a
a e
so s.,
l l
O O
O CR-UE Att&Oh, 3 Issue 17 Pago 5 of 14 r.
TABLE 3A X/Q VALUES (X10 6 3
sec/m ) AT A DOWNWIND DISTANCE OF 4 MILES FOR AN ANEMOMETER LOCAlfD AT A IIEICHI 0F 10 METERS ACCORDING TO THE EQUATIONS OF NRC REG CUIDE 1.145 1
bINDoPEED AT 10 METERS (MPH)
Stability class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 FO.0 30.0 50.0 A
0.069 0.034 0.023 0.014 0.010 0.008 0.006 0.005 0.003 0.002 0.001 I
D 0.155 0.018 0.052 0.031 0.022 0.017 0.013 0.010 0.078 0.005 0.003 C
3.963 1.982 1.321 0.793 0.566 0.440 0.330 0.264 0.198 0.132 0.019 D
14.87 7.434 4.956 3.028 2.271 1.823 1.411 1.132 0.849 0.566-0.340 i
E 29.17 14.59 9.725 6.053 4.757 3.918 3.095 2.476 1.857 1.238 0.743 F
f5.46 32.73 21.82 13.85 11.40 9.626 7.585 6.068 4.551 3.034 1.820 G
132.81 66.42 44.28 29.04 25.85 22.67 19.37 13.90 10.42 6.948 4.169 I
CR-UE Attach. 3
'~
Issue 17 Page 6 of 14
~~
1r2
. _J_1..
.__1
.-..-.-_g.-
t i
1 l
i I
~
,r3 FIGURE 3A.
DISPER$lON FACTOR R/Q) vs. WIND 5 PED FOR A DOWWIND DISTANCE OF 4 MI:.E'i, ACCDRDING TO THE EQUATIONS OF s
NRC REG. GUIDE 1.145.' WINDSPEDS SHOWN ARE THE INDICATIONS FOR AN ANEMOMETER 1.DCATED AT A HEIGHT OF10 METERS.
i I
e i
i j
i I
i i
i i
8 5
=
\\ \\
s t
\\\\
i i
i l
l 8
I i
1
\\ \\. \\'
i l
i
!( h.!
l-I 5
'm E'~
m i-
' r-1
~
~
\\
\\
1 x
x e
Q'
[
i\\
iN N ih i i
i i
E,. !
~~
h i i
!l
l
- l l
i l
m 3,
e 5
.] s A
a
.A 9 t
t l
1 i
At I
i l
i
,..i.
i i.t.I I
i
..!;r ln l
- 5 a
e 8
4 l a
1
' \\
8 t
I s \\ \\
)'
i l
l
' k, lk-l l4 l
t i
l l
.i;.: M !i
-l!!-l:i'!lii:
l
- j. ' '
~'
i x%
t i
i i.
i, o,..
i
' lA!
i l
j.
l!I-lj.;;j
,)
,e I
4 t
8 i
i
,i i
0 m
3 40 m
WINDSPED INDICATION (men)
~-
w m---w---+w--,-
a
._.m.
_.. ~. -
k O
O O.
CFt-UE Attacle. 3 isst6e 17 Page 7 or 14 TABLE 4A X/Q VALUES (X10 6 sec/m ) Al A DOWNWIND DISTANCE or 5 MILES FOR AN ANEMOMETER LOCATED AT A HEICHT of 10 MET [kS ACCORDING TO THE EQUATIONS OF NRC REG GUIDE 1.145 W'NOSPEED AT 10 METERS (MPH) a Stability Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 20.0-30.0 50.0 1
l A
0.057 0.028 0.019 0.011 0.008 0.006 0.005 0.004 e 003 0.002 0.001 II 0.072 0.036 0.024 0.014 0.010 0.008 0.006 0.005 0.004 0.002 0.001 C
2.704 1.352 0.902 0.58:1 0.366 0.301 0.225 0.180 0.135 0.090 0.054.
i 0
10.96 5.478 3.652 2.224 1.655 1.322 1.017 0.816.
0.612
- 0. sa08 0.245 E
22.43 11.21 7.476 4.630 3.586 2.927 2.294 1.837 I.377 0.918 9.551 r
52.07 26.03 17.36 10.93 8.819 7.347 5.759 4.608 3.456 2.304.
1.382 y
G 107.7 53.86 35.91 23.30 20.14 17.34 13.34 10.67 8.005 5.336 3.202 8
e
=
i CR-UE i
Attach, I Issue 17 Page 8 of 14 i
i i
~
~
- to 2 '
i,
i_..___.__..__-_..
~
"IGURE 4.A.
~~~ ~ ~ ~
NSPERSION FACTOR (X/Q) vs.WINDSPEED FOR A DOD. WIND
'. DtS7ANCE OF 5 Mu.15. ACCDRDING TO THE IQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE T'4E INDICATIONS J
i l
l i POR AN ANEMOMETER 1.DCATED AT A HEIGHT OF 10 METERS.
i i
i i
it*'I -
5 I
i i
e i
i l
i i
i t
I.
t i.
I Strd s
S i s I \\\\'
l i,\\ \\
l I
i i
i I
i l
.3.
,ya y
~
,1
~
d
i x w
a___
j
~
8 t
s x x
1 4
i 4
\\e N i
6 l\\
\\
\\!
i,. I I
i
\\!
['l5
. l i
I E
s
,e*
.g m
x w
I N
A p
s i
1 I
e l
I*
\\1 I!'
2 i a
m C
- 5 i
n i
- gg i \\\\ i.
i i
i i
t.
i e
i l
l
,j,.!'
t I
a i.
l l
l l
e M
'm iw 5
NN I
(
e I
AA w N 1
l t
r 4
y
~~
w g
m s.
I i
I i
19 3
3 WINDSPEED INDICATION (men)
.---._,__-__.-_.-__-.._,_..--,m.
..._-. ~ - - ~._
. _. _ - ~. -.,
~....
O O
0 4
CR-UE Attach.'3 issue 17 Page 9 or 14-a TABLE 5A 3
X/Q VALUES (X10* sec/m ) AT A DOWNWIND DISTANCE Or 6 MILES FOR AN ANLMohETER LOCATED AT A ifElGH1 Of 10 MEifRS ACCC.tDINC TO Tile EQUATIONS OF NRC REG CUIDE 1.145 WINDSPEED AT 10 METERS (MPH)
Stability Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.0 P9.0*
30.0 50.0 A
0.485 0.243 0.162 0.097 0.069 0.054 0.040 0.032 0.024 0.016 0.010 2
0 0.616 0.308 0.206 0.123 0.008 0.068 0.051 0.041 0.031 0.021 0.012 C
19.72 9.859 6.573 3.944 2.817 2.191 1.643 1.315 0.986
'O.657 0.394 D
55.61 42.81 28.54 17.35 12.84 10.21 7.830 6.284
.4.713 3.142
'1.885-E 179.6 89.81 59.87-36.93 28.31 22.96 17.88 14.33 10.75 7.166 4,299 r
431.9 215.9 144.0 90.18 71.65 59.15 46.17 36.93 21.70
.18.47 11.08 c
909.7 454.9 303.2 195.3 165.2 140.4 108.1 86.45 64.84 43.23 25.94'
!f i
i s
t e
u.
ma
4 CR-UE Attach. 3 Issue 17 Page 10 of 14 l
3r2
~~
S
- L _.__.__..____
.. FIGURE 5.A.
Ot3PERSION FACTOR 0U0) vs.WINDSPEED POR A DOWNWIND DISTANCE OF 6 MIL.ES, ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.145. WINDSPEEDS SHOWN ARE THE INDICATIONS FOR AN ANEMOMETER LOCATED AT A HEIGHT OF 10 METERS
,ys s
'x i\\
i 1
'\\\\
l 1
- \\\\ N dG
i i
,~
x
's N
1 I
1 1
s i s x
I \\ \\
N * ["
\\! M t
~1 t
i.,i\\ NI N Ei 1
i i
t s
m i
go
'x x
x N
h h (*
'O
~
j b
i 6
i
.i i'
~
h i
)-
l 1
- 1 i
l~,.
l I.
I I-z 4
' I.
i
, i g
m x
g 6
g r
k 4
i i
i i
i \\\\ i.
i i
I l'
t.;
.illl:..l.,ii:iili'ij.i.j-
.l l
j i
ier-u Vs
~.
's xx 6-i
- 3 ;!
i..
i
.i.
i 1
6.;
- t-l 1
i '.
i i
m-i tre g
I l
s 1
n s
s
+
t t
i t
l i.
)
?
l 1
i i
i kij.j t
l I
l l-i i
ire i
,m.
se
=
=
=
=
WINDSPEED INDICATION (men)
O.
O O
CR-UE Attacle. 3 Issue 17 Page 11 or 14 TABLE 6A X/Q VALUES (X10" sec/m ) AT.A DOWNWIND DISTANCE Of 8 HILES FOR AN ANEMOMETER LOCATED AT A IIEICHT OF 10 METERS ACCORDING 10 Tile EQUATIONS OF WRC REC GUIDE 1.145 WINDSPEED AT 10 METERS (MPil)
Stability s
Class 1.0 2.0 3.0 5.0 7.0 9.0 12.0 15.C.
ca.0 30.0 50.0 A
O.379 0.190 0.126 0.076 0.054 0.042 0.032 0.025 0.019 0.013 0.006 n
(1. f 84 0.Pl 2 0.161 0.097 0.069 0.054 0.0h0 0.032 0.0284
.0.016
-0.010 l
C 12.66 6.329 4.219 2.531 1.808 1.406 1.055 0.844 0.633 0.422 0.253 D
57.94 28.97 19.31 11.71 8.599 6.808 5.195 4.169 3.126-2.084' 1.251 E
126.3 63.15 8:2.10 25.84 19.54 15.71-12.18e 9.735 T.301 4.867 2.920 r
322.7 161.4 107.6 66.87 52.07 42.47
-32.93 26.35 19.76 13.17
- 7. 9 08s 389.2 232.8 Its8.2 121.7 101.6 78.19 62.55 0
698.4 76.91 31.28.
18.77 4
1
.a
~
CR-UE Attach, 3 Issue 17 Page 12 of 14
- 'O
~
-..s
, -.~
i i
l FIGURE 6.A.
DISPERSION FACTOR (X/Q) vs.WINDSPEED FOR A DOWNWIND 3,3 OISTANCE OF S MILES, ACCORDING TO THE EQUATIONS OF NRC REG. GUIDE 1.143. WINDSPEEDS SHOWN ARE THE INDICATIONS s
FOR AN ANEMOMETER LOCATED AT A MEIGHT OF 10 METERS.
s t
i i
i
__s t
?
I i_ _. \\
I\\ \\i i
- l.
t*
i i i
i l
i i
(
)
l !'l!i l
'fij'l l
g n
q
% -- %'2 is x
\\ \\
\\
f\\ \\e Nt t
i e
a ammy.
t
'l I \\ \\ ' a l ' Al l""
it i l 'i i i
I 1'l*'il'i 5
lg!:
!!!!' !!ll!!'li' 3
m x
m 5
l g
\\._
N t
t
.A W
\\'
4,
I ki' l'!l1lI I
I l..*
\\
- l l
l
- 8 ii! Ii: '!!!!ll
.j;i!!!!!!ltl>l.
2U'!.
ac
,pa w
b
=
s iI f.
a s n-s o.
i il i !
't
- *1
\\\\; l i s '
l'-
illil
- l IlI'i !!lil
~~
I.'!'!l!!'lII!I
.l.
l
!!Il
,e n
1 1 5
\\
' i i
\\\\
t 4
3 8 i
!'I i.ii i i* i l i
'i4 l
l?!6tli!I'lt*
t h'
l
! l l!! illi te mim A
5 4
i 4
l *i ll l
}!!
'I II l5 l
if 8 I
I
' e.
l
'l l
't I
l
'I ! ! '-
,e I
i l
i e
(
10 2D 23 M
s
'WINDSPEED INDICATION (meh)
O'
~~
O O
.O CR-UE Attach. 3 isstee 11 6
Page II of 14 1ABLE 7A
-7 l
X/Q VALUES (X10 sec/e ) AT A DOWNWIND OBSTANCE Of 10 MILES FOR AN ANEMOMETER LOCATED AT A iTICHT of to METERS ACCORDING TO THE EQUATIONS of NRG REC CulDE 1,145 WINDSPEED AT 10 METERS (MPil)
Stability i
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
0.313 0.156 0.104 0.063 0.045 0.035 0.026 0.021 0.016 0.010 0.006-D 0.402 0.201 0.134 0.080 0.057 0.045 0.033 0.027 0.020 0.013
- 0. (MHS C
8.833 4.416 2.9t:4 1.767 1.262 0.981' O.736
'O.589 0.442 0.294 0.177 0
43.02 21.51 14.34 8.678 6.345 5.008 3.810 3.057 2.293 1.528 0.917 E
99.81 49.90 33.27 20.35 15.26 12.20 9.384 7.521 5.645 3.763 2.258 1
F 256.9 128.5 85.64 52.96 40.71 32.95 25.44 20.35 15.26 10.18 6.105
- 0 568.7 288.3 189.6 119.8 96.40 79.62 61.16 48,93 36.70 28s.4 6 14.68 8
4 0
9 m
f q
CR-UE Attacn, 3 Issue 17 Page 14 of 14
_....._:. r _--..
5.
. _. ~ _ _
FIGURE 7.A.
DISPERSION FACTOR (X)Q) vs. WIND 5 PEED FOR A DOWNWIND p
DISTANCE OF 10 MILES, ACCORDING TO THE EQUATIONS OF
-f NRC REG. GUIDE 1.1.L' WIND 5PEEDS SHOWN ARE THE INDICATION!
s FOR AN ANEMOMETER LOCATID AT A HEIGHT OF 10 METERS.
1 a
i g(
i i,
tre x
m
.1 x
sx x
\\X
- N
.c-l
.N' i
E l
I l
t t
.[
i W
1 X
N_
L_
sa
'x p.
c 1
U j
\\-;
i 7x i
2 i
i A
t j
5 u
i i
i
,r N
=
m m
X
~
.i 8
I I
i ik
~
i,
... I.
e.
i
,g m
m w
w, t
i INN I
i e
i t
i i
l i
N-i I
l-t i
I:
i
+
4 e
\\.
e t
- i i
i i
i l
i j.' ]-
i i
I.
i i
e i
i i
to 3
2 88 IS i
~
^J a
WIND 5 PEED INDICATION (m) 4
PUBLIC SERVICE COMPANY OF COLORADD CR-UE uh t1 FORT ST. VRAIN NUOLEAR GENERATING STATION Page 1 of 2 s
Datasheet 1 - Data Logger (or IBM) Monitored Release A.
Projection - Option 2 1.
Current and release start date and time:
a)
/
/
b) 2.
Projected end of release date and time:
a) _/
/
b) 3.
Radiation Monitor Values, Noble Gas a) RT-7324, 1 cpm
)) RT-7324. 2 cpm O
If one of the above is offscale or inoperative:
a) E-500 or Cutie Pie?
b) Instrument Reading mR/hr 4.
Exhaust Stack Flow Rate efm 5.
Radioiodine Monitor Values; RT-73437, I a) Initial Reading from chart cpm b) Intermediate Reading from chart epm c) Peak or Current Reading from chart cpm d) Time between a and b
. minutes e) Time between b and c minutes 6.
Wind Direction (preferred samoling poirt is 10 met 2r instrument ca 60 meter meteorological tower)
C iV PORM 3 72 22 3643
/
PUBLIC SERVICE COMPANY OF COLCRADO CR-UE Datasheet 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issum 17 Page 2 of 2 O
7.
Wind Speed (Preferred sampling point is 10 meter instrument on 60 meter meteorological tower) mph 8.
Distance between upper and lower temperature instruments meters 9.
Delta Temperature between temperature instruments F
10.
Standard Deviation (Sigma Theta) of Wind Direction - 15 min. average B.
Puff - Option 2 1.
Current and release start date and 0
time:
a) ___/
/
b) 2.
End of Puff date and time (not to exceed 15 minutes after B.1) a)
/
/
b)
C.
Total for All Puffs - Option 3 Change option and execute DF 41-0-0.
4 FORM 372 22 36C3 l
PUBLIC SERVICE COMPANY OF COLORAD3 CR-UE
~
f FORT ST, VRAIN NUCLEAR GENERATING STATION Page 1 of 2
,V Datasheet 2 - Data Logger (or IBM) Unmonitored Reler.se) 1.
Date and Time of beginning of release a)
/
/
b) 2.
Time of Louvers closed 3.
Maximum CPM, RIS-9301 cpm 4.
a)
Primary coolsnt I-131 equivalent circulating inventory Ci b)
Primary coolant I-131 equivalent plateout inventory
()
Ci 5.
Primary Coolant Volume t
sce 6.
a)
PCRV Pressure Before Release psig b)
PCRV Pressure After Release psig 7.
Wind Direction (prefererd sampling point is 10 meter instrumentation on 60 meter meteorological tower)
O 8.
Wind speed (preferred sampling point is 10 meter instrumenation on 60 meter meteorological tower) mph FORM 372 22 36C3
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Datasneet 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 2 of 2 O
9.
Distance between.
upper and lower temperature instruments meters
- 10. Delta Temperature between temperature instruments
- F
- 11. Standard Deviation (Sigma Theta) of wind Direction - 15 min. average O
9 O
F O R M 372 22 36.J
PUBLIC SERVICE COMPANY OF COLCRADO CR-UE Datasheet 3 FORT ST. VRA1N NUCLEAR GEN 5 RATING STATION Issua 17 Page 1 of 2 b,
PRELIMINARY ASSESSMENT OF PLANT CONDITIONS TECHNICAL ADVISOR l
1.
Brief description of event 2.
Date/ Time of event 3.
Date/T.me of assessment 4
If the data logger is operating, obtain the Demand Function Printout (or print specified displays):
NOTE: All screens accessible on Display 900 Helium Inventory 0F 69-0-0 DF 76-0-0 0
DF 77-1-0 Post Trip Review PRIMARY SYSTEM 5.
Current Reactor Power 6.
Rod Runback Occur (Y/N)
If yes, record positions 2B 4A 7.
If shutdown, are all rods fully inserted (Y/N) 8.
Circulators Operating A B C D MODE: Steam Feedwater Cond.
Firewater 9.
Purification Train A B To: storage, FCRV, or Ventilation 10.
Is heat removal capability aceauate at this time (Y/N)
Ov FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Datasheet 3 FORT ST. VRAIN NUCLEAR GENERATitlG STATION Issue 17 Page 2 of 2 0-SECONDARY SYSTEM 11.
Loops Operattr,g I
II 12.
Feec to S/G's:
Norm FW Emer.
FW Emer. Cond.
Firewater
- 13. Status of Aux. Boilers Remarks Time Description O
O POFtM 372 22 3643 t
(
l
PUBLIC SERVICE COMPANY OF COLORADD CR-VE M kli t 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of I EMERGENCY C00RDINATOR'S CHECKLIST 1.
Initiate Emergency Procedure actions.
2.
Technical Advisor notified.
3.
Obtain preliminary assessment of release.
4.
Obtain meteorological data.
5.
Initiate protective actions for station personnel.
6.
Contact management and confirm classification.
(Checklist 3) 7.
Complete Notifications Form.
NOTIFICATION OF UNUSUAL EVENT nttachment 1 8.
Make Notifications (Attachmc it 1, Page 2)
NOTIFICATION OF UNUSUAL EVENT State E0C Governor's Office or Mansion NRC's Operations Center O
F ORM 370 22 - 3643 r
PUBLIC SERVICE COMPANY OF COLORAD3 CR-UE Checklist 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17
~
Page 1 of 2 i
Checklist 2 - Data Logger Monitored Release NOTE:
Initialize the summing s:reen by entering option 4 and running DF 41-0-0.
This should be done for the first calculation only.
1.
" DEMAND FbHCTION OVERVIEW" key, located cursor on DF 41-0-0 and "XMIT CURSOR."
2.
Step 1 brings up display 941.
Follow steps on this display. They lead the user from screen to screen through the basic pragram steps.
Always utilize program "0PTION 2"
when performing calculations for record keeping or dose reporting purposes.
This "0PTION" reverts !.o a "1" after the Demand Function is run and must be res,at to a "2" each time.
3.
Perform a
" duration of release" calculation utilizing the projected or estimated end of release time. Utilize 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> from current as a default value wherieur tnis value isn't known.
4.
.. int displays from this calculation.
5.
Display results and print
- NOTE:
Be certain to reset option to "2" after performance of a calculation.
h 1
O l
PORM 372 - 22 3M3
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Checklist 2 FORT ST. VR AIN NUCLEAR GENERATING STATION Issue 17 Page 2 of 2
()
I 6.
Perform a " puff" calculation utilizing a projected ending time 15 minutes from the current time shown on step 3 of this checklist. Release start time should be the same as current time.
7.
Print displays from step 6.
8.
Display results and print 9.
Set "0PTION" to "3" and rerun DF 41-0-0 10.
Print Display 951 which tabulates the results O
SUMMARY
OF DISPLAYS TO PRINT Step No.
Displays Verification 4.
944, 942, 948, 951 5.
945, 947 7.
944, 942 8.
945, 947 10.
949 O
FORM 372 22 + M43
PUBLIC SERVICE COI IPANY OF COLORADO CR-UE e kli t 3 i
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 1
')
MANAGEMENT CONTACT NOTIFICATION LIST The first management contact will make the following notification:
l N01E: Any change to this notification list requires a change be made l
to RERP-HOME, Checklist #1.
l Subsequent l
Date/
l l
l Contacts l
Time i
Remarks l
l Plant Management l l
l l(Contact 1) l l
l l Suet. of Oper.
l l
l l
I
_ _l i_l Station Manager l l
l
-l l
l lAcminiarative/ l j
l l Tech tarv._Mgr. l l
l
-I l
l lMgr.. Nuc. Prod. l l
l lifa~ai at i on P '-
I
~
l ltection Manager ]
[
l IicePresident, l
l loroduction l
l l
.. I I
l 1
I l
l Redia Relations l l
l l%b Burns l
l l
1 l
l l
1 1
1 or l
l IGary Reeves l
l l
1 l
l I
I l
l or l
l l
.lMarily McAdams l
l l
l l
l I
I l
l NRC l
l l
l_ Bill Dickerson l l
l I
jl l
l
~
l ur l
l l
lG.L. Plumlee, III]
l l
I l
l
- Calls to PSC phones from outside of the PSC telephone system may require use of a different telephone exchange.
In these cases, utili:e the exchange in parentheses.
'T PORM 372 22 3643 i
PUBLIC SERVICE COMPANY CF COLORAD3 CR-UE Worksheet 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issua 17 Page 1 of 9 U,,
i WORKSHEET 1 ASSESSMENT OF RELEASE-MONITORED PELEASE This attachnent is to be used only if the TI-59 calculator program is n_ot 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 gancia dose and dose rate at the EAB; c)
Classification of the release; d)
Projected v' sole body and thyroid gamma dose at the EAB; and e)
Recommended protective action for the general population.
1.
Date/ Time of beginning of release.
O 2.
oete Time of endin9 of reiease.
If releese is still occurring, enter the Date/ Time of the calculation.
3.
Hours between 1. and 2.
4.
Collect the following data:
a)
Maximum CPM, RIS-7324-1:
(RR-93539, red pen) cpm b)
Sensitivity, RIS-7324-1:
(I-14, 403-P7) pCi/cc/ cpm c)
Maximum CPM, RIS-7324-2:
(RR-93539, blue pen) cpm d)
Sensitivity, RIS-7324-2:
(I-14,203-P7) pCi/cc/ cpm e)
Maximum CPM / Min, RIS-73437-1:
cpm / min N0' E: Maximum CPM / Min must be calculated as:
(Maximum CPM _ Initial or Intermediate CPM)
(
Elapsed Time (min)
)
from strip chart.
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRADO CR-UE ksh t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 9
/~N' f)
Sensitivity, RIS-73437-1:
pCi/cc/ cpm / min g)
Site Area Emergency Limit (as posted):
1) 6.6E-2 pCi/cc noble gas i
2) 6.7E-5
_uC1/cc282I h)
Ten Times Technical Specificatiar, Limits (as posted):
1) 2.5E-2 pCi/cc noble gas 2) 7.0E-8 pCi/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 i
degrees -
c.w.
m)
Differential Temperature:
F Circle appropriate instrument 60m tower Reactor Building 5.
Determine sectors affected using Site Sector Map.
(Figure 3)
Sector (s) 6.
Determine Stability Category usirg Table 5, Step 4k), and 4m).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
l O
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRADO CR-UE ksh et 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 9 I
I l
Noble Gas Concentration l
l 1
7.
Calculate the exhaust stack noble gas cencentration.
a)
RIS-7324-1 concentration = (step 4a) x (step 4b)
=(
)x(
)
yC1/cc
=
b)
RIS-7324-2 concentration = (step 4c) x (stap 4d)
=(
)x(
)
pCi/cc
=
c)
If either RIS-7324-1 or RIS-7324-2 is off-scale high, record the stack concentration as obtained by local, portable instrument (refer to HPP-56 or Attachment 2 for inst ructions).
V Local Indicated Concentration =
pCi/cc d)
Enter the highest of 7a), 7b), or 7c) pCi/cc I
I l
Noble Gas Release Rate l
l l
8.
Calculate the Source Term, Q (i.e., Noble Gas Release Rate).
Q = (step 7d) x (stc-p 4j) x (1 E -6 Ci/pci)
=(
)x(
) x (1 E -6)
Ci/sec
=
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORAD3 CR-UE
! ksh t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 9 V
I i
l Classification of Ivent l
i_
l 9.
Determine weighted noble gas dose conversion factor from Table 2.
7.5E+2 Rem / hour Ciim'
- 10. Determine tne EAB dilution factor from Attach-ment 1 using the Stability Category (Step 6) and wind speed (Step 4k).
Dilution Factor =
sec/m' General Etercency Determination
- 11. Determine whole body dose rate at the EAB.
Dose Rate = (step 8) x (step 9) x (step 10)
=(
)x(
)x(
)
Rem / hour p
=
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 14 of this attachment.
Site Area Emergency Determination
- 12. Criteria for Site Emergency:
If Step 7d) is greater than or equal to 6.6E-2 uCi/cc, the cia.;sification of the event is SITE AREA EMERGENCY.
Inform the Shift Supervisor of the Site Emergency Condition. Then go directly to Step 14 of this attachment.
Rcdiological Alert Determination
- 13. Criteria for Radiological Alert:
If Step 7d) is greater than or equal to ten times the Technical Specification limit 2.5E-2 bCi/cc*,
the classification of the event is-RADIOLOGICAL ALERT.
Inform the Shift Supervisor of the Radiological Alert Condition.
Then proceed with Step 14.
- NOTE: Technical specification limit = 2.5E-3pCi/cc 10x Technical Specification limit = 2.5E-2 uCi/cc, as stated above.
!O Ponu 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRADO CR-Ve
! ksh t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 9 O
I I
l Curies of Noble Gas Released l
l l
14.
Calculate the curies of noble gas released to present time.
Curies released = (step 8) x (step 3) x (3.6 E +3 s/hr)
=(
)x(
) x (3.6 E +3)
Curies
=
l I
l Accumulated Whole Body Gamma Dose at EAB l
i I
15.
Calculate the dose received at the EAB.
f]
Dose = (step 11) x (step 3)
=(
)x(
)
=
Rem NOTE:
This calculation assumes the recipient was at the EAB for the entire duration of the release.
l l
Projections 1
I l
16.
If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e.,
from beginning to end).
If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hours.
4 O
FORM 372 22 3643
PUBLIC (ERVICE COMPANY OF COLORADD CR-UE
!!orksheet 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Pago 6 of 9 ok)
~
17.
Project the totoal whole body gamma dose at the EAS.
Projected dose at EAB = (step 11) x (step 16)
=(
)x(
)
=
Rem l'
I i
131 I Cor. centration ~
l I
i
- 18. Calculate the exhaust stack 1'11 concentration.
RIS-73437-1 concentration = (step 4e) x (step 4f)
=(
)x(
)
pCi/cc
=
3 l
l (J
l 1311 and Total Radioiodine Release Rate l
I 1
19.
Calculate the source term Q (1'11 release rate).
Q = (step 18) x (step 4j) x (1 E -6)
=(
)x(
) x (1 E -6)
Ci/sec
=
20.
Calculate Q f r total radioiodine release.
T Q
= (step 19) x (1.05 E + 2)*
7
=(
) x (1,05 E + 2)*
Ci/sec
=
- Ratio of total radiciodines to l'11 in design inventory.
1 FOftM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADS CR-UE h'o ksh t1 FORT ST. VRAIN NUCLEAR GENERATING STATION
~
Page 7 of 9
(~h G
I I
l Classification of Event l
l l
- 21. Determine weighted radiciodine dose conversion factor from Attachment 8.
5.3E+4 Rem / hour ti/m 3
General Emergency Determination
- 22. Determine the thyroid dose rate at the EAB.
Dose Rate = (step 20) x (step 21) x (step 10)
=(
)x(
)x(
)
Rem / hour
=
If the resulting dose rate at the EAB is 2 5 Rem / hour, the classification of the event is GENERAL EMERGENCY.
Inform the Shift Supervisor c'
the General Emergincy Condition.
Then go
/"
directly to Step 25 of this attachment.
Site Area Emergency Determination
- 23. Criteria for Site Area Etergency:
If Step 18 is great than or equal to 6.7E-5 pCi/ce, the classifiestion of the event is SITE EMERGENCY.
Inform the Shift Supervisor of the Site EmerSency Condition. Then go directly to Step 25 of this attachment.
Radiological Alert Determination
- 24. Criteria for Radiological Alert:
If Step 18 is greater than or equal to ten times the Technical Specification limit 7.0E-8 uCi/cc*, the classification of the event is RADIOLOGICAL ALERT.
'nform the Shift Supervisor of the Radio!cgical Alert Condition.
Then proceed with Step 25.
I NOTE: Technica' Specification Limit = 7.0E-9pCi/cc l
10x Technical Specification Limit = 7.0E-8pCi/ce, as stated above.
l 4
v FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADD Ch-UE ksh t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 8 of 9 I
I l
Curies of Radiciodine Released l
I I
P5. Calculate the curies of radiciodine released to present time.
Curies Released = (step 20) x (step 3) x (3.6 E +3)
=(
)x(
) x (3.6 E +3) curies
=
I l
l Accumulated Thyroid Dose at EAB l
I I
- 26. Calculate the dose received at the EAB.
Dose = (step 22) x (step 3)
=(
)x(
)
=
NOTE: This calculation assume, the recipient was at the EAB for the entir* duration of the release.
1
-l l
Projections l
l l
~2 7.
If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e.,
from beginning to end).
If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hours.
28.
Prcject the total thyroid case at the EAB.
Projected Dose at EAB = (step 22) x (step 27)
=(
)x(
)
,{}
=
F ORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORAD3 CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION
!!orksheet I g
Issue 17 Page 9 of 9 CT G
29.
Determine the recommended protective action fer the general population based on the results of steps 17 and 28, refer to PERP-PAG.
30.
The whole body gamma dose rate at the EAB is (step 11):
Rem / hour
- 31. The classification of the event based on noble gases is (step 11 or step 12 or step 13):
- 32. The noble gas release rate is (step 8):
C1/sec
- 33. The accumulated whole body gamma dose at the EAB is (step 15):
Rem 34.
The total number of curies of noble gas release to the present time is (step 14):
Curies
- 35. The projected whole body gamma dose at the EAB is (step 17):
Rem Based on projected release duration of (step 16):
hours
/D
- 36. The thyroid dose rate at the EAB is (step 22):
Rem / hour V
37.
- The classification of the event based on radio-iodines is (step 22 or step 23 or step 24):
38.
The radiciodine release rate is (step 20):
Ci/sec
- 39. The accumulated thyroid dose at the EAB is (step 26):
Rem 40.
The total number of curies of radiofodine released to the present time is (step 25):
Curies 41.
The projected thyroid dose at the EAB is (step 28):
Rem Based on projected release duration of (step 27):
hours
- If this classification differs from the classification in step 31, the higher (i.a., more severe) classification is to be used to Uetermine recommended protective 3Ction.
m
)
l FORM 372 22 - 3643
PUBLIC SERVICE COMPANY OF COLORADD CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Worksheet 2 Issue 17 Page 1 of 7
(~),
WORKSHEET 2 ASSESSMENT OF RELEASE USING TI-59 CALCULATOR PROGRAM-MONITORED RELEASE l
his attachment is only to be used if the TI-59 calculator program is i
used.
I# the program is no* used, use Worksheet 1.
l l
This attachment is used to determine the following:
a)
Estimated noble gas and radioiodine release and release rate; b)
Estimated whcle bcdy and thyroid gamma dose and dose rate at the EAB; c)
Classification of the release; d)
Projected whole body and thyroid gamma dose at the EAB; and e)
Recommended protective action for the general population.
1.
Collect the following data:
()
a)
Date/ Time of beginning of release:
b)
Date/ Time of ending of release.
If release is still occurring, enter the Date/ Time of the calculation:
c)
Hours between la) and Ib):
hours (ST0 11) d)
Maximum CPM, RIS-7324-1:
cpm (RR-93539, red pen)
(STO 03) e)
Sensitivity RIS-7324-1:
uCi/cc/ cpm (I-14,403-P7)
(STO 04) f)
Maximum CPM, RIS-7324-2:
cpm (RR-93539, blue pen)
(STO 05) g)
Sensitivity, RIS-7324-2:
uti/cc/ cpm (I-14, 203-P7)
(ST0 06)
Ov FORM 372 22 36CB
FUBLIC SERVICE COMPANY OF COLORADO CR-UE llorksheet 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 2 of 7 (O
.g
- h)
Maximum mR/nr, Cutie Pie-2520 Probe:
mR/hr (STO 01)
- i)
Maximum mR/hr, E-500-GM Probe mR/hr (ST0 02) j)
Maximum CPM / MIN, RIS-73437-1:
cp.7/mi n (STO 07)
NOTE: Maximum CPM / Min must be calculated as:
(Maximum CPM - Initial or Intermediate CPM)
(
Elapsed Time (min)
)
from strip chart.
k)
Sensitivity, RIS-73437-1:
pCi/cc/ cpm / min (STO 08) 1)
Site Emergency Limit (as posted):
- 1) 6.6E-2 pCi/cc noble gas
{)
- 2) 6.7E-5 pCi/cc 2'2I m)
Ten Times Technical Specification Limits (as posted):
- 1) 2.52-2 pCi/cc noble gas
- 2) 7.0E--8 pCi/cc 2'21 n)
Exhaust Stack Flow (cfm):
(I-15, FI-7320) cfm (STO 09) o)
Average Wind Speed at 10 meters:
mph p)
Wind Direction at 10 meters:
NOTE: North = 0 increasing degrees-c.w. From Degrees q)
Differential Temperature F
Circle appropriate instrument 60m Tower Reactor Building Steps lh) and li) used only if RIS-7324-1 or RIS-7324-2 n
off-scale high.
U l
FORM 372 22 3643 i
PUBLIC SERVICE COMPANY OF COLORADO CR-UE
'o ksh et 2 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 7 O
G 2.
Determine sectors affected using Site 1
Sector Map (Figure 3):
Sector (s) l 3.
Deter.nine Stability Category using Table 5 and Steps lo) and Iq).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
4.
Determine the EAB dilution factor from using the Stability Category (Step 3) and wind speed (Step lo).
Dilutten Factor sec/m' (STO 10) 5.
If tte release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end).
If the release has termi-nated, enter value from step Ic).
Preliminary estimate of release hours hours.
(ST0 12)
O FChu 372 22 3843
~
PUBLIC SERVICE COMPANY OF COLORAD3
$r[Seet2 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 4 of 7 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 3nd TI-59.
d)
Depress " TRACE" button on printer, e)
Obtain the magnetic card labeled "FSV Off-Site Dose Calculation (RERP) - Monitored Release."
f)
Read magnetic card i;1to TI-59.
1)
Depress IIl,l@l,l@l, lWRITEl keys.
2)
Insert magnetic card into right side of TI-59.
Card shuuld be right side up with the "1" ir the upper left-hand corner.
3)
"1" will be displayed if the card was read properly -continue with Step 7.
If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card with the same title and repeat Step 6f).
FORM 372 22 3843 1
PUDLIC SERVICE COMPANY OF COLORADO CR-UE ksh t2 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 5 of 7 O
7.
Input the necessary data into the indicated TI-59 storage registers.
a)
Step Ic) = l@l 11 b)
Step Id) = l@l 03 c)
Step le) = ]@l 04 d)
Step If) = [@l 05 e)
Step 1 ) = l@l 06 9
f)
Step 1h) = l@l 01 g)
Step 11) = l@l 02 O
07 h)
Step lj) = l S3l i)
Step ik) = l@l 08 l
j)
Step In) = l@l 09 l@l 10 k)
Step 4)
=
]@l 12 1)
Step 5)
=
8.
Run Dose Assessment Program a)
Depress l@l key.
b)
Wait until a number is displayed. A flashing number indicates improper execution of the program. Depress l_b_l and lP5TI u
keys and repeat Steps 7 and 8.
O FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLSRAD3 CR-UE t!crksheet 2 FORT ST. VRAIN NUCLEAR GEN ~ RATING STATION Issue 17 Page 6 of 7 OO l
SUMMARY
l 9.
a)
The whole body gamma dose rate at the EAB is(RCL 19):
Rem / hour b)
The classification of the event based on noble gases is:
1)
If Step 10.a) 2 1 Rem / hour, GENERAL EMERGENCY.
2)
If RCL 17 2 6.6E-2 pCi/cc (Step 1.1)1),
SITE AREA EMERGENCY.
3)
If RCL 17 2 2.5E-2 pCi/cc (Step 1.m)1) and s 6.6E-2 pCi/cc, RADIOLOGICAL ALERT.
c)
The noble gas release rate is (RCL 18):
Ci/sec d)
The accumulated whole body gamma dose at the EAB is (RCL 21):
Rem O
e)
The total number of curies of noble gas released to the present time is (RCL 20):
Ci f)
The projected whole body gamma dose at the EAB is (RCL 22):
Rem g)
The thyroid dose rate at the EAB is (RCL 27):
Rem / hour F OR M 372 + 22 - 3643
PUBLIC SERVICE COMPANY OF COLORAD3 CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION rksh t2 Page 7 of 7 O
l
- h)
The classification of the event based on radiciodines is:
1)
If Step 10.g) 2 5 Rem / hour,
'ENERAL EMERGENCY.
2)
If RCL 23 2 6.7E-5 pCi/cc (Step 1.:)2),
SITE AREA EMERGENCY.
3)
If RCL 23 2 7.0E-8 pCi/cc (Step 1.m)2) and
< 6.7E-5 pC1/cc, RADICLOGICAL 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 O
Prese"t ti e is cac' 28):
c' 1)
The projectee 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.
- If this classificatica differs from the classification in Step 10b),
the higher (i.e., more severe) classification is to be used to determine recommended protective actions.
4 O
FORM 372 22 3643
PUBi lC SERVICE COMPANY OF COLORADO CR-UE het 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 10
'w/
WORKSHEET 3 ASSESSMENT OF RELEASE-UNMONITORED RELEASE lhis attachment is to be used only if the TI-59 calculator program is g 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 br.,c/ snd thyroid gamma dose and dose rate at the EAB; b)
Classification of the release; c)
Projected whole body and thyroid gamma dose at the EAB; and d)
Recommended protective action for the general population.
1.
Date/ Time of beginning of release 2.
Date/ Time of ending of release.
If release is u
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 28 c)
Primary coolant I equivalent circulating inventory:
_.C i d)
Primary coolant 2'2I equivalent plateout inventory:
Ci e)
Primary Coolant Volume:
sec f)
Sice Emergency Limit (as posted):
1) 6.6E-2. pC1/cc noble gas 2) 6.7E-5 pCi/cc '2I 2
g)
Ten times Technical Specification Limits (as posted):
1) 2.5E-2 pCi/cc noble t]
gas FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLCRAD9 CR-VE ksh et 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 2 of 10 O
l 2) 7.0E-8 pCi/cc 2'2I 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
Circle instrument used:
60m tower Reactor Building 5.
Determine sectors affecttd using Site Sertor Map (Figure 3):
Sector (s) 6.
Determine Stability Category using Table 5, Step 41 and Step 4j:
Stability Category riOTE: Usc proper column based on whether 60m tower or reactor building s
AT instruments used.
7.
Calculate the release noble gas concentration:
RIS-9301 cc.1 centration = (step 4a) x (step 4b)
=(
)x(
)
pCi/cc
=
8.
alculate the source term, Q (n ble gas release rate):
ng a)
Reactor Building _ouvers Q
- (step 7) x (5.8 E +7)* x (1 E -6 C1/vci) ng
=(
) x (5.8 E +7)* x (1 E -6)
Ci/sec
=
l
POMM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Worksheet 3 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 3 of 10
/*O b)
PCRV Safety Valves
- (step 7) x (1.9 E +7)** x (1 E -6)
O ng
=(
) x (1.9 E +7)** x (1 E -6)
_Ci/sec
=
- Release rate (cc/sec) from both PCRV safeties (FSAR, Section 6.8).
I I
l Classification of Event I
1 l
9.
Determine weighted noble gas dose conversion factor from Table 2:
7.5E+2 Rem / hour Ci/m'
- 10. Determine the EAB atmospheric dilution factor from Attachment 1 using Steps 6 and 4h:
Dilution Factor sec/m' General Emergency Determination
- 11. Determine the whole body dose rate at the EAB:
a)
Reactor Building Louvers Dose Rate = (step Sa) x (step 9) x (step 10)
=(
)x(
)x(
)
Rem / hour
=
b)
PCRV Safety Valves Dese Rate = (step 8b) (step 9) x (step 10)
=(
)x(
)x(
)
Rem / hour
=
12.
If the resulting dose rate at the EAB is 2 4 Rem / hour, the classiffcation of the event is GENERAL EMERGENCY.
Inform the Shift Supervisor of the General Emergency Condition. Then go "O
directly to Step 15.
FORM 172 3643
SERVICE COMPANY OF COLORADO CR-UE E PUBLIC ksh et 3 FORT ST. VRAIN NUCLEAR GENERATING STATidN Page 4 of 10 O'
O Site Area Emergency Determinatior.
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.
Radiological Alert Determination 14.
If Step 8a.
or 8b. is greater than or equal to ten times the Technical Specification limit 3.7E-1 C1/sec, the classification of the event is RADIOLOGICAL ALERT.
Inform the Shift Supervisor of the Radiologicai Alert Condition. Then proceed with Step 15.
NOTE: Technical Specification Limit = 3.7E-2 Ci/cac.
10x Technical Specification Limit = 3.7E-1 Ci/cc, as stated above l
i l
Curies of Noble Gas Released j
/~T l
l 9
- 15. Calculate the curies of noble gas released to present time.
a)
Reactor Building Louvers Curies Released = (step 8a) x (step 3) x (3.6 E +3)
=(
)x(
) x (3.6 E +3)
Curies
=
b)
PCRV Safety Valves Curies Released = (step 8b) x (step 3) x (3.6 E +3)
=(
)x(
) x (3.6 E +3)
Curies
=
O FORM 372 - 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE
!!crksheet 3 FORT ST. VRA!N NUCLEAR GENERATING STATION Issue 17 Page 5 of 10
(^
C)
^
l l
l Accumulated Whole Body Gamma Dose at EAB l
l
__ l
- 16. Calculate the dose received at the EAB.
a)
Reactor Building Louvers Dose = (step 11a) x (step 3)
=(
)x(
)
Eem
=
b)
PCRV Safety Valves Dose = (step lib) x (step 3)
=(
)(
)
=
NOTE: This calcuiation assumes the recipient was at the EAB for the entire duration of the release.
I
'l l
Drojections l
l
.I 17.
If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e.,
from beginning to end).
If the release has terminated, enter value from sce? 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(
)
=
O FORM 372 22 7643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE
! ksh t3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 10 0
5)
PCRV Safety Valves Projected Dose at EAB = (step lib) x (step 17)
=(
)x(
)
=
- 19. Calculate the release 182I equivalent concentration (Reactor Building Louvers or PCRV Safety Valves).
8821 Equivalent Concentration =
^"
(step 4c) + (step 4d) x (5.7 E -3)
+ (step 4e)
=(
)+
(
') x (5.7 E -3)
+(
)
Ci/cc
=
- " Arroun t of plateout l'11 equivaient released (FS/R, Section 14.11.2.7.1).
- 20. Calculate the source term, Q (2'2I equivalent release rate).
a)
Reactor Building Louvers Q = (step 19) x (5.8 E +7)
=(
) x (5.8 E +7)
Ci/sec
=
b)
PCRV Safety Valves Q = (step 19) x (1.9 E + 7)
=(
) x (1.9 E +7)
Ci/sec
=
I i
l Classification of Event l
1
_I
- 22. Determine 2'2I dose conversion factor from Attachment 8.
1.2E+6 Rem / hour 3
C1/m O
FORM 372 22 3643 0
PUBLIC SERVICE COMPANY OF COLORADD CR-UE h t3 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 7 of 10 It/
- 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 EmergencL etermination 0
23.
If the resulting dose rate at the EAB is ;t 5 Ram / hour, the classification of the event is GENERAL EMERGENCY.
Inform the q
Shift Supervisor of the General Emergency Condition. Then go C
directly to Step 26 of this attachment.
Site Area Emergency Determination 24 If Step 20a. or 20b. is greater than or equal to 9.8E-4 Ci/sec, the classification of the event is SITE AREA EMERGENCY.
Inform the Shift Supervisor of the Site Area Emergency Condition. Then go directly to Step 26 of this attachment.
Radiological Alert Determination
'2 5.
If Step 19 is grea'er than or equal to ten times the Technical Specificatten limit 1.0E-7 Ci/sec, the classification of the I
event is RADIOLOGICAL ALERT Inform the Shift Supervisor of the Radiological Alert Conditior,. Then proceed tcith Step 26.
NOTE: Technical Specification Limit = 1.0E-8 C1/cc 10x Technical Specification Limit = 1.0E-7 Ci/cc, as stated above.
FOftM 372 22 3643
m PUBLIC SERVICE COMPANY OF COLORADO CR-UE Worksheet a, FORT ST. VRAIN NUCLEAR GENERATING STATION Issy, 17 i
Page 8 of 10 rh, U
l l
l l
Curies of 222I Equivaient Released l
l l
26.
Calculate the curies of 2821 equivalent released to present
- time, a)
Reactor Building Louvers Curies Released = (step 20a) x (step 3) x (3.6 E +3 s/hr)
=(
)x(
) x (3.6 E +3)
Curies
=
b)
PCRV Safety Valves Curies Released = (step 20b) x (step 3) x (3.6 E +3)
=(
)x(
) x (3.6 E +3)
TN
=
Curies L]
I l
l Accumulated Thyrnid Dose at EA2 l
I l
27.
Calculate the dose rece'ved at the EAB.
a)
Rea: tor Building Louvers Dose =
= (step 22a) x (step 3)
=
b)
PCRV Safety Valves Dose = (step 22b) x (step 3)
=(
)x(
)
=
Rem NOTE:
This calculatior, assumes the recipient was at the EAB for the entire duration of the release.
FORM 372 22 364J
PUBLIC SERVICE COMPANY OF CELORAD3 CR-UE t! ksh t3 FORT ST. VRAIN NUCJAR GENERATING STATION Page 9 of 10 f3 V
l l
l Projections l
l l
28.
If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e.,
frcm beginning to end).
If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hour (s).
- 29. Project the total thyroid dose at the EAB.
a)
Reactor Building Louvers Projected Dose at EAB = (step 22a) x (step 28)
=(
)x(
)
=
Rem l
{)
b)
PCRV Safety Valves Projected Dose at EAB = (step 22b) 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.
1 I
l Summary l
l l
31.
The whole body gamma dose rate at the EAB is (Step 11a or lib):
,_ Rem /hr 32.
The classification of the event based on noble gases is (Step 12 gr Step 13 or Step 14):
33.
The noble gas release rate is (Step 8a or 8b):
Ci/sec O
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE llorksheet 3 FORT ST. VRAIN NUCLEAR GENERATING STATION
^
'I Issue 17 Page 10 of 10
(~)
(_-
e 34 The accumulated whole body gamma dose a; the EAB is (Step 16a or 16b):
- 35. The total number of curies of noble ga:
released to the present time is (Step 15a or 15b):
Curies
- 36. The projected whole oody gamma dose at the EAB is (Step 18a or 18b):
- 37. Based on projected release duration of (Step 17):
hours
- 38. The thyroid dose rate at the EAB is (Step 22a or 22b):
Rem / hour 39.
- The classification of the event based on 282I equivalent is (Step 23 or Step 24 or Step 25):
40.
The 2'21 equivalent release rate is (Step 20a or 20b):
Ci/sec O
41.
The accumulated thyroid dose at the EAB is (Step 27a or 27b):
Rem 42.
The total numbea of curies of 22;I 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
- If this classification differs from the classification in Step 31, the higher (i.e., more severe) classification is to be used to determine recommended protective action.
(~',
s_/
FORM 372 22 36C3
PUBLIC SERVICE COMPANY OF COLORADD CR UE
!!orksheet 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 1 of 6 L'O J
WORKSHEET 4 ASSESSMENT OF RELEASE USING TI-59 CALCULATOP. PROGRAM-UNMONITORED PELEA.SE This attachment is only to be used if the TI-59 calculator program is used.
If the proaram is not 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)
Reccmra rded protective action for the general population.
1.
Collect the following data:
O e)
Dete/ Time of eesinnine of release:
b)
Date/ Time of ending of release.
If release is still occurring, enter the Date/ Time of the calculation:
c)
Hou s between la) and Ib):
hours (ST0 07) d)
Maximum CPM, DIS-9301:
com (RR-93256,Pt. 10)
(GTO 01) e)
Sensitivity RIS-9301:
vCi/cc/ cpm
'(ST0 02) f)
Primary Coolant 121I equivalent Ci circulating inventory:
(posted)
(ST0 03) 122 g)
Primary Coolant equivalent Ci
~
plateout invantory:
(pested)
. (STO C4) h)
Primary Coolant Volume:
(posted)
' cc (STO 05)
O FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Worksheet 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 page 2 of 6 m
Lal i)
Site Emergency Limit:
(posted)1) 6.6E-2 pCi/cc noble gas l
- 2) 6.7E-5 pCi/cc 222I j)
Ten Times Technical Specification i
limits (posted):
- 1) 2.5E-2 pCi/cc noble gas
- 2) 7.0E-8 pCi/cc **2I k)
Average Wind Speed at 10 meters:
mph 1)
Wind Direction at 10 meters:
NOTE: North = 0 in:reasing degrees-c.w. From
,_ Degrees m)
Differential Temperature
- F Circle instrument used g-s 60m Tower Reactor Building V
2.
Determine sectors affected using Site Secte r Map (Figure 3):
Sector (s) 3.
Cetermine Stability Category ustr,9 Table 5 and Steps 1.1) and 1.m).
Stability Category NOTE: Use proper column based on whether 60m tower or reactor building AT instruments used.
4.
Determine the EAB dilution factor from using the Stability Category (Step 3) and wind speed (Step Ik).
D;iu. ton Faccor sec/m 2
(STO 06)
O FORM 372 22 - 36El
PUBLIC SERVICE COMPANY OF COLORADO CR-UE
! ksh t4 FORT ST. VRAIN NUCLEAR CEf ERATiNG STATION Page 3 of 6 5.
If the release is continuing, consult with the Shift Supervisor and estimate the total number of hours the release will continue (i.e., from beginning to end).
If the release has termi-nated, enter value from step 1.c).
Preliminary estimate of rei eise hours hours.(ST0 08) 6.
Prepare the TI-59 for data ertry.
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) - Unmo.71tored Release."
f)
Read magnetic card into TI-59.
q 1)
Depresslll,lMl,l@l, l WRITE l keys.
O 2)
Insert magnetic card intc right side of TI-59.
Card should be right side up with the "1" in the upper left-hand corner.
3)
"1" will be displayed if the card was read properly - continue with Step 6f)4).
If a flashing number is displayed, the card was not read properly. Obtain the other magnetic card with the same title and repeat Step 6f).
4)
Depress l2l,lMl,l@l, l WRITE l 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 reagi properly. Obtain the other magnetic card with the same title and repeat Step 6f). '
FORM 372 22 3643
PUBLIC SERVICE COMFANY OF COLORADO CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION
!!orksheet 4 Issue 17 Page 4 of 6 C
7.
Input the necessary data into the indicated TI-59 storage registers.
a)
Step 1c) = l@l 07
~
b)
Step Id) = l S_T,0 l 01 c)
Step le) = l@l 02 d)
Step If) = l@l 03 e)
Step ig) = l@l 04 f)
Step.1h) = l@l 05 l@]
06 g)
Step 4
=
O h)
Sten 5 imi 08
=
8.
Run Dose Assessnent Program.
a)
Depress l@l key.
b)
Walt until a number is displayed. A flashing number indicates improper execution of the program. Depress lCLRlandI[STl keys and repeat Steps 7 and 8.
o FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Worksheet 4 FORT ST. VRAIN NUOLEAR GENERATING STATION Issue 17 Page 5 of 6 O
l
SUMMARY
l 9.
a)
The release path is:
1)
Reactor Building Louvers 2)
PCRV Reliefs b)
The whole body gcama dose at the EAB is (RCL 12 for louvers, RCL 13 for reliefs).
rem / hour c)
The classification of the event based on noble gases is:
1)
If Step 10b) 2 1 Rem / hour, GENERAL EMERGENCY.
2)
If Step ?.0c) 2 9.6E-1 Ci/sec SITE AREA EMERGENCY.
3)
If Step 10c) 2 3.7E-1 Ci/sec and s 9.6E-1 Ci/sec,
())
RADIOLOGICAL ALERT.
4)
If RCL 11 2 9.6E-1 Ci/sec, SITE AREA EMERGENCY.
5)
If RCL 11 > 3.7E-1 C1/sec and < 9.6E-1 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)
Tha projected whole body gamma dose at the EAB is (RCL 18 for louvers, RCL 19 for reliefs):
Rem Based on a projected release duration of (RCL OS):
hours FORM 372 22 364
\\
PUBLIC SERVICE COMPANY OF COLORADD CR-UE f ksh et 4 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 6 of 6 O
i h)
The thyroid dose rate at the EAB is (RCL 24 for louvers, RCL 25 for reliefs):
Rem / hour 1)
The l'8 equivalent release rate is (RCL 22 for louvers, RCL 23 for reliefs):
Ci/sec
- j)
The classification of the event based on 1821 equivalent is:
1)
If Step 10n) 2 5 Rem / hour, GENERAL EMERGENCY.
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 Ci/sec RADIOLOGICAL ALERT.
k)
The accumulated thyroid dose at the EAB is (RCL 28 for louvers, RCL 29 for i
reliefs):
Rem 5
1)
The total number of curies of 1811 equivalent released to the present time is (RCL 26 for louvers, RCL 27 for reliefs):
Ci m)
The projected thyroid dose at the EAB is (RCL 30 for louvers, RCL 31 for reliefs):
Rem Based on projected release duration of (RCL 08):
hours
- 10. Determine tne recommended protective action for the general population. Refer to RERP-PAG.
- If this classification differs from the classification in Step 10b),
the higher (i.e., more severe) classification is to be used to determine recommended protective actions.
O FORM 372 22. %43
PUBLIC SERVICE COMPANY OF COLCRADO CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 3 O
Work /Datasheet/ Checklist Control List Worksbeet No.
Title Number Cooies 1
Monitored Release Calculations (Manual) 5 2
Monitored Release Calculations (TI-69) 5 3
Unmonitored blease Calculations (Manual) 2 4
Unmonitored Release Calculations (TI-59) 2 Datasheet No.
1 Dataloager Monitored Release 5
2 Datalogger Unmonitored Re: ease 2
3 Preliminary Assessment of Plant Conditions 2
Checklist No.
1 Emergency Coordinator / Control Room 2
Director Checklist 2
Datalogger Monitored Release 5
3 Plant Management Contact L.ist 2
Attachment ;10.
1 Notification of Unusual Event
-2 O
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLORADD CR-UE WS/DS/CL FCRT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 2 of 3 C
FORMS USE REPORTING SHEET Technical Clerk and Recorder:
This sheet is being transmitted to report use of forms from a controlled copy of the Radiological Emergency
Response
Plan Implementing Procedures, BOOK NO.
located at The following forms have been utilind from this copy:
Worksheet Numbers Copies Used O
Datasheet Numbers Copies Used Checklist Numbers Copies Used J
The procedure affected by this sheet is shown ir, the header to this page, unless otherwise noted below in the comments to this reporting form.
Wnen this form is received, it will be necessary to replace h
the noted number of forms, as well as this " Forms Use Reporting I
Sheet" for the affected procedure in the affected book.
FORM 372 22 3643 l
PUZLIC SERVICE COMPANY OF COLORADO CR-UE FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 3 FORMS USE REPORTING SHEET (Continueql COMMENTS i
Reported By:
Date:
Technical Clerk and Recorder Date Received Date Replaced Technical Clerk and Recorder will transmit this form to the d
originating individual / department upon completion of this form to V
notify users that the procedure has been updated and that all worksheets, checklists, and datasheets are present in the required number of copies.
9 O
FORM 372 22 3643 l
l
PUBLIC SERVICE COMPANY OF COLORADO CR-UE L'orksheet 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Page 1 of 9 O
'JORKSHEET 1 ASSESSMENT OF RELEASE-MONITORED RELEASE i
This attachment is to be used only if the TI-59 calculator program is M used.
If the TI-59 is used, Workshest 2 is to be used.
This attachment is used to determine the following:
a)
Estirnated noble gas and iodine release and release rate;-
b)
The estime.ted 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.
i 1.
Cate/ Time of beginning of release.
O 2-o t <Ti or e#d'#9 or reie se-trri 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) uti/cc/ cpm c)
Maximum CPM, RIS-7324-2:
(RR-93539, blue pen) cpm d)
Sensitivity, RIS-7324-2:
(I-14,203-P7) pCi/cc/ cpm e)
Maximum CPM / Min, RIS-73437-1:
cpm / min NOTE: Maximum CPM / Min must be calculated as:
(Maximum CPM - Initial or Intermediate CPM)
(
Elapsec Time'(min)
)
from strip chart.
FORM 372 22 - 3443 l
l l
~
PUBLIC SERVICE COMPANY OF COLORAD3 CR-UE
' ksh t1 FORT ST. VRAIN NUCLEAR GENERATING STATION z
Page 2 of 9 O
a f)
Sensitivity, RIS-73437-1:
vCi/cc/ cpm / min g ) ',
Site Area Emergency Limit (as posted):
1) 6.6E-2 uCi/cc noble gas 2) 6.7E-5 uCi/cc182I h)
Ten Times Technical Specification Limits (as posted):
1) 2.5E-2 uCi/cc noble gas 2) 7.0E-8 uCi/cc585I 1)
Exhaust Stack Flow (cfm):
(I-15,FI-R320) cfm j)
Exhaust Stack Flow (cc/sec):
(Step 41 x 4.72E + 2) cc/sec n)
Average Wind Speed at 10 meters:
mph 1)
Wind Direction at 10 meters:
From Degrees NOTE: North = 0* increasing e
degrees -
c.w.
m)
Differential Temperattree-
'F Circle appropriate instrament 60m tower Reactor Building 5.
Determine sectors affected using Site Sector Map.
(Figure 3)
Sector (s) 6.
Determine stability Category using Table 5, Step 4k), and 4m).
Stability Category h0TE: Use proper column based or, whether 60m tower or reactor building AT instruments used.
O PORM 372 22 3643
____._._-_____m__
[
PUBLIC SERVICE COMPANY OF COLORADO CR-UE rksh et 1 I
FORT ST. VRAIN NUCLEAR GENERATING STATION Page 3 of 9 I
I l
Noble Gas Concentration i
~
l l
7.
Calculate the exhaust stack noble gas concentraticn.
a)
RIS-7324-1 concentration e (step 4a) x (step 4b)
=(
)x(
)
uCi/cc
=
b)
RIS-7324-2 concentration = (step 4c) x (step 4d)
=(
)x(
)
pCi/cc l
=
c)
If either RIS-7324-1 or RIS-7324-2 is off-scale high, l
record the stack concentration as obtained by local, l
portable instrt: ment (refer to HPP-56 or Attachment 2 for instructions).
Local Indicated Concentration =
pCi/cc d)
Enter the highest of 7a), 7b), or 7c) uCi/cc I
l l
Noble Gas Release Rate l
l l
8.
Calculate the Source Term, Q (i.e., Noble Gas Release Rate).
Q = (step 7d) x (step 4j).: (1 E -6 Ci/uci)
=(
)x(
) x (1 E -6)
Ci/sec
=
b O
FORM 372 22 3643
PUBLIC SERVICE COMPANY OF COLSRAD3 CR-UE ksh t1 FORT ST. VRAIN NUCLEAR GENERATING STATION Page 4 of 9 I
l l
Classification of Event l
l l
9.
Determine weighted noble gas dose conversion factor from Table 2.
7.5E+2 Rem / hour Ci/m3-
- 10. Determine the EAB dilution factor from Attach-ment I using the Stability Category (Step 6) and wind speed (Step 4k).
Dilution Factor =
sec/m' General Emeroency Determination
- 11. Determine whole body dose rate at the EAB.
Oose Rate = (step 8) x (step 9) x (step 10)
=(
)x(
)x(
)
Rem / hour p
=
v If the resulting dose rate at the EAB is 2 i Rem / hour, the classification of the event is GENERAL EMERGENCY.
Inform the Shift Supervisor of the General Emergency condition. Then go directly to Step 14 of this attachment.
Site Area Emeroency Determination
- 12. Criteria for Site Emergency:
If Step 7d) is greater than or equal to 6.6E-2 pCi/ce, the classification of the event is SITE AREA EMERGENCY.
Inform the Shift Supervisor of the Site Emergency Condition. Then go directly to Step 14 of this attachment.
Radiolooical Alert Determination
- 13. Criteria for Radiological Alert: If Step 7d) is greater than or equal to ten times the Technical Specification limit 2.5E-2 l
uCi/cc*, the classification of the event is RADIOLOGICAL ALERT.
l Inform the Shift Supervisor of the Radiological Alert Condition.
Tnen proceed with Ster 14.
l
- NOTE: Technical specification limit = 2.5E-3pCi/cc 10x Technical Specification limit = 2.5E-2 uCi/ce, as stated above.
O PoRM 372 22 3843 l
l PUBLIC SERVICE COMPANY CF COLORADO
.CR-UE ksh et 1 FORT ST. VRt.!N NUCLEAR GENERATING STATION Page 5 of 9
.O I
I l
Curies of Noble Gas Released l
l l
14.
Calculate the curies of nob!e gas released to present time.
l Curies released = (step 8) x (step 3) x (3.6 E +3 s/hr)
=(
)x(
) x (3.6 E +3)
=
Curies i
l l
l l
Accumulated Whole Gody Gammc Dose at EAB l
l l
- 15. Calculate the dose received at the EAB.
(}
Dose = (step 11) x (step 3)
=(
)x(
)
=
Rem NOTE:
This calculation assumes the recipient was at the EAB for the entire duration of the release.
I I
l Projections l
I i
16.
If the release is continuing, consult gith the Shift Supervisor and e-tinate the total number of hours the release will continue
( i. e!',
from beginning to end). If the release has terminated, enter value from step 3.
Preliminary estimate of release hours hours.
C)
PORM 3M. 22 300
.e
PUBLIC SERVICE COMPANY OF COLORADO CR-UE Workshtet 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Issue 17 Paga 6 of 9 0
I
- 17. Project the totoal whole body gamma dose at the EAB.
Projected dose at EAB = (step 11) x (step 16)
}
=(
)x(
)
=
i I
l 131 I Concentration 1
1 I
- 18. Calculate the exhaust stack 181I concentration.
RIS-73437-1 concentration = (step 4e) x (step 4f)
=(
)x(
)
pCi/cc
=
O-I I
l 131I and Total Radioiodine Release Rate l
l l
- 19. Calculate the source term Q (18 81 rele:ase rate).
Q = (step 18) x (step 4j) x (1 E -6)
=(
)x(
1 x (1 E -6)
=_
C1/sec
- 20. Calculate Q for total radioiodine release.
T Q
= (step 19) x (1.05 E + 2)*
T =(
) x (1.05 E + 2)*
Ci/see
=
- Ratio of total rad:otodines to 122I in design inventory.
O PORM 372 22 3643
=a w
a -.
vs w
PUBLIC SERVICE COMPANY OF COLORAD3 CR-UE b'
ksh et 1 FORT ST. VRAIN NUCLEAR GENERATING STATION Fage 7 of 9 I
l l
Classification of Event i
i I
- 21. Determine weighted radioiodine dose conversion factor from Attachment 8.
5.3E+4 Rem / hour 3
C1/m Genatal Emergency Determination
- 22. Determine the thyroid dose rate at the EAB.
Dose Rate = (step 20) x (step 21) x (step 10)
=(
)x(
)x(
)
Rem / hour
=
If the resulting dose rate at the EAB is 2 5 Rem / hour, the classificatian of the event is GENTAAL EMERGENCY.
Inform the Shift Supervisor of the General Emergency Condition. Then go directly to Step 25 of this attachment.
Site Area Emergency Determination
- 23. Criteria for Site Area Emergency: If Step 18 is great than or equal to 6.7E-5 pCi/cc, the classification of the event is SIIE EMERGENCY.
Inform the Shift Supervisor of the Site'Emergucy Condition. Then go directly to Step 25 of this attachment.
Radiological Alert Determination 24.
Criteria for Radiological Alert: If Step 13 is greater than or equal to ten times the Tecnnical Specification limit 7.0E-8 uC1/cc*, the classification of the event is RADIOLOGICAL ALERT.
Inform the Shift Supervisor of the Radiological Alert Condition.
Then proceed with Step 25.
NOTE: Technical Specification Limit = 7.0E-9uC1/cc 10x Technical Specification Limit = 7.0E-BuC1/ce, as stated above.
O PORM 372 22 3643
- _ _