ML20049H407
| ML20049H407 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 02/10/1982 |
| From: | NORTHERN STATES POWER CO. |
| To: | |
| Shared Package | |
| ML20049H405 | List: |
| References | |
| F3-2-01, F3-2-1, NUDOCS 8203020749 | |
| Download: ML20049H407 (42) | |
Text
.
PAGE 1 OF 2
EMERGENCY PLAN IMPLEMENTING PRAIRIE ISLAND NUCLEAR PROCEDURES GENERATING PLANT 1
NORTHERN STATES POWER COMPANY Number: TABLE OF CONTENTS Rev: 6 History Copy A
Retention Time:
5 Years d)
_. TITLE:
SUFt' Mad Ptsk EMERGENCY PLAN IMPLEMENTING PROCEDURES TABLE OF CONTENTS i
NUMBER TITLE REV #
1 Onsite Emergency Organization 1
2 Classifications of Emergencies L
3 Responsibilities During a Notification of Unusual Event 1
4 Responsibilities During an Alert, Site, or General Emergency 2
5 Emergency Notifications 3
6 Activation and Operation of Technical Support Center 1
7 Activation and Operatioa of Operational Support Center 1
8 Recommendations for Offsite Protective Actions 0
9 Emergency Evacuation 0
10 Personnel Accountability 1
11 Search and Rescue 1
12 Emergency Exposure Control 1
13 Offsite Dose Calculations 1
34 Onsite Radiological Monitoring 1
15 Responsibilities of the Radiation Survey Teams During a Radioactive Airborne Release 2
/gb EP-402-B,28 8203020749 B20223 PDR ADOCK 05000282 F
- ~ = =.-. _ -.
a Table of Contents Page 2 Rev. 6 NUMBER TITLE REV #
l 16 Responsibilities of the Radiation Survey Teams During a Radioactive Liquid Release 1
17 DELETED 4
18 Thyroid Iodine Blocking Agent (Potassium Iodide) 0 a
j 19 Personnel and Equipment Monitoring and Decontamination 0
20 Manual Determination of Radioactive I
Release Concentrations 2
1 21 Establishment of a Secondary Access Control Point 2
22 Prairie Island Radiation Protection Group Response to a Monticello Emergency 1
23 Emergency Sampling 1
24 Record Keeping During an Emergency 0
25 Re-Entry 1
26 Drills 0
t 27 Training 0
i 28 Revi^ew and Revision of Emergency Plans 0
29 Emergency Security Procedures 0
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EP-902-B,29 y
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.an
f' PAGE 1 OF 40 i
l l EMERGENCY PLAN IMPLEMENTING l
l PRAIRIE ISLAND NUCLEAR PROCEDURES l
l GENERATING PLANT l
l NORTHERN STATES POWER COMPANY Number:
F3-2 Rev: 1 l
l History Copy l m
t g
Retention Time:
5 Years l
ll Reviewed By:
Jc/
l l
C,d l TITLE:
l i
l Supt.~RadPrge'ction l
CLASSIFICATIONS OF l
l Approved By:
l EMERGENCIES l
l 7,[Oww, [
l l
l Pla t anager/ ' '
l l
l OC#:
2-10 l l
l
_ t l
l l
l l
l l
1.0 PURPOSE l
I l
l The purpose of this procedure is to specify the Emergency Action l
l Levels that indicate that an emergency condition exists and to l
l properly classify the emergency into one of the four graded levels of l
l emergency classifications.
l l
l l
2.0 APPLICABILITY l
l l
l This instruction SilALL apply to all Shift Supervisors, Control Room l
l Operators, Shift Technical Advisors and Emergency Directors.
l Q
l I
V l
3.0 PRECAUTIONS l
l 1
4 l
3.1 The operator should believe his indications and take at. tion l
j l
based on those indications, however, he shall attempt to l
1 l
verify his indications by checking secondary or coincident l
l indicators.
l l
l l
3.2 Cont 2nuously monitor the control room instrumentation, radia-l l
tion monitors, or any other developments which would be l
l indicative of further system degradation.
Be prepared to l
l escalate to a more severe emergency classification.
l l
l l
l l
4.0 DISCUSSION l
l l
l 4.1 Definitions l
l l
l 4.1.1 Notification of Unusual Event - events that are in l
l progress or have occurred which indicate a potential l
l degradation of the level of safety of the plant.
l l
t I
l l
No releases of radioactive material requiring offsite l
l response or monitoring are expected unless further l
l degradation of safety systems occurs.
l Os l
l l
1 I
l
F3-2 Rev. 1 PAGE 2 e
4.1.2 Alert - events are in progress or have occurred which involve actual or potential substantial degradation of the level of safety of the plant.
It is the lowest level of emergency classification when some necessity for emergency planning and offsite response is necessary.
Any releases expected are limited to small fractions of the EPA Protective Action Guideline exposure levels.
4.1.3 Site Emergency - events are in progress or have occurred which involve actual or likely major failure of plant functions needed for protection of the public.
Any releases are not expected to exceed the EPA Protective Action Guideline exposure levels except near the site boundary.
4.1.4 General Emergency - events are in progress or have occurred which involve Os actual or imminent substantial core 7
degradation or melting with a potential for loss of containment integrity.
Releases during:a General Emergency can be reasonably expected to exceed the EPA i
Protective Action Guideline exposure levels offsite for more than the immedi-L ate site area.
4.1.5 Emergency Action Levels (EAL) - specific instrument readings, surface or airborne contamination levels or radiation dose rates that designate a specific emergency class requiring emergency measures for that class.
t 4.2 Summary i
Attached to this procedure is a Summary of Emergency Action Levels. This table identifies i
the four emergency classifications, the initiating.
conditions (s), emergency actions levels for each classification, and, where applicable, specific instruments and indications to be used to detect and classify an emergency.
O L
F3-2 Rev. 1 PAGE 3 The emergency action levels for each classification and the instrument readipgs and indications listed do not reflect a complete list of instrumentation that will show abnormal indications but does list those key l
parameters useful in classifying the event.
The Summary of Emergency Action levels lists all the initiating conditions as required by Appendix 1 of NUREG-0654 and some accidents analyzed in the Prairie Island FSAR.
5.0 PROCEDURE 5.1 Any significant event that may be classified as an emergency condition shall be reported to the Shift Supervisor immediately.
I i
l NOTE: The events may be instrumentation l
l readings or visual observations made l
l by plant personnel.
l l
l Attempt to verify the initial indication by comparing
)
5.2 the indication to redundant instrument channels or to other related parameters, visual observations, and field reports as applicable.
5.3 Assess the situation and determine the emergency classification, using the guidelines of Attachment 1.
i I
l l NOTE: Personnel should become familiar with l l
Attachment I during training sessions. l l
1 5.4 Take immediate actions, using applicable plant operating procedures, Sections C and E of the Operations Manual, to return the plant to normal (or cold shutdown, if determined to be necessary).
5.5 Declare the appropriate emergency' classification and perform actions as specified in the appropriate responsibility procedure applicable to emergency classification:
5.5.1 For a Notification of Unusual Event, proceed to
.F3-3
.s,/
5.$.2 For an Alert, Site or General Emergency, proceed to F3-4.
i
1 i
4 a
i F3-2 Rev. 1 l
4 PAGE 4 l
l r
i 9 5.6 Continue to assess and respond to the emergency a
l condition.
4 7
l I
j' l NOTE: Watch for changing parameters or l
j l
visual indication of further system l l
l
. degradation and be prepared to es-l l
calate to a more severe emergency l
l classification as indicated by the l
l Emergency Action Levels in Attach-l 4
l ment 1.
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PAGE 5 i
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SUMMARY
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i EMERGENCY ACTION LEVELS i
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F3-2 Rsv. s PAGE 6
SUMMARY
OF EMERGENCY ACTION LEVELS Condition Initiating Condition Indication Used Emergency Classification 1
1.
Safety System ECCS initiated and dis-1.
First out on reactor trip panel:
Alert Functions charge to vessel.
a.
Containment High Pressure NOTE: FSAR Sections SI-Reactor Trip; or 14.2.4 b.
A Steam Generator Lo-Lo 14.2.5 Pressure SI; or 14.2.6 c.
B Steam Generator Lo-Lo 14.3 Pressure SI; or d.
Pressurizer Lo Pressure SI P
and 2.
Confirmation from indicators:
a.
2/3 High Containment Pressure (4psig) PI-945, PI-947, PI-949; or b.
2/3 Lo Steam Line Press. Loop A (500 psig) PI-468, PI-469, PI-482A; or c.
2/3 Lo Steam Line Press. Loop B (500 psig) PI-478, PI-479, PI-483A; or d.
Lo Prz. Press (1815 psig)
PI-429, PI-430, PI-431 and t
3.
Confirmation of SI Flow indicated by FI-925 and FI-924.
i EI 4.
Manual SI-Reactor Trip initiated if Auto SI did not occur at confirmed
' indicator setpoints (#2 above) or when pressurizer level is off scale low on at least 2/3 channels, LI-426, LI-427, LI-428.
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m Rev. 1 PAGE 7 Condition Initiating Condition Indication Used Emergency Classification
.l.
Safety Systems Loss of Contair. ment inte-Loss of Containment Integrity, defined Notification of Unusual Functions (Cont'd) grity requiring shutdown by Technical Specification 3.8, Event by technical specification which requires a unit shutdown, as determined by the Shift Supervisor.
Loss of engineered safety Engineered Safety Feature found
. Notification of feature requiring shutdown inoperable, as defined by Unusual Event by Technical Specification Technical Specification 3.3, which requires a unit shutdown, as determined by the Shift Supervisor.
Loss of fire protection Loss of fire protection systems, Notification of system function requiring defined by Technical Specificatica Unusual Event shutdown by Technical 3.14, which requires a unit shutdown, Specification as determined by the Shift Supervisor.
Failure of a safety or Pressurizer safety or relief valve Notification of relief valve in a safety opens and then fails to reset, as Unusual Event related system to close indicated by:
following reduction of applicable pressure.
- 1. (a) Annunciator " Pressurizer Safety / Relief Valve Flow"; and (b) Annunciators; (1) " Pressurizer Power Relief line High Temp; or (2) " Pressurizer Safety Valve line A or B High Temp" EE (c) Safety / Relief line high Temper-ature indicated by
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Condition Initiating Condition Indication Used Emergency Classification 1.
Safety Systems (1) Pressurizer safety valve Functions (Cont'd) outlet temperature, TI-436 >
225*F; or (2) Pressurizer safety valve outlet temperature, TI-437 >
225*F; or (3) Pressurizer relief valve outlet temperature, TI-438 >
225*F.
Steam Generator safety or relief valve opens and then fails to reset, as indicated by:
1.
Visual and/or audible indication at vent. stacks of open steam generator safety or relief valve; and 2.
Shift Supervisor's opinion 2.
Abnormal Primary Primary system leak rate 1.
Primary system leak rate, other Notification of Le.k Rate.
from unidentified or uncon-than controlled leakage sources, Unusual Event trolled sources exceeding exceeds Technical Specification Technical Specifications 3.1.c; and 2.
Requires a unit shutdown, as determined by the Shift Supervisor.
Primary coolant leak rate
- 1. (a) Decreasing pressurizer level, Alert greater than 50 gpm as indicated by LI-426, LI-427, LI-428; or (b) High radiation levels in contain-ment, as indicated by:
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PAGE 9 C:?.dition Initiating Condition Indication Used Emergency Classification 2.
Abnormal Primary R2 High Alarm - 50mR/hr; or Leak Rate (Cont'd)
R7 High Alarm - 50mR/hr; or R-11 (Containment Positiog)
High Alarm - 5 x 10 eps, or
' R-12 (Containment Positlag)
High Alann - 6 x.10 cpe; and
- 2. Annunciator " Charging Pump in Auto High/ Low Speed"; and
- 3. Charging line flow (FI-128B) greater than 50 gpm more than Letdown Flow (FI-134).
i l NOTE: Rapid Temperature decreasel l
in RCS results in same l
l indications however no l
t l
primary coolant leak rate.]
I I
Loss of. coolant. accident 1.
No Pressurizer Level indicated Site Area Emergency
.with leak rate in excess of by LI-426, LI-427, LI-428 i
available pump capacity (Charging, High Head In-
,a_nd jection, and Low Head In-jection).
2.
All available pumps running as
=
1 indicated by the red light at t
the switch.
Small'LOCA and initially 1.
LOCA has occurred; and General Emergency successful ECCS. Subsequent failure of containment heat 2.
Inadequate. containment cooling removal systems over several exists, as indicated by:
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PAGE 10 Candition Initiating Condition Indication Used Emergency Clasaification 2.
Abnormal Primary hours could lead to core Leak Rate (Cont'd) melt and likely failure of (a) Containment temperature has containment.
become excessive, > 300*F, and is still rising; or (b) Containment pressure > 23 psig with minimum containment pressure suppres-sion equipment not available:
(1) No fan cooler units operating and less than two spray pumps;
?E (2) No spray pumps operating and less than four fan cooler units; EE (3) Less than two fan cooler units running with one spray pump.
Small and large LOCA's 1.
Loss of coolant indicated by:
General Emergency with failure of ECCS to perform leading to (a) (1) Pressurizer low pressure severe core degradation trip (1900 psig); or or melt in from minutes RCS pressure decreasing to hours. Ultimate failure uncontrollably; of containment likely for melt sequences.
and (2) High containment pressure; or High containment humidity; or High containment sump levels; or High containment radiation levels and (3) Steam Generator's A and B pressures equal
1 PAGE 11
/
Condition Initiating Condition Indication Used Emergency Classification 2.
Abnormal Primary
--or Leak Rate (Cont.'d)
(b) (1) Decreasing RCS pressure; and (2) Loss of subcooling margin
((10 F) and 2.
Fuel Damage indicated by:
- a. R48 High Alarm - 200 R/hr; or R49 High Alarm - 200 R/hr EE
Loss of ECCS indicated by (a) High head SI failure; or (b) Low head SI failure.
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R:v. I PAGE 12 Ccadition Initiating Condition Indication Used Emergency Classification 3.
Abnormal Coolant Abnormal coolant tempera-At Steady State Power Operations; Notification of Temperature /
ture and/or pressure or Unusual Event Pressure abnormal fuel temperatures
- 1. Tav8 > 564*F; or--
outside of Technical Specification limits.
- 2. RCS pressure > 2385 psig; or
- 3. RCS pressure ( 2205 psig, and core exit temperature > 620*F, as indicated by a valid thermacouple; I
- 4. Core Subcooling Margin ( 10*F.
4.
Abnormal Prima ry/
Primary / Secondary leak When shutdown commences, as deter-Notification of Secondary Leat rate exeeding Technical mined by the Shift Supervisor Unusual Event Specification of 1.0 gpm and Duty Engineer requiring a unit shutdown Failure of -team generator
- 1. First out on reactor trip panel:
Alert tube (s) resulting in
" Pressurizer Low Press Sl" ECCS initiation and
- 2. Confirmation from Prz. Press indi-cators, PI-429, PI-420, PI-431, (2/3 Low pressure, 1815 psig).
and
l F3-2
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Rev. 1 PAGE 13 Condition Initiating Condition Indication Used Emergency Classification
- 4. Abnormal Primary /
- 3. Annunciators:
Secondary Leak
- a. "A SG High Water Level" (Cont'd) or
- b. "B SG High Water Level" and
- 4. Confirmation from SG level indi-cators:
- a. LI-461, LI-462, LI-463 (2/3 greater than 67%)
or
- b. LI-471, LI-472, LI-473 (2/3 greater than 677.)
- 5. Safety injection flow indicated by FI-925 and FI-924 and pump
' scharge pressure corresponding i
to flow Failure of steam generator
- 1. First out on reactor trip panel:
Site Area Emergency l
tube (s) resulting in ECCS
" Pressurizer low pressure SI" l
initiation and, loss of offs :.e poieE and
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- 2. Confirmation from Prz. Press indicators: PI-429, PI-430, PI-431 (2/3 low pressure, 1815 psig)
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- 3. Annunciators:
l 1
- a. "A SG tlater Level.High" l
or i
1
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PAGE 14 Condition Initiating Cecdition Indication Used Emergency Classification i
- 4. Abaorsal/ Prima ry
- b. "E SG Water Level High" Secondary Leak I
(Cont'd) and 1
- 4. Confirmation from SG level indi-cators:
- a. LI-461, LI-462, LI-463 (2/3
)
greater than 67%)
I or
- b. LI-471, LI-472, LI-473 (2/3 l
greater than 671) r j
and l
l I
- 5. Safety injection flow indicated by l
FI-626 and FI-928 l
and j
- 6. All of the following indicators:
l
- a. 4.16 KV bus voltage (O Volts) l Buses 11-14 and 21-24
[
and
- b. D1 and D2 generators rur.aing L
and closed in on safeguard I
buses:
(1) D1 & D2 Tach, (* 900 rpm) f (2) D1 & D2 Volts, (4260-43S0 1
Volts)
(3) Safeguard breakers closed
[
Bus 15, Breaker 15-2 Bus 26, Breaker 26-2 Bus 16, Breaker 25-6 Bus 25, Breaker 16-7 2
b i
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r3-2 Rev. 1 PAGE 15 Cendition.
Initiating Condition
-Indication Used Emergency Classification
- 5. Core Fuel Fuel Damage Indication
- 1. Letdown line radiation monitor Notification of Damage R-9 indicates greater than 1 R/hr Unusual Event as confirmed by portable instru-mentation EE
- 2. High coolant activity sample:
- a. exceeding Technical Specifi-cation.for total specific activity in primary coolant EE
- b. erceeding Technical Specifi-cation limit on primary coolant iodine activity which requires a unit shutdown.
Severe loss of fuel
- 1. Very high coolant activity Alert cladding sample; 1000 pCi/cc iodine equiva-lent, as determined by chemical analysis EI
- 2. Letdown line radiation monitor R-9, indicates greater than 10 R/hr, as confirmed by portable instrumentation t
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F3-2 Rzv. 1 PAGE 16
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Condition Initiating Condition Indication Used Emergency Classificatior.
' 5. Core Fuel Degraded. core with
- 1. Degraded core, indicated by:
Site Area Emergency
. Damage (Cont'd) possible loss of coolable geometry
-(a) High primary coolant activity,
) 1000 pCi/ce; or (b) High core exit temperature, indicated by exit thermocouples,
) 700*F; or (c) Inadequate subcooling margin,
( 10*F;.ojE (d) Indication of core uncovered i
(Shift Supervisor's opinion) and
- 2. Loss of coolable geometry, indicated by:
(a) Core 6T increasing; or (b) No core AT; or l
(c) Shift Supervisor's opinion 1
Loss of 2 of 3 fission The first two of-the Initiating General Emergency product barriers with a Conditions exist and the third potential loss of 3rd is possible.
barrierJ(e.g., loss of primary coolant boundary,.
(a).Very high coolant activity sample, 1.
clad. failure, and high 1000 pCi/cc Iodine equivalent as deter-potential.for loss of mined by chemical analysis; and containment).
(b) Primary system leak in excess of 1000 gpm as indicated by safety injection flow greater than 1000 gpm (FI-924 and FI-925) and pump discharge pressure corresponding to flow r
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F3-2 R:v. 1 PAGE 17 Condition Initiating Condition Indication Used Emergency Classification
- 5. Core Fuel 2.
Valid high radiation levels in Damage (Cont'd) containment, as indicated by:
(c) R-48 High Alarm - 200 R/hr; or (b) R-49 High Alarm - 200 R/hr; and
- 3. Minimum containment pressure suppression equipment is not available:
- a. No fan cooler units operating and less than two spray pumps or
- b. 50 spray pumps operating and less than four fan ecoler units EE
- c. Less than two tan cooler units running with one spray pump with (1) Annunciator "High Containment Pressure" with 2/3 greater than 4 psig, PI-945, PI-947, PI-949 and containment pressure increasing and (2) Annunciator " Containment Spray Activated", with 2/3 greater than 23 psig PI-945, PI-947, PI-946, PI-948, PI-950
- 6. Secondary Coolant Rapid depressurization of 1.(a) Steam Generator A/B Pressure Nottfication of Anomaly Secondary Side Differential, 2 100 psig; and Unusual Event (b) High Containment Pressure, 4 psig;
_ _ - - ~ -.. - -.. _ -. -.. -. _ -. _ _
1 PAGE 18 Condition Initiating Condition I.2dication Used Emergency Classification I
l
- 6. Secondary Coolant or Anomaly (Cont'd) l 2.(a) Hi Steau Flow,.745 x 10 lb/hr; j
and
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(b) Lo-Lo Tavg,540*F l
I L
j or I
- 3. Steam line pressure Safety Injection Signal; i
HE l
- 4. Failed Open Steam Dump, Relief, i
l or Safety Valve; O_E l
l S. Shift Supervisors opinion l
i Rapid depressurization
- 1. First out on reactor trip panel:
Alert j
of secondary cide (any
- a. "A Stear Generator Lo-Lo i
Sten:n Line Break with pressure SI" j
0-50 gpm primary to or secondary icah rate)
- b. "B Steam Generator Lo-Lo l
i i
Note:
FS/P 16.2.5 Pressure SI" I
i l
and l
- 2. Confirmation froa Steau Generator i
pressure indicators:
I
- a. PI-468, PI-469, P!-482 (2/3 J.
Iess then 500 psig),
l EE
- b. PI-473, PI-477, PI-483 (2/3 t
I less than 500 psig)
I l
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1 PAGE 19 i
I i
l Condit. ton laitiating 4.cadition Indicatien Used Emergency Classification
- 6. Secondary Coolant and, if primary to secondary Anomaly (Cont'd) leak rate is occurring:
l
- 3. Hi radiation on:
R-15 Air Ejector Rag Monitor, a.
greater than 5 x 10 cpm; I
j and i
i 7
- 4. Leak rate as calculated Steam line break with
- 1. First out on reactor trip panel:
Site Area Emergency t
greater than 50 gpm pri-
- a. "A Steam Generator Lo-Lo i
t.ury to secandary Pressure SI" l
leakage an* mdication
- b. "B Steam Generator Lo-Lo i
of fue3 dan 2 v. e Pressure SI" l
l and
- 2. Confimation froca Steam Generator pressure indicators:
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j
- a. PI-468, PI-469, PI-482 (2/3 i
less than 500 psig),
l E
- b. PI-478, PI-479, PI-433, (2/3 4
less than 500 psig) and I
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PAGE 20 Ccadition Initiating Ccadition Indication Used Emergency Classification
- 6. Secondary Ccolant
- 3. Indication of primary to secondary Anomaly (Cont'd) leakage by:
- a. R-15 Air Ejector Rad Mcnitor, 4
) 5 x 10 cpm; and
- b. leak rate calculation > 50 gpm; and
- 4. Indication of fuel damage:
- a. Primary sample > 1000 pCi/cc Iodine 131 equivalent; or
- b. Steam Line Monitor in valid mode:
R-51, 100 mR/hr; or R-52, 100 mR/hr.
or
- c. High Containment Radiation levels indicated by:
R48 High Ala rm - 200 R/hr; or R49 High Alarm - 200 R/hr; Transient initiated by
- 1. a. Loss of main condenser which General Emergency loss of feedwater and includes all Condensate and condensate systems Main Feed Pumps; and (principal heat removal
- b. Loss of all Aux Feedwater; and system) followed by
- c. No High Head Safety Injection failure of emergency feedwater system for or extended period. Core melting possible in 2, a. Successful High Head Safety several hours. Ultimate injection with failure of containment (1) Loss of main condenser which likely if core melts.
includes all Condensate and Main Feed Pumps; and (2) Loss of all Aux Feedwater and
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F3-2 Rev. 1 PAGE 21 Condition Initiating Condition Indication Used Emergency Classification
- b. Either of the following not established within 30 minutes:
1 (1) Aux Feedwater; or i
(2) Normal RER Cooling
'7. Radiological Airborne Radiological Any of the following gaseous effluent Notification of Effluents effluent Technical monitors in valid alarm mode:
Unusual Event Specification limits exceeded 3
Note: FSAR Section
- 1. 1R-22 (5 x 10 cp,)
14.2.2
- 2. 2R-22 (5 x 10 cpm)
Due to release rate of radioactive gases (except halogen and particulates 3
with T 1/2 > 8 days) averaged over I hour exceed (fC)I
= 1.1 x 105,3/sec I
per Technical Specification 3.9.B.I.b Liquid Radiological Any of the following valid liquid Notification of effluent Technical effluent monitor readings which Unusual Event Specification limits exceed:
exceeded (1) R-18 High alarm setpoint and
' Note: FSAR Section isolation valve fails to 14.2.2 close.
(2) R-19 High alare setpoint (while blowdown is directed to river) and isolation valve fails to close.
Due to release rate of radioactive I
liquids exceeding values listed in 10CFR20, Appendix B, Table II, Column 2, per Technical Specifica-tion 3.9.A.I.b.
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. y3 2 R:v. 1 PAGE 22 Condition Initiating Condition Indication Used Emergency Classification Ji. Radiological Airborne Radiological Any of the following' gaseous effluent Alert Effluents effluents greater than' monitors in valid alarm mode:
I (Cont'd).
ten times Technical 4
7 Specification instantan-
- 1. IR-22 Hi-Hi Alarm (4 x 10 cpm) 4 cous limits (an instan-
- 2. 2R-22 Hi-Hi Alarm (4 x 10 epm)
L taneous rate which, if
'3. IR-50 Greater Than 1.2 mR/hr continued for over two
- 4. 2R-50 Greater Than 1.2 mR/hr hours, would result in about I mR at the site Due to release rate of gases exceeding l
. boundary noder average Technical Specification 3.9.B.I.b by meterological conditions) a factor of 10.
i i
Airborne Effluent
- 1. Any of the following valid gaseous Site Area Emergency monitors detect levels effluent monitor readings:
corresponding to greater than:
(a) 1R-50 Hi (70 mR/hr)
I
- 1. 50 mR/hr whole body-(b) 2R-50 ?!i (70 mR/hr) i for one-half hour or
. 2. 250 mR/hr for one-half or hour for the thyroid, or
- 3. 500 mR/hr whole body
- 2. Offsite dose projection calculations for two minutes, or result in the following dose projec-l
- 4. 2500 mR/hr to the tions at the site boundary, greater thyroid for two minutes than:
at the site boundary' I
for adverse meterology (a) 50 mR/hr whole body for 1/2 hour; OE v.s (b) 250 mR/hr thyroid for 1/2 hour; y
(c) 500 mR/hr whole body for 2 minutes; 2E (d) 2500 mR/hr thyroid for 2 minutes i
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'F3-2 R:v.-l PAGE 23 Condition Initiating Condition Indication Used' Emergency Classification 7.
Radiological
- 3. Radiation Survey Teams measure Effluents dose rates greater than 50 mR/hr for
'(Cont'd) 1/2 hour or greater than 500 mR/hr for 2 minutes (beta + gamma) at the site boundary; EI
- 4. Radiation Survey Teams measure thyroid dose rates (equivalent 1-131 Concentrations), at the site boundary, which are greater than:
T (a) 250 mR/hr for 1/2 hour, or (b) 2500 mR/hr for 2 minutes.
Effluent monitors detect
- 1. Any of the following gaseous General Emergency levels corresponding to:
effluent monitor readings:
1.
IR/hr whole body, or
- 2. SR/hr thyroid (a) 1R-50 Hi-Hi Alarm (1000 mR/hr) at the site boundary (b) 2R-50 Hi-Hi Alarm (1000 mR/hr) under actual meteorologi-cal conditions or,
- 2. Of fsite dose projection calcula-tions result in the following dose projections at the site boundary, greater than:
(a) 1R/hr whole body; or (b) SR/hr thyroid; or or,
l F3-2 l
2 Rev. 1 i
j PAGE 24 I
1 Condition
- itiating Condition Indication Used Emergency Classification.
l I
- 7. Radiological
- 3. Radiation Survey Teams measure Effluents dose rates greater than IR/hr 1
(Cont'd) whole body t
I l
or l
i
- 4. Radiation Survey Teams ceasure f
l thyroid doce rates (equivalent I-131 Concentrations), at the j
site boundary, which are greater l
than SR/hr.
l 4
Radiation levels or
- 1. Unexpected radiation levels Alert f
airborne centamination above 1000 mR/hr l
uhich indicate a severe
\\
degradation in the control or l
l of r dicactiva materials l
(e.g., increare of factor
?. Widespread contamination ebove of 1000 in direct radia-10,000 dpn/ !00,r n' beta-garsa er tion reading within 500 dpe/100 ca,~ alpha activity
[
l fa cility).
i j
C. tiajor I'lectrica}
Loss of Offrite Power All of the following indicators:
Notification of Failures Note-FSAR Sectior
'!. 4.16 KV Bus Voltage (O Volts)
Unacual Event l
l 14 1.3
- a. Eus 11(21), 4:1G304 (4172806) l
)
- b. Bus 12(22), 411c305 (4172E05)
- c. Bus 13(23). 4119306 (4172306) d Bus 14(24), 4119307 (4172807)
I l
and i
l i
i i
-,,.. - -, -,. - -,, - - -.. - - - - -....., -. - -, -.. - -, - -.. -, - - - - - - - -, -. - - - - - - ~ ~ - -. - - - - - - - - - - -. - - - - - -. - - - - - - - - - - - - - - -. - - - - - - _ _
~
'[ }
F3-2 a- /
'd R2v. I PAGE 25 Ctadition.
Initiating Condition Indication Used Emergency Classification'
- 8. Major Electrical'
- 2. D1 & D2 Generators up to Speed Failures.(Cont'd) and Voltage and Supplying Safe-guard buses:
D1 (D2) Tach (900 rpm) a.
b.
D1 (D2) Gen. Volts (4260-4380 Volts) c.
Safeguard bus breakers closed:
Bus 15, Breaker 15-2 Bus 26, Breaker 26-2 Bus 16, Breaker 25-6 Bus 25, Breaker 16-7 Loss.cf onsite AC Power Loss of both diesel generators Notification of Capability Unusual Event Loss of offsite power All of the following indicators:
Alert and loss of all onsite
- 1. 4.16 KV Bus Voltage (0 Volts)
AC power (See Site Area
- a. Bus 11(21), 4119304 (4172804)
Emergency for extended
.b. Bus 12(22), 4119305 (4172805) loss).
- c. Bus 13(23), 4119306 (4172806)
~ Note: FSAR Section
- d. Bus 14(24), 4119307 (4172807) 14.1.11 and
- 2. Loss of both ' diesel generators Loss of offsite power All of the following indicators:
Site Area Emergency and loss of'onsite AC
- 1. 4.16 KV Bus Voltage (O Volts) power for more than
- a. Bus 11(21), 4119304 (4172804) 15 minutes-
- b. Bus 12(22), 4119305 (4172805)
O (D
h)
I F3-2 N )n s
%)
Rev. I U
PAGE 26 Conditior.
Initiating Condition Indication Used Emergency Classification
- 8. Major Electrical
- c. Bus 13(23), 4119306 (4172206)
Failures (Cont'd)
- d. Bus 14(24), 4119307 (4172807) and
- 2. Loss of both diesel generators and
- 3. Blackout has occured fer core than 15 minutes.
(
l failure of cir:,ite and
- 1. Loss of AC power, (offsite &
General Emergency I
i onsite power along with onsite) indicated by:
}
total loss of cmergency feedvater makeup capability
- a. 4.16 KV Bus Voltage (O Volts)
[
j for several hours. This (1) Bus 11(21), 4119304 (4172804) would lead to eventual (2) Bus 12(22), 4119305 (4172605)
'l core uelt at.d likely (3) Bus 13(23), 4119306 (4172806) failure of containment.
(4) Bus 14(24), 4119307 (4172807) and
- b. Loss of both diesel generators and
?
I
- 2. Turbine driven Aux Feedwater pumps inoperable for several hours.
I i
Loss of all onsite DC All of the following annunciators Alert l
power (See Site Area received:
[
Emergency for extended loss).
?
i
]
1 l
9 l
4
- ee
_-,.-----,------.ee,mwe.~ee,
. c----
--.e
I F3-2 Rev. 1 PAGE 27 Candition~
Initiating Condition Indication Used Emergency Classification l
t
- 8. Major Electrical
- 1. " Safeguard Train A DC Control i
Failures (Cont'd)
Room Supply Failure" and
- 2. " Safeguard Train B DC Control Room Supply Failure" NOTE: 4 annunciators numbered:
47018-0501 47018-0502 47518-0501 47518-0502 t
Loss of all vital onsite All of the following annunciators Site Area Emergency
-DC power for more than received:
15 minutes.
- 1. " Safeguard Train A DC Control Room Supply Failure" and
- 2. " Safeguard Train B DC Control Room Supply Failure" NOTE:
4 annunciators numbered:
47018-0501 47018-0502 47518-0501 47518-0502 1
and
- 3. Loss of DC Power has lasted more than 15 minutes.
1-
~. -- -
-..e
1 PAGE 28 Ccadition laitiating Cauditica Indication Used Emergency Classification 9.
Control hoos Esacaation of the control As required by the Shift Supervisor Alert room anticipated or re-quired with control of shutdcun systems estab-lished from Hot Shutdown Panels and local stations Evacuation of the control As required by the Shift Supervisor Site Area Emergency room and control of shutdown systems not established from hot shutdown panel and local stations within 15 minutes
- 10. Fire Fire in vital area or on As reported by Fire Brigade Chief Notification of the cont.olled side of the Unusual Event plant Jastieg more than 10 minutes after initial use of fire extinguishing equipment Fire potentially affecting
- 1. Observation that fire could Alert safety systems affect safety systems; and
- 2. Shift Supervisor's opinion Fire comprising the func-
- 1. Observation of major fire that Site Area Emergency Lions of safety systems.
defeats safety systems or functions; and
- 2. Shift Supervisor's opinion
. ~ _. _ _
Y
(
l F3-2
\\
d Rev. 1 PAGE 29-Condition -
Initiating Condition
- Indication Used Emergency Classification
- 11. Plant Shutdown
- Nonfunctional indications
- 1. Annunciators:
Notification of Functions
- or alarms in the Control
- a. "NSSS Annunciator System Unusual Event i
. Room requiring a plant Power Failure" shutdown or
- b. " BOP' Annunciator System i
Power Failure" and
- 2. Failed indicatiot. as determined
[
by the Shift Supervisor l
Ali alarm (aununciators)
Annunciators received:
Alert lost
- 1. "NSSS Annunciator System Power Failure" V
and
- 2. " BOP Annunciator System Power Failure" t
- All alarms (annunciators) is.munciators received:
Site Area Emergency I
lost while unit is not-
- 1. "NSSS Annunciator System Powe.
in cold shutdown or during Failure"
.E plant transient or
- 2. " BOP Annunciator System Power Failure" t
during a. transient, as determined by the. Shift Supervisor L>-
L e
4 s.+--
,.-.,n+
+-,w,.,-,
---..,,..e.-,-
n,
-n,
1
(-)
(_,)
F3-2
)
y Rev. 1 PAGE 30
' Condition Initiating Condition Indication Used Emergency Classification
- 11. Plant Shutdown Complete loss of functions As determined by Shif t Supervisor Alert Functions (Cont'd) needed for plant cold shutdown Complete loss of functions As determined by Shift Supervisor Site Area Emergency needed for plant hot shutdown Turbine Failure requiring
- 1. High Vibration (7 mils)
Notification of a re "---/ turbine trip Unusual Event and
- 2. High-High Vibration (14 mils) as indicated by Control Room recorder and alarms Turbine Failure causing
- 1. High Vibration (7 mils)
Alert casing penetration and
- 2. High-High Vibration (14 mils) as indicated by Control Hoon.
recorder and alarms and
- 3. As determined by Visual Inspectica
(a~ -)
,r'%
(7--)
F3-2
()
/
Rev. 1 PAGE 31 Condition-Initiating Condition Indication Used Emergency Classification
- 11. Plant Shutdown Failure of the reactor
- 1. Any Reactor Trip Setpoint and Alert Functions (Cont'd) protection system to redundancy requiring a reactor initiate and complete trip has been exceeded a trip which brings the reactor subcritical and
- 2. Intermediate range detector output not decaying Transient requiring
- 1. Failure to 'uring reactor subcriti-Site Area Emergency operation of shutdown cal with control rods; and systea.s with failure to scrat (coatinued power
- 2. No indication of core damage; and generation
'.ut no core damage immectately evi-
- 3. Shift Supervisor's opinion that dent).
a transient is in progress Transient requiring opera-
- 1. Reactor remains critical after General Emergency tion of shutdown systems trip; with failure to scram which results in core and damage or additional failure of core cooling
- 2. Indication of overpressurization and makeup systems (which of RCS because of inability to could lead to corb melt) remove heat, as indicated by:
(a) RCS pressure greater than safety valve setpoint (2485 psig); or (b) Rapidly increasing containment pressure an_d temperature
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F3-2
~~
pey, 1 PAGE 33 Condition Initiating Condition Indication Used Emergency Classification
- 12. Fuel Handling Major damage to spent
- 1. For fuel damage in containment:
Site Area Emergency Accident (Cont'd) fuel in containment or (a) Any of the following valid fuel handling building radiation monitor readings:
(e.g., large object (1) R48 200 R/hr; or damages fuel or water (2) R49 200 R/hr loss below fuel level) and (b) Shift Supervisor's opinion or
- 2. For fuel damage in the Spent Fuel Pool:
(a) Valid Radiation Monitor readings on:
(1) R50 70 mR/br; or l2) Pd 1 R/hr a_nd (b) Shift Supervisor's opinion
- 13. Cociant Pump Coolant pumn seizure
- 1. RCP Trip (over current 86 Alert leading to iuel f ailt.re.
lock-out);
Note FSAN Section 14.1.8 and_
- 2. Primary sample analysis indicating fuel failure () 1000 pCi/cc iodine 131 equivalent)
-. ~... -.. -
1 PAGE 34 l
e I
t Condition Initiat.ing Londition Indication Used Emergency Classification i
- 14. Serious or Iransportation of a As determined by the Shift Supervisor Notification of I
i Fatal Injury aeriously or fatally Unusual Event
)
injured (may or may n %
NOTE: Serious injury is considered l
involve contamination; to be one that will require l
individual from site to admission for treatment or hospital for treatment observation for an extended l
period of time (greater than i
1 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />)
{
s f
L t
i
- 15. Security security threat or Per security plan Notification of l
Threat attempted sabotage Unusual Event j
i l
Ongoin;; security Per security plan Aler;
(
compromisc
[
Ir.ainent lors of ler security plan Site Area Emergency physical control of plant 1
i 1.oss of physical control ler security plan General Emergency l
of plant 4
i 1
l
- 16. Jiazards to Aircraft crash onsite
- 1. Visual observation by plant Noti fication of i
Plant Operation or unusual aircraft personnel and/or plant security Unusual Event l
activity ov>_r facility personnel; and j
1
- 2. Reported to the Shift Supervisor I
i i
i F
l
F3-2 i
Rev. 1 i
PAGE 35 I
I i
l Condition Initiating Condition Indication Used Emergency Classification f
i
{
- 15. Hazards to A1.rc ra t t crash in tne Visual observation by plant Alert f
l P] ant Operation protected area personnel and/or plant security (Cont'd) personnel i
)
I i
I Aircraft. crash within Visual observation by plant Site Area Emergency i
protected area and affect-personnel and/or plant security
{
j ing vital structures by personnel i
j impact or fires 1
j Near or onsite
- 1. Visnal observation by plant Notification of l
j explosioa personnel and/or plant security Unusual Event personnel; and
- 2. Reported to the Shift Supervisor t
1 t
i Known explosion damage Visual observation by plant tiert
(
to facility affecting personnel l
plant operation l
t Severe damage to engi-tisual observation by plant Site Area Emergency t
i neered safety system personnel j
equipment from explo-f I
sions t
L Near or ousite toxic or Gaseous hazards being experienced Notification of tlam:nacle gas release or projected, onsite (out of piant),
Ur.w2al Event
(
as detected by portable instrunentation, which exists in concentrations greater l
than:
)
i l
l l
O G
=
1 PAGE 36 Condition-Initiating Condition Indication Used Emergency Classification i
IC. dazards to (1) 80 ppm hydrazine; or l
"lant. Operation (2) 25 ppm chlorine; or (Cont'd)
(3) 500 ppa ammonia; or (4) explosive limits as detected by explosive meter, and, reported to the Shift Supervisor.
I i
i i
1 Entry into the plant Gaseous hazads being experienced Alert environs of toxic or or projected, within the plant, flammable gases as detected by portable instru-mentation, which exists in concen-trations greater than:
_(1) 80 ppm hydrazine; or (2) 25 ppm chlorine; or i
(3) 500 ppm acconia; or (4) explosive limits as detected by explosive meter, and, reported to the Shift Supervisor Entry of toxic or Gaseous hazards being experienced or Site Area Emergency flammable gases into projected within vital areas,of the
- vital areas plant, as detected by portable instru-mentation, which exists in concentrations i
greater than:
(1) 60 ppm hydrazine; or l
(2) 25 ppm chlorine; or (3) 500 ppn ammonia; or (4) explosive limits as detected by explosive mater, j
and, reported to the Shift Supervisor
}
)
i i
F3-2 Rev. 1 PAGE 37 Condition Initiating Condition Indication Used Emergency Classification
.i
- 16. Ilazards to Missible impacts from Visual observation by plant personnel Alert Plant Operation whatever source on and/or plant security personnel l
(Cont'd) facility j
-Severe damage to engin-Visual observation by plant personnel Site Area Emergency eered safety system from missiles i
i
- 17. Natural Events Any earthquake Annunciator " Seismic Event" received Notification of on the seiscograph Unusual Event i
l i
I l
Earthquake greater than Annunciator " Operational Earthquake" Alert
}
Operational Basis Earth-received on the seismograph quake l
l l
Earthquake greater than Annunciator " Design Basis Earthquake" Site Area Emergency i
Design Basis Earthquake received on the seismograph I
I i
l Any tornado visible frcm Visual observation by plant personnel Notification of site and/or plant security and reported Unusual Event to the Shift Supervisor.
Any tornado striking the Visual observation by plant personnel Alert iacility and/or plant security and reported to the Shift Supervisor.
1 l
I 50 year flood 686' elevation Noti fication of
{
Unucual hvent I
I i
I
. m
_ _ _. _. _ _ _ _ _.. _. -. _. _.. _. _ _.. _. _.. _ _. _ _. ~. _ _. _ _ _. _.
i F3-2 Rev. 1
[
PAGE 38 Candition Initiating Condition Indication Used E.nergency Classification
[
t
- 17. Natural Events Flood levels approaching 692' elevation - requires both units Alert h
(Cont'd) design levels to be shut down r
t Flood levela exceeding 698' elevation - highest level Site area Emergency design levels transformers will function Low water levels being 672.5' elevation - (At 672.5' Notification of experienced or projected elevation, both 11 and 21 cooling Unusual Event
'i j
beyond usual levels water pumps t rip)
I I
/
I l
Low water levels being Approximately 669.5' elevation Alert experienced or projected j
l to be near design levels Low water levels being
- 1. Approximately 666.5' elevation Site Area Emergency f
1 experienced or projected corresponding to loss of set of l
to be greater than design miter gates or loss of one spill-l levels or failure of vital way gate t
equipment with plant not in l
cold shutdown.
or I
i l
- 2. Pfajor vital equipment failure l
l at low water level f
J s
i Sustained winds being Sustained wind speed indicateu by Al e r t.
(
j experienced or projected net tower in excess of 90 mpt l
4 near design levels i
i
{
Sustained winds being in Sustained wind speed indicated by Site Area Emergency 1
excess of design levels act tower, in excess of 100 mph i
a being experienced or pro-i jected with plant ny in cold shutdown t
i l
?
i f
F3-2 Rev. 1 PAGE 39 C.mdition Initiating Condition Indication Used En.e rlen cy Classitication li. Nat. ural Events Any major internal or As determined by the Shift General Emergency (Cont'd) external events (e.g.,
Supervisor and/or Emergency fires, earthquake, sub-Director stantially beyond design i
levels) which could or has caused massive damage to plant systems re-sulting or potential for resulting in large i
releases to the offsite i
environment in excess of the EPA Protective Action Guides l
.5.
Other Conditions that warrant Duty Engineer and Shif t Supervisor Notification of Stat.e and/or local of fi-concurrence Unusual Event cial awareness I
Conditions that require Duty Engineer and Shift Supervisor Notification of plant shutdown under concurrence Unusual Event Technical Specification requirements or involve other than normal con-f trolled shutdown Conditions that warrant Duty Engineer and Shif t Supervisor Alert activat. ion of Technical concurrence Support Center and near-site Emergency Operating Facility
F3-2 Rev. 1 PAGE 40 Condition Initiating Condition Indication Used Emergency Classification i
- 18. Other (Cont'd)
Other plant conditions Shif t Supervisor opinion Site Area Emergency that warrant activation of emergency operating centers and monitoring teams or a precautionary notification to the public near the site i
Other plant conditions Shift Supervisor's opinion General Emergency exist, from whatever source, that make release of large amounts of radio-activity in a short time period possible, e.g., any l
core melt situation.
l l
i L.
^