ML20079P372
| ML20079P372 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/05/1984 |
| From: | Grundstrom R, Kanyo J UNION ELECTRIC CO. |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| Shared Package | |
| ML20079P369 | List: |
| References | |
| 782, EIP-ZZ-00101-01, EIP-ZZ-101-1, NUDOCS 8401310192 | |
| Download: ML20079P372 (60) | |
Text
.
EIP-ZZ-00101 I
December 27, 1983 Revision 1 CALLAWAY PLANT EMERGENCY PLAN IMPLEMENTING PROCZDURE EIP-ZZ-00101 CLASSIFICATION OF EMERGENCIES DEPT. hecaw.dggg,kwA PREPARED BY 3.3. bhhhn RESP.
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~s This procedure contains the following:
Pages 1
through 3
Attachments 1
through 1
Appendices through Checklist through INFORMATION ONLY UNCONTROLLED CO?Y 8401310192 840120 9FPDR ADOCK 05000483 pg
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Proced. No.
EIP-ZZ-00101 g
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1 Table of Contents Section Page Nunber 1.0 Purpose anj 3 cope 1
2.0 Responsibilities 1
3.0 Initiating Conditions 1
4.0 Procedure 1
5.0 Final Conditions 3
6.0 Records 3
7.0 References 3
~3; 8.0 Attachments 3
(U
. - Emergency Action Levels i
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Proced. No. EIP-ZZ-00101
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Rev.
1 i
i CLASSIFICATION OF EMERGENCIES 4
1.0 PURPOSE AND SCOPE 4
The purpose of this procedure is to provide i
guidelines for classification of emergencies and indications for determining conditions at which specific emergency classifications shall be declared.
2.0 RESPONSIBILITIES 2.1 All plant personnel shall immediately report any abnormal condition or event to the Shift Supervisor.
2.2 The Shif t Supervisor is responsible for the in-
[.
itial implementation of this' procedure whenever, in his judgement, the plant status warrants declaration of an emergency.
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r 2.3 The Emergency Coordinator shall use this proce-dure to reclassify emergencies as plant condi-l tiens change.
3.0 INITIATING CONDITIONS l
This procedure is initiated when:
3.1 Alarms, abnormal. instrument. readings, or reports of conditions that~ indicate an l,
emergency situation -(either real or potential) i:
has occurred.
3.2 A subsequent action step in a plant operating abnormal, or Emergency Procedure which refers to this procedure for classification of the in-dicated plant conditions.
~j' 4.0 FROCEDURE When abnormal or emergency conditions (real or-
~
potential) ~ occur, the Shif t Supervisor shall:
NOTE Initial cl.assification should take place within.15 minutes
~
)-
of recognition of. initiating l
. conditions.
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4.1 Ensure that immediate actions (e.g., use of Emergency Procedures, dispatch the Fire Bri-gade, personnel etc.) are taken for the safe and proper operation of the plant.
4.2 Using the indications available (alarms, read-ings, reports, etc. ) and Attachment 1, Emergency Action Levels, determine the appro-priate emergency classification as follows:
4.2.1 Go to the " Group" Tab (In Attachment 1) tnat relates to the indications being received.
The groups are:
I.
Group One Primary System Events Group Two Decrease in RCS Inventory Group Three Safety System Functions i
Group Four Electrical System Events Group Five Secondary System Events Group Six Radiation Release Events Group Seven Hazards to Station Operations
..{.
Group Eight Natural Events 4.2.2 Find the corresp'onding indication (s) and condi tion ( s) appropriate 'tx) the actual ind ication (s).
NOTE Some of the Emergency Action Levels listed are not, by their very nature, intended to be used during maintenance and/or testing-situations where abnormal temperature, pressure, equipment status, etc. is ex-pec ted.
The Shif t Supervisor or Emer-gency Coordinator shall, however,-declare an appropriate emergency classification when-ever, in his judgement, the station status warrants such a declaration.
4 4.2.3 Declare the emergency classification that is-listed corresponding to the condition derived from Step 4.2.2.
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4.3 Perform the necessary emergency implementing actions as outlined in EIP-ZZ-00102, Emetgency Implementing Actions, to ensure the proper response is taken to implement the Union Elec-tric Radiological Emergency Reponse Plan.
NOTE If necessary the EDO should be contacted to discuss emergency actions.
1.4 Reclassify the emerger.cy as conditions dictate in accordance with this procedure.
5.0 FINAL CONDITIONS 5.1 The Emergency condition has stabilized or has been terminated and further actions are to be taken per the Plant Operating Manual.
5.2 Recovery has been declared per EIP-ZZ-00260, Recovery.
6.0 RECORDS None
'l. 0 REFERENCES _
7.1 Callaway Plant Radiological Emergency Response Plan
.i 7.2 NUREG-0 6 5 4 / FEMA-REP-1, Rev. 1, Appendix 1 I
7.3 NUREG-0818, Emergency Action Levels for Light Water Reac tors.
7.4 EIP-ZZ-00102, Emergency Implementing Actions 7.5 EIP-ZZ-00260, Recovery 7.6 Callaway Plant Final. Safety Analysis Report 8.0 ATTACHMENTS 8.1, Emergency Action Levels.
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- i Proced. No. EIP-ZZ-00101 Rev.
1 EMERGENCY ACTION LEVELS U
Group One - Primary System Events Condition Indication (s)
Classification A.
Unplanned Initia-1.
a.
Centrifugal Charging UNUSUAL EVENT tion of ECCS with Pump A or B status Discharge to Core lig h t ( s) indicate pump (s) running i-AND i;
b.
Contrifugal Charging j'
Pumps to Boron Injec-L:
tion Tank flow element EM-FI-917A and
{'
EM-FI-917B indicate flov in the lines OR 2.
a.
Safety Injection Pumo A or B status light (s) indicate pump (s) running AND
(,' -
b.
Safety Injection Pump Discharge flow ele-i ments EM-F1-918 or'922 indicate flow in the lines OR 3.
a.
RHR Pump A or B status ligh t(s) indicate pump (c) running AND b.
RHR/ Accumulator Injec-tion flow element (s)'
EJ-FI-618 or 619 indi-cate flow in the lines i
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EMERGENCY ACTION LEVELS Grouc One - Primary System Events Condition Indication ( s)
Classification B.
Abnormal Coolant
- 1. a.
Combination or Thermal UNUSUAL EVENT Temoerature and/or Power, Pressurizer Pressure, or Press, and RCS Average Abnormal Fuel Temp. exceeds limits Temperature of Tech. Spec. Figure 2.1-1 OR 2.
a.
RCG Press > 2735 psig per Tech. Spec. 2.1.2 OR
- 3. a.
Core Subcooling <
0 deg. F(based on the subccoling meter (s) or derived value from the core exit thermo-
.. -(q) couples) OR <20 deg. F (based on derived value from Th or Tc) 1.
RCS Degrees Subcooling Instrument (s)
RP081A or RP0813 OR 2.
Derived by taking difference between saturation temperature inferred frcm wide range RCS pressure i
from PT403 or PT405 and the highest of either Th, Tc or core exit thermocouples.
x_
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Rev.
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EMERGENCY ACTION LEVELS Group One - Primarf Svstem Events Condition Indication (s)
Classification C.
High Coolant 1.
1.
Confirmed Reactor UNUSUAL EVENT Activity Sample Coolant Analysis Indi-
'or Failed Fuel cates > 1.0 but < 15 Monitor Alarms uCi/ gram Dose Equiva-lent I-131 AND b.
Plant Shu tdown is required OR 2.
a.
Confirmed Reactor Coolant Analysis Indi-cated Doce Equivalent I-131 Activity exceed-ing the limits of Tech. Spec. Figure 3.4-1 i
OR 3.
a.
Confirmed Reactor Coolant Analysis Indicates > 100/E
- bar uCi/ gram OR 4.
a.
Chemical and Volume Control System Letdown Monitor (Failed Fuel Monitor) SJ-RE-01 Alarms AND b.
Confirmed Analysis Indicates an Increase of > 0.1% but < l.0%
Equivalent Fuel Fail-ures within 30 minutes i
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.)
ATTACHMENT 1 Page 3 of 52 1
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Proced. No. EIP-SZ-00101 Rev.
1 EMERGENCY ACTION LEVELS Group One - Primary System Events Condition Indication (s)
Classification i
4 D.
Very High Coolant 1.
a.
Confirmed Reactor ALERT Activity Samole or Coolant Anayisis Indi-
~>l.0% Fuel Failures cates > 15 uCi/ gram in 30 min, or 5%
Dose Equivalent I-131 Total Fuel Failure OR 2.
a.
Chemical and Volume Control System Letdown Monitor (Failed Fuel Monitor) SJ-RE-01 e',larms AND 5.1. Confirmed Analysis Indicates an Increase of > 1.0% Equivalent t
Fuel Failures within 30 minutes 47 OR 7 ' -'
2.
Confirmed Analysis Indicates that Total Failed Fuel equals or exceeds 5% of Total Fuel 1
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,i ATTACHMENT 1 Page 4 of 52
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EMERGENCY ACTION LEVELS
't 1
Group One - Primary System Ev_ents 2
Condition Indication (s)
Cla ss ifica tion 1
E.
Degraded Core with 1.
a.
Activity in the SITE EMERGENCY Possible Loss of Reactor Coolant > 300 Coolable Geometry uCi/ gram Dose Equivalent I-131 or
u b.
RCS Degrees Subcooling Instruments Reading > 500
~
deg. I'. superheat OR 4
c.
Incore Thermocouple Readings of > 1200 deg.
F.
OR r
d.
Core Water Leve'l < 35%
as determined (Zs'Skh from the Reactor S
Vessel Level' Indica-l tions System Narrow Range with no Reactor coolant pumps running.
3+
AND 2.
a.
Temperature Differen-tial (delta t) as determin-ed by, comparing Tc and Th on Instruments BB-1:
TR-413, 423, 433 or
]l 443 is Increasing Rapidly it OR b.
Temperature Differen-tial (delta t) as determin-ed from Instruments BB-TR-413, 423,.433 or 443 is O deg.F.
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i.s EMERGENCY ACTION LEVELS 1
Group One - Primary System Events Condition Indica tion ( s)
Classification i:
F.
, Loss of 2 out of Any two sets of the fol-GENERAL EMERGENC:
_3 Fission Product lowing conditions exist Barriers with a and the third is imm-Potential of inent:
losing the 3rd 4
FIRST SET - FAILURE OF CONTAINMENT l
- 1. a.
Containment pres-sure > 17.7 psig (High II) from instruments GN-PI-934, 935, 936 or 937 AND i-b.
Containment Phase A
- {
if-isolation does NOT automatically occur and CANNOT be perform-ed manually OR j.
- 2. a.
Containment Integrity does NOT exist as per Tech. Spec. 1.8
,i' OR I t
- 3. a.
High Containment pres-sure > 30 psig f rom instruments GN-PI-934, 935, 936 or 937 AND b.
Containment Phase B 1
isolation and contain--
II ment spray actuation does-NOT occur and
.i cannot be performed manually' (Con t. )
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EMERGENCY ACTION LEVELS II Group One - Primarv 5ystem Events Condition Indica tion ( 3)
Classification l'
SECOND SET - FAILURE OF GENERAL EMERGENC'.
PRIMARY COOLANT BOUNDARY r
a.
High Containment Radi-ation Ir. vel > 1 R/HR from instruments SH-RI-1 or 2 AND
- 2. a.
Pressurizer low pres-sure < 1770 psig from instruments BS-PI-455A, 456, 457 or 458 with both Centrifugal Charging Pumps running OR
'[ f b.
Pressu'rizer low level
< 17% from instruments BB-LI-459A, 460A or 461 with both Centri-fugal Charging Pumps running or c.
High Containment pressure > 6 psig from instruments GN-PI-934, j
935, 936 or 937 OR d.
High level in Contain-ment Normal Sumo of >
36 inches over a period of 30 minutes as seen from instruments EJ-LR-6 or EJ-LI-7 or 8 AND
- 3. a.
Steam pressure not
>300 psi lower in one steam generator than in the others OR b.
Tc not >30 Deg F in one reactor coolant loop L than s
)
in the others.
(Cont.)
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1 EMERGENCY ACTION LEVELS i
Group One - Primary Svstem Events Condition Indication ( s)
Classification 9
THIRD SET - FAILURE OF GENERAL EMERGENC:
CLADDING 1.
a.
Failed Fuel Monitor SJ-RE-01 Hi-Hi Alarm OR b.
Confirmed Reactor Coolant analysis indi-i' cated > 300.uCi/ Gram l
Dose Equivalent I-131 AND 2.
a.
High core temperature from Incore Thermo-couple Map Reading >
1200 deg F
.crs
.i':)
OR b.
Inadequate subcooling f rom. RCS Degrees Sub-cooled Instrument Reading > 500 deg F Superheat OR c.
Low Reactor Vessel Mater Level from Reac-tor Vessel Level Indi-cation instruments BB-LI-1311, 1312, 1321, or 1322
< 35% narrow range with e
no reactor coolant pumps running Any of the following conditions exist plus those of the above THIRD SET - Failure of Cladding:
Failure of Steam Generator Tubes j
l' l.
a.
Steam Generator liquid monitor SJ-RE-2 Hi-Hi Alarm l
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b.
Confirmed Steam Gener-ator sample analysis indicates > lE-4 uCi/ Gram
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Dose Equivalent I-131 (Cont.)
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EMERGENCY ACTION LEVELS Grouc One - Primarv System Events i
Condition Ind ication ( s)
Classification OR GENERAL EMERGENC' 2.
a.
Steam Generator Blowdown Processing System monitor BM-RE-25 Hi-Hi Alarm AND b.
Confirmed Steam Gener-i 3
ator blowdown analysis S
indicates > lE-4 uCi/ Gram q'
a.
Condenser Air Dis-i charge Monitor GE-RE-92 Hi Alarm j'
AND b.
Confirmed Condenser
- j discharge analysis f f?
indicates > 2E-5 uCi/ Gram i
\\-
Dose Equivalent I-131 G.
Coolant Pump
- 1. a.
RCP A, B, C, or D ALERT Seizure or Partial Overload Trip Alarm and/or Total Loss OR of RCS Flow Lead-b.
Low Flow P7 or PS i
ji ing to Fuel Fail-Reactor Trip Occurs i
ure OR I'
c.
Reactor Coolant Looo II Flow Instruments Indi-cate.a Decrease in RCS 1;
Flow 1
AND 2.'a, Chemical and Volume Control System Letdown
[
Monitor'(Failed Fuel-Monitor)- SJ-RE-01 Hi-Hi Alarm I
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ATTACHMENT.1 Page 9 of 52
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Proced. No. EIP-Z2-00101 Rev.
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~'l) i EMERGENCY ACTION LEVELS Group Two - Decrease in RCS Inventory Condition Ind ica tion ( s)
Classification A.
RCS Leak Rate >
RCS Leakage Evaluation or UNUSUAL EVENT Allowed by Water Inventory Balance Technicial Indicating:
Soecifications
- 1. a.
Total Primary to Secondary Leakage from all Steam Generators is > 1 gpm q
OR b.
Total Primary to Secondary Leakage from one Steam Generator is > 500 gallons per day OR l
2.
a.
Unidentified Leakage is > 1 gpm for more I
(..
than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> OR l
- 3. a.
Identified ACS Leakage is >' 10 gpm for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 5
OR j,
l 4.
a.
Controlled leakage at 2235 + 20 osig RCS
- i pressure is > 40 gpm for more than 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> il B.
RCS Leak Rate
- 1. a.
Pressurizer Program ALERT
> 50 gpm Level Recorder BB-LR-459 indicates actual level equal to program level AND b.
A misaatch exists
]
between charging and i
total letdown (letdown.
plus identified and controlled leakage) flow of > 50 gpm
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Proced. No. EIP-32-00101 i
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.;i EMERGENCY ACTION LEVELS i
i Group Two - Decrease in RCS Inventory i
Condition Indica tion (s)
Classification 4
C.
Loss of Coolant 1.
a.
1.
RCS Pressure Decreas-SITE EMERGENCY Accident > Charg-ing uncontrollably as ing Pumn Capacity shown on Trend Recorder BB-PR-403 OR 2.
Pressurizer Low Pressure Reactor Trip
+
occurs i
AND
- b. 1.
Steam Pressure is NOT
+
Lower in one Steam Generator than the
]
others AND i
- c. 1.
High Containment l
[9R Pressure > 6 psig on i-
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Instruments GN-PI-934, t
935, 936 or 937 OR 2.
High Containment Radi-ation level > 1 R/hr from Instruments SH-RI-l or 2 i
- 2. a. 1.
RCS Pressure Decreas-ing uncontrollably as shown on Trend d
Recorder BB-PR-403
.i AND
- b. 1.
RCS Degrees Sub-cooling Instruments Read-ing > 500 deg F.
superheat i
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- e m-EMERGENCY ACTION LEVELS Group Two - Decrease in RCS Inventory
- I Condition Indication (s)
Classification 1
i s
I l
D.
Small or Large 1.
a.
1.
Mismatch exists GENERAL EMERGENC' LOCA with Failure between charging and lj of ECCS Leading to total letdown (letdown ji Core Decradation plus identified and
?!
controlled lenkage) l flow of > 50 gpm OR
- I 2.
Pressurizer Pressure
'j and/or Level Decreas-M ing Rapidly it AND
!j
- b. 1.
Steam pressure is NOT
!j
'> 300 psi lower in 2
one Steam Generator i{
than the others.
s 1
AND l'
T'
- c. 1.
Containment radia-f' tion level > l R/HR OR 2.
Containment pres-sure > 6 psig AND
- f d.
1.
Less than.the following si Equipment Operable:
a.
1-Centrifugal charg-
-j ing pump
~.t-AND b.
1-Safety Injection pump AND
- f c.
1-RHR pump
'i AND d.
1-Containment Spray-pump (If containment pressure > 30 psig AND
- e. 1.
Failed Fael Monitor Hi-Hi Alarm SJ-RE-01 3
OR l
2.
Confirmed Reactor
' )
Coolant Analysis > 300 uCi/ Gram Dose Equiva-lent I-131 (Cont.)
ATTACHMENT 1 Page 12 of 52 t
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Proced. No. EIP-ZZ-00101 Rev.
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-J EMERGENCY ACTICN LEVELS Group Two - Decrease in RCS Inventory Condition Indication ( s)
Classification f
OR 4
3.
Cora Exit Thermo-couples >1200 deg F OR 4.
Core Water level
<35% as determined from Reactor Vessel
' level Indications System Narrow Range with no reac-tor coolant pumps running.
- 2. a. 1.
Shif t Supervisor 's, EDO's, or Emergency Coordinator's Opinion (Si c.
E.
Small LOCA and l. 'a. 1.
Pressurizer Low GENERAL EMERGENC:
Initially Successful Pressure Reactor trip ECCS With Suoseguent AND Failure of Contain-
- b. 1.
Pressurizer Low Pressure ment Heat Removal Safety Injection Signal Systems AND
. c '. 1.
Containment Temperature Is > 190 Degrees F NOT l'
Decreasing as shown on Trend Recorder GN-TR-63 AND d.
1.
ECCS Flow is Inade-guate for longer than 1/2 hour and Reactor Vessel Level Indication BB-LI-1311, 1312, 1321, and 1322 is Decreasing AND e.
1.
RCS Temperature rising as shown on Tavg - Treference l
Recorder AND
- f. 1.
Fuel Degradation is l,
,)
Possible Within the
~j' Next Few Hours (Cont.)
y.
ATTACHMENT 1 Page 13 of 52 l
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..i EMERGENCY ACTION LEVELS Group Two - Decrease in RCS Inventorv Condition Indication (s)
Classification i
- 2. a.
1.
Shift Supervisor's, EDO's, or Emergency Coordinator's opinion F.
Rapid Pailure of 1.
a.
1.
Rapid Uncontrollable ALERT Steam Generator Decrease in Tubes Pressurizer Pressure on B3-PI-455A, 456, 457, or 458 OR 2.
Rapid Uncontrollable Decrease in Pressur-izer Level on'SB-LI-i
/TS 459A, 460A or'461 i
AND
- b. 1.
Condenser Air Dis-charge Monitor GE-RE-92 on SP056A Reading >
2E-5 uCi/ Gram Dose Equivalent I-131 OR 2.
High Radiation in Steam Generator Blow-down Line Reading >
0.1 uCi/ gram Dose Equivalent I-131 AND
- c. 1.
Unexpected Rapid Rise.
in Any Steam Generator
. i Narrow Range Level OR
- 2. a.
1.
Shift Supervisor's, EDO's, or Emergency Coordinator's Opinion 9
)
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Proced. No. EI? ~2-00101 Rev.
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EMERGENCY ACTION LEVELS Group Two - Decrease in RCS Inventory Condition Indication (s)
Classification G.
Rapid Gross Fail-1.
a.
Decreasing RCS Pres-ALERT ure of One Steam sure or Pressurizer Generator Tune Level with NO Indicat-with Loss of Off-ed Increase in Con-site Power tainment Ptessure, Temperature or Humidity' AND b.
1.
Rise in any Steam Gene r a to rs, Narrow Range Level > 4% per minute OR 2.
High Radiation from SG safety relief (s) or atmospheric relief (s)
(,'. - )
as measured on Monitors RE-111,112,113, or 114 OR 3.
High Radiation found in Steam Generator Sample > 0.1 uCi/ Gram Dose Equivalent I-131 AND
- c. 1.
Undervoltage Indica-tion on PA01 and PA02 OR 2.
Shift Supervisor's, EDO's, I
or Emergency Coordinator's Opinion
=
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.D.
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u-EMERGENCY ACTION LEVELS Group Two - Decrease in RCS Inventory l-Condition Indication (s)
Classification A
l H.
Rapid Failure of 1.
a.
1.
Rapidly Decreasing RCS S!!E EMERGENCY l
Steam Generator Pressure or Pressur~
t' Tuoes wi-n Loss of izer Level with NO D
Offsite Power Indicated Increase in Containmen'; Pressure, 1
!~
Temperature, or L
Humidity AND 3
b.
1.
Rise in Any Steam Generator Narrow Range Level Indi-cation > 8% per minute OR 2.
High Radiation ji from SG safety
[' :sk.))
spheric relief (s) as i
relief (s) or atmo-llt:
measured on monitors RE-111,ll2,ll3, or 114 OR 3.
High Radiation Found
).
in Steam Generator Sample-> 0.2 uCi/ Gram Dose Equivalent I-131 AND
- c. 1.
Undervoltage Indica-tion on PA01 and PA02
- 3 Buses OR
- i
- 2. a.
1.
Shift Supervisor's, EDO's, Emergency Coordinator's Opinion I I i i a
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EMERGONCY ACTION LEVELS l1 Grouc Three - Safety System Functions Condition Indication (s)
Classification A.
Failure of Press-1.
- a. 1.
Pressurirer Pressure UMUSUAL EVENT urizer or Steam
< 2315 psig I
[
Generator Safety AND or Relief valve
- b. 1.
Pressurizer Safety Valve (s) Discharge Temperature Increasing on BB-TI-463, 464,465, or 466, on BB-TI-455A, 456, 457, 458 OR 2.
Pressurizer Power Ooerated Relief Dis-charge Temperature BB-TI-463 is Increasing OR 3.
Pressurizer Safety
(' ;~.
Valve (s) Discharge Temperature BB-TI-464, l
465 or 466 Js Incraas-ing OR 2.
- a. 1.
Steam Gcnerator A, B,
C, or D Steam Dump to Atmosphere Valve Posi-tion AB-2L-1A, 2A, 3A and 4A Indicate Valve (s) Open OR 2.
Visual and/or Audible
?
Indication of an open Steam Generator Safety or Steam Dump Valve AND
- b. 1.
Main Steam Pressure is
< 100 psi below set point of affected value l
?
ATTACHMENT 1 Pago 17 of 52
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Proced. No. EIP-22-00101 Rev.
1
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EMERGENCY ACTION _JEVELS Group Three - Safety System Functions Condition Indica tion ( s)
Classification B.
Loss of Contain-1.
a.
All Penetrations are UNUSUAL EVENT ment Integrity NOT capable of being Recuiring Plant closed by an Operable Shu tdown by Tech.
Automatic Isolation Specs.
Valve System or by Manual Valves, Blind Flanges, or Autcmatic Valves in the Shut position except as indicated in Technical Specifications, Limiting Condition For Ocerations For Containment' Isolation Valves OR b.
Equipment Hatch is NOT fg
' -.y closed and sealed
~
OR c.
Air Lock (s) are NOT operable per Technical Specifications, Limitir.g Condition For Operations For Containment Air Locks OR d.
Containment Leakage rates exceed the limits of Technical Specifications, Limiting Condition For Operations For Containment Leakage OR e.
A Sealing Mechanism i
(Associated with each Penetration) is NOT Operable AND
- 2. a.
CANNOT be Restored Within One Hour I
l ATTACHMENT 1 Page 13 of 52
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s, Proced. No. EIP-22-00101' Rev.
1 EMERGENCY ACTION LEVELS Group Three - Safety System Functions Condition Indication (s)
Classificati6n I
i
- ![
C.
Los_q of Enoineered 1.
a.
An Engineered Safe *.y UNUSUAL EVENT 1
Safety Feature or Feature Actuation li Fire Protection System Functional Unit I,
System Recuiring is found to be inoper-Plant 3hutdown by able per the Technical Tech. Specs.
Specifications, Limiting Condition for Operations For the Engineered Safety Feature Actuation System Instrumentation.
OR b.
The Fire Suppression Water System is found j
to be inoperable per i
the Technical Speci-
.c4 fications, Limiting
, 1)
Condition for Opera-tions For the Fire Suppression Water System 4
AND 2.
a.
Plant Shutdown is required 1:
2 l
t h
s I'
I i
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ATTACHMENT 1 Page 19 of 52
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EMERGENCY ACTION LEVELS Group Three - Safety System Functions
- l Condition Indica tion (s)
Classification
~
D.
Indications or
- 1. a.
Radiation Monitoring UNUSUAL EVENT Alarms not Func-Instrumentation "ess tional in Control Than Minimun Channels Rocm Requirine Operable per Technical Plant Shutdown or Specifications, Limit-Sig nif icant Loss ing Condition For of Assessment or Operations For Radia-Communications tion Monitoring Fct l'
Capability Plant Operations.
OR l
2.
a.
Accident Monitor-ing Instrumentation Less Than Minimum Channele Operable per Technical Specifica-
.l tions, Limiting Condi-f1l')
tion For Operations 1?
lu For Accident Monitor-ing Instrumentation OR 3.
a.
Meterological Moni-toring Instrumentation Less Than Required to perform offsite Dose l
Calculations (wind speed, direction, and stability class)
OR 4.
a.
Complete Failure of Plant Telephone and Paging Systems u
n l
-J la ATTACEMENT 1 Page 20 of 52 g
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1 Proced. No. EIP-2Z-00101 Rev.
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A EMERGENCY ACTION LEVELS 1
Group Three - Safety System Functions Condition Indica tion (s)
Classification f
E.
Conclete Loss of Either of the Following ALERT l
Any Function Need-sets of Conditions Exist:
ed For Cold Shut-down FIRST SET - NORMAL COOL-DOWN 1.
a.
Steam Generator Levels
< 61% and Decreasing on AE-LI-501, 502, 503 and 504 OR l
'b Total Available Auxiliary Feedwater Flow to Steam Generator < 235,000 lb/hr on AL-FI-1A, 2A, 3A, and 4A AND
~
- 2. a.
Stea'm Dump Valves to Condenser AB-UV-34, 35 or 36 are NOT Responding to Steam t i Header Pressure Con-troller as indicated on AB-ZI-34, 35 or 36 l
OR b.
Steam Generator Steam Dump Valves to Atmos-1-
phere are NOT Operat-
' l ing Properly as Deter-mined From AB-PIC-1A, 2A, 3A, or 4A lS,ECOND SET - RHR COOLDOWN]
1.
a.
_RHR Pumps A and B status light indicate pumps not running (green lights on)
AND 2.
a.
RHR/ Accumulator Injec-tion Flow EJ-FI-618 I
. h 619 Indicates < 2500 gpm (Cont.)
'/
,l i
ATTACHMENT 1 Page 21 of 52-e
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1 r.
a EMERGENCY ACTION LEVELS
- 4 Group Three - Safety System Functions I
Condition Indication (s)
Classification i
1 AND ALERT 1
3.
a.
Component Cooling Water to RHR Heat EX-l changes A and B Hi/Lo i.
Alarm and Computer Points EGF63 and EGF64 indicates < 7350 gpm AND 4.
a.
Complete Loss of Servi'ce or Essential Service Water F.
Complete Loss of 1.
- a. 1.
Reactor Trip Setpoint SITE EMERGENCY Any Function Need-exceeded with a Failure j
ed For _ Hot Shu t-of the Reactor Trip System "7
down to shutdown to reactor as indicated by the Nuclear Instrumentation SE-NI-413, through 44B, 31B and D, 32B j
and D, 35B and D, or 36B and D, l
- 2. a. 1.
Steam Dump Valves to Condenser AB-UV-34, 35, or 36 are NOT respond-t ing to Steam Header i
Pressure Controller as Indicated on AB-ZI-34, 35, or 36 OR 2.
Steam Generator Steam Dumo Valves to Atmosphere are !FXC I
Operating Properly as Determined From AB-PIC-1A, 2A, 3A, or 4A (Cont.)
i
' i
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1 EMERGENCY ACTION LEVELS Groun Three '- Safety System Functions Condition Indication (s)
Classification AND SITE EMERGENCY b.
1.
Steam Generator Levels
< 61% and Decreasing as Indicated on AE-LI-20 1, 502, 503, and 504 OR 2.
Total Available Auxiliary Feedwater Flow to the Steam Generator is
~
]
< 235,000 lb/hr as Indicated on AL-PT-1A,
,.i' 2A, 3A, and 4A OR l
3 a.
1.
Centrifugal Charging Pump A and B and Posi-tive Displacement f
(Ek}
Charging Pump Status NU Lights Indicate Pumps
(.
NOT Running.
l l'
(green lights on) 1; AND l
- b. 1.
Charging Header Flow Instrument BG-FI-121A indicated Flow <32 gpm l
2.
Centrifugal Charging Pumps Flow to Boron Injection Tank on EM-FI-917A, 917B indicates < 150 gpm t
G.
Failure of Reactor 1.
a.
Manual or Automatic ALERT Protection System Reactor. Trip to Initiate and Initiated Complete a Trip AND Which Brings the
- 2. a.
Intermediate Range Reac tor Subcriti--
Monitcr Indicating cal Zero or-Positive Start up Rate Meter AND
'T
- 3. a.
. Shif t Supervisor 's,
'l EDO's or Emergency Coordinators Opinion ATTACEMENT-1 Page 23 of 52-
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Proced. No. EIP-02-00101 Rev.
1 q
,)
DIERGENCY ACTIO'i LEVELS Group Three - Safety System Functions Condition Indication (s)
Classification H.
Transient Recuir-1.
a.
A Plant Transient SITE EMERGENCY ing Coeration of occurs which reaches a
'Shu tdown Systems Reactor Trip setpoint with Failure to with NO Reactor Trip Trip Initiated as Indicated by by NO Rod Bottom Lights AND
- 2. a.
No Evidence of Core Damag e AND 3.
a.
Shif t Supervisor's, EDO's, or Emergency Coordinator's,
~,
Opinion 4mU]
t ei ATTAC!iMENT 1 Page 24 of 52
7 i
o
.i i
a Proced. No. EI?-2Z-00101 Rev.
1
- r, w/
g EMERGENCY ACTION LEVELS
- t
- i Group Three - Safety System Functions Condition Indication (s)
Classification i
i.
I.
Transient Requir-1.
a.
A Plant Transient GENERAL EMERGENC' ing Operation of occurs which reaches a Shutdown Systems Reactor Trip Setpoint with Failure to with NO Reactor Trip TE p Which Results Initiated i
in Core Damage or OR Additicnal. Cool-b.
Shift Supervisor's, EDO's ing or Makeuo or Emergency Coordinator's Systems Failure Opinion i
AND
- 2. a.
Flow indication from the ECCS (Charging, Safety Injection and RHR) is inadequate for Plant pressure as
- I
(~r Determined from EM-FI-917A, 917B, 918 and 922 or EJ-FI-618 and619 i !
AND l
- 3. a.
Failed Fuel Monitor 4.
Hi-Hi Alarm on SJ-RE-01 OR i
b.
Confirmed RCS sample of > 300 uCi/ Gram
c.
Core exit thermo-cj couples > 1200 deg F OR d.
Core Water level
> 35% as determined from Reactor Vessel.
level Indication Sys-tems Narrow Range with no reactor coolant pumps running.
I 1
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. _/
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ATTACHMENT 1 Page 25 of 52
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~
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1 EMERGENCY ACTION LEVELS Group Three - Safety System Functions Condition Indication (s)
Classification J.
Most or All Alarms 1.
a.
M.nnunciator Panels ALERT
( Annu nc iator s)
RK014 through RK026 Lost are Inoperable AND b.
Station Computer NOT functioning properly OR
- 2. a.
Shif t Supervisor s, EDO's, or Emergency Coordinator's Opinion l
K.
Most or All Alarms 1
a.
1.
Station Computer NOT SITE EMERGENCY
[Annuncia tor s) functioning Properly
,- g Lost and Plant OR
~q}
i Transient Initiat-2.
Annunciator Panels ed or in Progress RK014 through RK026 are Inoperable for longer than 15 minutes AND b.
1.
Uncontrollable Plant Transient has Initiated OR
- 2. a. 1.
Shift Supervicor's, EDO's, or Emergency Coordinator's Opinion N-)
l C
ATTACHMENT l-Page 26 of 52
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^g Rev.
1
._ ]
EMERGENCY ACTION LEVEL 5
)
Group Four - Electrical System Events Condition Indication (s)
Classification A.
Loss of Offsite
- 1. a.
Undervcitage on buses UNUSUAL EVENT Power or Loss of PA01 and PA02 as Onsite AC Power indicated on meters l
'Cacability PA-EI-l and 2
.i '
OR 2.
a.
Undervoltage on buses NB01 and NB02 as indicated on meters a
t NB-EI-l and 2 B.
Loss of Offsite 1.
a.
Undervoltage on buses ALERT Power and Loss of PA01 and PA02 as All Onsite AC Indicated on Meters P
Power PA-EI-l and 2 c
1
(-
AND
- 2. a.
Undervoltage on buses NB01 and UB02 as Indicated on Meters NB-EI-l and 2 AND 3.
a.
Either offsite or on-site power is restored f?
in less than 15 minutes
!.}
4 j
l" i
D' ATTACHMENT 1 Page 27 of'52
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Proced. No. EIP-ZZ-00101 Rev. _
1
^
m EMERGENCY ACTION LE"ELS l
Group Four - Electrical System Events Condition Ind ica tion ( s)
ClassificatioI.
C.
Loss of Offsite
- 1. a.
Undervoltage en buses SITE EMERGENCY Power and Loss PA01 and PA02 as of All Onsite AC Indicated on Meters Power t
- More PA-EI-l and 2 j
l Than 15 hinutes AND
- 2. a.
Undervoltage on buses NB01 and NB02 as Indicated on Meters a
NB-EI-l and 2 i
AND
- 3. a.
Offsite and Onsite I
Power is NOT restored within 15 minutes ij OR b.
The Shif t supervisor lI l.' 7 Leaves the Control Room without a direct means of communicating I,
with the Control Room during the first 15 minutes OR 4
c.
The Shift Suoervisor l{
was initially out of the Control Room and ii has not returned in 15 l
minutes, and his where-abouts is unknown or G
he has NOT communicated
- i with the Control Room, then the senior operator in the Control Room shall declare a SITE "MERGENCY
-sN l
ATTACEMENT 1 Page 28. of 52
m _
- j Proced. No. EIP ~3-00101 Rev.
1 EMERGENCY ACTION LEVELS C
Group Four - Electrical System Events i
Condition Indication (3)
Classification i
D.
Failure of Offsite
- 1. a.
Undervoltage on buses GENERAL 2MERGENC' and Onsite Power PA01, and PA02 as l,
with a Total Loss Indicated on Meters y
of Auxiliarv Feed-PA-EI-1 and 2 water Flow for AND Several Hours 2.
a.
Undervoltage on buses NB01 and N302 as Indicated n
on Meters NB-EI-l and 2
]
AND 1
3.
a.
No Auxiliary Feedwater P
Flow to the Steam Gen-I erators as Indicated on AL-FI-1A, 2A, 3A, and 4A Lasting Longer l
than 2 Hours t
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+
E.
Loss of All Vital 1.
a.
Undervoltage on buses ALERT U
Onsite DC Power NK01, 02, 03, and 04 as Indicated on Meters NK-EI-l thru 4 AND i'
2.
a.
DC Pcwer is restored ij in less than 15 minutes I 3 i
't 4
i l
I
- 2
.T)
,3 i
v i
ATTACHMENT.-l Page 29 of.52
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.6 Proced. No._EIP "Z-00101 Rev.
1 1
EMERGENCY ACTICN LEVELS, Group Four - Electrical System Events 1
Condition Indica tion ( s)
Classification I-h F.
Less of All Vital 1.
a.
Undervoltage on buses SITE EMERGENCY Onsite DC Power NK01, 02, 03, and 04 as C
for Extended Indicated on Meters Periods NK-EI-l thru 4 d'
AND j.
2.
a.
DC Power is NOT restored within 15 minutes i
OR fi b.
The Shift SGpervisor Leaves the Control Room without a direct it means of communicating with the Control Room
!{
during the first
,l cc, 15 minutes 4 ~
OR c.
The Shif t Supervisor was initially out of ll the Control Room and has not returned in 15 l
minutes, and his where-is abouts is unknown or he l3 has NOT communicated with the Control Room, then the Senior Ooerator a
in the Control Room shall declare a SITE it EMERGENCY O
i n
~
i s
l' i
4 ATTACHMENT 1 Page 30 of 52
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Proced. No. ~EIP-22-00101 3
Rev.
l
)
v EMERGENCY ACTION LEVELS Group Five - Secondary System Events Condition Indication (s)
Classification l
A.
Rapid Cepressur-1.
a.
Low Steam UNUSUAL EVENT ization of Second-I Pressure < 585 psig as ary Side indicated on AB-PI-514A, 515A, 516A, 524A, 525A, 526A.
1 534A, 535A, 536A, 544A, 545A, 546A.
with RCS Pressure
> 1970 psig AND b.
Coincidence of 2 of 3 Steam pressure instruments reading
<585 psig in one or more steam generator (s).
OR i,
i,.
(fr.s
- 2. a.
High Negative Steam
~~
Pressure Rate (-100 psig in < 50 second's)
Steam Line Isolation with Steam Line Pressure SI Blocked (A 1
and B Trains)
OR 3.
a.
Containment Pressure 17.7 psig (High II), From GN-PI-934, 935, 936, or i
937 with no significant increase in containment radiation levels.
- 4. a.
Shift Supervisor's, ED0's, or'Emer--
gency Coordinator's Opinion i
1 d
4 i
AT2ACEMINT l Page 31.of 52
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j Proced. No. EIP-ZZ-00101
x Rev.
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EMERGENC'I ACTION LEVELS i
Group Five - Secondary System Events i
Condition Indication ( s)
Classification L
i S.
Steam Line Break 1.
a.
1.
Low Steam ALERT with > 10 gpm Pressure < 585 psig as Primarv to Second-indicated on AB-PI ary Leakage 514 A, 515A, 516A, 524A, 525A, 526A, 534A, 535A, 536A, 544A, 545A, 546A.
With RCS Pressure
> 1970 psig AND 2.
Coincidence of 2 of 3 steam pressure instruments reading
< 585 psig in one or more steam generators.
OR fd
- b. 1.
High Negative Steam s'
Pressure Rate (100 l
psig in <. 50 seconds)
Steam Line Isolation with Steam Line Pressure SI Biccked (A and B Trains) i OR l;
- c. 1.
Containment Pressure 17.7 psig~ (High II), From GN-PI-934, 935, 936, or
~;
937
- i AND 2.
- a. 1.
Condenser Air ji Discharge Monitor Alert Alarm GE-RE-92 OR if
- b. 1.
Confirmed Condenser Air Discharge Analysis Activity > 2E-6 uCi/ Gram Dose Equivalent I-131 OR c.
1.
High Containment Radiation level >
20 times background j
)
using instruments
'1 SH-RI-l or 2.
l l
l 0
(,
. ATTACHMENT 1 P2ge 32 of 52
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er Proced. No. EIP-ZZ-00101 Rev.
1 7
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EMERGENCY ACTION LEVELS Grouc Five - Secondary System Events Condition Indication (s)
Classification l
C.
Steam Line Break 1.
- a. 1.
Low Main Steam SITE EMERGENCY with > 50 gpm Pressure < 5S5 psig as Primary to Second-Indicated on AB-PI-ary Leakage and 514A, 515A, 516A, 524A, Indication of Fuel 525A, 526A, 534A, 535A, Damage 536A, 544A, 545A, 546A with RCS Pressure
> 1970 psig AND 2.
Coincidence of 2 of 3 steam pressure instruments reading
< 585 psig in one or more steam gen-erators 4
- t. :.
- b. 1.
High Negative Steam Pressure Rate (-100 psig in < 50 seconds)
Steam Line Isolation with Steam Line Pressure SI Block A and B OR c.
1.
Containment Pressure 17.7 psig (High II), From GN-PI-934, 935, 936, or 937 AND l
2.
- a. 1.
Condenser Air Dis-charge Monitor Alert Alarm GE-RE-92 OR
[
- b. 1.
Confirmed Condenser Air Discharge Analysis Activity > 2E-6 uCi/ Gram Dose Equivalent I-131 AND
(
l
- 3. a. 1.
Failed Fuel Monitor SJ-RE-01 Hi-Hi Alarm j
.s
)
- b. 1.
Confirmed RCS Activity Analysis > 300 uCi/ Gram
[
Dose-Equivalent-I-131 i
ATTACHMENT 1 Page.33 of 52' y.,%-
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..J EMERGENCY ACTION LEVELS Group Five - Secondary System Events Condition Indica tion ( s)
Classification O.
Loss of Peedwater 1.
a.
1.
Available Main Feed-GENERAL EMERGENC and Condensate water Flow to All Systems followed~
Steam Gemerators by a Failure of
< 235,000 lb/hr as Auxiliary Feed-indicated on AE-FI water _for an Ex-510A, 511A, 520A, 521A, tended Period 530A, 531A, 540A, and 541A AND 2.
Available Auxiliary Feedwater Flow to all Steam Generators < 235,000 lb/hr as indicated on AL-FI-1A, 2A, 3A, and 4A l
AND 3.
Centrifugal charging Pumps A and B Status o!
Lights Indicate Pumps
\\
~
NOT running and pumps cannot be started manually (red lights of f)
(Cont.)
m 1
t ATTACHMENT 1 Page 34 of 52
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Proced. No. EIP-22-00101 i
Rev.
1
.]
EMERGENCY ACTION LEVELS Grouc Five - Secondary System Events i
Condition Indica tion ( s)
Classification i.
l OR GENERAL EMERGENC 2.
a.
1.
Available Main Feed-I water Flow to All Steam Generators e
< 235,000 lb/hr as l
indicated on AE-FI-510A, t
511A, 520A, 521A, 530A, 531A, 540A, and 541A U
AND y
2.
Available Auxiliary Feed-water Flow to all Steam Generators < 235,000 lb/hr as indicated on AL-FI-1A, 2A, 3A, and 4A o
AND
- l 3.
Centrifugal. Charging Pumps D
c~s A and B Available (d,/
i' AND
- b. 1.
30 minutes has elapsed AND
- c. 1.
RHR Pumps A and B Status Lights Indicate Pumps NOT Running and Pumps cannot be started-manually (red lights off)
OR 2.
Available Auxiliary Feed-water Flow to all Steam Generators < 235,000 lb/hr as indicated on AL-FI-1A, 2A, 2A, 3A, and 4A 4
i i.
i 4
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. ATTACHMENT-1 Page 25 of 52.
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Proced. No. _EIP-ZZ-00101 Rev.
1
.4 EMERGENCY ACTION LEVELS
]
Group Six - Radiation Release Events
.Ij Condition Indication (s)
Classification io A.
Radiological Ef-
- 1. a.
Valid Digital Radia-UNUSUAL EVENT fluent Technicaf tion Monitoring Panel i'
Specification (SPOS6A) Alarm on one of Limits Exceeded the following effluent i-monitors: Liquid Radwaste Discharge HS-RE-18, SG Bloudown BM-RS-52, j
Turbine Bldg. Drain LE-R5-59, Secondary Liquid Waste Discharge HF-RE-45, Unit Vent Activity GT-RE-21A, 21B, Radwaste Bldg. Vent GH-RE-10 l'
AND l
b.
Isolation Does Not Occur AND
$D c.
Confirmed samole
.. [l) analysis.for 'a Gaseous or Liquid Release I.
Indicates greater.than I
Limiting Condition For Operations For Gaseous
]i or Liquid Effluents (See Note 6-1)
OR j
- 2. a.
Confirmed sample j4 analysis for a Gaseous or Liquid Release Indicates greater than Limiting Condition For Operations For Gaseous or Liquid Effluents
- (See Note 6-1) 4
=
I ATTACH!iENT 1 Page 36 of 52 i
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l Proced. No. EIP-ZZ-00101 Rev.
1_._
s a
EMERGENCY ACTICM LEVELS l
Group Six - Radiation Release Events Condition Indica tion ( s)
Classification S.
Radiological Ef-1.
a.
Valid 41 arm on the ALERT fluent > 10 times Digital Radiation the Technical Monitoring Panel Speciflcation (SP056A) from a Gase-Instantaneous ous or Liquid Effluent Limits Monitoring Instrumen-tation Cnannel AND b.
Isolation Does Not Occur AND c.
Confirmed Sample Analysis for a Gaseouc or Liquid Release Indicates greater than 10 times Limiting
..l Condition For Operations For Gaseous or Liquid Effluents (See Note 6-1)
OR 2.
a.
Confirmed Sample Analysis for a Gasecas or Liquid Release Indicates greater than Limiting Condition For Operations For Gaseous or Liquid Effluents (See Note 6-1) t t
ATTACF. MINT 1 Page 37 of 52 l
o oced. No. EIP-22-00101 Rev.
1
}
EMERGENCY ACTION LEVELS Group Six - Radiation Release Events Condition Indication (s)
Classification
'ieasured or Pro-1.
1.
Unit Vent Monitor GT-SITE EMERGENCY C.
jected Dose Rates RE-21A/ 21B indicates or Effluent Moni-
> 0.24 uCi/cc for longer tors Detect Levels than 30 minutes or > 2.4 Corte_sponding to >
uCi/cc for longer than 50 mR 7n t for 1/2 2 minutes hour or > 500 OR mR/hr for 2 Min-2.
a.
Radwaste Bldg. Vent utes Whole Body at GH-RE-10 A/ 10 B, indicates the EXCLUSION AREA
> 1.3 uCi/cc for longer BOUNCARY or 5 times than 30 minutes or thesa levels to the 13.2 uCi/cc for longer thyroid using ad-than 2 minutes versemeteorology OR
- 3. a.
Containment Activity nn Monitor GT-RE-59/60 fc) indicates > 233 uci/cc at a pressure of 48 psig CR
- 4. a.
A Field Monitoring Team Reports 50 mR/hr for 1/2 hour or 1.35E-7 uCi/cc I-121 (or Higher) at the EXCLUSION AREA BOUNDARY OR b.
A Field Monitoring Team Reports 500 mR/HR for 2 Minutes or 1.35E-6 uci/cc I-131 or Higher at the EXCLUSION AREA BOUNDARY j
ATTACIBiENT 1 Page 38 of 52
Preded. No. EIP-32-00101 Rev. ~s EMERGEY.Ci' ACTION LEVELS Grouo Six - Radiation Release Events Condition Indic ation (s)
Classification D.
Measured or Pro-1.
a.
Unit Vent Monitor GENERAL EMERGENC'.
i l
1ected Dose Rates GT-RE-21A, 213 indicates or Effluent Moni-a Release of > 5 uCi/cc tors Detect Levels or the Radwaste Bldg.
Correspondins to Vent GH-RE-10 A, 108-
~
1 R/hr Whols'5o3y indicatas a Release of
[
or 5 R/hr Thyroid
> 26 uCi/cc at the EXCLUSION OR AREA BOUNDARY
- 2. a.
Projected Doses at the using Actual EXCLUSION AREA BOUNDARY Meteorology Greater than or Equal to 1 R/hr Whole Body j
or 5 R/hr Thyroid (or Higher) using Actual Meterology OR jj
.Q])
i
- 3. a.
A Field Monitoring Team. Reports 1 R/hr or 2.7E-6 uCi/cc I-131 (or Higher) at the EXCLUSION AREA BOUNDARY
- i E.
Area Radiation
- 1. a.
Digital Radiation ALERT Levels or High Monitoring Panel Airborne Activity (SP056A) Alarm with
.)
T 1000 times Unanticipated General it Normal Radiation Levels >
1000 Times Normal as
[
Confirmed by Direct Area Radiation Survey OR 2.
a.
Area Radiation Monitor Local Alarms and Readouts > 1000 Times Normal as Confirmed by Direct Area Radiation Survey m,
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Proced. No. EIP-ZZ-00101 Rev.
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EMERGENCY ACTICM LEVELS Group Six - Radiation Release Events Condition Ind ication ( s)
Classification F.
EPA Protective 1.
a.
Computer calculated SITE EMERGENCY 4
Action Guidelines Dose Projections f rom as projected to be the Radiological exceeded Outside Release Information the EXCLUSION System indicate the ARIA SCUNDARY Potential for EPA
~
~
Protective Action Guidelines to be exceeded outside the EXCLUSION AREA BOUNDARY OR 2.
a.
Manually calculated Dose Projections indicate the Potential 1
%{:[j)
~*.
for EPA Protective 1-Action Guidelines to be exceeded outside the EXCLUSION AREA l,
BOUNDARY 1
G.
Other Plant Condi-
- 1. a.
An Event occurs that GENERAL EMERGENC:
,,l tions Exist that is NOT covered else-maKe a Release of where in the Emergency Large Amounts of Classification Scheme a
~j Radioac tivity in a but indicates that a j
Short Time Period rapid release of large Possible amounts of Radioactiv-ity in a Short Time Period is ?ossible AND 2.
a.
Shif t Supervisor 's, EDO's, or Emergency Coordinator's Opinion i
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ATTACHMENT 1 Page 40 of 52 w
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.2 Proced. No.~EIP-32-00101 Re'f.
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s EMERGENCY ACTION LEVELS Crouc Six - Radiation Release Events Condition Ind ica tion ( s)
Classification H.
Fuel Damage Acci-1.
a.
Reports from Fuel ALERT dent _with Release Handling Personnel of Radioactivity Indicating that an to Centainnent or Irradiated Fuel Assem-Fuel Su11 ding bly has been Damaged
~
and Radioactive Gases Escaping OR b.
Spent Fuel Pool Bridge Crane Area Monitor Hi Alarm OR c.
Fuel Building Portable Area Radiation Monitors Indicate > 100 mR/hr OR
,.7) d.
Containment Porta' ale Area Radiation
~'
Monitors Indicate > lE-5 uCi/cc Gaseous Activity OR e.
Containment Atmospheric Monitor (s) GT-RE-31 or 32 Alert Alars l
OR 2.
a.
Shift Supervisor's, EDO's, or Emergency Coordinator's Opinion 4
l j
ATTACEMENT 1 Pace 41 of 52
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s Proced. No._E,I?-22-00101 i
Rev.
1 EMERGENCY ACTION LEVELS L
Group Six - Radiation Release Events Condition Indica tion ( s)
Classification i
.I T
I.
Major Dar. age to 1.
a.
Fuel Suilding Portable SITE EMERGENCY Spent Fuel in Con-Area Monitors Indicate tainment or the
> 1E-4 uCi/cc Gaseous Fuel 3uilding 7.c tiv i ty -
OR i
b.
Fuel Building E::haust Monitors Hi Alarm GG-RE-27 and 28 with 1
ESFAS initiation of the Fuel Building 1'
Emergency Ventilation j'
System OR c.
Containment Portable Area Monitors Indicate q.;
> lE-4 uCi/cc Gaseous U
Activity OR d.
Containment Atmospher-ic Monitor (s) GT-RE-31 or 32 Hi Alarm AND 2.
a.
Shif t Supervisor 's, EDO's, or Emergency Coordinator's Opinion
.I N
ti J.
Transportation of 1.
a.
Any Event which.
UNUSUAL EVENT EXTERNALLY CONTAM-Requires the transpor-4 INATED INJURED /ILL tation of an EXTERNALLY 4
Individual from CONTAMINATED INJURED /ILL Site to an Individual to an.Offsite Offsite Hosoital Medical Facility 4
l 1
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ATTACHMENT 1 Page 42 of 52
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E:iERGENCY ACTION LE'/ELS i
Grouc Six - Radistion Release Ev*nts Condition Ind ica tion ( s)
Classification i
NOTE 6-1 LIMITING CONDITIONS FOR OPERATIONS Gaseous - The dose rate due to radioactive materials released in
^
gaseous effluents from the site shall be limited to the following:
a.
For noble gases:
Less than or equal to 500 ?. rem /yr to the total oody and less than or equal to 3000 mrem /yr to the skin, and j
P For all radiciodines and for all radioacti're materials in particulate form and radionuclides (other than noble gases) with half lives greate_ than 8 days:
Less than or equal to 1500 mrem /yr to any organ (from the inhalation pathvay l
only).
l J Iuid - The concentration of radioactive material released from the i
G.f. e shall be limited to the concentrations specified in 10 CFR Part
%d', Appendix B, Table II, Column 2 for radionuclides other than dis-Solved or entrained noble gases.
For dissolved or entrained noble
^
gases, the concentration shall be limited.to 2 E-4 microcuries/ml total activity.
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j Proced. No. EIP-23-00101 Rev.
1
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EMERGENCY ACTION LEVELS Groun Seven - Mazards to Station Ocerations condition Indica tion (s)
Classification i
b A.
Fire Within 1.
3.
Fire within any UNUSUAL EVENT Plant Structures Plant Structure which 4,
Lasting Longer is not under control than 10 Minutes within 10 minutes after-Fire Fighting efforts begin B.
Fire Potentially 1.
a.
Fire within the ALERT Affecting Safety Plant which has the Systems potential for causing e Safety System NOT to be operable as defined in Tech. Spec. 1.18 OR 4
- 2. c.
Shif t Supervisor's, EDO's, l}
Ulf or Emergency Coordinator.'s i'
Opinion.
j, J.
C.
Fire Causing
- 1. a.
Fire within the SITE EMERGENCY Degradation of Plant which causes Safety Systems Major Degradation of Safety System Function Required for: protection of the Public.
- t AND b.
Affected Systems are NOT operable per Definition of Goerable-l4 Operability in the Tech-nical Specifications
- s.
1
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1 ATTACHMENT 1 LPage 44 of 52 l
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EMERGENCY ACTION LEVELQ Group Seven - Hazards to Station Operations i
condition Indication (s)
Classification
=
D.
Securitv Threat or
- 1. a.
Confirmed Report by a U:1 USUAL EVENT Attempted Entry or senior member of the Sabotage Security Force of an Attempted Entry, Attempted Sabotage or a Security Threat that Cannot be properly com-pensated within 10 minutes.
E.
Ongoing Security
- 1. a.
Confirmed Report by a ALERT Compromise senior member of the Security Force that Security of the Plant
,f.
has been Degraded en through an Occuoation of Plant Are,as, But Loss of Vital Areas i
and Control of Shut-do'in Capability is not imminent.
j.
F.
Imminent Loss of
- 1. a.
Reports or Observa-SITE EMERGENCY Physical Control tions of a Physical of the Plant Attack on the Plant involving Imminent Occupancy of the
?
Control Room, Auxil-iary shutdown Stations, or other Vital Areas of the Plant I
ATTACHME1T 1 Page-45 of.52 m.. _ _ _.
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Proced. No. EIP-22-00101 Rev.
1
. ~h EMERGENCY ACTION LEVELS Group Seven - Hazards to Station Operations Condition Indication (s)
Classification G.
Lo:s of Physical
- 1. a.
Reports or Observa-GENERAL E!iERGENCY Control of the tions of the occupa-Facility tion of the Control Room, Auxiliary Shutdown Stations, or other Vital Areas of o
the Plant by Unauthor-
+
ized Personnel 1
H.
Other Hazards 1.
a.
Observation of an UNUSCAL EVENT Seing Experienced Aircraft Crash Onsite or Projected On.-
or Unusual Aircraft
]
site or Near the Activity over the i
Plant facility 1
- c..$
OR Y~'
- 2. a.
Observation of a Train Derailment Onsite or Reoorts of a
~
. Derailment near the site that involves Flammable, Explosive, or Toxic Materials OR
- 3. a.
Observations or Reports of a Near or 4
j Onsite Explosion
'l OR
[
- 4. a.
Observation or Warning from Outside N
the Plant; Detection of gases using port-able instrumentation which exists in con-centrations which 4
exceed the limits of flammability or toxicity i:
OR 5.
a.
Turbine. Trip and' i
Observation of a Turbine Rotating n-}
Component Malfunction or Failure t
i ATTACHMENT 1 Page 46 of 52
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Procad. No. EI?-22-00101 Rev.
1 i
m.
.ji EMERGENCY ACTION LCVELS t
Groun Sevea - ilazards to Sta. tion O_cerations
-=
Condition Indication ( s)
Classification
,1 I.
Other !!azards 1.
a.
Observation of an ALERT 5eina Exterienced Aircraft crash into or Projected in
?lant structures the Plan OR
- 2. a.
Observation of missile Impacts on ?lant Structures or Components OR
- 3. a.
Observation of Il Explosion Damage to the Facility Affecting Plant Operation OR 4.
a.
Obser ration or Detection of gases in the Facility Environ 3 o
h..
Exceed sq limits of i
flammal ity or toxicity i
OR i
- 5. a.
Turbine Trig and Observation of a Failure Causing Casing Penetration t
.i t
i
,1 ATTACHMENT 1 Page 47~of 52
wm; I-Proced. No. EI?-Z -00101 i
Rev.
1
~ EMERGENCY ACTION LEVELS Grouc Seven - Hazards to Station Ocerations Condition Indication (s)
Classification e
J.
Othat_ Hazards
- 1. a.
Observation of an Air-SITE EMERGE';CY Sein _ Experienced
-craft Crash Affecting or Projected in Vital Structures such Vital Areas of the as the Reactor Build-Plant with the ing, Control Room, Plant not in Cold Auxiliary Building, shutdown Fuel Building, or Turbine Building by Impact or Fire OR
- 2. a.
Indications of an Explosion or missile Damage which in the e
D Judgement of the Shift
]
Supervisor causes severe j;
Damage to Equipment nec-i
/"
essary for the safe shut-
'~J down of the plant m
- 3. a.
Detection of the Entry of Flammable or Toxic Gases into Vital Areas-j:
of the Plant such as the Control Room, Cable Spreading Rooms, Reactor Building, 3
Auxiliary Shutdown Panels, or Switchgear and Diesel Generator D
Rooms where Lack of
- ~
Safety Problem-Access Constitutes a i
i
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i.
4 4
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Proced. No. EIP-22-00101 Rev.
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ENERGEMCY ACTION LEVELS Group Seven - Hazards to Station Onerations Condition Indication (s)
Classification K.
Anv Major Interna' l.
a.
Anv Major Explosion or GENERAL EMERGENCY Zvent anich E
Fiie which causes
~
cause Mas _si Te massive common damage Common Damage to to Plant Systems such I
Plant Svstems that a potential core 3esultin2 in Core melt situation exists
~
ciel t OR 2.
a.
Shift Supervisor's, ED0's, or Emergency Coordinator's Opinion L.
Evacuation of con-1.
a.
Evacuation of the con-ALERT trol Room Antici-trol Room is Antici-il cated or Required pated or Required
- ~
r;
Shutdown Systems
- 2. a.
Control of Shutdown with Control of AND Established at Systems is Established Local Stations at Local Stations within 15 minutes 3,
3 M.
Evacuation of Con-1.
a.
Evacuation of the SITE EMERGENCY trol Room and Con-Control Room is trol of Shutdown Required Svstems not Estab-AND h.'
'ished from Local
- 2. a.
Control of Shutdown l
Stations for an Systems is not Extended Period Established locally within-15 minutes 1-l*
j i i 1
t ll 1
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Ii T.J ATT;CHMENT~l - Page_49 of 52
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EMERGENCY ACTION LEVELS
)
Group Seven - Hazards to Station Ocerations Condition Indica tion (s)
Classification N.
Other Plant Condi-
- 1. a.
Events not covered UNUSUAL EVENT rions Exist that elsewhere in the Warrant IEcreased Emergency Classifica-Awareness on the tion Scheme that fart of the Plant Warrant an Increased i
0,cerating Staff or Awareness by the State and Local Operations Staf f or j'
Authorities State and Local Authorities AND
- 2. a.
Shift Supervisor's, EDO's, or Emergency Coordinator's Opinion 73 Other Plant Condi-
- 1. a.
Events EOT covered ALERT E'
tions Exist that elsewhere in the Emer-Warrant Precau-gency Classification tionarv Activa-Scheme that Warrant a tion of the TSC Precautionary Activa-and Placing the tion of the TSC and i
EOF Staf f on Placing the EOF Staff
}'
Standby on Standby 1l AND l
- 2. a.
Shif t Suoervisor's, EDO's, or Emergency Coordinator's Opinion I'
h I'
P.
Other Plant Condi-1.
a.
Events NOT covered SITE EMERGENCY
+
tionc Exist that elsewhere in the Emer-Warrant Activa-gency Classification j
tion of Emergency Scheme that Warrant Centers and Mon-Activation of the TSC, i
toring Teams or a EOF, and Monitoring Precautionary No-Teams or Precautionary l
tification to the Notification of.the Puolic Near the Nearsite Public Sire AND a.
Shift Supervisor's, EDO's, or Emergency. Coordinator's c-)'
Opinion ATTACHMENT 1 Page 50 of 52 w
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Proced. No. E!?-33-00101 Rev.
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\\ e.M EMERGENCY ACTION LEVELS Group Eight - Natural Events J
Condition Indica tion ( s)
Classification A.
Aqv Earthquake
- 1. a.
Response Spectrum UNUSUAL EVENT Felt In-Plant or Recorder Ooerating Detected on Sta-Annunciator 98E j
tion Seismic In-Alarms in the Control i
strumentation Room B.
Earthquake Greater 1.
a.
Operating Basis Earth-ALERT than Operating quake Annunicator B_ asis Earthquake 98D Alarms in the (OBE) Levels Control Room AND
- 2. a.
Earthquake greater than OBE Levels (0.129) in the Horizontal and Vertical Directions as (Oh Indicated by SG-AS-01
(
j) and SG-AS-03 i
C.
Earthquake Greater
- 1. a.
Safe Shutdown Earth-SITE EMERGENCY than Safe Shutdown quake Annunciator Earthauake (SSE) 988 Alarms in the Level 3 Control Room AND
- 2. a.
Earthquake greater than SSE Levels 0.20g in ooth the horizontal and vertical directions as Indicated by SG-AS-02 and SG-AS-04 4
D.
Any Tornado Onsite
- 1. a.
Observation or Reports UNUSUAL EVENT from Station Personnel of any Tornado'that crosses the EXCLUSION AREA SOUNDARY
- x
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k.l EtiERGE:;CY ACTION LEVELS s
Group Eight - Natural Events e
Condition Indication (s)
C:assification E.
Any Tornado 1.
a.
Observation or Reports ALERT Striking the from Station ?ersonnel Facility of any Tornado Strik-ing Plant Structures such as Reactor, Auxiliary or Radvaste Buildings t
-i F.
Sustained Winds or 1.
a.
Tornado which strikes SITE EMERGENCY Tornadoes in Ex-the power block and cess of Design a potential for Levels common damage to plant systems.
-l OR 2.
a.
Wind Speed is > 85 mph m3
j as indicated by RRIS or Chart Recorder G.
Any Maior External
- 1. a.
Any Major - rthquake GENERAL EMERGENCY Event Which could or Tornado b yond Cause Massive DeGign Levelc which Common Damage to causes massis common Plant systems damage to Plant Resulting in Core Systems.such that a Melt Potential Core Melt Situation Exists OR 2.
a.
Shift Superviscr's Opinion m.
tJ ATTACHMENT 1 Page 52 of 52 l
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DATE 01/05/84 PAGE 1
of
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UNION ELECTRIC COMPANY f9Eb NDGNLY CALLAWAY PLANT EMERGENCY PLAN IM EMERGENCY PREPAREDNES\\ CL NIR0 LLED COPY Procedure Date Deficiency Resp.
Number Title Rev.
Issued Pace Date Dept.
i EIP-ZZ-00101 Classification of 1
01/05/84 Hlth Phy Emergencies EIP-ZZ-00102 Emergency Implementing 1
12/13/83 Emg. Prep i'
Actions i
s EIP-ZZ-00201 Notifications 0
04/29/83 04/20/83 Hlth Phy EIP-ZZ-00202 Callout of Emergency 0
07/18/83 06/20/83 Hlth Phy Organization EIP-ZZ-00203 Additional Assistance 0
07/07/83 Hlth Phy EIP-ZZ-00210 In-Plant Radiological 0
07/18/83 06/14/83,' Hlth Phy Controls i-C.
EIP-ZZ-00212 Protective Action 0
07/18/83 Hlth Phy Recommendations EIP-ZZ-00213 Technical Assessment 0
07/18/83 Hlth Phy EIP-ZZ-00214 Personnel / Vehicle 1
12/13/83 12/08/83 Emg. Prep Monitoring and Decontamination 1
EIP-ZZ-00216 Potassium Iodine 0
10/04/63 Emg. Prep Administration EIP-ZZ-00220 Emergency Team Formation 0
04/29/83 Hlth Phy EIP-ZZ-00221 Search and Rescue 0
04/29/83 Hlth Phy EIP-ZZ-00222 Emergency Repair 0
04/29/83 Hith Phy EIP-ZZ-00223 Field Monitoring 0
05/18/83 05/12/83 Hltn_Phy EIP-ZZ-00224 Transport of Contaminated 0
04/29/83 04/19/83 Hith Phy Injured / il Personnel i
.T EIP-ZZ-00225 Reentry 0
06/15/83 Hlth Phy i
,i
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EIP-ZZ-00230 Evacuation 1
12/13/83 09/13/83 Emg. Prep l
c.,
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of 2
^-)
4' EMERGENCY PREPAREDNESS Procedure Date Deficiency. Resp.
Number Title Rev.
Issued Page Date Deot.
i EIP-ZZ-00240 Technical Support Center 1
12/13/83 Eng. Prep Operations EIP-ZZ-00241 Operational Support Center 1 12/13/83 Emg. Prep Operations EIP-ZZ-00250 Communications & Records 0
05/18/83 Hlth Phy Keeping EIP-ZZ-00260 Recovery 0
05/18/83 Hlth Phy EIP-ZZ-01211 Initial Dose Assessment 0
10/19/83 09/30/83 Emg Prep EIP-ZZ-02211 Intermediate Phase and 0
10/19/83 09/30/83
'Emg Prep Subsequent Dose Assessment
([. EIP-ZZ-A0010 Emergency Drills and 0
12/07/83 11/20/83 Hlth Phy Exercises EIP-ZZ-A0020 Maintaining Emergency 0
12/07/83 Hith Phy Preparedness EIP-ZZ-C0010 Duties of the Corporate 0
12/07/83 12/02/83 Er.ig Prep Emergency Organi'.ation EIP-ZZ-C0020 Callout of Corporate 0
12/07/83 12/02/83 Emg Prep Emergency Organization I
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UNION ELEC~RIC NUC' EAR CPERAT:CNS COUR7tLED DOCUMENT TRANSH!- AL AND RECE!PT FORM h
ed YA h,4 9 d n. s. h b.. Lk".p V*l IO L
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2CS55 g g,5,
yn FROM: Document Control
- ,g, Enclosure (s)
EIP INDEX EIP-ZZ-00101 P27 1 JPK/cre Please insert the enclosed material into your Manual / Procedure File.
Return sheet to:
J. P. Kanyo RMS Supervisor, Document Control Union Electric Company Callaway Plant - CA-46C Acknowledgement:
I htve brought my Manual / Procedure File to current status by incorporating the above material. Superseded pages have been removed and destroyed.
Signature:
Dates _
?!LI *A6L.16 CA-832A Rev. 12/82 0
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