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{{#Wiki_filter:}} | {{#Wiki_filter:"*"""" um a VIZINIA POWER SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE 10 NUMBER PROCEDURE TITLE REVISION 15 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE (With 1 Attachment) 1 of 8 PURPOSE To initially assess a potential emergency condition and initiate corrective actions. | ||
USER Shift Supervisor or Station Emergency Manager ENTRY OONDITIONS Any one of the following: | |||
: 1. Another station procedure directs initiation of this procedure | |||
: 2. A potential emergency condition is reported to the Shift Supervisor. | |||
R{g{0gECOfkGE(S): 1 of 8 and 5 of 8 DATE: 01-13-84 REV. 10 PAGE(S): 1, 6; Att. 1, pgs. 6, 7, 8 and 9 DATE: 02-02-84 REV. 11 PAGE(S): 1 of 8 and 5 of 8 DATE: 03-01-84 REV. 12 PAGE(S): 1, 2, 3, 4, 5, 6 and 7 of 7 DATE: 05-21-85 REV. 13 PAGE(S): Entire Procedure and Attachment 1 DATE: 05-27-86 REV. 14 PAGE(S): Att. 1, pgs 2,10,11.22 thru 25, 27 & 28 DATE: 06-25-86 REV. 15 PAGE(S): 1,4;Att. 1, pgs 2 thru 24,26,28 thru 41 DATE: q q APPRO L EC MM ED SNSOC REVIEW p OATE O - A ' | |||
JUL 3 4 1980 G /V m b-6C REVIEW STATION MAN GER APPROVAL DA TE | |||
/JO_Mo1 48 4 t m, | |||
[ 0609040159 860729 PDR ADOCK 05000280 4 F PDR EPIPA - | |||
um n | |||
(( yt;ZINIA POWER SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE A | |||
NUMBER PRO 2 DURE TITLE REVISION 15 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE l | |||
(With 1 Attachment) 1 of 8 j l | |||
PURPOSE 1 Tc initially assess a potential emergency condition and initiate corrective ; | |||
actions. , | |||
1 USER Shift Supervisor or Station Emergency Manager ENTRY CONDITIONS Any one of the following: | |||
: 1. Another station procedure directs initiation of this procedure | |||
: 2. A potential emergency condition is reported to the Shift Supervisor. | |||
"fM! &'c FRGE(S): 1 of 8 and 5 of 8 DATE: 01-13-84 REV. 10 PAGE(S): 1, 6; Att. 1, pgs. 6, 7, 8 and 9 DATE: 02-02-84 REV. 11 P AGE (S): 1 of 8 and 5 of 8 DATE: 03-01-84 REV. 12 PAGE(S): 1, 2, 3, 4, 5, 6 and 7 of 7 DATE: 05-21-85 REV. 13 PAGE(S): Entire Procedure and Attachment i DATE: 05-27-86 REV. 14 PAGE(S): Att. 1, pgs 2,10,11,22 thru 25, 27 8 28 DATE: 06-25-86 REV. 15 PAGE(S): 1,4;Att. 1, pgs 2 thru 24,26,28 thru 41 DATE:g.,g g I 4 1980 6C REVIEW STATION MAN GER APPROVAL DA TE aoLA /7/d& as< m | |||
[ 8608040159 860729 PDR ADOCK 05000280 a F PDR | |||
-- EPIPA- -- - _ . _ _ . _ _ _ | |||
Ns.97887210 NUNDER PROCEDURE TITLE REVISION 15 O EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 2 of 8 | |||
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTORTAINED | |||
: 1. INITIAL ASSESSMENT: | |||
a) Perform initial assessment from EAL tables b) IF EAL exceeded, b) IF,no EAL exceeded, THEN initiate EPIP-1.01: return to procedure in effect | |||
: 1) BY: | |||
DATE: | |||
TIME: | |||
) NOTE: Continue through this and all further instructions unless other-wise directed to hold. | |||
: 2. IDENTIFY EVENT: . | |||
a) Event-TRANSPORT OF CONTAMI- a) GO TO Step 2b,of this in-NATED INJURED PERSONNEL struction. | |||
: 1) Initiate EPIP-5.01 Transport of Contami- | |||
. nated Injured Personnel | |||
; 2) Verify initiation of i | |||
EPIP-4.20, H.P. Actions I for Transport of Injured Contaminated Personnel | |||
! 3) Continue this instruction i | |||
1 I | |||
Me.C788721% | |||
NUNDER PROCEDURE TITLE REVISION 15 O EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 3 of 8 | |||
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED | |||
: 2. [ continued] | |||
; b) Event-Any of the fo'11owing; b) GO E Step 3_ of this in-struction. | |||
* Radiation Release | |||
* Fuel Handling Incident | |||
* Secondary Release | |||
* S/G Tube Rupture | |||
* LOCA | |||
: 1) Request Health Physics O initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure, and continue this instruction e | |||
l J | |||
; O | |||
- . . - . . - - . - . . _ _ - . . . . . - . - _ . - _ _ _ _ - . _ - - - ~ - . - _ _ - _ . _ _ _ _ _ _ _ _ - . - - - - - . - _ _ . - - , . - . . . - - - - . _ _ - . - | |||
Pee. 97887210 NUNDER PROCEDURE TITLE REVISION O | |||
V EPIP-1.01 15 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 4 of 8 | |||
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED | |||
, CAUTION: Declaration of the highest emergency class for which an , | |||
Emergency Action Level is exceeded shall be made. | |||
NOTE: The SPDS is potentially unreliable in the event of an earthquake. There-fore, the SPDS should be evaluated for reliability of accident assessment should this situation occur. | |||
: 3. ASSESSMENT AND CLASSIFICATION: | |||
a) Use the SPDS to obtain a) ))[ SPDS NOT operable, GO TO indications of emergency Step 3.b. | |||
I conditions listed in the EAL Table, as necessary. . | |||
b) Use EPIP 1.01, of Attach-ment 1,, Index Emergency Action Levels to determine event category AND l | |||
i GO TO proper EAL tab l | |||
I c) Evaluate event to deter-mine classification, AND , | |||
GO p Step 4_ of this pro-cedure O | |||
~ | |||
Pse.97887210 NUNDER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 5 of 8 | |||
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED | |||
: 4. NOTIFICATION AND VERIFICATION: | |||
a) LEOF - NOT ACTIVATED a) E LEOF activated, announce transfer of command from TSC to LEOF and proceed to step 4.b. | |||
b) TSC - NOT ACTIVATED b) E TSC activated, GO TO Step 6_. | |||
c) Notify SRO-On-Call or Super- c) Notify Station Manager or intendent of Operations Asst. Station Manager. | |||
d) Verify emergency classifica-tion e) If required by ALERT SITE AREA, or GENERAL emergency, request initiation of STANDING ORDER #21, Augmented Staff Resources During Emer-gency Plan Activation. . | |||
NOTE: Return to Step 2 of this instruction as necessary to consider additional events and reclassification. | |||
: 5. VERIFY EALS EXCEEDED: | |||
a) Assure EALs - EXCEEDED a) H EALs NOT exceeded, DO NOT declare an emergency classification, AND GO TO Step J,of this procedure. | |||
i b) E required, assign appropri-ate individual as Emergency Communicator c) E required, direct senior H.P. | |||
personnel on site to initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure | |||
pee, ovestaD NUN 8ER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE | |||
; 6 of 8 | |||
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTOCTAINED | |||
: 6. DETERMINE EPIPS: | |||
a) Event classification - a) GO TO Step b6_b,of this in-NOTIFICATION OF UNUSUAL EVENT struction. | |||
i 1) C0 TO EPIP-1.02, Response i | |||
to Notification of Unusual Event b) Event classification - ALERT b) GO TO Step 6c_ of this instruction. | |||
: 1) GO TO EPIP-1.03, Response to Alert c) Event classification - SITE c) CO TO Step 6d of this AREA EMERGENCY instruction 7 | |||
: 1) GO TO EPIP-1.04, Response to Site Area Emergency d) Event classification - | |||
GENERAL EMERGENCY | |||
: 1) CO TO EPIP-1.05, Response to General Emergency i | |||
: 7. SECURE FROM EVENT: | |||
.a) Notify involved station personnel that emergency condition does not exist b) CO TO Step 11 of this instruc-tion 1 | |||
O i | |||
1 | |||
Pee. 97887210 NUMMR PROCEDURE TITLE REVISION 15 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE | |||
; 7 of 8 | |||
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTORTAINED l | |||
: 8. TERMINATION NOTIFICATIONSt a) Initiate termination notifi-i cation to state and local governments IAW EPIP-2.01, Notification of State and Local Governments b) Initiate termination notifi-cation to NRC IAW EPIP-2.02, Notification of NRC | |||
: 9. REPORTING O a) Verify required reports and notifications IAW EPIP-2.03, Reports to Offsite Agencies | |||
: 10. RECOVERY ACTIONS: | |||
a) Notify involved station j personnel of emergency j termination l | |||
b) Initiate recovery actions b) JJ[ required, GO TO EPIP-6.01 IAW established station Reentry / Recovery Guidelines | |||
- procedures and capabilities | |||
) c) )); required, deactivate | |||
! station emergency response l facilities and personnel O | |||
I i | |||
I | |||
.. m. | |||
MUNetR PROCEDURE TITLE REVISION g 15 | |||
) EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 8 of 8 | |||
= STEP ACTIONNXPECTED RESPONSE RESPONSENOTORTAINEO i | |||
i | |||
: 11. TERMINATE EPIP-1.01: | |||
a) COMPLETED BY: | |||
DATE: | |||
TIME: | |||
i | |||
; b) Forward completed EPIP-1.01, 1 | |||
forms and other applicable | |||
) records to Secretary SNSOC , | |||
END l | |||
i l | |||
t I | |||
i i | |||
l | |||
} . | |||
l i | |||
l I | |||
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i O | |||
No. 91887tto r NUMBER A TTACHMENT TITLE REVISION | |||
$ EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE 1 INDEX 1 of 41 CAUTIO/t Declaration of the highest emergency class for which an EAL is exceeded shall be made. | |||
GO TO IF EVENT CATEGORY IS: TAB i, | |||
: 1. Safety, Shutdown, or Assessment System Event . . . . . . . . . . . . . . . . . . . . A | |||
: 2. Reactor Coolant System Event ....................................B | |||
: 3. Fuel Failure or Fuel Handling Accident...........................C | |||
: 4. C o n t a i nme n t Ev e n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D | |||
: 5. Radioactivity Event..............................................E | |||
: 6. C on t amina t e d P e r s o nne l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F | |||
: 7. LOSS of Secondary Cooling........................................G | |||
: 8. E le c t r ic a l Fa ilu r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H | |||
! 9. Fire.............................................................I | |||
) 10 . Security Event...................................................J | |||
: 11. Hazard to Station Operation......................................K | |||
: 12. Natural Events...................................................L | |||
: 13. Miscellaneous Abnormal Events...............................- ....M 6 | |||
j 1 | |||
No.9788722) | |||
NUMBER A TTACHMENT TITLE REVISION ss EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAE A) 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 2 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Non-spurious ECCS Non-spurious ECCS NOTIFICATION OF initiation initiation as vali- UNUSUAL EVENT dated by Emergency AB0VE CSD CONDITION Procedures t | |||
: 2. Mode reduction required Intentional reduction in NOTIFICATION OF by Tech. Spec. Limiting Power, Load or Temperature UNUSUAL EVENT Condition for Opera- because the unit has entered tion an Action Statement or will exceed a Limiting Condition l POWER & HSB for Operation. , | |||
1 NOTE: In the event that other | |||
, plant conditions require a shutdown, NOTIFICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required by the Tech Spec. | |||
: 3. Loss of Function needed Total loss of: SITE AREA for unit HSD condition EMERGENCY a) Charging /SI System ABOVE CSD CONDITION O,R, b) Main feedwater AND Auxiliary Feedwater Systems i | |||
N).97007220 NUMBER A TTACHMENT TITLE REVISION l | |||
[ | |||
\ | |||
EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 A TTACHMENT (TAB A) ppgg i SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 3 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 4. Loss of function need- Loss of heat removal ALERT ed for unit CSD con- capability due to total dition loss of any of the following systems: | |||
CSD a) Service Water 8 E | |||
b) Component Cooling E | |||
c) Residual Heat Removal O 5. Failure of a safety or relief valve to Condition a) or b) exists: NOTIFICATION OF UNUSUAL EVENT close after pressure reduction a) Pressurizer safety or PORV flow as indicated ALL CONDITIONS by accoustical or tem-perature monitoring equipment i | |||
AND RCS subcooling - LESS THAN 30*F b) Excessive flow through Steam Generator Safety, | |||
- PORV, or Decay Heat Release valve indicated by RCS cooldown rate | |||
: > 50*F per hour I | |||
i O | |||
N3.97887223 sq NUMBER A TTACHMENT TITLE REVISION f ; EPIP-1.01 15 | |||
\~ / EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB A) ppgg 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENI 4 of 41 b | |||
CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 6. Failure of the Reactor Condition a) and b) , SITE AREA to trip (ATWT) exists with c) EMERGENCY POWER & HSB a) RX trip setpoint and coincidences - EXCEEDED i | |||
AND b) Manual Rx trip - INITIATED AND c) Rx power indication-NOT DECREASING b | |||
: 7. Trip following ATWT that a) ATWT - Manual Reactor ALERT takes the Rx Suberitical Trip following failure of Auto Trip Circuit POWER & HSB AND , | |||
I | |||
. b) Reactor power - | |||
DECREASING | |||
: 8. Indications or alarms Intentional reduction in NOTIFICATION OF on process or effluent Power, Load or Temperature UNUSUAL EVENT i | |||
parameters required for because the unit has incident assessment NOT entered an Action Statement available or will exceed a Limiting Condition for Operation. | |||
ABOVE CSD CONDITION | |||
! NOTE: In the event that - | |||
- = _ _ _.d l other plant conditions , | |||
l require a shutdown, NOTI- ~ - ~ | |||
FICATION OF UNUSUAL EVENT | |||
{ | |||
must still be declared on , | |||
the basis that a shutdown would have been required by the Tech Spec. | |||
- . _ . --._ -. . . . - - . - - . _ - - - - - - _ _ _ = _ --. . . . . . | |||
No. 97007330 l | |||
1 NUMMR A TTACHNENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE | |||
: ATTACHNENT (TAB A) PAGE 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 5 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 9. Failure of meteorological Loss of all onsite and off- NOTIFICATION OF instrumentation required site meterological monitoring UNUSUAL EVENT to perforn offsite dose capability calculations. | |||
ALL CONDITIONS t | |||
: 10. Loss of plant communica- Complete failure of: NOTIFICATION OF tions capability UNUSUAL EVENT ALL CONDITIONS a) Station Gai-Tronics system , | |||
^"" | |||
O b) Station UHF radio system | |||
: 11. All main board annunci- a) Complete loss of all SITE AREA ator alarms and unit annunciator alarms on EMERGENCY computer lost for more panels "A" to "K" than 15 minutes during a unit transient AND l POWER & HSB b) Loss of unit computer for GREATER THAN 15 minutes AND c) Unit operational tran-t sient - IN PROGRESS | |||
: 12. All main board annunci- a) Simultaneous loss of all ALERT | |||
! ator alarms and unit annunciator alarms on computer lost panels "A" to "K" l | |||
POWER & HSB AND b) Loss of unit computer 5 | |||
i l | |||
. -. -..,n.. ,__c.. -- . -;. , . . _ _ . - . . . - _ . . , | |||
Nr.97887220 NUMBER A TTACHMENT TITLE REVISION 0 EPIP-1.01 A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAE A) 15 PAGE 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 6 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 13. Evacuation of Main Con- Evacuation of the Control SITE AREA trol Room with control Roon with stable shutdown EMERGENCY NOT established within control NOT established 15 minutes within 15 minutes ALL CONDITIONS g | |||
: 14. Evacuation of Main Con- Evacuation of the Control ALERT trol Room required Room with stable shutdown control established within ALL CONDITIONS 15 minutes 1 | |||
O 4 | |||
0 | |||
nu. oreenn NUMBER A TTACHMENT TITLE REVISION O EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 A TTACHMENT (TAB B) PAGE 1 REACTOR COOLANT SYSTEM EVENT 7 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION ' | |||
: 1. Tech. Spec. Safety Limits Verification of any Tech. NOTIFICATION OF for RCS exceeded Spec. Safety limit for RCS UNUSUAL EVENT POWER & HSB I | |||
: 2. RCS leak rate exceeds EP-2.00, Loss of Reactor SITE AREA i | |||
makeup capacity Coolant - IMPLEMENTED EMERGENCY ABOVE CSD CONDITION AND i | |||
Pressurizer level cannot be maintained with two (2) | |||
, Charging /SI Pumps in operation l | |||
: 3. RCS' leak rate exceeds Intentional reduction in ALERT 50 gpm Power, Load or Temperature because the unit has ABOVE CSD CONDITION entered an Acticn State-ment or will exceed a | |||
. Limiting Condition for Operation. | |||
j NOTE: In the event that other plant conditions require a shutdown, NOTI-FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required by the Tech Spec. | |||
l l | |||
a) Actions required IAW AP-16, Excessive Primary Plant Leakage , | |||
AND l | |||
l O b) RCS inventory balance indicates leakage - | |||
GREATER THAN 50 gpm i | |||
" ~ | |||
, i N:9. 97887223 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE PA GE A TTACHMENT (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 8 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 4. RCS leak rate requiring Intentional reduction in NOTIFICATION OF plant shutdown IAW Power, Load or Temperature UNUSUAL EVENT T.S. 3.1.C because the unit has entered an Action State-POWER & HSB ment or will exceed a Limiting Condition for Operation. | |||
NOTE: In the event that other plant conditions require a shutdown, NOTI-FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown - | |||
would have been required by the Tech Spec. | |||
a) Unidentified RCS leakage - GREATER | |||
! THAN 1 gym E | |||
b) Indentified leekege - | |||
GREATER THAN H gpm E | |||
I c) Non-isolatable fault of RCS pressure boundary I | |||
O | |||
NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 O A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAE B) ppgg i | |||
i REACTOR COOLANT SYSTEM EVENT 9 of 41 CONDITION / APPLICABILITY INDICATIOli CLASSIFICATION I | |||
: 5. RCP locked rotor a) Flow in one or more ALERT leading to fuel dam- RC loops - LESS THAN age 90J POWER AND , | |||
b) RCP trip caused by Phase Overcurrent Relay - | |||
ACTUATION AND c) High Range Letdown Rad-iation Monitor (RM-CH-118, | |||
-218) indication incregses to - GREATER THAN 5x10 O- cpm | |||
: 6. Gross Primary to Second- EP-4.00, Steam Generator SITE AREA ary leakage with loss of Tube Rupture - IMPLEMENTED EMERGENCY offsite power AB0VE CSD CONDITION AND e | |||
Loss of offsite power indi-cated by zero volts for 4160V Buses D, E & F l | |||
l 1 | |||
i O | |||
l | |||
N3.97857220 NUMBER A TTACHMENT TITLE REVISION | |||
'T EPIP-1.01 15 | |||
: s. EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B) ppgg 1 REACTOR COOLANT SYSTEM EVENT 10 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 7. Excessive Primary to Intentional reduction in ALERT Secondary leakage with Power, Load or Temperature loss of offsite power because the unit has entered an Action Statement ABOVE CSD CONDITION or will exceed a Limiting Condition for Operation. , | |||
a) Primary to Secondary leakage - GREATER THAN 1.gpm 0,R, | |||
/h GREATER THAN 500 gal. | |||
k-/ per day per generator AND b) zero volts for 4160V busses D, E & F. | |||
: 8. Gross Primary to EP-4.00, Steam Generator ALERT Secondary leakage T,ube Rupture - IMPLEMENTED ABOVE CSD CONDITION I | |||
( | |||
l l | |||
l | |||
I us.steersso NUMBER A TTACHMENT TITLE REVISION y | |||
EPIP-1.01 15 l EMERGENCY ACTION LEVEL TABLE PAGE A TTACHMENT (3gg g) 1 REACTOR COOLANT SYSTEM EVENT 11 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 4 | |||
: 9. Primary to Secondary Intentional reduction in NOTIFICATION OF leakage - GREATER THAN Power, Load or Temperature UNUSUAL EVENT 1 gpm because the unit has entered an Action State-ABOVE CSD CONDITION ment or will exceed a , | |||
Limiting Condition for Operation. | |||
NOTE: In the event that other plant conditions require a shutdown, NOTI-FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required O by the Tech Spec. | |||
a) Primary to Secondary leakage - GREATER THAN J_ 8Pm 2. | |||
GREATER THAN 500 gal, per day per generator. | |||
i | |||
>s | |||
N3.97887220 x NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 12 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 10. Loss of 2 of 3 fission Any two of a), b) or c) GENERAL product barriers with exist and the third is EMERGENCY potential loss of 3rd imminent barrier a) Fuel clad integrity ALL CONDITIONS failure as indicated by any of the following: 3 | |||
: 1) RCS specific activity - | |||
GREATER THAN OR EQUAL TO 300 pCi/ gram dose equivalent I-131. | |||
: 2) 5 or more core exit thermocouples reading-O GREATER THAN 1200*F b) Loss of RCS integrity as indicated by any of the following: | |||
: 1) PORV failed open | |||
: 2) Loss of Reactor Coolant | |||
: 3) Outside Containment High Range Gamma Radiation Monitor (RM-RMS-161, -261) read 2x10{ng-GREATERTHAN mR/hr c) Loss of containment integ-rity as indicated by any of the following: | |||
: 1) Containment pressure - | |||
GREATER THAN 60 psia AND NOT DECREASING ' | |||
: 2) OP-1E, Containment Integrity Checklist. | |||
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAE B) 1 REACTOR COOLANT SYSTEM EVENT 13 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 11. Fuel failure with steam Any two of a), b) or c) GENERAL generator tube rupture exists and the third is ' EMERGENCY imminent ALL CONDITIONS a) Fuel clad integrity failure as indicated by any of the following: | |||
: 1) RCS specific activity - | |||
GREATER THAN 300 pCi/ | |||
gram dose equivalent I-131 | |||
: 2) 5 or more core exit thermocouples indi-cate - GREATER THAN | |||
) 1200 *F b) S/G tube rupture as indicated by both of the following: | |||
: 1) RCS Low Pressure SI - | |||
INITIATED | |||
: 2) EP-4.00, Steam Genera-tor Tube Rupture. - | |||
IMPLEMENTED c) Loss of Secondary integ-rity as indicated by: | |||
: 1) Steam discharge to at-mosphere | |||
: 2) EP-3.00, Loss of Secondary Coolant - | |||
{ | |||
IMPLEMENTED i O | |||
N3. 97887223 NUMBER A TTACHMENT TITI.E REVISION EPIP-1.01 Q EMERGENCY ACTION LEVEL TABLE 15 A TTACHMENT (TAB C) PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 14 of 41 ; | |||
CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Ccre damage with pos- Condition a) exists with SITE AREA sible loss of coolable b) EMERGENCY geometry a) Fuel clad failure as ABOVE CSD CONDITT.ON indicated by any of the following: 1 | |||
: 1) RCS Specific activ-ity - GREATER THAN 60 pCi/ gram dose equivalent I-131 | |||
: 2) High Range Letdown Radiation Monitor - | |||
. (RM-CH-118, -218) | |||
(' indicatiog - GREATER THAN 1x10 cpm AND b) Loss of cooling as in-dicated by any of the following: | |||
: 1) 5 confirmed core exit thermocouples - GREATER THAN 1200*F | |||
, 2) Core AT - ZERO | |||
: 3) Core AT - RAPIDLY DIVERGING O | |||
N3.97887223 NUMBER A TTACHMENT TITLE REVISION | |||
.m EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 15 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 2. Severe Fuel Clad a) RCS specific activity - ALERT Damage GREATER THAN 300 pCi/ gram dose equivalent I-131 ABOVE CSD CONDITION , | |||
E High Range Letdown Radi-ation Monitor (RM-CH-118, | |||
-218)indicationgnereases GREATER THAN 5x10 cpm within 30 minutes AND remains 7or at least M minutes | |||
: 3. Fuel clad damage Intentional reduction in NOTIFICATION OF indication Power, Load or Temperature UNUSUAL EVENT because the unit has ABOVE CSD CONDITION entered an Action State-8 ment or will exceed a Limiting Condition for Operation. | |||
NOTE: In the event that other plant conditions require a shutdown, NOTI-l FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required l by the Tech Spec. | |||
E a) High Range Letdown Radiation Monitor indication increases - | |||
GREATER THAN 10,5 cpm i within 30 minutes AND I remains for at least H minutes. | |||
O | |||
No. 97987tt9 REVISION m NUMBER A TTACHMENT TITLE j) EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 16 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 4. Probable large radio- a) EP-2.00, Loss of Reactor GENERAL activity release Coolant, - IMPLEMENTED, EMERGENCY initiated by LOCA with ECSS failure leading to AND core degradation RCS specific activity - | |||
AB0VE CSD CONDITION GREATER THAN 3f0,pCi/ gram dose equivalent 1-131 AND b) High or Low Head ECCS flow - NOT being delivered to the core I 5. Probable large radio- a) Loss of Main FW system GENERAL activity release and Condansate System EMERGENCY initiated by loss of neat sink leading to core AND degradation b) Loss of Auxiliary FW ABOVE CSD CONDITION System AND c) RHR System - NOT OPERABLE | |||
: 6. Probable large radio- a) Rx nuclear power af ter GENERAL activity release a trip remains - GREATER EMERGENCY initiated by failure of THAN 5% | |||
protection system to bring Rx suberitical AND and causing core de-gradation b) RCS pressure - GREATER THAN 2485 psig AND NOT AB0VE CSD CONDITION decreasing , | |||
0,,R Containment pressure and | |||
[''} | |||
(m ,/ | |||
temperature are RAPIDLY INCREASING | |||
Nr.97887220 NUMBER A TTACHMENT TITI.E REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE L(TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 17 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 7. Probable large radio- a) ECA-2, Loss of All ac GENERAL activity release Power - IMPLEMENTED EMERGENCY initiated by loss of AC and all feedwater AND ABOVE CSD CONDITION b) Turbine Driven Auxiliary , | |||
Feedwater Pump NOT OPERABLE AND c) Restoration of a) or b) above not likely within 2, hours | |||
: 8. Probable large radio- a) EP-2, Loss of Reactor GENERAL O''- activity release Coolant - IMPLEMENTED EMERGENCY initiated by LOCA with loss of ECCS and con- AND tainment cooling b) High Ojt Low Head ECCS ABOVE CSD CONDITION flow NOT being delivered | |||
- to the core AND c) Containment RS sump temp-erature-GREATER THAN 190*F AND NOT DECREASING pR Containment Spray and Recir-culation Spray Systems- NOT OPERABLE i | |||
O | |||
2. | |||
N3.97887220 t | |||
NUMBER A TTACHNENT TITLE REVISION EPlP-1.01 15 J | |||
EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE l (TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 18 of 41 i | |||
CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 9. Major fuel damage a) Water level in Rx vessel SITE AREA accident with radio- during refueling - BELOW EMERGENCY activity release to TOP OF CORE containment or fuel buildings R O_R ALL CONDITIONS .W ater level in Spent Fuel , | |||
Pit verified - BELOW TOP OF SPENT FUEL AND b) Verified damage to irra-diated fuel resulting in . | |||
; readings on Ventilation 4 | |||
g ,/ VentGaseousMonigor-GREATER THAN 1x10 cpm | |||
: 10. Fuel damage accident a) Verified accident involv- ALERT with release of radio- ing damage to irradiated activity to containment fuel or fuel buildings AND ALL CONDITIONS b) Health Physics confirms a fission product release l | |||
from fuel SR c) Readings on the Ventila-tion Vent Gaseous Monitor (RM-fG-110) - GREATER THAN 1x10 cpm | |||
: 11. Spent Fuel Storage a) Verified loss of all cask / ALERTk' Facility accident with fuel containment barriers release of radioactivity AND O ALL CONDITIONS b) Health Physics confirms fission product release a | |||
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C) PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 19 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 12. Spent Fuel Storage a) Verified SSSC seal leak- NOTIFICATION OF Facility accident age UNUSUAL EVENT ALL CONDITIONS OR b) Spent Fuel Storage Cask dropped or mishandled O | |||
NB.97887223 NUMBER A TTACHMENT TITLE REVISION O' EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 PAGE A TTACHMENT (TAB D) 1 CONTAINMENT EVENT 20 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Extremely high Con- a) Outside Containment High GENERAL tainment radiation, Range Radiation Monitor EMERGENCY pressure and tem- (RM-RMS-161, -261 - | |||
perature GREATERTHAN5x10{mR/hr AB0VE CSD CONDITION AND e b) Containment pressure - | |||
GREATER THAN 45 psia AND is NOT decreasing 0.R | |||
^, | |||
Containment temperature - | |||
GREATER THAN 280*F | |||
: 2. High Containment a) Outside Containment High SITE AREA radiation, pressure, Range Radiation Monitor EMERGENCY and temperature (RM-RMS-161, -261 - | |||
GREATERTHAN2x10}mR/hr ABOVE CSD CONDITION AND e b) Containment pressure - | |||
3 psia GREATER THAN _23, and is NOT decreasing | |||
, OR 1 | |||
l Containment temperature - | |||
GREATER THAN 200*F I | |||
i O | |||
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB D) 1 CONTAINMENT EVENT 21 of 41 l | |||
CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 3. High Containment radia- a) Outside Containment High ALERT tion, pressure and Range Radiation Monitor temperature (RM-RMS-161, -2pl) - | |||
GREATER THAN 10 mR/hr ABOVE CSD CONDITION ' | |||
AND b) Containment pressure - | |||
GREATER THAN 17.7 psia pR Containment temperature - | |||
GREATER THAN 150 *F | |||
: 4. Loss of Containment Intentional reduction in NOTIFICATION OF integrity Power, Load or Temperature UNUSUAL EVENT because the unit has entered ABOVE CSD CONDITION an Action Statement or will exceed a Limiting Condition a for Operations. | |||
NOTE: In the event that other plant conditions l, require a shutdown. NOTI- | |||
! FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required by the Tech Spec. | |||
a) Loss of Containment integrity as indi-cated by OP-1E, Containment Integrity Checklist. | |||
D | |||
, . _ . _2 N2.91991220 CD EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB E) 1 RADI0ACTIVI;Y EVENT 22 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Projected or actual a) Confirmed actual or GENERAL site boundary doses projected site boundary EMERGENCY exceed 2 Rem W.B. or doses - GREATER THAN g Rem thyroid ex- 2.0 Rem Whole Body OR posure 12.0 Rem Thyroid exposure as determined ALL CONDITIONS from EPIP-4.01. | |||
a | |||
: 2. Projected or actual a) Confirmed actual or SITE AREA N site boundary doses projected site boundary EMERGENCY of 0.5 Rem to 2 Rem doses - GREATER THAN W.B. or 1 Rem to 12 0.5 Rem Whole Body or Rem thyroid exposure 1.0 Rem Thyroid exposure as determined ALi, CONDITIONS from EPIP-4.01. | |||
a O | |||
l 1 | |||
ND.97887223 NUMBER ATTACHMENT TITLE REVISION O EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 A TTACHMENT PAGE (TAB E) 1 RADI0 ACTIVITY EVENT 23 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 3. High radiation or air- Valid unexpected readings ALERT borne contamination on any of the following levels indicate a monitors have increased by severe degradation in a factor of 1000 control of radioactive material a) Control Room Area Monitor (RM-RMS-157) | |||
ALL CONDITIONS b) Auxiliary Building a Control Area Monitor (RM-RMS-154) c) Auxiliary Building Drumming Area Monitor (RM-RMS-ISS) d) Decontamination Building Area Monitor (RM-RMS-151) e) Fuel Pit Bridge Area Monitor (RM-RMS-153) f) New Fuel Storage Area Monitor (RM-RMS-152) g) Laboratory Area Monitor (RM-RMS-158) h) Sample Room Area Monitor (RM-RMS-156) i O | |||
,, .--,m | |||
N3.97887220 r NUMBER A TTACHMENT TITLE REVISION | |||
( EPIP-1.01 15 | |||
-- EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB E) 1 RADIOACTIVITY EVENT 24 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 4. Effluent Release GREATER a) Ventilation Vent Gaseous ALERT THAN 10 TIMES T.S. Monitor (RM-VG-110 or instantaneous allowable RM-VG-131) - GREATER limits THAN 1000% T.S. value as determined from Attach-ALL CONDITIONS ment 1, AP-5.20 E | |||
b) Process Vent Gaseous Monitor (RM-GW-102 or RM-GW-130) - GREATER THAN 1000% T.S. value I as determined from Attachment 1, AP-5.01 m | |||
c) Air Ejector Monitor (RM-SV-111, -211)6-GREATER THAN 1x10 cpm AND Air ejector exhaust - | |||
NOT diverted to contain-ment. | |||
E d) Discharge Tunnel Monitor (RM-SW-120, -220) 5 GREATER THAN 1.3x10 cpm 9.R e) Sampling and Analysis Team confirms effluent l | |||
i release GREATER THAN 1000% T.S. value as determined from EPIP-4.01. | |||
'l | |||
N3.97087220 p NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB E) 1 RADI0 ACTIVITY EVENT 25 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 5. Effluent release GREATER a) Ventilation Vent Gaseous NOTIFICATION OF THAN T.S. allowable Monitor (RM-VG-110 or UNUSUAL EVENT Limit RM-VG-131) - GREATER THAN 100% T.S. value as ALL CONDITIONS detemined from Attach-ment 1, AP-5.20 0,R b) Process Vent Gaseous Monitor (RM-GW-102 or RM-GW-130) - GREATER THAN 100% T.S. value as determined from p Attachment 1 AP-5.01 a | |||
c) Air Ejector Monitor (RM-SV-111, -211) 5 GREATER THAN 1.99x10 cpm AND Air Ejector Exhaust - | |||
NOT diverted to contain-cent. | |||
pR d) Discharge Canal Monitor (RM-SW-120, -220) 4 GREATER THAN 1.3x10 cpm e) Sampling and Analysis Team confirms effluent release GREATER THAN 100% T.S. value as i determined from EPIP-4.01. | |||
O | |||
2 N9.97887220 CD EPIP-1,01 EMERGENCY ACTION LEVEL TABLE 15 ATTACHMENT PAGE (TAB E) 1 CONTAMINATED PERSONNEL 26 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Transportation of Contaminated injured indi- NOTIFICATION OF contaminated injured vidual enroute to off-site UNUSUAL EVENT individual to off-site facility for treatment facility ALL CONDITIONS i | |||
I | |||
.O l | |||
6 | |||
!O | |||
N3.97887223 | |||
/~ NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB G) 1 LOSS OF SECONDARY COOLANT 27 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Major Secondary line a) EP-3.00, Loss of SITE AREA break with Primary to Secondary Coolant - EMERGENCY Secondary leakage IMPLEMENTED AND GREATER THAN 50 gpm and verified non-spurious fuel damage indicated AND AB0VE CSD CONDITION b) RCS specific activity - | |||
GREATER THAN 300 pCi/ gram E | |||
Letdown High Range Radia-t | |||
' tion Monitor (RM-CH-118 5 | |||
-218) - GREATER THAN 10 cpm t AND c) Condenser Air Ejector RadiationMonitor(RM-Sg-111 | |||
-211) - GREATER THAN 10 cpm Steam Generator Blowdown Radiation Monitor (RM-SS-112, | |||
-113,-g12,-213)-GREATER THAN 10 cpm E | |||
MS Line High Range Radiation Monitor (RM-RI-MS-124, -125, | |||
-126,-224,-225,-236)- | |||
GREATER THAN 7.5x10 mR/hr l i | |||
O | |||
.a Ns 91997220 p NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB G) PAGE 1 LOSS OF SECONDARY COOLANT 28 of 41 t | |||
CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 2. Major Secondary line a) EP-3.00, Loss of Second- ALERT break with Primary to ary Coolant - IMPLEMENTED Secondary leakage AND verified to be non-greater than 10 GPM spurious ABOVE CSD CONDITION AND , | |||
] | |||
; b) Condenser Air Ejector Radiation Monitor | |||
~ | |||
(RM-SV-111 -211)6 GREATER THAN 1x10 cpm E | |||
O Steam Generator Blowdown Radiation Monitor (RM-SS-112, -113 -212 ~ | |||
5 | |||
)~ | |||
GREATER THAN 10 cpm E | |||
MS Line High Range Radia-tion Monitor (RM-RI-MS-124, | |||
-125, -126, -224, -225, | |||
-226) - GREATER THAN 0.5 mR/hr I | |||
: 3. Major Secondary line EP-3.00, Loss of Secondary NOTIFICATION OF break Coolant, - IMPLEMENTED UNUSUAL EVENT AND verified non-spurious ABOVE CSD CONDITION I i i | |||
O | |||
a N3.97887220 Q NUMBER A TTACHMENT TITLE REVISION V EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B) PAGE 1 ELECTRICAL FAILURE 29 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Loss of off-site a) Unit Main Generator AND NOTIFICATION OF power or on-site AC both Emergency Diesel UNUSUAL EVENT power capability Generators out of service ALL CONDITIONS OR a | |||
b) Loss of all 34.5KV Reserve Station Service Buses | |||
: 2. Loss of off-site and The following conditions SITE AREA on-site AC power for exist for a period - EMERGENCY more than 15 minutes GREATER THAN 15_ minutes | |||
^" ' "" "' "" "' ^ -''''' ' ' ''' ' "''''"' | |||
* CD Station Service Buses D,E, | |||
& F all - ZERO AMPS AND b) Ammeters for 4160V Station Service Buses A,B & C all ZERO AMPS AND c) Ammeters for 4160V Emer-gency Buses H & J both - | |||
ZERO AMPS | |||
[ | |||
t l | |||
O I | |||
J | |||
Ns.91881220 | |||
'% NUMBER A TTACHMENT TITLE REVISION I | |||
EFIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B) PAGE 1 ELECTRICAL FAILURE 30 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 3. Loss of all off-site a) Ammeters for 4160V Re- ALERT and on-site AC power serve Station Service Buses D, E,& F all - | |||
ZERO AMPS ALL CONDITIONS 8 | |||
AND b) Ammeters for 4160V Sta-tion Service Buses A, B,& C all - ZERO AMPS AND c) Ammeters for 4160V Emer-gency Buses H and J both - | |||
O ZERO AMPS | |||
: 4. Loss of all on-site The following conditions SITE AREA DC ' power for-GREATER exist for a period - EMERGENCY THAN 15 minutes GREATER THAN M minutes ALL CONDITIONS a) All Station Battery volt- , | |||
meters - ZERO VOLTS AND b) No light indication avail-able to Reserve Station l Service Breakers 15D1, 1 15El and 15F1 | |||
: 5. Loss of all on-site a) All Station Battery volt- ALERT DC power meters - ZERO VOLTS ALL CONDITIONS AND a | |||
b) No light indication avail- i able to Reserve Station l Service Breakers 15DI, 15El and 15F1 1 | |||
- _ _ _ _ . _ . _ _ ~ _ . | |||
ND.97887220 NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE PAGE A TTACHMENT (TAB I) 1 FIRE 31 of 41 CONDITION / APPLICABILITY INDICATICN CLASSIFICATION | |||
: 1. Fire resulting in de- a) Fire within the Station SITE AREA gradation of safety which causes major de- EMERGENCY systems gradation of a safety system function required ABOVE CSD CONDITION for protection of the public , | |||
AND b) Affected systems are caused NOT to be operable as defined by T.S.1.0.D and 3.02 | |||
: 2. Fire potentially affect- Fire within the Station ALERT O ing station safety sys-tems which has potential for causing a safety system NOT to be operable as ABOVE CSD CONDITION defined by T.S.1.0.D and 3.0.2 | |||
. 3. Fire lasting-GREATER Fire within the Station NOTIFICATION OF THAN 10 minutes which is not under con- UNUSUAL EVENT trol within 10 minutes ALL CONDITIONS after fire fighting i efforts begin 1 | |||
l O | |||
- - - - - - - - , - - - - - . . - - - , . . - , . _ . . , - . , , - - . . . , . - , . . - - - - - , . , - - - - - . _ , . - , - - - - - - - . , .. c . -- , | |||
r N3.97887220 Q | |||
D NUMBER EPIP-1.01 A TTACHMENT TITLE REVISION 15 EMERGENCY ACTION LEVEL TABLE A TT/CHMENT PAGE (TAB J) 1 SECURITY EVENT 32 of 41 CONDITION / APPLICABILITY INDICATION 'CLI,SSIFICATION | |||
: 1. Loss of Station a) Shift Supervisor has GENERAL physical control been informed that , | |||
EMERGENCY the security force has ALL CONDITIONS been neutralized by , | |||
attack, resulting in ' | |||
loss of physical control of station pR b) Shift Supervisor has been informed of intru-sion into one or more Vital Areas which are occupied or controlled | |||
\ by an aggressor | |||
: 2. Imminent loss of Supervisor Security Shift SITE AREA physical Station has notified the Shif t EMERGENCY control Supervisor of imminent intrusion into a Vital ALL CONDITIONS Area , | |||
: 3. Ongoing Security com- Supervisor Security Shift ALERT promise has notified the Shift Supervisor of a confirmed ALL CONDITIONS unneutralized intrusion , | |||
into the Protected Area | |||
: 4. Bomb potentially Shift Supervisor notifi- ALERT affecting station cation of a verified bomb safety systems discovered on or near a safety related system ALL CONDITIONS l | |||
l i | |||
O i | |||
A | |||
: m. .n.nu | |||
) NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB 3) 1 SECURITY EVENT 33 of 41 i | |||
CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 5. Security threat, un- Supervisor Security Shift NOTIFICATION OF authorized attempted has initiated SPIP-29, UNUSUAL EVENT entry, or attempted Response to Security l sabotage Contingency Events ALL CONDITIONS , | |||
: 6. Bomb threat or a) Shift Supervisor notifi- NOTIFICATION OF discovery cation of a bonafide UNUSUAL EVENT bomb threat ALL CONDITIONS , | |||
q b) Shift Supervisor notifi-cation of bomb discovery y | |||
within the Protected Area I | |||
l V | |||
: s. _ , | |||
N 3. 97887220 t | |||
NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 | |||
- EMERGENCY ACTION LEVEL TABLE PAGE A TTACHMENT (TAB K) ' | |||
1 HAZARD TO STATION OPERATION 34 cf 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Aircraft damage to Aircraft crash adversely SITE AREA vital plant systems affecte vital structures EMERGENCY by impact or fire ABOVE CSD CONDITION I | |||
: 2. Aircraft crash on the a) Aircraft crash within ALERT facility the Protected Area ALL CONDITIONS OR a | |||
b) Aircraft crash in Station Switchyard | |||
: 3. Aircraft crash or un- a) Confirmed notification NOTIFICATION OF O usual aircraf t activity of aircraft crash within the site boundary UNUSUAL EVENT ALL CONDITIONS ' | |||
0R b) Unusual aircraf t activ-ity in the vicinity of the site as determined by the Shift Supervisor or Supervisor Security Shift | |||
: 4. Severe explosive damage Explosion which results in SITE AREA severe degradation of any EMERGENCY ABOVE CSD CONDITION systems required for safe ' | |||
shutdown i | |||
i 1 | |||
O | |||
ND.97887220 NUMBER ATTACHMENT TITLE REVISION 0 EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 PAGE ATTACHMENT (TAB K) 1 HAZARD TO STATION OPERATION 35 of'41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 5. Explosion damage to Unplanned explosion result- ALERT facility ing in damage to plant structure or equipment ALL CONDITIONS , | |||
: 6. Onsite explosion Confirmed report of un- NOTIFICATION OF planned explosion onsite UNUSUAL EVENT ALL CONDITIONS | |||
: 7. Entry of toxic or flam- a) Uncontrolled release SITE AREA mable gases into plant of toxic or flam- EMERGENCY vital areas mable agents into Vital O' ABOVE CSD CONDITION Arcas AND b) Evacuation of Vital Area required S | |||
Loss of a safety system function required for protection of the public | |||
: 8. Entry of toxic or flam- Uncontrolled release of ALERT mable gases or liquids toxic OR flammable agent | |||
'into plant facility which cause: | |||
a) Evacuation of personnel from plant areas ALL CONDITIONS , | |||
I b) Safety related equipment , | |||
to be rendered inoperable l | |||
1 l | |||
l _ ___ __ _ __ | |||
r . | |||
I l | |||
N3.97887220 ) | |||
i NUMBER A TTACHMENT TITLE REVISION p | |||
t EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB K) PAGE 1 HAZARD TO STATION OPERATION 36 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 9. On or nearsite release Unplanned release of toxic NOTIFICATION OF of toxic or flammable OR flammable agents which UNUSUAL EVENT liquids or gases may affect safety of station personnel E ALL CONDITIONS equipment , | |||
: 10. Severe missile damage Missile impact causing SITE AREA to safety systems severe degradation of safety EMERGENCY systems required for unit ABOVE CSD CONDITION shutdown i | |||
: 11. Missile damage to Notification of missile ALERT hs) safety related equip- impact causing damage N' ment or structures to safety related equip-ment or structures AB0VE CSD CONDITION . | |||
: 12. Turbine failure Failure of Turbine / ALERT with penetration Generator rotating equip-ment resulting in casing POWER penetration , | |||
: 13. Turbine rotating com- Failure of Turbine /Gener- NOTIFICATION OF ponent failure without ator rotating component UNUSUAL EVENT casing penetration resulting in unit trip POWER AND STARTUP i i | |||
O | |||
No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 A TTACNMENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB L) 1 NATURAL" EVENTS 37 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Earthquake greater a) Earthquake which acti- SITE AREA than DBE levels vates the Event Alarm EMERGENCY on the Strong Motion ABOVE CSD CONDITION Accelerograph AND b) AP-37, Seismic Event, calculations indicate horizontal motion of 0.15g fMt GREATER pR i | |||
Safety related systems l | |||
are significantly de-graded by earthquake | |||
: 2. Earthquake greater a) Confirmed earthquake ALERT than OBE levels which activates Event Alarm on the Strong ALL CONDITIONS Motion Accelerograph l | |||
AND b) AP-37, Seismic Event, calculations indicate i | |||
horizontal motion of 0.07gfytGREATER | |||
{ OR I | |||
Safety related equipment is rendered inoperable by earthquake l | |||
l | |||
: 3. Earthquake detected Confirmed earthquake which NOTIFI:ATION OF i activates the Event Alarm UNUSUAL EVENT i ALL CONDITIONS on the Strong Motion Accelerograph 8 | |||
I Ns.97887220 NUMBER A TTACHMENT TITLE REVISION Q EPIP-1.01 15 CMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB L) PAGE 1 NATURAL EVENTS 38 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 4. Tornado striking Tornado visually detected ALERT facility striking within the Pro-tected Area or Switchyard ALL CONDITIONS | |||
: 5. Tornado onsite Tornado visually detected NOTIFICATION OF onsite UNUSUAL EVENT ALL CONDITIONS | |||
: 6. Severe winds Sustained severe winds in SITE AREA excess of 100 mph caused by EMERGENCY ABOVE CSD CONDITION Hurricane, Tornado or other O severe weather condition | |||
: 7. Extreme winds Sustained extreme winds ALERT between 80 and 100 mph AB0VE CSD CONDITION Hurricane or other severe weather conditions | |||
: 8. High winds Sustained wind speed onsite NOTIFICATION OF measured or projected to be UNUSUAL EVENT ALL CONDITIONS between 73 and 80 mph , | |||
pR, System Operator notification of hurricane watch for Surry County | |||
! k l | |||
i O | |||
N3.97887220 NUMBER A TTACHMENT TITLE REVISION | |||
\/ EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB L) PAGE 1 NATURAL EVENTS 39 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 9. Flood or low water Flood in the James River - SITE AREA level above design. GREATER THAN +27 feet MSL EMERGENCY levels pR ALL CONDITIONS ' | |||
Water level in the James River - LESS THAN -9 feet MSLasindicatedbTloss of Emergency SW Pump suc-tion | |||
: 10. Flood or low water Flood in the James River - ALERT level near design GREATER THAN +21 but LESS levels THAN +27 feet MSL Q ALL CONDITIONS OR , | |||
Water level in the Surry Power Station Intake Canal - | |||
LESS THAN 18, feet AND DECREASING | |||
: 11. Flood or low Flood in the James River - NOTIFICATION OF water level GREATER THAN +12 but LESS UNUSUAL EVENT THAN +21 feet MSL ALL CONDITIONS a BR l | |||
Water level in the Surry Power Station Intake Canal - | |||
LESS THAN 18, feet AND NOT INCREASING I | |||
O | |||
I e . | |||
N3.9788Th?O O ?! UMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAE M) 1 MISCELLANEOUS ABNORMAL EVENTS 40 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 1. Any major internal or Shift Supervisor / Station GENERAL external events which Emergency Manager judge- EMERGENCY singlely or in combin- ment ation cause massive damage to station fa-cilities ALL CONDITIONS | |||
: 2. Station conditions Shift Supervisor / Station SITE AREA which warrant activation Emergency Manager judgement EMERGENCY of emergency facilities | |||
. monitoring teams and precautionary Protection | |||
( Action Recommendations ALL CONDITIONS l 3. Station conditions Shift Supervisor / Station ALERT l which warrant precau- Emergency Manager judgement tiocary Protection Action Recommendations ALL CONDITIONS O | |||
r , | |||
N3.97887220 NUMBER A TTACHMENT TITLE REVISION | |||
\ EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB M) PAGE 1 MISCELLANEOUS ABNORMAL EVENTS 41 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION | |||
: 4. Station conditions Shif t supervisor judgement NOTIFICATION OF which warrant increased that any of the following UNUSUAL EVENT awareness of state and/ exist: | |||
or local authorities a) Intentional reduction ALL CONDITIONS in Power, Load or Temperature because I the unit has entered | |||
, an Action Statement or will exceed a Limiting Condition for Operation. | |||
l NOTE: In the event that other plant conditions require a shutdown, NOTI-FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required by the Tech Spec. | |||
SE. | |||
b) Unit shutdown is other than a controlled shut-down i | |||
( | |||
91L l c) Unit is in an uncontrolled condition during operation SE! l l | |||
d) A condition exists that has I the potential for escala- ! i tion and, therefore, ! | |||
warrants notification. | |||
O | |||
_ -- __ ._ _ .}} |
Latest revision as of 20:52, 30 December 2020
ML20204F337 | |
Person / Time | |
---|---|
Site: | Surry ![]() |
Issue date: | 07/24/1986 |
From: | Miller H VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
To: | |
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EPIP-1.01, NUDOCS 8608040159 | |
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"*"""" um a VIZINIA POWER SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE 10 NUMBER PROCEDURE TITLE REVISION 15 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE (With 1 Attachment) 1 of 8 PURPOSE To initially assess a potential emergency condition and initiate corrective actions.
USER Shift Supervisor or Station Emergency Manager ENTRY OONDITIONS Any one of the following:
- 1. Another station procedure directs initiation of this procedure
- 2. A potential emergency condition is reported to the Shift Supervisor.
R{g{0gECOfkGE(S): 1 of 8 and 5 of 8 DATE: 01-13-84 REV. 10 PAGE(S): 1, 6; Att. 1, pgs. 6, 7, 8 and 9 DATE: 02-02-84 REV. 11 PAGE(S): 1 of 8 and 5 of 8 DATE: 03-01-84 REV. 12 PAGE(S): 1, 2, 3, 4, 5, 6 and 7 of 7 DATE: 05-21-85 REV. 13 PAGE(S): Entire Procedure and Attachment 1 DATE: 05-27-86 REV. 14 PAGE(S): Att. 1, pgs 2,10,11.22 thru 25, 27 & 28 DATE: 06-25-86 REV. 15 PAGE(S): 1,4;Att. 1, pgs 2 thru 24,26,28 thru 41 DATE: q q APPRO L EC MM ED SNSOC REVIEW p OATE O - A '
JUL 3 4 1980 G /V m b-6C REVIEW STATION MAN GER APPROVAL DA TE
/JO_Mo1 48 4 t m,
[ 0609040159 860729 PDR ADOCK 05000280 4 F PDR EPIPA -
um n
(( yt;ZINIA POWER SURRY POWER STATION EMERGENCY PLAN IMPLEMENTING PROCEDURE A
NUMBER PRO 2 DURE TITLE REVISION 15 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE l
(With 1 Attachment) 1 of 8 j l
PURPOSE 1 Tc initially assess a potential emergency condition and initiate corrective ;
actions. ,
1 USER Shift Supervisor or Station Emergency Manager ENTRY CONDITIONS Any one of the following:
- 1. Another station procedure directs initiation of this procedure
- 2. A potential emergency condition is reported to the Shift Supervisor.
"fM! &'c FRGE(S): 1 of 8 and 5 of 8 DATE: 01-13-84 REV. 10 PAGE(S): 1, 6; Att. 1, pgs. 6, 7, 8 and 9 DATE: 02-02-84 REV. 11 P AGE (S): 1 of 8 and 5 of 8 DATE: 03-01-84 REV. 12 PAGE(S): 1, 2, 3, 4, 5, 6 and 7 of 7 DATE: 05-21-85 REV. 13 PAGE(S): Entire Procedure and Attachment i DATE: 05-27-86 REV. 14 PAGE(S): Att. 1, pgs 2,10,11,22 thru 25, 27 8 28 DATE: 06-25-86 REV. 15 PAGE(S): 1,4;Att. 1, pgs 2 thru 24,26,28 thru 41 DATE:g.,g g I 4 1980 6C REVIEW STATION MAN GER APPROVAL DA TE aoLA /7/d& as< m
[ 8608040159 860729 PDR ADOCK 05000280 a F PDR
-- EPIPA- -- - _ . _ _ . _ _ _
Ns.97887210 NUNDER PROCEDURE TITLE REVISION 15 O EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 2 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSE NOTORTAINED
- 1. INITIAL ASSESSMENT:
a) Perform initial assessment from EAL tables b) IF EAL exceeded, b) IF,no EAL exceeded, THEN initiate EPIP-1.01: return to procedure in effect
- 1) BY:
DATE:
TIME:
) NOTE: Continue through this and all further instructions unless other-wise directed to hold.
- 2. IDENTIFY EVENT: .
a) Event-TRANSPORT OF CONTAMI- a) GO TO Step 2b,of this in-NATED INJURED PERSONNEL struction.
- 1) Initiate EPIP-5.01 Transport of Contami-
. nated Injured Personnel
- 2) Verify initiation of i
EPIP-4.20, H.P. Actions I for Transport of Injured Contaminated Personnel
! 3) Continue this instruction i
1 I
Me.C788721%
NUNDER PROCEDURE TITLE REVISION 15 O EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 3 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED
- 2. [ continued]
- b) Event-Any of the fo'11owing; b) GO E Step 3_ of this in-struction.
- Radiation Release
- Fuel Handling Incident
- Secondary Release
- S/G Tube Rupture
- 1) Request Health Physics O initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure, and continue this instruction e
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- . . - . . - - . - . . _ _ - . . . . . - . - _ . - _ _ _ _ - . _ - - - ~ - . - _ _ - _ . _ _ _ _ _ _ _ _ - . - - - - - . - _ _ . - - , . - . . . - - - - . _ _ - . -
Pee. 97887210 NUNDER PROCEDURE TITLE REVISION O
V EPIP-1.01 15 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 4 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINED
, CAUTION: Declaration of the highest emergency class for which an ,
Emergency Action Level is exceeded shall be made.
NOTE: The SPDS is potentially unreliable in the event of an earthquake. There-fore, the SPDS should be evaluated for reliability of accident assessment should this situation occur.
- 3. ASSESSMENT AND CLASSIFICATION:
a) Use the SPDS to obtain a) ))[ SPDS NOT operable, GO TO indications of emergency Step 3.b.
I conditions listed in the EAL Table, as necessary. .
b) Use EPIP 1.01, of Attach-ment 1,, Index Emergency Action Levels to determine event category AND l
i GO TO proper EAL tab l
I c) Evaluate event to deter-mine classification, AND ,
GO p Step 4_ of this pro-cedure O
~
Pse.97887210 NUNDER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 5 of 8
- STEP ACTION / EXPECTED RESPONSE RESPONSENOT08TAINED
- 4. NOTIFICATION AND VERIFICATION:
a) LEOF - NOT ACTIVATED a) E LEOF activated, announce transfer of command from TSC to LEOF and proceed to step 4.b.
b) TSC - NOT ACTIVATED b) E TSC activated, GO TO Step 6_.
c) Notify SRO-On-Call or Super- c) Notify Station Manager or intendent of Operations Asst. Station Manager.
d) Verify emergency classifica-tion e) If required by ALERT SITE AREA, or GENERAL emergency, request initiation of STANDING ORDER #21, Augmented Staff Resources During Emer-gency Plan Activation. .
NOTE: Return to Step 2 of this instruction as necessary to consider additional events and reclassification.
- 5. VERIFY EALS EXCEEDED:
a) Assure EALs - EXCEEDED a) H EALs NOT exceeded, DO NOT declare an emergency classification, AND GO TO Step J,of this procedure.
i b) E required, assign appropri-ate individual as Emergency Communicator c) E required, direct senior H.P.
personnel on site to initiate EPIP-4.01, Radiological Assessment Director Controlling Procedure
pee, ovestaD NUN 8ER PROCEDURE TITLE REVISION EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE
- 6 of 8
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTOCTAINED
- 6. DETERMINE EPIPS:
a) Event classification - a) GO TO Step b6_b,of this in-NOTIFICATION OF UNUSUAL EVENT struction.
i 1) C0 TO EPIP-1.02, Response i
to Notification of Unusual Event b) Event classification - ALERT b) GO TO Step 6c_ of this instruction.
- 1) GO TO EPIP-1.03, Response to Alert c) Event classification - SITE c) CO TO Step 6d of this AREA EMERGENCY instruction 7
- 1) GO TO EPIP-1.04, Response to Site Area Emergency d) Event classification -
GENERAL EMERGENCY
- 1) CO TO EPIP-1.05, Response to General Emergency i
- 7. SECURE FROM EVENT:
.a) Notify involved station personnel that emergency condition does not exist b) CO TO Step 11 of this instruc-tion 1
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Pee. 97887210 NUMMR PROCEDURE TITLE REVISION 15 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE
- 7 of 8
- STEP ACTIONNXPECTED RESPONSE RESPONSENOTORTAINED l
- 8. TERMINATION NOTIFICATIONSt a) Initiate termination notifi-i cation to state and local governments IAW EPIP-2.01, Notification of State and Local Governments b) Initiate termination notifi-cation to NRC IAW EPIP-2.02, Notification of NRC
- 9. REPORTING O a) Verify required reports and notifications IAW EPIP-2.03, Reports to Offsite Agencies
- 10. RECOVERY ACTIONS:
a) Notify involved station j personnel of emergency j termination l
b) Initiate recovery actions b) JJ[ required, GO TO EPIP-6.01 IAW established station Reentry / Recovery Guidelines
- procedures and capabilities
) c) )); required, deactivate
! station emergency response l facilities and personnel O
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MUNetR PROCEDURE TITLE REVISION g 15
) EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 8 of 8
= STEP ACTIONNXPECTED RESPONSE RESPONSENOTORTAINEO i
i
- 11. TERMINATE EPIP-1.01:
a) COMPLETED BY:
DATE:
TIME:
i
- b) Forward completed EPIP-1.01, 1
forms and other applicable
) records to Secretary SNSOC ,
END l
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No. 91887tto r NUMBER A TTACHMENT TITLE REVISION
$ EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE 1 INDEX 1 of 41 CAUTIO/t Declaration of the highest emergency class for which an EAL is exceeded shall be made.
GO TO IF EVENT CATEGORY IS: TAB i,
- 1. Safety, Shutdown, or Assessment System Event . . . . . . . . . . . . . . . . . . . . A
- 2. Reactor Coolant System Event ....................................B
- 3. Fuel Failure or Fuel Handling Accident...........................C
- 4. C o n t a i nme n t Ev e n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . D
- 5. Radioactivity Event..............................................E
- 6. C on t amina t e d P e r s o nne l . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . F
- 7. LOSS of Secondary Cooling........................................G
- 8. E le c t r ic a l Fa ilu r e . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . H
! 9. Fire.............................................................I
) 10 . Security Event...................................................J
- 11. Hazard to Station Operation......................................K
- 12. Natural Events...................................................L
- 13. Miscellaneous Abnormal Events...............................- ....M 6
j 1
No.9788722)
NUMBER A TTACHMENT TITLE REVISION ss EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAE A) 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 2 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Non-spurious ECCS Non-spurious ECCS NOTIFICATION OF initiation initiation as vali- UNUSUAL EVENT dated by Emergency AB0VE CSD CONDITION Procedures t
- 2. Mode reduction required Intentional reduction in NOTIFICATION OF by Tech. Spec. Limiting Power, Load or Temperature UNUSUAL EVENT Condition for Opera- because the unit has entered tion an Action Statement or will exceed a Limiting Condition l POWER & HSB for Operation. ,
1 NOTE: In the event that other
, plant conditions require a shutdown, NOTIFICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required by the Tech Spec.
- 3. Loss of Function needed Total loss of: SITE AREA for unit HSD condition EMERGENCY a) Charging /SI System ABOVE CSD CONDITION O,R, b) Main feedwater AND Auxiliary Feedwater Systems i
N).97007220 NUMBER A TTACHMENT TITLE REVISION l
[
\
EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 A TTACHMENT (TAB A) ppgg i SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 3 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Loss of function need- Loss of heat removal ALERT ed for unit CSD con- capability due to total dition loss of any of the following systems:
CSD a) Service Water 8 E
b) Component Cooling E
c) Residual Heat Removal O 5. Failure of a safety or relief valve to Condition a) or b) exists: NOTIFICATION OF UNUSUAL EVENT close after pressure reduction a) Pressurizer safety or PORV flow as indicated ALL CONDITIONS by accoustical or tem-perature monitoring equipment i
AND RCS subcooling - LESS THAN 30*F b) Excessive flow through Steam Generator Safety,
- PORV, or Decay Heat Release valve indicated by RCS cooldown rate
- > 50*F per hour I
i O
N3.97887223 sq NUMBER A TTACHMENT TITLE REVISION f ; EPIP-1.01 15
\~ / EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB A) ppgg 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENI 4 of 41 b
CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 6. Failure of the Reactor Condition a) and b) , SITE AREA to trip (ATWT) exists with c) EMERGENCY POWER & HSB a) RX trip setpoint and coincidences - EXCEEDED i
AND b) Manual Rx trip - INITIATED AND c) Rx power indication-NOT DECREASING b
- 7. Trip following ATWT that a) ATWT - Manual Reactor ALERT takes the Rx Suberitical Trip following failure of Auto Trip Circuit POWER & HSB AND ,
I
. b) Reactor power -
DECREASING
- 8. Indications or alarms Intentional reduction in NOTIFICATION OF on process or effluent Power, Load or Temperature UNUSUAL EVENT i
parameters required for because the unit has incident assessment NOT entered an Action Statement available or will exceed a Limiting Condition for Operation.
ABOVE CSD CONDITION
! NOTE: In the event that -
- = _ _ _.d l other plant conditions ,
l require a shutdown, NOTI- ~ - ~
FICATION OF UNUSUAL EVENT
{
must still be declared on ,
the basis that a shutdown would have been required by the Tech Spec.
- . _ . --._ -. . . . - - . - - . _ - - - - - - _ _ _ = _ --. . . . . .
No. 97007330 l
1 NUMMR A TTACHNENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE
- ATTACHNENT (TAB A) PAGE 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 5 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. Failure of meteorological Loss of all onsite and off- NOTIFICATION OF instrumentation required site meterological monitoring UNUSUAL EVENT to perforn offsite dose capability calculations.
ALL CONDITIONS t
- 10. Loss of plant communica- Complete failure of: NOTIFICATION OF tions capability UNUSUAL EVENT ALL CONDITIONS a) Station Gai-Tronics system ,
^""
O b) Station UHF radio system
- 11. All main board annunci- a) Complete loss of all SITE AREA ator alarms and unit annunciator alarms on EMERGENCY computer lost for more panels "A" to "K" than 15 minutes during a unit transient AND l POWER & HSB b) Loss of unit computer for GREATER THAN 15 minutes AND c) Unit operational tran-t sient - IN PROGRESS
- 12. All main board annunci- a) Simultaneous loss of all ALERT
! ator alarms and unit annunciator alarms on computer lost panels "A" to "K" l
POWER & HSB AND b) Loss of unit computer 5
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. -. -..,n.. ,__c.. -- . -;. , . . _ _ . - . . . - _ . . ,
Nr.97887220 NUMBER A TTACHMENT TITLE REVISION 0 EPIP-1.01 A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAE A) 15 PAGE 1 SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 6 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 13. Evacuation of Main Con- Evacuation of the Control SITE AREA trol Room with control Roon with stable shutdown EMERGENCY NOT established within control NOT established 15 minutes within 15 minutes ALL CONDITIONS g
- 14. Evacuation of Main Con- Evacuation of the Control ALERT trol Room required Room with stable shutdown control established within ALL CONDITIONS 15 minutes 1
O 4
0
nu. oreenn NUMBER A TTACHMENT TITLE REVISION O EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 A TTACHMENT (TAB B) PAGE 1 REACTOR COOLANT SYSTEM EVENT 7 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION '
- 1. Tech. Spec. Safety Limits Verification of any Tech. NOTIFICATION OF for RCS exceeded Spec. Safety limit for RCS UNUSUAL EVENT POWER & HSB I
makeup capacity Coolant - IMPLEMENTED EMERGENCY ABOVE CSD CONDITION AND i
Pressurizer level cannot be maintained with two (2)
, Charging /SI Pumps in operation l
- 3. RCS' leak rate exceeds Intentional reduction in ALERT 50 gpm Power, Load or Temperature because the unit has ABOVE CSD CONDITION entered an Acticn State-ment or will exceed a
. Limiting Condition for Operation.
j NOTE: In the event that other plant conditions require a shutdown, NOTI-FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required by the Tech Spec.
l l
a) Actions required IAW AP-16, Excessive Primary Plant Leakage ,
AND l
l O b) RCS inventory balance indicates leakage -
GREATER THAN 50 gpm i
" ~
, i N:9. 97887223 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE PA GE A TTACHMENT (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 8 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. RCS leak rate requiring Intentional reduction in NOTIFICATION OF plant shutdown IAW Power, Load or Temperature UNUSUAL EVENT T.S. 3.1.C because the unit has entered an Action State-POWER & HSB ment or will exceed a Limiting Condition for Operation.
NOTE: In the event that other plant conditions require a shutdown, NOTI-FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown -
would have been required by the Tech Spec.
a) Unidentified RCS leakage - GREATER
! THAN 1 gym E
b) Indentified leekege -
GREATER THAN H gpm E
I c) Non-isolatable fault of RCS pressure boundary I
O
NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 O A TTACHMENT EMERGENCY ACTION LEVEL TABLE (TAE B) ppgg i
i REACTOR COOLANT SYSTEM EVENT 9 of 41 CONDITION / APPLICABILITY INDICATIOli CLASSIFICATION I
- 5. RCP locked rotor a) Flow in one or more ALERT leading to fuel dam- RC loops - LESS THAN age 90J POWER AND ,
b) RCP trip caused by Phase Overcurrent Relay -
ACTUATION AND c) High Range Letdown Rad-iation Monitor (RM-CH-118,
-218) indication incregses to - GREATER THAN 5x10 O- cpm
- 6. Gross Primary to Second- EP-4.00, Steam Generator SITE AREA ary leakage with loss of Tube Rupture - IMPLEMENTED EMERGENCY offsite power AB0VE CSD CONDITION AND e
Loss of offsite power indi-cated by zero volts for 4160V Buses D, E & F l
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N3.97857220 NUMBER A TTACHMENT TITLE REVISION
'T EPIP-1.01 15
- s. EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B) ppgg 1 REACTOR COOLANT SYSTEM EVENT 10 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 7. Excessive Primary to Intentional reduction in ALERT Secondary leakage with Power, Load or Temperature loss of offsite power because the unit has entered an Action Statement ABOVE CSD CONDITION or will exceed a Limiting Condition for Operation. ,
a) Primary to Secondary leakage - GREATER THAN 1.gpm 0,R,
/h GREATER THAN 500 gal.
k-/ per day per generator AND b) zero volts for 4160V busses D, E & F.
- 8. Gross Primary to EP-4.00, Steam Generator ALERT Secondary leakage T,ube Rupture - IMPLEMENTED ABOVE CSD CONDITION I
(
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I us.steersso NUMBER A TTACHMENT TITLE REVISION y
EPIP-1.01 15 l EMERGENCY ACTION LEVEL TABLE PAGE A TTACHMENT (3gg g) 1 REACTOR COOLANT SYSTEM EVENT 11 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 4
- 9. Primary to Secondary Intentional reduction in NOTIFICATION OF leakage - GREATER THAN Power, Load or Temperature UNUSUAL EVENT 1 gpm because the unit has entered an Action State-ABOVE CSD CONDITION ment or will exceed a ,
Limiting Condition for Operation.
NOTE: In the event that other plant conditions require a shutdown, NOTI-FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required O by the Tech Spec.
a) Primary to Secondary leakage - GREATER THAN J_ 8Pm 2.
GREATER THAN 500 gal, per day per generator.
i
>s
N3.97887220 x NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB B) 1 REACTOR COOLANT SYSTEM EVENT 12 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 10. Loss of 2 of 3 fission Any two of a), b) or c) GENERAL product barriers with exist and the third is EMERGENCY potential loss of 3rd imminent barrier a) Fuel clad integrity ALL CONDITIONS failure as indicated by any of the following: 3
- 1) RCS specific activity -
GREATER THAN OR EQUAL TO 300 pCi/ gram dose equivalent I-131.
- 2) 5 or more core exit thermocouples reading-O GREATER THAN 1200*F b) Loss of RCS integrity as indicated by any of the following:
- 1) PORV failed open
- 2) Loss of Reactor Coolant
- 3) Outside Containment High Range Gamma Radiation Monitor (RM-RMS-161, -261) read 2x10{ng-GREATERTHAN mR/hr c) Loss of containment integ-rity as indicated by any of the following:
- 1) Containment pressure -
GREATER THAN 60 psia AND NOT DECREASING '
- 2) OP-1E, Containment Integrity Checklist.
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAE B) 1 REACTOR COOLANT SYSTEM EVENT 13 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 11. Fuel failure with steam Any two of a), b) or c) GENERAL generator tube rupture exists and the third is ' EMERGENCY imminent ALL CONDITIONS a) Fuel clad integrity failure as indicated by any of the following:
- 1) RCS specific activity -
GREATER THAN 300 pCi/
gram dose equivalent I-131
- 2) 5 or more core exit thermocouples indi-cate - GREATER THAN
) 1200 *F b) S/G tube rupture as indicated by both of the following:
INITIATED
- 2) EP-4.00, Steam Genera-tor Tube Rupture. -
IMPLEMENTED c) Loss of Secondary integ-rity as indicated by:
- 1) Steam discharge to at-mosphere
- 2) EP-3.00, Loss of Secondary Coolant -
{
IMPLEMENTED i O
N3. 97887223 NUMBER A TTACHMENT TITI.E REVISION EPIP-1.01 Q EMERGENCY ACTION LEVEL TABLE 15 A TTACHMENT (TAB C) PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 14 of 41 ;
CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Ccre damage with pos- Condition a) exists with SITE AREA sible loss of coolable b) EMERGENCY geometry a) Fuel clad failure as ABOVE CSD CONDITT.ON indicated by any of the following: 1
- 2) High Range Letdown Radiation Monitor -
. (RM-CH-118, -218)
(' indicatiog - GREATER THAN 1x10 cpm AND b) Loss of cooling as in-dicated by any of the following:
- 1) 5 confirmed core exit thermocouples - GREATER THAN 1200*F
, 2) Core AT - ZERO
- 3) Core AT - RAPIDLY DIVERGING O
N3.97887223 NUMBER A TTACHMENT TITLE REVISION
.m EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 15 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 2. Severe Fuel Clad a) RCS specific activity - ALERT Damage GREATER THAN 300 pCi/ gram dose equivalent I-131 ABOVE CSD CONDITION ,
E High Range Letdown Radi-ation Monitor (RM-CH-118,
-218)indicationgnereases GREATER THAN 5x10 cpm within 30 minutes AND remains 7or at least M minutes
- 3. Fuel clad damage Intentional reduction in NOTIFICATION OF indication Power, Load or Temperature UNUSUAL EVENT because the unit has ABOVE CSD CONDITION entered an Action State-8 ment or will exceed a Limiting Condition for Operation.
NOTE: In the event that other plant conditions require a shutdown, NOTI-l FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required l by the Tech Spec.
E a) High Range Letdown Radiation Monitor indication increases -
GREATER THAN 10,5 cpm i within 30 minutes AND I remains for at least H minutes.
O
No. 97987tt9 REVISION m NUMBER A TTACHMENT TITLE j) EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 16 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Probable large radio- a) EP-2.00, Loss of Reactor GENERAL activity release Coolant, - IMPLEMENTED, EMERGENCY initiated by LOCA with ECSS failure leading to AND core degradation RCS specific activity -
AB0VE CSD CONDITION GREATER THAN 3f0,pCi/ gram dose equivalent 1-131 AND b) High or Low Head ECCS flow - NOT being delivered to the core I 5. Probable large radio- a) Loss of Main FW system GENERAL activity release and Condansate System EMERGENCY initiated by loss of neat sink leading to core AND degradation b) Loss of Auxiliary FW ABOVE CSD CONDITION System AND c) RHR System - NOT OPERABLE
- 6. Probable large radio- a) Rx nuclear power af ter GENERAL activity release a trip remains - GREATER EMERGENCY initiated by failure of THAN 5%
protection system to bring Rx suberitical AND and causing core de-gradation b) RCS pressure - GREATER THAN 2485 psig AND NOT AB0VE CSD CONDITION decreasing ,
0,,R Containment pressure and
[}
(m ,/
temperature are RAPIDLY INCREASING
Nr.97887220 NUMBER A TTACHMENT TITI.E REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE L(TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 17 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 7. Probable large radio- a) ECA-2, Loss of All ac GENERAL activity release Power - IMPLEMENTED EMERGENCY initiated by loss of AC and all feedwater AND ABOVE CSD CONDITION b) Turbine Driven Auxiliary ,
Feedwater Pump NOT OPERABLE AND c) Restoration of a) or b) above not likely within 2, hours
- 8. Probable large radio- a) EP-2, Loss of Reactor GENERAL O- activity release Coolant - IMPLEMENTED EMERGENCY initiated by LOCA with loss of ECCS and con- AND tainment cooling b) High Ojt Low Head ECCS ABOVE CSD CONDITION flow NOT being delivered
- to the core AND c) Containment RS sump temp-erature-GREATER THAN 190*F AND NOT DECREASING pR Containment Spray and Recir-culation Spray Systems- NOT OPERABLE i
O
2.
N3.97887220 t
NUMBER A TTACHNENT TITLE REVISION EPlP-1.01 15 J
EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE l (TAB C) 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 18 of 41 i
CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. Major fuel damage a) Water level in Rx vessel SITE AREA accident with radio- during refueling - BELOW EMERGENCY activity release to TOP OF CORE containment or fuel buildings R O_R ALL CONDITIONS .W ater level in Spent Fuel ,
Pit verified - BELOW TOP OF SPENT FUEL AND b) Verified damage to irra-diated fuel resulting in .
- readings on Ventilation 4
g ,/ VentGaseousMonigor-GREATER THAN 1x10 cpm
- 10. Fuel damage accident a) Verified accident involv- ALERT with release of radio- ing damage to irradiated activity to containment fuel or fuel buildings AND ALL CONDITIONS b) Health Physics confirms a fission product release l
from fuel SR c) Readings on the Ventila-tion Vent Gaseous Monitor (RM-fG-110) - GREATER THAN 1x10 cpm
- 11. Spent Fuel Storage a) Verified loss of all cask / ALERTk' Facility accident with fuel containment barriers release of radioactivity AND O ALL CONDITIONS b) Health Physics confirms fission product release a
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C) PAGE 1 FUEL FAILURE OR FUEL HANDLING ACCIDENT 19 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 12. Spent Fuel Storage a) Verified SSSC seal leak- NOTIFICATION OF Facility accident age UNUSUAL EVENT ALL CONDITIONS OR b) Spent Fuel Storage Cask dropped or mishandled O
NB.97887223 NUMBER A TTACHMENT TITLE REVISION O' EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 PAGE A TTACHMENT (TAB D) 1 CONTAINMENT EVENT 20 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Extremely high Con- a) Outside Containment High GENERAL tainment radiation, Range Radiation Monitor EMERGENCY pressure and tem- (RM-RMS-161, -261 -
perature GREATERTHAN5x10{mR/hr AB0VE CSD CONDITION AND e b) Containment pressure -
GREATER THAN 45 psia AND is NOT decreasing 0.R
^,
Containment temperature -
GREATER THAN 280*F
- 2. High Containment a) Outside Containment High SITE AREA radiation, pressure, Range Radiation Monitor EMERGENCY and temperature (RM-RMS-161, -261 -
GREATERTHAN2x10}mR/hr ABOVE CSD CONDITION AND e b) Containment pressure -
3 psia GREATER THAN _23, and is NOT decreasing
, OR 1
l Containment temperature -
GREATER THAN 200*F I
i O
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB D) 1 CONTAINMENT EVENT 21 of 41 l
CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 3. High Containment radia- a) Outside Containment High ALERT tion, pressure and Range Radiation Monitor temperature (RM-RMS-161, -2pl) -
GREATER THAN 10 mR/hr ABOVE CSD CONDITION '
AND b) Containment pressure -
GREATER THAN 17.7 psia pR Containment temperature -
GREATER THAN 150 *F
- 4. Loss of Containment Intentional reduction in NOTIFICATION OF integrity Power, Load or Temperature UNUSUAL EVENT because the unit has entered ABOVE CSD CONDITION an Action Statement or will exceed a Limiting Condition a for Operations.
NOTE: In the event that other plant conditions l, require a shutdown. NOTI-
! FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required by the Tech Spec.
a) Loss of Containment integrity as indi-cated by OP-1E, Containment Integrity Checklist.
D
, . _ . _2 N2.91991220 CD EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB E) 1 RADI0ACTIVI;Y EVENT 22 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Projected or actual a) Confirmed actual or GENERAL site boundary doses projected site boundary EMERGENCY exceed 2 Rem W.B. or doses - GREATER THAN g Rem thyroid ex- 2.0 Rem Whole Body OR posure 12.0 Rem Thyroid exposure as determined ALL CONDITIONS from EPIP-4.01.
a
- 2. Projected or actual a) Confirmed actual or SITE AREA N site boundary doses projected site boundary EMERGENCY of 0.5 Rem to 2 Rem doses - GREATER THAN W.B. or 1 Rem to 12 0.5 Rem Whole Body or Rem thyroid exposure 1.0 Rem Thyroid exposure as determined ALi, CONDITIONS from EPIP-4.01.
a O
l 1
ND.97887223 NUMBER ATTACHMENT TITLE REVISION O EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 A TTACHMENT PAGE (TAB E) 1 RADI0 ACTIVITY EVENT 23 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 3. High radiation or air- Valid unexpected readings ALERT borne contamination on any of the following levels indicate a monitors have increased by severe degradation in a factor of 1000 control of radioactive material a) Control Room Area Monitor (RM-RMS-157)
ALL CONDITIONS b) Auxiliary Building a Control Area Monitor (RM-RMS-154) c) Auxiliary Building Drumming Area Monitor (RM-RMS-ISS) d) Decontamination Building Area Monitor (RM-RMS-151) e) Fuel Pit Bridge Area Monitor (RM-RMS-153) f) New Fuel Storage Area Monitor (RM-RMS-152) g) Laboratory Area Monitor (RM-RMS-158) h) Sample Room Area Monitor (RM-RMS-156) i O
,, .--,m
N3.97887220 r NUMBER A TTACHMENT TITLE REVISION
( EPIP-1.01 15
-- EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB E) 1 RADIOACTIVITY EVENT 24 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Effluent Release GREATER a) Ventilation Vent Gaseous ALERT THAN 10 TIMES T.S. Monitor (RM-VG-110 or instantaneous allowable RM-VG-131) - GREATER limits THAN 1000% T.S. value as determined from Attach-ALL CONDITIONS ment 1, AP-5.20 E
b) Process Vent Gaseous Monitor (RM-GW-102 or RM-GW-130) - GREATER THAN 1000% T.S. value I as determined from Attachment 1, AP-5.01 m
c) Air Ejector Monitor (RM-SV-111, -211)6-GREATER THAN 1x10 cpm AND Air ejector exhaust -
NOT diverted to contain-ment.
E d) Discharge Tunnel Monitor (RM-SW-120, -220) 5 GREATER THAN 1.3x10 cpm 9.R e) Sampling and Analysis Team confirms effluent l
i release GREATER THAN 1000% T.S. value as determined from EPIP-4.01.
'l
N3.97087220 p NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB E) 1 RADI0 ACTIVITY EVENT 25 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 5. Effluent release GREATER a) Ventilation Vent Gaseous NOTIFICATION OF THAN T.S. allowable Monitor (RM-VG-110 or UNUSUAL EVENT Limit RM-VG-131) - GREATER THAN 100% T.S. value as ALL CONDITIONS detemined from Attach-ment 1, AP-5.20 0,R b) Process Vent Gaseous Monitor (RM-GW-102 or RM-GW-130) - GREATER THAN 100% T.S. value as determined from p Attachment 1 AP-5.01 a
c) Air Ejector Monitor (RM-SV-111, -211) 5 GREATER THAN 1.99x10 cpm AND Air Ejector Exhaust -
NOT diverted to contain-cent.
pR d) Discharge Canal Monitor (RM-SW-120, -220) 4 GREATER THAN 1.3x10 cpm e) Sampling and Analysis Team confirms effluent release GREATER THAN 100% T.S. value as i determined from EPIP-4.01.
O
2 N9.97887220 CD EPIP-1,01 EMERGENCY ACTION LEVEL TABLE 15 ATTACHMENT PAGE (TAB E) 1 CONTAMINATED PERSONNEL 26 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Transportation of Contaminated injured indi- NOTIFICATION OF contaminated injured vidual enroute to off-site UNUSUAL EVENT individual to off-site facility for treatment facility ALL CONDITIONS i
I
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6
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N3.97887223
/~ NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB G) 1 LOSS OF SECONDARY COOLANT 27 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Major Secondary line a) EP-3.00, Loss of SITE AREA break with Primary to Secondary Coolant - EMERGENCY Secondary leakage IMPLEMENTED AND GREATER THAN 50 gpm and verified non-spurious fuel damage indicated AND AB0VE CSD CONDITION b) RCS specific activity -
GREATER THAN 300 pCi/ gram E
Letdown High Range Radia-t
' tion Monitor (RM-CH-118 5
-218) - GREATER THAN 10 cpm t AND c) Condenser Air Ejector RadiationMonitor(RM-Sg-111
-211) - GREATER THAN 10 cpm Steam Generator Blowdown Radiation Monitor (RM-SS-112,
-113,-g12,-213)-GREATER THAN 10 cpm E
MS Line High Range Radiation Monitor (RM-RI-MS-124, -125,
-126,-224,-225,-236)-
GREATER THAN 7.5x10 mR/hr l i
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.a Ns 91997220 p NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB G) PAGE 1 LOSS OF SECONDARY COOLANT 28 of 41 t
CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 2. Major Secondary line a) EP-3.00, Loss of Second- ALERT break with Primary to ary Coolant - IMPLEMENTED Secondary leakage AND verified to be non-greater than 10 GPM spurious ABOVE CSD CONDITION AND ,
]
- b) Condenser Air Ejector Radiation Monitor
~
(RM-SV-111 -211)6 GREATER THAN 1x10 cpm E
O Steam Generator Blowdown Radiation Monitor (RM-SS-112, -113 -212 ~
5
)~
GREATER THAN 10 cpm E
MS Line High Range Radia-tion Monitor (RM-RI-MS-124,
-125, -126, -224, -225,
-226) - GREATER THAN 0.5 mR/hr I
- 3. Major Secondary line EP-3.00, Loss of Secondary NOTIFICATION OF break Coolant, - IMPLEMENTED UNUSUAL EVENT AND verified non-spurious ABOVE CSD CONDITION I i i
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a N3.97887220 Q NUMBER A TTACHMENT TITLE REVISION V EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B) PAGE 1 ELECTRICAL FAILURE 29 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Loss of off-site a) Unit Main Generator AND NOTIFICATION OF power or on-site AC both Emergency Diesel UNUSUAL EVENT power capability Generators out of service ALL CONDITIONS OR a
b) Loss of all 34.5KV Reserve Station Service Buses
- 2. Loss of off-site and The following conditions SITE AREA on-site AC power for exist for a period - EMERGENCY more than 15 minutes GREATER THAN 15_ minutes
^" ' "" "' "" "' ^ - ' ' ' "''"'
- CD Station Service Buses D,E,
& F all - ZERO AMPS AND b) Ammeters for 4160V Station Service Buses A,B & C all ZERO AMPS AND c) Ammeters for 4160V Emer-gency Buses H & J both -
ZERO AMPS
[
t l
O I
J
Ns.91881220
'% NUMBER A TTACHMENT TITLE REVISION I
EFIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B) PAGE 1 ELECTRICAL FAILURE 30 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 3. Loss of all off-site a) Ammeters for 4160V Re- ALERT and on-site AC power serve Station Service Buses D, E,& F all -
ZERO AMPS ALL CONDITIONS 8
AND b) Ammeters for 4160V Sta-tion Service Buses A, B,& C all - ZERO AMPS AND c) Ammeters for 4160V Emer-gency Buses H and J both -
O ZERO AMPS
- 4. Loss of all on-site The following conditions SITE AREA DC ' power for-GREATER exist for a period - EMERGENCY THAN 15 minutes GREATER THAN M minutes ALL CONDITIONS a) All Station Battery volt- ,
meters - ZERO VOLTS AND b) No light indication avail-able to Reserve Station l Service Breakers 15D1, 1 15El and 15F1
- 5. Loss of all on-site a) All Station Battery volt- ALERT DC power meters - ZERO VOLTS ALL CONDITIONS AND a
b) No light indication avail- i able to Reserve Station l Service Breakers 15DI, 15El and 15F1 1
- _ _ _ _ . _ . _ _ ~ _ .
ND.97887220 NUMBER ATTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE PAGE A TTACHMENT (TAB I) 1 FIRE 31 of 41 CONDITION / APPLICABILITY INDICATICN CLASSIFICATION
- 1. Fire resulting in de- a) Fire within the Station SITE AREA gradation of safety which causes major de- EMERGENCY systems gradation of a safety system function required ABOVE CSD CONDITION for protection of the public ,
AND b) Affected systems are caused NOT to be operable as defined by T.S.1.0.D and 3.02
- 2. Fire potentially affect- Fire within the Station ALERT O ing station safety sys-tems which has potential for causing a safety system NOT to be operable as ABOVE CSD CONDITION defined by T.S.1.0.D and 3.0.2
. 3. Fire lasting-GREATER Fire within the Station NOTIFICATION OF THAN 10 minutes which is not under con- UNUSUAL EVENT trol within 10 minutes ALL CONDITIONS after fire fighting i efforts begin 1
l O
- - - - - - - - , - - - - - . . - - - , . . - , . _ . . , - . , , - - . . . , . - , . . - - - - - , . , - - - - - . _ , . - , - - - - - - - . , .. c . -- ,
r N3.97887220 Q
D NUMBER EPIP-1.01 A TTACHMENT TITLE REVISION 15 EMERGENCY ACTION LEVEL TABLE A TT/CHMENT PAGE (TAB J) 1 SECURITY EVENT 32 of 41 CONDITION / APPLICABILITY INDICATION 'CLI,SSIFICATION
- 1. Loss of Station a) Shift Supervisor has GENERAL physical control been informed that ,
EMERGENCY the security force has ALL CONDITIONS been neutralized by ,
attack, resulting in '
loss of physical control of station pR b) Shift Supervisor has been informed of intru-sion into one or more Vital Areas which are occupied or controlled
\ by an aggressor
- 2. Imminent loss of Supervisor Security Shift SITE AREA physical Station has notified the Shif t EMERGENCY control Supervisor of imminent intrusion into a Vital ALL CONDITIONS Area ,
- 3. Ongoing Security com- Supervisor Security Shift ALERT promise has notified the Shift Supervisor of a confirmed ALL CONDITIONS unneutralized intrusion ,
into the Protected Area
- 4. Bomb potentially Shift Supervisor notifi- ALERT affecting station cation of a verified bomb safety systems discovered on or near a safety related system ALL CONDITIONS l
l i
O i
A
- m. .n.nu
) NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAB 3) 1 SECURITY EVENT 33 of 41 i
CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 5. Security threat, un- Supervisor Security Shift NOTIFICATION OF authorized attempted has initiated SPIP-29, UNUSUAL EVENT entry, or attempted Response to Security l sabotage Contingency Events ALL CONDITIONS ,
- 6. Bomb threat or a) Shift Supervisor notifi- NOTIFICATION OF discovery cation of a bonafide UNUSUAL EVENT bomb threat ALL CONDITIONS ,
q b) Shift Supervisor notifi-cation of bomb discovery y
within the Protected Area I
l V
- s. _ ,
N 3. 97887220 t
NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15
- EMERGENCY ACTION LEVEL TABLE PAGE A TTACHMENT (TAB K) '
1 HAZARD TO STATION OPERATION 34 cf 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Aircraft damage to Aircraft crash adversely SITE AREA vital plant systems affecte vital structures EMERGENCY by impact or fire ABOVE CSD CONDITION I
- 2. Aircraft crash on the a) Aircraft crash within ALERT facility the Protected Area ALL CONDITIONS OR a
b) Aircraft crash in Station Switchyard
- 3. Aircraft crash or un- a) Confirmed notification NOTIFICATION OF O usual aircraf t activity of aircraft crash within the site boundary UNUSUAL EVENT ALL CONDITIONS '
0R b) Unusual aircraf t activ-ity in the vicinity of the site as determined by the Shift Supervisor or Supervisor Security Shift
- 4. Severe explosive damage Explosion which results in SITE AREA severe degradation of any EMERGENCY ABOVE CSD CONDITION systems required for safe '
shutdown i
i 1
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ND.97887220 NUMBER ATTACHMENT TITLE REVISION 0 EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 15 PAGE ATTACHMENT (TAB K) 1 HAZARD TO STATION OPERATION 35 of'41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 5. Explosion damage to Unplanned explosion result- ALERT facility ing in damage to plant structure or equipment ALL CONDITIONS ,
- 6. Onsite explosion Confirmed report of un- NOTIFICATION OF planned explosion onsite UNUSUAL EVENT ALL CONDITIONS
- 7. Entry of toxic or flam- a) Uncontrolled release SITE AREA mable gases into plant of toxic or flam- EMERGENCY vital areas mable agents into Vital O' ABOVE CSD CONDITION Arcas AND b) Evacuation of Vital Area required S
Loss of a safety system function required for protection of the public
- 8. Entry of toxic or flam- Uncontrolled release of ALERT mable gases or liquids toxic OR flammable agent
'into plant facility which cause:
a) Evacuation of personnel from plant areas ALL CONDITIONS ,
I b) Safety related equipment ,
to be rendered inoperable l
1 l
l _ ___ __ _ __
r .
I l
N3.97887220 )
i NUMBER A TTACHMENT TITLE REVISION p
t EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB K) PAGE 1 HAZARD TO STATION OPERATION 36 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. On or nearsite release Unplanned release of toxic NOTIFICATION OF of toxic or flammable OR flammable agents which UNUSUAL EVENT liquids or gases may affect safety of station personnel E ALL CONDITIONS equipment ,
- 10. Severe missile damage Missile impact causing SITE AREA to safety systems severe degradation of safety EMERGENCY systems required for unit ABOVE CSD CONDITION shutdown i
- 11. Missile damage to Notification of missile ALERT hs) safety related equip- impact causing damage N' ment or structures to safety related equip-ment or structures AB0VE CSD CONDITION .
- 12. Turbine failure Failure of Turbine / ALERT with penetration Generator rotating equip-ment resulting in casing POWER penetration ,
- 13. Turbine rotating com- Failure of Turbine /Gener- NOTIFICATION OF ponent failure without ator rotating component UNUSUAL EVENT casing penetration resulting in unit trip POWER AND STARTUP i i
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No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 A TTACNMENT EMERGENCY ACTION LEVEL TABLE PAGE (TAB L) 1 NATURAL" EVENTS 37 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Earthquake greater a) Earthquake which acti- SITE AREA than DBE levels vates the Event Alarm EMERGENCY on the Strong Motion ABOVE CSD CONDITION Accelerograph AND b) AP-37, Seismic Event, calculations indicate horizontal motion of 0.15g fMt GREATER pR i
Safety related systems l
are significantly de-graded by earthquake
- 2. Earthquake greater a) Confirmed earthquake ALERT than OBE levels which activates Event Alarm on the Strong ALL CONDITIONS Motion Accelerograph l
AND b) AP-37, Seismic Event, calculations indicate i
horizontal motion of 0.07gfytGREATER
{ OR I
Safety related equipment is rendered inoperable by earthquake l
l
- 3. Earthquake detected Confirmed earthquake which NOTIFI:ATION OF i activates the Event Alarm UNUSUAL EVENT i ALL CONDITIONS on the Strong Motion Accelerograph 8
I Ns.97887220 NUMBER A TTACHMENT TITLE REVISION Q EPIP-1.01 15 CMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB L) PAGE 1 NATURAL EVENTS 38 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Tornado striking Tornado visually detected ALERT facility striking within the Pro-tected Area or Switchyard ALL CONDITIONS
- 5. Tornado onsite Tornado visually detected NOTIFICATION OF onsite UNUSUAL EVENT ALL CONDITIONS
- 6. Severe winds Sustained severe winds in SITE AREA excess of 100 mph caused by EMERGENCY ABOVE CSD CONDITION Hurricane, Tornado or other O severe weather condition
- 7. Extreme winds Sustained extreme winds ALERT between 80 and 100 mph AB0VE CSD CONDITION Hurricane or other severe weather conditions
- 8. High winds Sustained wind speed onsite NOTIFICATION OF measured or projected to be UNUSUAL EVENT ALL CONDITIONS between 73 and 80 mph ,
pR, System Operator notification of hurricane watch for Surry County
! k l
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N3.97887220 NUMBER A TTACHMENT TITLE REVISION
\/ EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB L) PAGE 1 NATURAL EVENTS 39 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 9. Flood or low water Flood in the James River - SITE AREA level above design. GREATER THAN +27 feet MSL EMERGENCY levels pR ALL CONDITIONS '
Water level in the James River - LESS THAN -9 feet MSLasindicatedbTloss of Emergency SW Pump suc-tion
- 10. Flood or low water Flood in the James River - ALERT level near design GREATER THAN +21 but LESS levels THAN +27 feet MSL Q ALL CONDITIONS OR ,
Water level in the Surry Power Station Intake Canal -
LESS THAN 18, feet AND DECREASING
- 11. Flood or low Flood in the James River - NOTIFICATION OF water level GREATER THAN +12 but LESS UNUSUAL EVENT THAN +21 feet MSL ALL CONDITIONS a BR l
Water level in the Surry Power Station Intake Canal -
LESS THAN 18, feet AND NOT INCREASING I
O
I e .
N3.9788Th?O O ?! UMBER A TTACHMENT TITLE REVISION EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE (TAE M) 1 MISCELLANEOUS ABNORMAL EVENTS 40 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 1. Any major internal or Shift Supervisor / Station GENERAL external events which Emergency Manager judge- EMERGENCY singlely or in combin- ment ation cause massive damage to station fa-cilities ALL CONDITIONS
- 2. Station conditions Shift Supervisor / Station SITE AREA which warrant activation Emergency Manager judgement EMERGENCY of emergency facilities
. monitoring teams and precautionary Protection
( Action Recommendations ALL CONDITIONS l 3. Station conditions Shift Supervisor / Station ALERT l which warrant precau- Emergency Manager judgement tiocary Protection Action Recommendations ALL CONDITIONS O
r ,
N3.97887220 NUMBER A TTACHMENT TITLE REVISION
\ EPIP-1.01 15 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB M) PAGE 1 MISCELLANEOUS ABNORMAL EVENTS 41 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION
- 4. Station conditions Shif t supervisor judgement NOTIFICATION OF which warrant increased that any of the following UNUSUAL EVENT awareness of state and/ exist:
or local authorities a) Intentional reduction ALL CONDITIONS in Power, Load or Temperature because I the unit has entered
, an Action Statement or will exceed a Limiting Condition for Operation.
l NOTE: In the event that other plant conditions require a shutdown, NOTI-FICATION OF UNUSUAL EVENT must still be declared on the basis that a shutdown would have been required by the Tech Spec.
SE.
b) Unit shutdown is other than a controlled shut-down i
(
91L l c) Unit is in an uncontrolled condition during operation SE! l l
d) A condition exists that has I the potential for escala- ! i tion and, therefore, !
warrants notification.
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_ -- __ ._ _ .