ML20215H308
| ML20215H308 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 09/29/1986 |
| From: | Costello J, Grody W, Miller H VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18149A370 | List: |
| References | |
| EPIP-1.01, NUDOCS 8610230091 | |
| Download: ML20215H308 (49) | |
Text
. _ - _ _ _ _ _ _ _ _ _ _ _ _
UTM 22 No 9788T230 VIRZINIA POCER SURRY POWER STATION
,[
EMERGENCY PLAN IMPLEMENTING PROCEDURE
/
\\d NUMBER PROCEDUPE TITLE REVISION 16 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PA GE (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 EN TRY CONDITIONS f'N Any one of the following:
LJ 1.
Another station procedure directs initiation of this procedure 2.
A potential emergency condition is reported to the Shift Supervisor.
8610230091 861017 PDR ADOCK 05000200 F
PDR REVISION RECORD 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:
07-24-86 REV. 16 PAGE(S):
Entire Procedure and Attachment 1 DATE: SEP 2 9 1985 O
APPROV R COMME ED SNS C REVIEW DA TE f
f f*(,
06 REVIEW STATION MANA ER APPPOV L DA TE uls w I -
9-l9-FC
/
EPIPA
No.97807210 NUMBER PROCEDURE TITI.E REVISION 16 O
EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 2 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 1.
INITIAL ASSESSMENT:
a) Perform initial assessment from EAL tables b)
Il[ EAL exceeded, b), Return to procedure in initiate EPIP-1.01:
effect 1)
BY:
DATE:
TIME:
4 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 2.b NATED INJURED PERSONNEL 1)
Initiate EPIP-5.01, Transport of Contami-nated Injured Personnel
- 2) Verify initiation of EPIP-4.20, H.P. Actions for Transport of Injured Contaminated Personnel
- 3) Continue this instruction
[ Step 2, continued on next page]
l
...--.n.
no. s7sento NUMBER PROCEDURE TITLE REVlil0N.
e 16 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 3 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOSTAINED 2.
IDENTIFY EVENT:
[ continued]
b) Event-Any of the following; b) g 3 Step 3_
Radiation Release Fuel Handling Incident Secondary Release S/G Tube Rupture LOCA
- 1) Request Health Physics initiate EPIP-4.01, O
Radiological Assessment Director Controlling Procedure, and continue this instruction O
we.orse7 to NUMBER PROCEDURE TITLE REVISION 16 fs t
)
EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE s
PAGE 4 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSENOTOBTAINED 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) GO TO Step 3.b.
indications of emergency conditions listed in the EAL Table, as necessary.
b) Use EPIP 1.01, Attach-ment 1, Emergency Action Level Table Index to determine event category AND GO T0 proper EAL tab c) Evaluate event to deter-mine classification,
- AND, GO YO Step 4 of this pro-cri5re C1
No.97887210 NUMBER PROCEDURE TITLE REVISION 16 I
EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE
~
5 of 8 i
STEP ACTION / EXPECTED RESPONSE RESPONSE NOT08TAINE0 4.
NOTIFICATION AND VERIFICATION:
a) LEOF - NOT ACTIVATED a) Announce transfer of command from TSC to LEOF and proceed to step 4.b.
b) TSC - NOT ACTIVATED b)' C0 TO Step 6.
l 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 f)
AREA, or GENERAL emergency,
\\,s_,/
request initiation of the Operations Department, Directive for augmenting s:aff resources during Emergency 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) DO NOT declare an emergency classification, AND GO TO Step 7,.
b)
II[ required, assign appropri-ate individual as Emergency Communicator fsO
[ Step 5, continued on next page]
No. 9788410 NUMBER PROCEDURE TITLE REVISION s
16 s
EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PAGE 6 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOBTAINED 5.
VERIFY EALS EXCEEDED:
(continued]
l c)
IF required, direct senior HP personnel on site to initiate EPIP-4.01, Radiological Assessment, Director Controlling Procedure 6.
DETERMINE EPIPS:
a) Event classification -
a) GO TO Step 6.b.
l NOTIFICATION OF UNUSUAL EVENT
- 1) GO TO EPIP-1.02, Response
~%
to Notification of Unusual Event b) Event classification - ALERT b) GO TO Step 6.c.
- 1) GO TO EPIP-1.03, Response to Alert c) Event classification - SITE c) GO TO Step 6.d.
l AREA EMERGENCY
- 1) GO TO EPIP-1.04, Response to Site Area Emergency d) Event classification -
GENERAL EMERGENCY l
l
- 1) C0 TO EPIP-1.05, Response to General Emergency 7.
SECURE FROM EVENT:
a) Notify involved station personnel that emergency condition does not exist
)
b) GO TO Step 11.
i
No. s7senso NUMBER PROCEDURE TITLE REVISION 16
(N EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE Q
PAGE 7 of 8 l
i STEP ACTION / EXPECTED RESPONSE RESPONSENOTORTAINEO 8.
TERMINATION NOTIFICATIONS:
a)
Initiate termination notifi-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:
a) Verify required reports and
()
notifications IAW EPIP-2.03, Reports to Offsite Agencies 10.
RECOVERY ACTIONS:
a) Notify involved station personnel of emergency termination b)
Initiate recovery actions b) GO TO EPIP-6.01, Reentry /
IAW established station Recovery Guidelines procedures and capabilities I
I c)
IF_ required, deactivate.
station emergency response facilities and personnel l
l l
l l
O
so.s7ss7:so NUMBER PROCEDURE TITI.E REVISION 16 EPIP-1.01 EMERGENCY MANAGER CONTROLLING PROCEDURE PA GE 8 of 8 STEP ACTION / EXPECTED RESPONSE RESPONSE NOTOSTAINED 11.
TERMINATE EPIP-1.01:
a) COMPLETED BY:
DATE:
TIME:
b) Forward completed EPIP-1.01, forms and other applicable records to Secretary.SNSOC O
EhT l
O
1 No.97sa722o
)
i NUMBER A TTACHMENT TITLE REVISION b
EPIP-1.01 16
\\--
EMERGENCY ACTION LEVEL TABLE A TTACHMENT PAGE 1
INDEX 1 of 41 CAUTION: Declaration of the highest emergency class for which an EAL is exceeded shall be made.
GO TO IF EVENT CATEGORY IS:
TAB 1.
Safety, Shutdown, or Assessment System Event
....................A 2.
Reactor Coolant System Event
....................................B
' 's 3.
Fuel Failure or Fuel Handling Accident...........................C 4.
Containment Event................................................D 5.
Radioactivity Event..............................................E 6.
Contaminated Personnel
..........................................F 7.
Loss of Secondary Cooling........................................G 8.
Electrical Failure...............................................H 9.
Fire.............................................................I 10.
Security Event...................................................J 11.
Hazard to Station Operation......................................K 12.
Natural Events...................................................L 13.
' Miscellaneous Abnormal Events....................................M bv
No. 918 81220
(
NUMBER A TTACHMENT TITLE REVISION
())
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB A)
PAGE 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 ABOVE CSD CONDITION Procedures 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 POWER & HSB for Operation.
NOTE:
In the event that other s.
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 0,,R h) Main feedwater AND Auxiliary Feedwater I
Systems O
r No.97887220 i
NUMBER A TTACHMENT TITLE REVISION O
EPIP-1.01 EHERGENCY ACTION LEVEL TABLE 16 (TAE A) ppcg A TTACHMENT 1
SAFETY,. SHUTDOWN, OR ASSESSMENT SYSTZM EVENT 3 of 41 i
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 l
a) Service Water I
0]!
b) Component Cooling pR c) Residual Heat Removal 5.
Failure of a safety Condition a) or b) exists:
NOTIFICATION OF or relief valve to UNUSUAL EVENT 4
I
.close after pressure reduction a) Pressurizer safety or PORV flow as indicated i
ALL CONDITIONS by accoustical or tem-i perature monitoring i
equipment AND l
RCS subcooling - LESS l
THAN 30*F b) Excessive flow through Steam Generator Safety, PORV, or Decay Heat Release valve indicated by RCS cooldown rate i
> 50*F per hour i
O
.,-.-,----.,--,,,,,.,~..,._.e_--,-.,_--,-,,
..... ~ -, -.,.. -. - -. - -, _.,. -, - -,. _ _ -, - -, -.....
w~.---.,_,--..-
No. 978 87220 NUMBER A TTACHMENT TITLE REVISION
(-'T EPIP-1.01
's l EMERGENCY ACTION LEVEL TABLE 16 (TAB A) p,gg A TTACHMENT 1
SAFETY, SHUTDOWN, OR ASSESSMENT SYSTEM EVENT 4 of 41 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 AND b) Manual:Rx trip - INITIATED AND c) Rx power indication-NOT DECREASING 4
V 7.
Trip following ATWT that a)~ ATWT - Manual Reactor ALERT takes the Rx Suberitical Trip following failure of Auto Trip Circuit POWER & HSB AND b) Reactor power -
DECREASING 8.
Indications or alarms Intentional reduction in NOTIFICATION OF on process or effluent Power, Load or Temperature UNUSUAL EVENT 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 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
-g by the Tech Spec.
O
No.97887220 s
NUMBER A TTACHMENT TITLE REVISION O,
EPIP-1.01 16 EMERCENCY ACTION LEVEL TABLE A TTACHMENT (TAE 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 perform offsite dose capability calculations.
ALL CONDITIONS 10.
Loss of plant communica-Complete failure of:
NOTIFICATION OF tions capability UNUSUAL EVENT ALL CONDITIONS a) Station Gai-Tronics system O
AND
\\s /
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 i-a unit transient AND POWER & HSB b) Loss of unit computer for CREATER THAN 15 minutes AND c) Unit operational tran-sient - IN PROGRESS 12.
All main board annunci-a) Simultaneous loss of all ilERT ator alarms and unit annunciator alarms on computer lost panels "A" to "K" POWER & HSB AND b) Loss of unit computer V
No. 97887220 t
NUMBER A TTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAE A)
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 Room with stable shutdown EMERGENCY NOT established within control NOT established E minutes within 15 minutes ALL CONDITIONS 14.
Evacuation of Main Con-Evacuation of the Control ALERT trol Room required Room with stable shutdown control established within ALL CONDITIONS 15 minutes O
N 3. 97887220
"')
NUMBER A TTACHMENT TlTLE REVlSION (Q
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAE 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 2.
RCS leak rate exceeds EP-2.00, Loss of Reactor SITE AREA makeup capacity or Secondary Coolant -
EMERGENCY IMPLEMENTED ABOVE CSD CONDITION AND 1
Pressurizer level cannot be raintained with two (2)
(
Charging /SI Pumps in operation 3.
RCS leak rate exceeds Intentional reduction in ALERT 50'gpm Power, Load or Temperature because the unit has ABOVE CSD CONDITION entered an Action State-ment or will exceed a L'.miting Condition for 0 eration.
1 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) Actions required IAW AP-16, Excessive Primary Plant Leakage AhT s_,)
b) RCS inventory balance indicates leakage -
GREATER THAN 50,gpm j
Hm.97887220 NUMBER A TTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAE B)
REACTOR COOLANT SYSTEM EVENT 8 of 41 l
CONDITION /APPLTCABILITY INDICATION CLASSIFICATION 4.
ECS 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 p
by the Tech Spec.
a) Unidentified RCS leakage - GREATER THAN 1,gpm O_R b) Indentified leakage -
GREATER THAN 10,gpm 0,3 c) Non-isolatable fault of RCS pressure beundary O
A ND 97887220 e
NUMBER A TTACHMENT TITLE REVISION n)
EPIP-1.01 (V
EMERGENCY ACTION LEVEL TABLE 10 9oY41
^Y '
REACTOR C00 STEM EVENT CONDITION / APPLICABILITY INDICATION CLASSIFICATION 3
RCP locked rotor a) Flow in one or more ALERT leading to fuel dam-RC loops - LESS THAN age
,90%
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 (b}
cpm 6.
Gross Primary to Second-EP-4.00, Steam Generator SITE AREA ary leakage with loss of Tube Rupture - IMPLEMENTED EMEFGENCY offsite power AB0VE CSD CONDITION AND Loss of offsite power indi-cated by zero volts for 4160V Buses D, E & F
No.97887220 f -.
NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 EMERGENCY ACTION LEVEL TABLE 16 i
(TAB B)
PAGE A TTACHMENT 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 J_gPm S.R_
GREATER THAN 500 gal.
v' 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 Tube Rupture - IMPLEMENTED ABOVE CSD CONDITION O
No. 97887220 NUMBER A TTACHMENT TITLE REVISION (s-EPIP-1.01 ~
16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B).
PAGE 1
REACTOR COOLANT SYSTEM EVENT 11 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 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-AB0VE CSD CONDITION ment or will exceed a-Limiting Condition for Operation.
NOTE:
In the event that other plant conditions require a shutdown, NOTI-F1 CATION OF UNUSUAL EVEh"I must still be declared on the basis that a shutdown would have been required f~
by the Tech Spec.
b a) Primary to Secondary leakage - GREATER THAN 1 Spm 0R GREATER THAN 500 gal.
per day per generator.
1 o
No 97887220 NUMBER A TTACHMENT TITLE REVISION O
/
EPIP-1.01 EME2GENCY ACTION LEVEL TABLE A TTACHMENT (TAB B)
PAGE 1
REACTOR COOLANT SYSTEM EVENT 12 of 41 l
l 1
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:
- 1) RCS specific activity -
GREATER THAN OR EQUAL TO 300 pCi/ gram dose equivalent I-131.
- 2) 5 or more core exit therrocouples reading-GREA'lER THAN 1200*F
'U b) Loss of RCS !ntegrity 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 {ng-GREATERTHAN 2x10 mR/hr c) Loss of containment integ-rity as indicated by any of the following:
- 1) Containment pressure -
GREATER THAN Q psia AND NOT DECREASING
- 2) OP-1E, Containment Integrity Checklist.
N3.97887220 f%
NUMBER A TTACHMENT TITLE REVISION ~
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB B)
PAGE 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 fitminent ALL CONDITIONS a) Fuel clad integrity failure as indicated by any of the following:
- 1) RCS specific activity -
GREATER THAN 300 taci/
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) Faulted steam gener-ator as indicated by EP-2.00, Loss of Reactor or Secondary Coolant O
No. 97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT ~
(TAB C)
PAGE 1
FUEL FAILURE OR FUEL HANDLING ACCIDENT 14 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 1.
Core damage with pos-Condition a) exists with SITE AREA sible loss of coolable b)
EMERGENCY.
geometry a)
Fuel clad failure as AB0VE CSD CONDITION indicated by any of the following:
- 2) High Range Letdown Radiation Monitor (RM-CH-118. -218)
O 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 INCREASING v
No. 978 87220 e
NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C)
FUEL FAILURE OR FUEL HANDLING ACCIDENT 15 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 2.
Severe Fuel Clad a) RCS specific activity -
ALERT Damage GREATER TRAN 300 pCi/ gram dose equivalent I-131 ABOVE CSD CONDITION SE High Range Letdown Radi-ation Monitor (RM-CH-118,
-218)indicationgncreases 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 s,
. because the unit has ABOVE CSD CONDITION entered an Action State-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.
EE a) High Range Letdown Radiation Monitor indication increases -
GREATER THAN 105 cpm within 30 minutes AND
~
remains for at least 15, minutes.
O
Nn.9788722C NUMBER A TTACHMENT TITLE REVISION (y
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C)
PAGE 1
FUEL FAILURE OR FUEL HANDLING ACCIDENT 16 of 41 CONDITIOiUAPPLICABILITY INDICATION CLASSIFICATION 4.
Probable large radio-a)
EP-2.00, Loss of Reactor GENERAL activity release or Secondary Coolant, -
EMERGENCY initiated by LOCA with IMPLEMENTED, ECSS failure leading to core degradation AND ABOVE CSD CONDITION-RCS specific activity -
GREATER THAN 300 pCi/ gram dose equivalent I-131 AND b) High.or Low Head ECCS flow - NOT being delivered to the core
~~
5.
Probable large radio-a) Loss of Main FW system GENERAL activity release and Condensate System EMERGENCY initiated by loss of heat sink leading to core AND degradation b) Loss of Auxiliary FW ABQVE CSD CONDITION System AND c) RHR System - NOT OPERABLE 6.
Probable large radio-a) Rx nuclear power after GENERAL activity release a trip remains - GREATER EMERGENCY initiated by failure of THAN 5,%
l protection system to bring Rx subcritical AND and causing core de-gradation b) RCS pressure - GREATER THAN 2485 psig AND NOT AB0VE CSD CONDITION decreasing 0,E Containment pressure and temperature are RAPIDLY
,,,j INCREASING
No. 97887220 NUMBER A TTACHMENT TITLE REVISION O
EPIP-1.01 16 k-EMERGENCY ACTION LEVEL TABLE s
A TTACHMENT (tab C)
PAGE 1
FUEL FAILURE OR FUEL HANDLING ACCIDENT 17 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 7.
Probable large radio-a)
ECA-1.00, Loss of All GENERAL activity release AC Power - IMPLEMENTED EMERGENCY initiated by loss of AC and all feedwater AND AB0VE CSD CONDITION b) Turbine Driven Auxiliary Feedwater Pump NOT OPERABLE AND c) Restoration of a) or b) above not likely within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 8.
Probable large radio-a) EP-2.00, Loss of Reactor GENERAL activity release or Secondary Coolant -
EMERGENCY initiated by LOCA with IMPLEMENTED loss of ECCS and con-tainment cooling AND AB0VE CSD CONDITION b) High OR Low Head ECCS flow NOT being delivered to the core AND c) Containment RS sump temp-erature-GREATER THAN 190*F AND NOT DECREASING 0, R Containment Spray and Recir-culation Spray Systems-NOT OPERABLE
()
\\)
n
~,-
N3.97887220 NUMBER A TTACHMENT TITLE REVISION I T EPIP-1.01
-/
EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB C)
PAGE 1
FUEL FAILURE OR FUEL HANDLING ACCIDENT 18 of 41 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 OJt ALL CONDITIONS Water level in Spent Fuel Pit verified - BELOW TOP OF SPENT FUEL AND b) Verified damage to irra-diated fuel resulting in readings on Ventilation Vent Gasecus Monigor -
<~'s
(,)
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) Heald Physics confirms fission product release from fuel 0,,R c) Readings on the Ventila-tion Vent Gaseous Monitor (RM-gG-110)-GREATERTHAN 1x10 cpm 11.
Spent Fuel Storage a) Verified loss of all cask / ALERT Facility accident with fuel containment barriers release of radioactivity AND ALL CONDITIONS
(
b) Health Physics confirms
\\/
fission product release
No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 16 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
N3.97887220 a
NUMBER A TTACHMENT TITLE REVISION C/
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB D)
PAGE 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 GREATERTHAN5x10}mR/hr (RM-RMS-161, -261 pressure and tem-perature ABOVE CSD CONDITION AND b) Containment pressure -
GREATER THAN M psia AND is NOT decreasing SR Containment temperature -
GREATER THAN 280*F 2.
High Containment a) Outside Containment High SITE AREA radiation, pressure, Range Radiation Monitor EMERGENCY GREATERTHAN2x10}mR/hr (RM-RMS-161, -261 -
and temperature AB0VE CSD CONDITION AND b) Containment pressure -
GREATER THAN 23 psia and is NOT de Weasing S
Containment temperature -
l-GREATER THAN 200*F O
N3. 97887220 NUMBER
. ATTACHMENT TITLE REVISION EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB D)
PAGE 1
CONTAINMENT EVENT 21 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 3.
High Containment radia-a) Outside Containment High ALERT tion, pressure and Range Radiation Monitor temperature (RM-RMS-161,-2g1)-
GREATER THAN 10 mR/hr ABOVE CSD CONDITION AND b) Containment pressure -
GREATER THAN 17.7 psia E
Containment temperature -
GREATER THAN 150 *F 4.
Loss of Containment Intentional reduction in NOTIFICATION OF
(
s integrity Power, Load or Temperature UNUSUAL EVENT because the unit has entered ABOVE CSD CONDITION an Action Statement or will exceed a Limiting Condition for Operations, t
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) Loss of Containment integrity as indi-cated by OP-1E, Containment Integrity Checklist.
O
No.97887220 NUMBER A TTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT
{ TAB E)
PAGE 1
RADI0 ACTIVITY 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 12, Rem' thyroid ex-2.0 Rem Whole Body OR posure 12.0 Rem Thyroid exposure as determined ALL CONDITIONS from EPIP-4.01.
2.
Projected or actual a) Confirmed actual or SITE AREA g-~
site boundary doses projected site boundary EHERGENCY
( j 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 ALL CONDITIONS from EPIP-4.01.
i t
O
N3. 97887220 NUMBER A TTACSIMENT TITLE REVISION l
EPIP-1.01
' ~ ' '
EMERGENCY ACTION LEVEL TABLE PAGE A TTACHMENT (TAB E)
'l 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 Control Area Monitor (RM-RMS-154) c) Auxiliary Building Drumming Area Monitor (RM-RMS-155) 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)
,.-g
---e.%-e.
,-s,
.+.-
...,, - -,.3.w---
y-p,
.e e-4
N3.97887220 NUMBER A TTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB E)
PAGE 1
RADIOACTIVITY EVENT 24 of 41
- =
CONDITION / APPLICABILITY INDICATION CLASSIFICATION 4.
Effluent Release CREATER a) Ventilation Vent Gaseous ALERT THAN 10 TIMES T.S.
Monitor (RM-VG-110 or instantaneous allowable RM-VG-131) - GREATEiI limits THAN 1000% T.S. value as determined from Attach-ALL CONDITIONS ment 1, AP-5.20 SE b) Process Vent Gaseous Monitor (RM-GW-102 or RM-GW-130) - GREATER THAN 1000% T.S. value as determined from, AP-5.01 V
_O_R.
c) Air Ejector Monitor (RM-SV-111, -211)6
~
CREATER THAN 1x10 cpm AND Air ejector exhaust -
NOT diverted to contain-ment.
SE d) Discharge Tunnel Monitor (RM-SW-120 -220) 5 GREATER THAN 1.3x10 cpm SE e)
Sampling and Analysis Team confirms effluent release GREATER THAN 1000% T.S. value as determined from EPIP-4.01.
iO
+ - - - '
y- - -,
,y--
-m,.
,----. -, --,,w
--s r
-.,g,---,.
m.
y-,----+
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ND.97887220 NUMBER A TTACHMENT TITLE REVISION
' {}
EPIP-1.01 16 w_/
EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB E)
PAGE 1
RADIOACTIVITY 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% ?.S. value as ALL CONDITIONS detemined from Attach--
ment 1, AP-5.20 b) Process Vent Gaseous Monitor (RM-GW-102 or RM-GW-130) - GREATER THAN 100% T.S. value as determined from, AP-5.01 S
c) Air Ejector Monitor (RM-SV-111, -211) 5 GREATER THAN 1.99x10 cpm AND Air Ejector Exhaust -
MOT diverted to contain-ment.
E d) Discharge Canal Monitor (RM-SW-120, -220)
GREATER THAN 1.3x10' cpm e)
Sampling and Analysis Team confirms effluent t
release GREATER THAN 100% T.S. value as determined from EPIP-4.01.
O
No.97887220 NUMBER A TTACHMENT TITLE REVISION EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB F)
PAGE 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 2ndividual to off-site facility for treatment fa-111ty ALL CONDITIONS 4
0 l
4 O
~
N3.97887220 p.
NUMBER A TTACHMENT TITLE REVISION
()
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB G)
PAGE 1
LOSS OF SECONDARY COOLANT 27 of 41
-CONDITION / APPLICABILITY INDICATION CLASSIFICATION 1.
Major Secondary line a) Faulted steam gener-SITE AREA break with Primary to ator r
'ndicated by EMERGENCY Secondary leakage EP-2.s Loss of Reactor GREATER THAN 50 gpm and or Secondary Coolent fuel damage indicated AND ABOVE CSD CONDITION b) RCS specific activity -
GREATER THAN 300 pCi/ gram 0,R Letdown High Range Radia-tion Monitor (RM-CH-118 5
-218) - GREATER THAN 10 cpm AND c) Condenser Air Ejector RadiationMonitor(RM-Sg-111
-211) - GREATER THAN 10 cpm E
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, -22g) R/hr GREATER THAN 2.55x10 m
O
No.97007220 NUMBER A TTACHMENT TITLE REVISION
/
EPIP-1.01 6
EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB G)
PAGE 1
LOSS OF SECONDARY COOLANT 28 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 2.
Major Secondary line a) Faulted steam generator ALERT break with Primary to as indicated by EP-2.00, Secondary leakage Loss of Reactor or greater than 10 GPM Secondary Coolant AB0VE CSD CONDITION AhT b) Condenser Air Ejector Radiation Monitor (RM-SV-111, -211)6
~
GREATER THAN 1x10 cpm OR Steam Generator Blowdown Radiation Monitor (RM-SS-112, -113, -212 -213) -
5 GREATER THAN 10 cpm 3.
Major Secondary line Faulted steam generator NOTIFICATION OF break as indicated by EP-2.00, LTUSUAL EVENT Loss of Reactor or Second-ABOVE CSD CONDITION ary Coolant l
O
Nh 97887220 O
NUMBER A TTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB H)
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 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 ALL CONDITIONS a) Ammeters for 4160V Reserve
[
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 4
I O
l N3.97887220 NUMBER A TTACHMENT TITLE.
REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB H)
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 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 -
ZERO AMPS
\\m 4.
Loss of all on-site The following conditions SITE AREA DC' power for-GREATER exist for a period -
EMERGENCY THAN 15 minutes CREATER THAN 5 minutes ALL CONDITIONS a) All Station Battery volt-meters - ZERO VOLTS AND b) No light indication avail-able to Reserve Station Service Breakers 15D1, 15El and 15F1 5.
Loss of all on-site a) All Station Battery volt-ALERT DC power meters - ZERO VOLTS ALL CONDITIONS AND b) No light indication avail-able to Reserve Station Service Breakers 15D1, 15El and 15F1 O
-__.,,.,y y-m.
._,__..___,_..,___-,_.,,m.
,___m..-.
.,_y_,_,n_,,.
ris,97007220 NUMBER A TTACHMENT TITLE REVISION
(
EPIP-1.01 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB 1)
PAGE 1
FIRE 31 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 1.
Fire resulting in de-a) Fire within the Station SITE AREA gradation of safety which causes major de-EMEPGENCY systems gradation of a safety system funct'on 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-which has potential for tems 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 efforts begin h
s No. 97887220 p
NUMBER A TTACHMENT TITLE REVISION
,V EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB 3)
PAGE 1
SECURITY EVENT 32 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 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 SE b) Shift Supervisor has been informed of intru-sion into one or more Vital Areas which are occupied or controlled O
by an aggressor 2.
Imminent loss of Supervisor Security Shift SITE AREA physical Station has notified the Shift 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 OJL near a g
safety related system ALL CONDITIONS
!O
No.91881220 NUMBER A TTACHMENT TITLE REVISION EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB J)
PAGE 1
SECURITY EVENT 33 of 41 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 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 b) Shift Supervisor notifi-O cation of bomb discovery within the Protected Area O
Ns.97887220 NUMBER A TTACHMENT TITLE REVISION i
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB K)
PAGE 1
HAZARD TO STATION OPERATION 34 cf 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 1.
Aircraft damage to Aircraft crash adversely SITE AREA vital' plant systems affects vital structures EMERGENCY by impact or fire ABOVE CSD CONDITION 2.
Aircraft crash on the a) Aircraft crash within ALERT facility the Protected Area ALL CONDITIONS 01[
b) Aircraft crash in Station Switchyard 3.
Aircraft crash or un-a) Confirmed notification NOTIFICATION OF
(N usual aircraft activity of aircraft crash within UNUSUAL EVENT
\\s /
the site boundary ALL CONDITIONS 0,R b) Unusual aircraft 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 AB0VE CSD CONDITION systems required for safe shutdown O
Ns.97687220 NUMBER A TTACHMENT TITLE PUISION p
Q1 EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB K)
PAGE 1
HAZARD TO STATION OPERATION 35 of 41 CONDITION / APPLICABILITY INDICATION CLASSIFICATION 5.
Exp?osion 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 Cg! flam-EMERGENCY l
vital areas mable agents into Vital ABOVE CSD CONDITION AND b) Evacuation of Vital Area required 2E i
Loss of a safety system function required for protection of the public 8.-
Entry of toxic or flam-Uncontrolled release of ALERT l
mable gases or liquids toxic (g! flammable agent l
into plant facility which cause:
l a) Evacuation of personnel t
from plant areas ALL CONDITIONS AND l
b)
Safety related equipment to be rendered inoperable
Ns.91881220 NUMBER A TTACHMENT TITLE REVISION
(_,/
EPIP-1.01 16 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 Oft flammable agents which UNUSUAL EVENT liquids or gases may affect safety of station personnel OR 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 11.
Missile damage to Notification of missile ALERT
[)
safety related equip-impact causing damage N-ment or structures to safety related equip-ment or structures ABOVE 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 O
No. 97487220 (Q
NUMBER A TTACHMENT TITLE REVISION V
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB L)
PAGE 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 oft GREATER 0_R fs Safety related systems
'('
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 AND b)
AP-37, Seismic Event, calculations indicate horizontal motion of 0.07g Oft GREATER 1R Safety related equipment is rendered inoperable by earthquake 4
3.
Earthquake detected Confirmed earthquake which NOTIFICATION OF activates the Event Alarm UNUSUAL EVENT ALL CONDITIONS on the Strong Motion Accelerograph i
l v
N3.97887220
,o NUMBER A TTACHMENT THTE REVISION
'~
EMERGENCY 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
()
severe weather condition 7.
Extreme winds Sustained extreme winds ALERT between 80 and 100 mph ABOVE 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 D
o
Nt 97887220 NUMBER A TTACHMENT TITLE REVISION
(
EPIP-1.01 16 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 0,, R ALL CONDITIONS Water level in the James River - LESS THAN -9 feet
~
MSL as indicated by loss 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
(}
ALL CONDITIONS Oft 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 OR Water level in the Surry Power Station Intake Canal -
LESS THAN 18 feet AND NOT INCREASING ~~
i O
us. sissnao
,e NUMBER A TTACHMENT TITLE REVISION p(j EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB M)
PAGE 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 Ih Action Recommendations k)
ALL CONDITIONS 3.
Station conditions Shift Supervisor / Station ALERT which warrant precau-Emergency Manager judgement tionary Protectirn Action Recommendations ALL CONDITIONS O
N3.97887220
.,.b NUMBER A TTACHMENT TITLE REVISION d
EPIP-1.01 16 EMERGENCY ACTION LEVEL TABLE A TTACHMENT (TAB M)
PAGE I
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 the unit has entered an Action Statement or will exceed a Limiting Condition for Operation.
NOTE:
In the event that other plant conditions O,'
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
_O_R_
l c) Unit is in an uncontrolled condition during operation SE d) A condition exists that has the potential for escala-tion and, therefore, warrants notification.
O
.