ML20027E767
| ML20027E767 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 10/04/1982 |
| From: | Ray H SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13333B820 | List: |
| References | |
| PROC-821004-01, NUDOCS 8211160078 | |
| Download: ML20027E767 (64) | |
Text
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A\\\\m SAN ONOFRE' NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16
=.
3 UNITS 1, 2 AND 3 COMPLETELY REVISED REVISION 2 PAGE 1 EFFECTIVE DATE OCT - 1582
)
NOTIFICATION
}
s p.t, TABLE OF CONTENTS j
SECTION PAGE 1.0 OBJECTIVE 2
4
2.0 REFERENCES
2 3.0 PREREQUISITES 2
4.0 PRECAUTIONS 2
5.0 CHECK-0FF LIST 3
6.0 PROCEDURE 3
7.0 RECORDS 7
8.0 ATTACHMENTS 7
PAGES CHANGED WITH THIS REVISION: ALL O
ej.
b" / G -h PREPARED BY:. Procedure Writer Date APPROVED BY:
f-//Vd.
H. B. RAT Date STATION GER l
DB:0268F/daj l
RECEIVEL l
OCT 4 1982 l
COM FiTE Sl~!Fl00?Y O
l 8211160078 821108 PDR ADOCK 05000206 F
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..~.a. c EMERGENCY PROCEDURE S0123-VIII-16 SAN ONOFRE NUCLEAR GENERATING STATIONREVISION 2 PAGE 2 UNITS 1, 2 AND 3
)
NOTIFICATION y? ?
1.0 OBJECTIVE This procedure provides instructions for notification of offsite 1.1 authorities and emergency response agencies in emergency situations.
,;y The Emergency Coordinator is responsible for implementation of the The Shift Communicator /
f 1.2 actions described in this procedure.
Emergency Planning Coordinator is designated to provide notification to Offsite agencies.
2.0 REFERENCES
NUREG-0654/ FEMA-REP-1, Rev. 1, Criteria for Preparation and Evaluation j
of Radiological Emergency Response Plans and Preparedness in Support 2.1 of Nuclear Power Plants.
5 San Onofre Nuclear Generating Station Unit 1, 2 and 3 Emergercy Plan.
2.2 3.0 PREREQUISITES An emergency condition has beea declared at SONGS-1, 2 or 3 in accordance with 501(23)-VIII-11.1 ' CLASSIFICATION OF EMER 3.1 OR An existing emergency condition has been reclassified to a higher or lower emergency category, and/or, a significant deterioration in 3.2 conditions has occurred.
OR The emergency situation has been corrected and the emergency 3.3 terminated.
OR Follow up notifiestion is required to update offsite agencies.
3.4 4.0 PRECAUTIONS _
No press releases on the incident shall be made prior to completion of all notifications, and will be made only by Southern California Edison 4.1 public information personnel.
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 50123-VIII-16 REVISION 2 PAGE 3 UNITS 1, 2 AND 3 T
~ ;
5.0 CHECK-0FF LIST pl*
5.1 None.
6.0*
PROCEDURE b:
i 6.1 Keep a " Notification Log" per procedure 50123-VIII-51 4
"Recordkeeping". Obtain assistance from other available TSC I
Personnel during times of heavy communciation.
IEDIALS 6.2 Notification Instructions:
The Shift communicator will proceed as follows:
CAUTION For NRC Notification use Attachments 8.5 (NRC Event Notification Form) Only.
6.2.1 Obtain from the Emergency Coordinator, or his designee, information needed to complete the required Notification Form.
INITIALS 6.2.2 When complete, ensure that if Protective Action recommendations are required, that the type of action (shelter or evacuate), affected sector and distances are listed under the additional information section of Attachmeints 8.2, 8.3 and 8.6 have the Emergency Coordinator authorize Notification Form prior to transmitting it to offsite agencies.
INITIALS 6.2.3 Using attachment 8.1 Table 1 " EMERGENCY NOTIF CATION CALL LIST" Contact each organization in the order listed as follows:
.1 Contact each organization using the primary number or the alternate number (s) if required.
(Use *99 when contacting Local Offsite Agencies.
l INITIALS NOTE:
If a party cannot be reached on the primary or alternate numbers listed, bypass that party and proceed down the list.
Y
SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE $0123-VIII-16 UNITS 1, 2 AND 3 REVISION 2 PAGE 4
'h'60
~
PROCEDURE (Continued) s 6.2.3.2 When the party answers note the name(s) of the
[t;.
individual (s) contacted and the time of the contact on
- .1.
Ensure that each individual has the
{,
latest revision of the notification form in use. (When v'
using *99 get all names prior to proceeding to next step).
<t INITIALS
.3 During times of heavy traffic on the Yellow (IAT) phone, do not read any notification form that will tie up the phone for an extended period of time.
Simply inform the offsite agencies of what kind of notification is to be transmitted and ask them to confirm receipt of their hard-copy on the teletype.
INITIALS
.4 Re:d the introduction paragraph on the notification form
.and pause to allow the individual (s) to obtain a copy of the form, on which to record the notification.
INITIALS
.5 The message serial number is an additional means to label each message. The first initial notification will always be #01 and each subsequent message will be in numerical sequence.
Message Sent would be Example:
Initial Notification Form - Msg Serial #1 1st Follow up Notification - Msg Serial #2 2nd Follow up Notification - Msg Serial #3 Event upgraded-initial notification - Msg Serial #4 1st Follow up Notification - Msg Serial #5 to upgraded event NOTE: Attachments 8.4 and 8.5'will not be serialized.
.6 When the individual (s) have a copy of the form, read the text of the notification, emphasizing information in the blanks.
INITIALS
.7 Confirm message receipt as follows:
a m.-.~~o
0.25 g, the event would be classified as an Alert (in accordance with S0123-VIII-11) and numbered as follows:
ALERT 81 NOTE: As shown above, each emergency condition, is numbered sequentially in its classification from January 1 thru December 31 of each year.
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SAC ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16 UNITS 1, 2 AND 3 REVISION 2 PAGE 8 6.0 PROCEDURE (Continued)
NOTE: This number is not to be confused with the 4.*
event classification number used on line number 1 of Attachments 8.1, 8.6 & 8.7.
r This number is used to track the number of
(.
emergency events and for a file number in COM.
7.0C RECORDS 7.1 After completion of checklists and when they are no longer required for immediate use, forward to the Administrative Leader (Manager, Station Emergency Preparedness if Emergency Organization is not activated.)
8.0 ATTACHMENTS 8.1 Emergency Notification Call-List (Table 1) 8.2 Initial Notification Form 8.3 Follow Up Notification Form 8.4 ODAC Notification Form 8.5 Event Notification Form (For use with ENS Phone)
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8.6 De-escalation Notification Form 8.7 Close Out Notification Form l
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UNITS 1,3 AND 3 REVISION 2 PAGE 1 o'f Y ATTACHMENT 8.1 EMERGENCY NOTIFICATION LIST _
DATE:
EMERGENCY EVENT NUMBER:
(See 6.5 for instruction. Example: Alert 81]
HARD CALL BACK TELE TIME /
COPY VERIFICATION NAME/ TIME ORGANIZATION IAT#
TYPE #
NAME OF CONTACT INITIALS RCVD ALTERNATE PHONE NUMBER SCE Dispatcher N/A N/A_
/
N/A l
PAX BELL I
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- NOT E : ALL CALL CODE FOR INTERAGENCY TELEPHONE (IAT) -
, Teletype -
U.S.M.C.
Cainp Pendletnn -
Duty Officer /
E.O.C.
- 22 N/A
/
V
'VCF Duty Officer -
Teletype In E.0.C.
(AskOperatorforassistance.)
Only E.O.C. -
State Parks
- 24 USB
/
Pendleton
{8-5.M-F)24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> dispatcher)
Coast If no answer refer to Emergency Phone Director for home numbers of Park Rangers) phone City of San
- 25 USC
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, Clonente City of San
- 26 USJ
/
, Juan Capistrano Trange County will contact i
I ($JC)
SJC when EOC is not manned.
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SAN ON0r-" NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 50123 "' #-16 s
UNITS '.
AND 3 REVISION 2 PAGE
- 2 ATTACitMENT 8.1 EMERGENCY NOTIFICATION LIST fL.'
~@o'ntinWd) q HARD
(.
CAlt. BACK TELE TIME /
COPY VERIFICATION - NAME/ TIME ORGANIZATION
!ATs TYPEt NAME OF_ CONTACT INITIALS RCVD ALTERNATE PHONE NUMBER i
- NOTE: ALL CALL CODE FOR INTERAGENCY TELEPHONE (IAT) -
, Teletype -
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Orange Cnunty
- ?7-ZZZ
/
I Comnunica t ions V8 Control One/
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E.0.C.
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San Diegn
- ?_9_
UES
/
County Disaster *33 Preparedness Control Center /
E.O.C.
C.H.P., Santa
- 30 USA Ana
/
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(after 5 p.m.) j C.ll.P., San
- 32 USD
/
Diego e
- ALL NOTIFICATIONS TO SACRAMENTO WILL BE MADE BY THE EOF WHErl ACTimTED****
i Office Of Emergency Services N/A N/A
/
(Sacramento)
TB1 d Phone)
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NRC
-(]Trect LTn/AeT NA N
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N/A i
Dethesda.
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SAN ONOFRE' NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16 UNITS 1, 2 AND 3 REVISION 2 Page 1 of 1 ATTACHMENT 8.2 INITIAL NOTIFICATION FORM
)
THIS NOTIFICATION MUST BEGIN WITHIN 2 HOURS AFTER DECLARATION OF AN UNUSUAL EVENT AND WITHIN 15 MINUTES FOR ALL HIGHER CLASSIFICATIONS.
b Da Time:
Emergency Event No.
"ThjsistheSanOnofreNuclearGeneratingStation.A(An)
(CMcle the applicable Classification Below)
UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY has occurred at Unit (s)
Record the following information on your Initial Notification Form.
MESSAGE I.D. NUM9ER 1.
Event No.
listed in the Manual of Emergency Events describes this event.
2.
There _
has been a release of radioactivity.
HAS/HAS NOT 3.
A release HAS/HAS NOT BEEN STOPPED /NEVER OCCURRED 4.
The release is to the fm ATMOSPHERE /0CEAN/NOT APPLICABLE 5.
There _
a potential for { ADDITIONAL) release.
IS/IS NOT (cross out if N/A) 6.
There a need for protective action beyond the Site Boundary.
15/15 NOT Affected Sectors:
/
/
/
/
/
/
/
/
Recommended Protective Actions:
7.
Additional information:
t 8.
If a Bell Phone was used, Call to verify receipt of this Notification.
BELL #
l 9.
Ensure your teletypes is in PRINT LINE mode.
Call _
to verify l
hard copy receipt.
IAT or BELL #
10.
San Clemente please read back this message. Other Stations check for accuracy.
DRAFTED:
APPROVED:
d SHIFT COMMUNICATOR /
EMERGENCY COORDINATOR EMERGENCY PLANNING COORDINATOR
SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16
, UNITS 1, 2 AND 3 REVISION 2 Page 1 cf 2 ATTACHMENT 8.3 FOLLOW-UP NOTIFICATION FORM s
THIS NOTIFICATION SHOULD BE MADE AT LEAST ONCE EVERY HOUR DURING h4-CHANGING PLANT CONDITIONS ONLY.
Time:
Emergency Event No.
[,
(Sequential Number for Each Year, See 6.5)
Dat "This is the San Onofre Nuclear Generating Station. This is a Follow-Up Notification a (an): (Circle the applicable Classification Below)
UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY Which is in progress at Unit (s)
Record the following information on your Follow-up Notification Form.
MESSAGE I.D. NUMBER:
1.
Current Plant Conditions:
b
\\ j 2.
Recommended Protection Actions:
3.
Prognosis of Emergency:
4.
Emergency Response Actions Underway:
5.
Request for Support:
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I SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16 UNITS 1,.2 AND 3 REVISION 2 Paga 2 cf 2 ATTACHMENT 8.3 3
Dose Projections / Measurements 5/j s/.
Site Boundary 2 Miles 5 Miles 10 Miles Whole Body Dose Rate (in mrem /hr)
/
/
/
/
r I'
Thyroid Dose (mrem)
/
/
/
/
7.
Meteorology Date:
Wind Direction From
'T/To
- T Wind Speed miles / hour 8.
If a Bell Phone was used, Call to verify receipt of this Notification.
BELL #
9.
Ensure your teletype is in PRINT LINE mode. Call to verify hard copy receipt.
IAT or BELL #
10.
San Clemente please read back this message. Other Stations check for accuracy.
DRAFTED:
APPROVED:
SHIFT COMMUNICATOR /
EMERGENCY COORDINATOR EMERGENCY PLANNING COORDINATOR O
SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16 REVISION 2 P ge I cf 2 UNITS 1, 2 AND 3 ATTACHMENT 8.4 ODAC NOTIFICATION FORM THIS NOTIFICATION SHOULD BE MADE AT LEAST ONCE EVERY HOUR DURING
{*
CHANGING PLANT CONDITIONS ONLY.
Emergency Event No.
- Timiri,
~
(Sequential Number for Each Year, see 6.5)
)
Date!
"This is the San Onofre Nuclear Generating Station. This is an 00AC Notification.
A(an):
(Circle the applicable Classification Below)
UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY Which is in progress et Unit (s)
The following Information is provided.
1.
Dose Projections Site Boundary 2 Miles 5 Hiles 10 Miles Whole Body Dose Rate (in mrem /hr)
/
/
/
/
Thyroid Dose (mrem)
/
/
/
/
Thyroid Dose (mrem) (2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)
/
/
/
/
Highest / Adjacent Sectors Affected:
/
/
/
/
l
/
/
/
/
2.
Measurements Time Location Whole Body Thyroid i
mrem /hr mrem /hr mrem /hr mrem /hr mrem /hr mrem /hr l
mrem /hr mrem /hr
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k,
'h I
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SAN ONOFRE' NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 50123-VIII-16 UNITS 1, 2 AND 3 REVISION 2 P:ge 2 cf 2 ATTACHMENT 8.4 2.
Airbcrne Release:
j
% f)
(:
Time Release Started AM/PM Release Duration hrs.
1 Expectied Release Rate C1/sec d Xe-133 Equivalent C1/sec I-131 Equivalent Release Rate C1/sec 3.
Meteorology Data:
Wind Direction From:
Wind Speed miles / hour Affected Sector (s)
/
/
/
/
/
/
/
/
Stability Class Precipitation 5.
Liquid Release:
Time Release Started AM/PM AM/PM Expected Release Duration hrs.
hrs.
I I
Release Rate gal.
C1/sec 6.
If a Bell Phone was used, Call to verify receipt of this Notification.
BELL #
7.
Ensure your teletype is in PRINT LINE mode. Call to verify hard copy receipt.
IAT or BELL #
l 8.
Please read back this message to check for accuracy.
l l
DRAFTED:
APPROVED:
SHIFT COMMUNICATOR /
EMERGENCY COORDINATOR l
EMERGENCY PLANNING COORDINATOR l
i l
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SA,N ONOFRE. NUCLEAR GENERATING STATION C4ERGENCY PROCEDURE S0123-VIII-16 UNITS ), 2 AND 3 REVISION 2 Pag 31 cf 6 ATTACHMENT 8.5 p
14UCLEAR REGULATORY COMISSION l
EVENT NOTIFICATION FORM Qi (FOR USE WITH ENS PHONE) h*
PART I j
HQ Duty Officer Name CobgletePartIforallincidentnotifications (4
A.
IDENTIFICATION:
Facility Caller's Name Phone Number Date/ time B.
EVENT CLASSIFICATION:
Notification of Unusual Event 50.72 Other Alert Site Area Emergency General Emergency C.
DESCRIPTION:
What Happened:
J Event Time _
Cause:
Consequences:
Actions:
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, SAR ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE $0123-VIII-16 UNITS 1, 2 AND 3 REVISION 2 Page 2 of 6 ATTACHMENT 8.5
~
NUCLEAR REGULATORY COMISSION EVENT NOTIFICATION FORM 5 f, (FOR USE WITH ENS PHONE) gj r-i-
PART I I
(Continued)
~
Current Status:
D.
NOTIFICATIONS:
(What notifications have been made by the licensee.)
STATE (S)
LICENSEE MANAGEMENT LOCAL OTHER NRC RESIDENT OTHER E.
PRESS RELEASE:
Has a press release been made or planned? (Yes/No)
APPROVED - EMERGENCY COORDINATOR O
SAN,ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16 UNITS 1, 2 AND 3 REVISION 2 Page 3 of 6 ATTACHMENT 8.5
~
A NUCLEAR REGULATORY COP 94ISSION I
g /j, EVENT NOTIFICATION FORM
\\-
{FORUSEWITHENSPHONE) p:
r PART II i:
STEAM PLANT STATUS 44 S/G Levels Equipment Failures Feedwater Source / Flow S/G Isolated Electrical Dist. Status:
Normal Offsite Power Available?
Major Busses / Loads Lost Safeguards Busses Power Source D/G Running?
Loades?
SECURITY / SAFEGUARDS:
Bomb Threat: Search Conducted?
Search Area Evacuated:
Site Evacuated:
Extortion:
Source (Phone, Letter, etc.)?
Location of Letter, Intrusion:
Insider?
Outsider?
Furthest Point of intrusion Fire Arms related?
Stolen / Missing Material Rx Oper/ Demonstration:
Size of group Demands Violence?
Fire Arms Related?
Sabotage / Vandalism:
Radiological?
Arson Involved Stolen / Missing Msterial? _
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16
- UNITS 1, 2 AND 3 REVISION 2 Page 4 cf 6 ATTACHMENT 8.5
' [(,)
~
NUCLEAR REGULATORY COMMISSION EVENT NOTIFICATION FORM gj (FOR USE WITH ENS PHONE) g 5 I, PART II i ',
(Continued)
TRANSPORTATION:
Mode (Road / Rail / Air /etc.)
Carrier Exact Location Type of Material (HEU/ Spent fuel / Cat III/Uther)
Description of Shipment Labels:
(On material package)
(On Vehicle)
Spillage Surveys Physical damage to container?
p Fire / Smoke Missing Material MATERIALS AND FUEL FACILITIES:
Kind of Licensee (processor, radiographer, medical, etc.)
Isotopes involved Solid / Liquified?
Sealed / Loose?
FURTHER LICENSEE ACTIONS:
Taken Planned Property Damage RADI0 ACTIVITY RELEASED (or Increased Released)?
Liquid / Gas?
Location / Source of Release Elevation Release Rate Duration Stopped?
Release Monitored:
O Amount of Release
% Technical Specifications __
m-
. SAN'ONOFREN0CLEARGENERATINGSTATION EMERGENCY PROCEDURE S0123-VIII-16
~
REVISION 2 Page 5 of 6 a
UNITS 1,'2 AND 3 ATTACHMENT 8.5 NUCLEAR REGULATORY COMISSION d
EVENT NOTIFICATION FORM g j?
{FOR USE WITH ENS P M )
b"e r-PART II L,
!{
(Continued)
~
4 Increased Radiation Levels in Plant:
Location (s):
Radiation Level (s)
Areas Evacuated Maximum offsite dose rates Integrated dose Location
,Meterology Wind Direction from Wind Speed (Meter /sec or miles /hr)
AT
(*C or *F) Sigma Theta n(,,
Temperature
(*C or *F)
Stability Class A B C D E F Raining (Yes/No)
PROJECTED DOSES:
DOSE RATES INTEGRATED DOSE 2 miles 5 miles 10 miles l
l SECTORS Contamination (Surface):
Inplant Onsite Offsite __
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16 UNITS 1, 2 AND 3 REVISION 2 Page 6 of 6 ATTACHMENT 8.5 NUCLEAR REGULATORY COMISSION EVENT NOTIFICATION FORM g j,*
(FOR USE WITH ENS PHONE) g'-*4 PART II (Continued) i r.
t; REAQj0ROPERATIONS:
Reactor Systems Status Power Level Pressure Temp.
Flow (Pumps on)
ECCS Operating / Operable Cooling Mode _
Containment Status l
Containment Isolated Containment Temp.
Containment Press Containment Temp.
R/hr.
Reactivity Controls Control Rods Inserted Status of Emer. Boration System APPROVED:
EMERGENCY COORDINATOR 0268F/jhm
SAN CN0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16 REVISION 2 Page 1 cf 1 i
' UNITS 1, 2 AND 3 ATTACHMENT 8.6 g
~
DE-ESCALATION NOTIFICATION FORM b
THIS NOTIFICATION SHOULD BEGIN WITHIN 15 MINUTES AFTER DE-ESCALATIO h
~
OF AN EMERGENCY EVENT.
Dati:'
Time:
Emergency Event No.
F_
(Sequential Number for Each Year, See 6.5)
"ThiYistheSanOnofreNuclearGeneratingStation.EmergencyCondition,have g
been de-escalated a (an):
(Circle the applicable Classification Below)
E UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMFRGENCY
{
I Record the following information on your De-Escalation
[
At Unit (s)
Notification Form.
f MESSAGE I.D. NUMBER:
listed in the Manual of Emergency Events describes this
{
1.
Event No.
event.
2.
There been a release of radioactivity.
j HAS/HAS NOT.
i i
3.
A release
__BEEN STOPPED /NEVER OCCURRED HAS/HAS NOT d4.
The release is to the i
ATMOSPHERE /0CEAN/NOT APPLICABLE 5.
There a potential for (ADDITIONAL) release.
IS/IS NOT (cross out if N/A) a need for protective action beyond the Site Boundary.
6.
There.._
IS/IS NOT Affected Sectors:
_ ]//
/
/
/
/
/
Recomnended Protective Action:
7.
Additional information:
- to verify receipt of this If a Bell Phoae was used, Call _ BELL # -
8.
Notification.
9.
Ensure your teletypes is in PRINT LINE mode. Call _
to verify IAT or BELL #
hard copy receipt.
10.
San Clemente please read back this message. Other Stations check for accuracy.
APPROVED:
DRAFTED:
EMERGENCY COdRDINATOR SHTFT COMMUNICATOR /
EMERGENCY PLANNING COORDINATOR
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S0123-VIII-16
' UNITS 1, 2 AND 3 REVISION 2 Page 1 of 1 ATTACHMENT 8.7 CLOSE-OUT NOTIFICATION FORM THIS NOTIFICATION SHOULD BEGIN WITHIN 15 MINUTES AFTER.CLOSE-OUT OF AN EMERGENCY EVENT.
Jime:
Emergency Event No.
t.
(Sequential Number for Each Year, See 6.5) si g te:
"Thjs is the San Onofre Nuclear Generating Station. The (Cross out the non-applicable C!assification Below)
UNUSUAL EVENT ALERT SITE EMERGENCY GENERAL EMERGENCY which has occurred at Unit (s) has been close-out. Record the following information on your Close-Out Notification Form.
MESSAGE I.D. NUMBER:
1.
Event No.
listed in the Manual of Emergency Events describes this
'N; event.
2.
There is no need for protective action beyond the Site Boundary.
3.
Additional information:
t KN 4.
If a Bell Phone was used, Call to verify receipt of this Notification.
BELL #
l 5.
Ensure your teletypes is in PRINT LINE mode.
Call to verify hard copy receipt.
IAT or BELL #
6.
San Clemente please read back this message. Other Stations check for accuracy.
l DRAFTED:
APPROVED:
SHIFT COMMUNICATOR /
EMERGENCY COORDifdT R EMERGENCY PLANNING COORDINATOR l
m =-. - -
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SAN.ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE $023-VIII-11.1
[
o UNITS 2 AND 3
. COMPLETE REVISION
. REVISION 2 PAGE 1 EFFECTIVE DATE OCT-4.jggj i
Y C,pSSIFICATION OF EMERGENCIES h;
te TABLE OF CONTENTS SECTION PAGE
~
1.0 OBJECTIVE 2
2.0 REFERENCES
~~
2 3.0 PREREQUISITES
?.
4.0 PRECAUTIONS 2
5.0 CHECK-OFF LIST 2
5 6.0 PROCEDURE 2
7.0 RECORDS 3
8.0 ATTACHkENTS 3
PAGES CHANGED WITH THIS REVISION: ALL O
PREPARED BY:
9-/L-PL TROCEDURE WHITER DATE Af? ROVED BY:
/ j
_7-/ /-f2-H. B. RAY
'DATE STATION MA 2ER
" ~
.s DB:0261F:daj RECEIVED OCT 4 1982 CDM F.iTE o
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 2
/
CLASSIFICATION OF EMERGENCIES
~
v1.0 OBJECTIVE g;
1.1 This procedure is used in conjuction with S0123-VIII-11 to recognize
,and classify the four emergency classifications: Unusual Event, Alert, Site Emergency and General Emergency.
2.0 REFERENCES
2.1 SONGS - 1, 2 & 3 Emergency Plan.
2.2 SONGS - 2 & 3 Operating Procedures 2.3 Title 10, code of Federal Regulations Part 50, Appendix E.
2.4 NUREG-0654/ FEMA-REP-1, " Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants".
2.5 SONGS - 2&3 Tech Specs.
3.0 PREREQUISITES 3.1 An off-normal event has occurred and has been verified by using redundant instrument channels, comparison to other related plant parameters, physical observations, and field measurements, as t
applicable.
4.0 PRECAUTIONS 4.1 Continued surveillance and assessment of plant conditions is necessary to ensure that the emergency classification is appropriately revised as conditions change, or as more definitive information is obtained.
5.0 CHECK-OFF LIST 5.1 None.
6.0 PROCEDURE 1
6.1 The use of this procedure is in conjuction with S0123-VIII-11
" RECOGNITION AND CLASSIFICATION OF EMERGENCIES", as a reference document to verify Emergency Action Levels (EAL'S).
1 n
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNIT,5 2 AND 3 REVISION 2 PAGE 3
'.0 RECORDS
~
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y 7.1 None 4
fra:
8.0 ATTACHMENTS 8.1.1, " Classification Matrix."
8.2.2, " Loss of RCS Inventory Instruments."
8.3.3, "Jnits 2&3 Safety Systems."
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SAN GNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1
- UNITS 2 AND 3 REVISION 2 PAGE 1 0F 38 ATTACHl4ENT 8.1
~
UNCONTROLLED RELEASE OF RADIOACTIVITY p:j i
UNUSUAL EVENT TAS A1 1.
For Moaes 1-6:
Any of the below listed process and effluent monitors meeting the following conditions:
a)
A valid Hi A' arm AND b)
Radiological Effluent Technical Specifications tabulated below l
are exceeded AND c)
The release path is not isolated TECHNICAL MONITOR DESCRIPTION SPECIFICATION 2/3 RT-7814B Waste Gas Header Monitor 6E3 CPM OR 2(3) RT-7804-1C Contai5 ent Airborne Full purge) 1.7E4 CPM Monitor (Mini puvae) 3.4E5 CPM OR 2/3 RT-7808C Plant Vint Stack Airborne O
Monitor; (2 Fans) 5.6E3 CPM (1 Fan) 1E4 CPM OR 2(3) RT-7870-1 Condensir Air Ejector Wide Range Monitor; IE3 uC1/sec OR 2(3) RT-7865 ContaiMent Purge or Plant Vent Stack Wide Range Monitor; 5.6E3 uC1/sec O
SAN,0N0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 2 0F 38 ATTACHMENT 8.1
]
UNCONTROLLED RELEASE OF RADI0 ACTIVITY kN f UNUSUAL EVENT i'
TAB A1
. 2. For Modes 1-6:
Any of the below listed process and effluent monitors meeting the following conditions:
a)
A valid Hi Alarm AND b)
Radiological effluent technical specifications tabulated below are exceeded AND c)
The release path is not isolated.
TECHNICAL MONITOR DESCRIPTION SPECIFICATION 2(3) RT-7817 Neutralization Sump Discharge Monitor; 1 Circ Pump SE4 CPM 2 Circ Pumps IES CPM OR 2/3 RT-7813 Radwaste Discharge Line Monitor; 1 Circ Pump 3E4 CPM 2 Circ Pumps 7E4 CPM 2(3) RT-7821 Turbine Plant Area Pump Monitor.
1 Circ Pump 4E5 CPM 2 Circ Pumps 8E5 CPM p
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1
- UNITS 2 AND 3 REVISION 2 PAGE 3 0F 38 ATTACHMENT 8.1 UNCONTROLLED RELEASE OF RADI0 ACTIVITY ALERT
$4 TAB A2 EAL 1.
For Modes 1-6:
~
Any of the below listed process and effluent monitors meeting the following cor.ditions:
a)
A valid Hi Alarm setpoint is exceeded AND b)
A valid reading exceeding 10 times the Radiological Effluent Technical Specifications as tabulated below AND c) tha release path is not isolated 10 Times TECHNICAL MONITOR DESCRIPTION SPECIFICATION 2/3 RT-7814B Waste Gas Header Monitor; 6E4 CPM OR 2(3) RT-7804-ic ContaiMent Airborne Monitor; (Full Purge) 1.7ES CPM (Mini Purge) 3.4E6. CPM OR 2/3 RT-7808 Plant Vent Stack Airborne O'
Monitor; (2 Fans) 5.6E3 CPM (1 Fan) 1E4 CPM OR 2(3) RT-7870-1 CondenHr Air Ejector Wide Range Monitor; IE4 uC1/sec OR 2(3) RT-7865-1 ContaiEent Purge or Plant Vent Stack Wide Range Monitor; 5.6E4 uCi/sec l
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I SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-11.1
~
. UNIT $ 2 AND 3 REVISION 2 PAGE 4 0F 38 ATTACHMENT 8.1
,i
~
UNCONTROLLED RELEASE OF RADI0 ACTIVITY r,
p.j ALERT TAB A2 EAL 2.
For Mo* des 1-6:
Any of the below listed process and effluent monitors meeting the following conditions:
I a)
A valid Hi Alarm.
AND b)
A valid reading exceeding 10 times the radiological effluent technical specifications AND c)
The release path is not isolated.
10 Times TECHNICAL MONITOR DESCRIPTION SPECIFICATION 2(3) RT-7817 Neutralization Sump Discharge Monitor; 1 Circ Pump SES CPM 2 Circ Pumps IE6 CPM OR 2/3 RT-7813 Radwaste Discharge Line Monitor; 1 Circ Pump 3E5 CPM 2 Circ Pumps 7E5 CPM 2(3) RT-7821 Turbin Plant Area Sump Monitor.
1 Circ Pump 4E6 CPM 2 Circ Pumps 8E6 CPM t
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SAN.ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE 5023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 5 0F 38 ATTACHMENT 8.1
~
T UNCONTROLLED RELEASE OF RADI0 ACTIVITY
{
glj' ALERT TAB A2 EAL j
3.
For Mo~ des 1-6:
A valid unexpected area radiation monitor alarm as listed below, AND A valid unexpected area radiation monitor reading as listed below, or if full scale, verified field survey readings at the monitor location as listed below:
2(3) RT-7842 Radwaste General Area
>2.5 R/hr; OR 2(3) RT-7854 Local SEple Lab
>2.5 R/hr; OR 2(3) RT-7844 High Raii Storage Area
>10. R/hr; OR 2(3) RT-7841 Waste GH Surge Tank Area
>2.5 R/hr; OR 2(3) RT-7847 Safety Q uipment General Area >2.5 R/hr; OR 2(3) RT-7850 Spent FH1 Loading Area
>2.5 R/hr; OR 2(3) RT-7852 RadiochE. Lab
>2.5 R/hr; O.R
(/
2(3) RT-7851 Control Room
>250mR/hr; OR 2(3) RT-7843 Radwaste Generrl Area
>2.5 R/hr; OR 2(3) RT-7884 Post-AcH dent Sample Lab >
>2 5 R/hr; OR 2(3) RT-7853 Hot Maciiine Shop
>2.5 R/hr; l
4.
For Modes 1-6:
Any unanticipated plant area iodine or particulate airborne l
concentration greater than 1000 times MPC as determined by radiological survey (see 10 CFR 20 Appendix B, table II.)
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SAN CN0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 6 0F 38 ATTACHMENT 8.1
)
- ^
UNCONTROLLED RELEASE OF RADIOACTIVITY ALEy g":#
s TAB A2 EAL 5.
For Mo8es 1-6:
Reported spent fuel handling accident concurrent with the applicable alarm of the following radiation monitors:
2(3) RT-7804-1 Containment Airborne Monitor; AND 2(3) RT-7822-1 Fuel HandTing Area Vent Airborne Monitor; AND 2(3) RT-7822-2 Fuel Handling Area Vent Airborne Monitor; Ch 2(3) RT-7856-1 Containdht Personnel Lock Area Morettor; AND 2(3) RT-7857-2 Containment General Area Monitor; 6.
For Modes 1-4:
A steam line breat concurrent with a primary to secondary leak that exceeds 10 gpm as. determined by:
(a)
Uncontrolled transient in steam generator pressure (s)
PI-1012A1, PI-1012A2, PI-1012A3, PI-1012A4, j
PI-1023A1, PI-1023A2, PI-1023A3, PI-1023A4.
(
AND r
l (b)
High Alarm on an/ one of the following Radiation Monitors:
l 2(3) RT-7875A1, 2(3) RT-7874A1, 2(3) RT-7875B1, 2(3) RT-7874B1, Main S uca Line Honitors.
AND i
(c)
A valid main condenser air ejector gas monitor 2(3) RT-7870-1 l
greater than low range alarm (2E-6 uCi/cc Xe-133)
CAUTION The main condenser air ejector gas monitor alarm criteria will only be applicable if the alarm is
=
received AND steam flow has not been terminated to the turbine generator or main condenser.
7.
For Modes 1-6:
An unmonitored gaseous release which is suspected to have exceeded 10 times MPC limits as determined by field sampling and radioanalysis.
8.
For Modes 1-6:
An unmonitored liquid release which is suspe~cted to have exceeded 10 times MPC limits as determined by field sampling and radioanalysis.
9.
For Modes 1-6:
Radiological Effluent release for which the doses projected at the site boundary are for the expected duration of the release are between 2-50 mrem whole body OR
(
between 50-500 mrem thyroid. --
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1
-UNITS 2 AND 3 REVISION 2 PAGE 7 0F 38 ATTACHMENT 8.1 j
UNCONTROLLED RELEASE OF RADIOACTIVITY
{*!
SITE EMERGENCY TAB A3 EAL 1.
For Mo' des 1-6:
2(3) RT-7865-1 Containment Purge or Plant Vent Stack Wide Range Monitor shows equivalent Xe-133 release rate greater than 1.1 Ci/sec. for 0.5 hr OR greater thE 10.6 Ci/sec for 2 minutes.
2.
For Modes 1-6:
Source Term determination shows equivalent I-131 release rate greater than 1.0 E-4 Ci/sec for 0.5 hr OR 1.0 E-3 C17sec for 2 minutes.
3.
For Modes 1-6:
Radiological monitoring teams measure whole body dose rates at the exclusion area boundary greater than 50 mrem /hr for 0.5 hr OR greater thH 500 mrem /hr for 2 minutes.
4.
For Modes 1-6:
Radiological monitoring teams measure thyroid dose rates (equivalent O
I-131 concentrations) at the exclusion area boundary greater than 250 mrem /hr for 0.5 hr (7.0 E-7 uCi/cc)
OR 2.5 Rem /hr for 2 minutes (7.0 E-6 uCi/cc).
5.
For Modes 1-6:
Reported major spent fuel damage concurrent with a high alarm on process monitor RT-202 l
AND i
greater than 10 times the alarm setpoint indication on any of the following radiation monitors:
2(3) RT-7804-1 Containment Airborne Monitor; AND 2(3) RT-7822-1 Fuel Handling Area Vent Airborne Monitor; AND 2(3) RT-7822-2 Fuel Handling Area Vent Airborne Monitor; OR 2(3) RT-7845 Containment Pere nnel Lock Area Monitor; AND 2(3) RT-7848 Containment General Area Monitor:
SAN.0N0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 8 0F 38 ATTACHMENT 8.1 UNCONTROLLED RELEASE OF RADI0 ACTIVITY
{
SITE EMERGENCY TAB A3 EAL 6.
For Mo8es 1-6:
Uncontrolled decrease in spent fuel pool water level to below the level of irradiated fuel as determined by 61C3, " Spent Fuel Pool Hi/ Low Level" alarm concurrent with full scale indication on 2(3) RT-7850, Spent Fuel Loading Area Monitor.
7.
For Modes 1-4:
Steam line break concurrent with primary to secondary leakage greater than 50 gpm tith indication of failed fuel as determined by:
(a)
Uncontrolled transients in steam generator pressure (s)
PI-1012A1, PI-1012A2, PI-1012A3, PI-1012A4, PI-2013A1, PI-1023A2, PI-1023A3, PI-1023A4.
AND (b)
A valid condenser air ejector gas monitor [2(3)-RT-7818] High Range alarm (8.2 E-2 uCi/cc Xe-133)
AND-(c)
RCS dose equivalent I-131 greater than 1.0 uCi/gm as determined by the most recent chemical analysis results.
CAUTION The main condenser air ejector gas monitor alarm will only be applicable if the alarm is received AND the x
steam flow has not been terminated to the turbine-generator or main condenser.
8.
For Modes 1-6:
Radiological Effluent release which corresponds to doses projected at the site Boundary for the expected duration of the release for greater than 50 mrem whole body but less than 500 mrem whole body l
0_R greater than 500 mrem thyroid but less than 5000 mrem thyroid at the site boundary.
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SAN.DN0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 9 0F 38 ATTACHMENT 8.1 9
UNCONTROLLED RELEASE OF RADI0 ACTIVITY g j, A
GENERAL EMERGENCY TAB A4 EAL 1.'
For Modes 1-6:
Dose projections or radiation levels measured in the environs indicate levels corresponding to or exceeding 0.5 Rem /hr whole body at the Exclusion Area Boundary.
2.
For Modes 1-6:
Dose projections or radiation levels measured in the environs indicate levels corresponding to or exceeding 5 Rem /hr thyroid at the Exclusion Area Boundary.
3.
For Modes 1-6:
Any Radiological effluent release which corresponds to doses projected at the Site Boundary for the expected duration of the release are greater than 500 mrem whole body OR 5000 mrem thyroid at the site boundary under actual meteorological conditions.
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SAN,0NOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1
. UNITS 2 AND 3 REVISION 2 PAGE 10 0F 38 ATTACHMENT 8.1 LOSS OF RCS INVENTORY
~
UNUSUAL EVENT TAB B1 b'
1.
For Modes 1, 2, 3 and 4 only:
The Reictor Coolant System (RCS) leakage is greater than any one of the below listed Technical Specifications limits, but less than 50 gpm AND the leakage cannot be reduced to below the limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (a)
I gpm unidentified leakage.
OR (b)
I gpm total F imary-to-secondary leakage through all steam generators and 720 gallons per day through any one steam generator.
OR (c) 10 gpm identified leakage from the RCS.
OR (d)
I gpm leakage at the RCS pressure of 2235 + 20 psig from any RCS pressure isolation valve specified in Technical Specifications Table 3.4-1.
NOTE:
See Attachment 8.2 for instrumentation that aids in determining RCS leakage.
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNIIS2AND3 REVISION 2 PAGE 11 0F 38 ATTACHMENT 8.1
~
LOSS OF RCS INVENTORY y.h ALERT i
TAB B2 1.
For Modes 1, 2, 3 and 4 Only:
The Re* actor Coolant System (RCS) leakage is greater than 50 gpm, but less than the maximum available makeup capacity of the charging system NOTE:
See Attachment 8.2 for instrumentation that aids in determining RCS leakage.
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SAN ONOFP.E NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 12 0F 38 ATTACHMENT 8.1 LOSS OF RCS INVENTORY
}U' SITE EMERGENCY h4 TAB B3 EAL 1.
For Modes 1-4:
The Reactor Coolant System (RCS) leakage is greater than the available charging pump capacity (Loss of Coolant Accident-LOCA)
If Emergency Operating Instruction S023-3-5.6, " Loss of Coolant Accident" has been activated, this Emergency Action Level (EAL) is valid.
NOTE:
See Attachment 8.2 for instrumentation that aids in determining RCS leakage.
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SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 13 0F 38 ATTACHMENT 8.1 LOSS OF RCS INVENTORY gi GENERAL EMERGENCY TAB B4 EAL 1.
For Modes 1-4:
Any loss of Coolant Accident (LOCA) as covered in Emergency Operating Instruction S023-3-5.6, " Loss of Coolant Accident",
AND the loss of Containment integrity as defined in Emergency Operating Instruction S023-3.5.11, " Loss of Containmenc Integrity",
AND the subsequent failure of emergency heat removal systems such that significant fuel damage is probable.
NOTE:
a.
Significant fuel damage can be determined by:
Sample analysis of the RCS or Letdown Monitor High alarm, both indicating the release of the Gap Activity to the primary coolant O_R High core temperatures indir sted on the core thermocouples (>1200 F) 0.R inadequate subcooling margin (0 SUBC00 LED) m OR the core uncovered for a l ustained period of time.
b.
The loss of containment integrity can be determined by:
Status indication on containment penetrations OR Rapidly increasing containment pressure with a failure of the containment spray system OR A steam line break downsU eam of the MSIV's with the MSIV's indicating open w
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE $023-VIII-11.1 i
UNITS 2 AND 3 REVISION 2 PAGE 14 0F 38 ATTACHMENT 8.1 DNB/ DEGRADED CORE SEQUENCE
~
UNUSUAL EVENT b'
TAB C1 EAL 1.
For Modes 1, 2, 3 and 4 Only:
Initiation of the High Pressure Safety Injection (HPSI) System, either by a valid safety circuit trip or a manual initiation of HPSI as a corrective action to abnormal plant parameter indications AND Flow indication of greater than Sgpm on 2(3)FI-0311 or 2(3)FI-0321 or 2(3)FI-0331 or 2(3)FI-3411.
2.
For Modes 1, 2, 3 and 4 only:
Rapid secondary depressurization due to:
A steam itne break OR Secondary sa'fety or relief valve failure OR Cold water 7 njection into the secondary side of the steam generator as covered in Emergency Operating Instruction S023-3-5.9, " Steam Line Rupture", and determined by uncontrolled transients in steam generator pressure (s) listed below, O
PI-1012A1, PI-1012A2, PI-1012A3, PI-1012A4, PI-1023A1, PI-1023A2, PI-1023A3, PI-1023A4.
3.
For Modes as shown below:
A plant shutdown is required due to exceeding a Technical Specifications Safety Limit:
(a)
Whenever the DNBR of the reactor has decreased to less than 1.20 as indicated by the Core Operating Limit Supervisory System (COLSS). Mode 1 only OR (b)
Whenever the peak linear heat rate (adjusted for fuel rod dynamics) of the fuel has exceeded 21.0 kw/ft, as indicated by Core Dperating Limit Supervisory System (COLSS). Mode 1 only OR (c)
Whenever the Reactor CooTant System Pressure has exceeded 2750 psia.
( Modes 1-5.)
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SAN ON0FRE N0 CLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1
- UNITS 2 AND 3 REVISION 2 PAGE 15 0F 38 ATTACHMENT 8.1 DNB/ DEGRADED CORE SEQUENCE i
%. h.
UNUSUAL EVENT ys, EAL 4.
For Modes 1, 2, 3 and 4 only:
The Reactor Coolant System (RCS) is less than 10'F subcooled as indicated by: 2(3)TI-0911-1, 2(3)TI-0921-2, Subcooling Margin Monitor
<10'F 5.
For Modes 1, 2, and 3:
A plant shutdown has been ordered as required by:
Technical Specification 3/A.4.7, " Specific Activity of the Reactor Coolant System" OR Technical Specificaton 3.7.1.4- " Activity of Plant Systems".
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 16 0F 38 ATTACHMENT 8.1 DNB/ DEGRADED CORE SEQUENCE
)
4 M.
ALERT g;
TAB C2 EAL 1.
For Modes 1, 2 and 3 only:
Severe loss of fuel cladding indicated on Process Radiation Monitor RE-202 (Alarm 58A33)
AND Verified by radiochemical analysis indicating an increase in failed fuel greater than 1.67E-5 Curtes/cc I-131 dose Equivalent in 30 minutes OR total failed fuel greater than 8.3 E-5 Curies /cc I-131 dose Equivalent.
2.
For Modes 1, 2 and 3 only:
RCS chemistry sample results indicate the dose equivalent I-131 greater than 300 uCi/cc, AND The sample result is not due to iodine spiking phenomenon.
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SAN QNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-11.1
. UNITS 2 AND 3 REVISION 2 PAGE 17 0F 38 ATTACPMENT 8.1 DNB/ DEGRADED CORE SEQUENCE d
_ SITE EMERGENCY TAB C3 4
EAL 1.
For MoBes 1, 2 and 3 only:
A " degraded core with the possible loss of coolable geometry" condition exists based on consideration of the following:
(a)
Inadequate Core Cooling as determined by the results of 5023-3-2.30, " Determination of Adequate Core Cooling".
(b)
Abnormally high Reactor coolant activity sample results (greater than 300 uCi/gm equivalent I-131).
(c)
Containment radioactivity levels indicated by:
2(3)RT-7820-1 (7820-2) High Range in Containment Monitors.
OR 2
2(3)RT-7858-1 (7859 2) (7860-3) Emergency Radiation Monitors.
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 t) NITS 2 ANO 3 REVISION 2 PAGE 18 0F 38 ATTACHMENT 8.1 N
DNB/ DEGRADED CORE SEQUENCE GENERAL EMERGENCY TAB C4 1.
For Modes 1-3:
Any combination of Emergency Core Cooling Systen (ECCS) failures such that:
Significant fuel damage is imminent or in progress AND Containment integrity is lost AND The probable loss of the reactor coolant boundary is imminent.
NOTE:
(a)
Significant fuel damge can be determined by:
Sample analysis of the RCS or letdown monitor High Alarm, both indicating the release of the Gap activity to the primary coolant OR High core temperatures iiidicated on the core thermocouples
(>1200 F)
QR Inadequate subcooling margin (0* subcooled)
OR The core is uncovered foT a sustainal period of time.
(b)
The loss of containment integrity can be determined by:
Status indication on containment penetrations OR Rapidly increasing contaEment pressure with a failure of the containment spray, OR A sudden drop in containiiIe'nt pressure that can not be explained by the initiation of containment spray OR A steam line break downstream of the MSIV's with the MSIV's indicating open, OR A rapid decrease in containment pressure.
__.N M
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SAN,ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 19 0F 38 ATTACHMENT 8.1 LOSS OF SAFETY FUNCTIONS 5l p.tj-UNUSUAL EVENT TAB D1 EAL 1.
For Modes 1, 2, 3 and 4 only:
Loss of all offsite power (Diesel Generators are operable) as defined by Emergency Operating Instructions S023-3-5.4, " Complete loss of Offsite Electrical Power" OR S023-3-5.4.1, " Complete Loss of Offsite Electrical Power to a Unit".
2.
For Modes 1, 2, 3 and 4 only:
Loss of operability of both emergency diesel generators (off-site electrical power available)
AND At least one of the inoperable diesel generators has not been restored to operable status within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
3.
For Modes 1 and 2 only:
A Technical Specification required shutdown due to exceeding a Limiting Condition for Operation as specified in Technical Specifications 3/4.5,
" Emergency Core Cooling Systems".
NOTE:
This Emergency Action Level is valid in the modes specified in Technical Specifications 3/4.5.
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1
. UNITS 2 AND 3 REVISION 2 PAGE 20 0F 38 ATTACHMENT 8.1 LOSS OF SAFETY FUNCTIONS
~
- /e UNUSUAL EVENT p*
TAB D1 EAL 4.
For Modes 1 and 2 only:
A Technical Specification required shutdown due to exceeding a Limiting Condition for operation as specified in Technical Specifications 3/4.6,
" Containment Systems".
5.
For Modes 1, 2, 3 and 4:
All Control Room annunciators are lost for greater than 5 minutes AND The plant is in a stable condition.
NOTE: See EAL D25 for Transient Conditions.
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SAN ONOFRE NUOLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 DNITS 2 AND 3 REVISION 2 PAGE 210F 38 ATTACHMENT 8.1 i
~
LOSS OF SAFETY FUNCTIONS ALERT h4 TAB D2 EAL 1.
For Modes 1, 2, 3 and 4:
The loss of all offsite AC electrical power as covered by Emergency Operating Instructions S023-3-5.4, "Corplete Loss of Offsite Electrical Power" or S023-3.5.4.1, " Complete loss of Offsite Electrical Power to a Unit" AND The loss of operability of both emergency diesel generators AND The busses remain deenergized for greater than 5 minutes.
NOTE: See EAL D31 for loss greater than 15 minutes.
2.
For Modes 1, 2, 3 and 4:
The loss of all units vital DC electrical power for greater than 5 minutes, as determined by:
63C31 125VDC Bus D1 Trouble Alarm; AND 63C52 125VDC Bus D2 Trouble Alarm; AND 63C55 125VDC Bus D3 Trouble Alarm; AND 63C58 125VDC Bus D4 Trouble Alarm.
NOTE: See EAL D32 for loss greater than 15 minutes.
3.
For Modes 1, 2, 3 and 4:
The ability to achieve or maintain cold shutdown has been lost based on the following:
Shutdown Cooling Capability is lost; AND Natural Circulation Cooldown capability is lost AND Safety Injection Capability is lost.
l O
m
SAN ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 22 0F 38 ATTACHMENT 8.1 LOSS OF SAFETY FUNCTIONS
}
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I f'-
ALERT TAB D2 h4
[
i EAL 4.
For Modes 1 and 2:
The Reactor remains critical after the receipt of an automatic Reactor Protection trip system signal or a manual Reactor Trip signal.
In either case, the plant is in a stable condition without an uncontrolled transient involved.
5.
For Modes 1 and 2:
All Control Room annunciators are lost for greater than 5 minutes AND The plant is in an unstable transient condition (an uncontrolled transient is involved).
6.
For Modes 1 and 2 only:
The evacuation of the Control Room is required and Control of the Shutdown systems is established from local stations.
NOTE:
See EAL D35 if control of the Shutdown system is not under control in 15 minutes.
O O
. -,c.,
SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-11.1
. UNIT'S 2 AND 3 REVISION 2 PAGE 23 0F 38
~
ATTACHMENT 8.1 LOSS OF SAFETY FUNCTIONS
).
y
\\
SITE EMERGENCY y,
TAB D3 EAL 1.
For Modes 1, 2, and 3 only:
The loss of all offsite AC electrical power as covered by Emergency Operating Instructions SD23-3-5.4, " Complete Loss of Offsite Electrical Power" or 5023-3.5.4.1, " Complete loss of Offsite Electrical Power to a Unit" AND The loss of operability of both emergency diesel generators AND The busses remain deenergeized for greater than 15 minutes.
2.
For Modes 1, 2, and 3 only:
The loss of all units vital DC electrical power for greater than 15 minutes, as determined by:
63C31 125VDC Bus 01 Trouble Alarm; AND 63C52 125VDC Bus D2 Trouble Alarm; AND 63C55 125VDC Bus 03 Trcuble Alarm; O
AND 63C58 125VDC Bus D4 Trouble Alarm.
3.
For Modes 1, 2, and 3 only:
The ability to achieve or maintain hot shutdown has been lost based on the following:
Reactor Trip Capability lost (Modes 1 and 2 only);
AND t
Emergency Boration Capability lost; AND l
Steam Dump Capability is lost; I
AND l
Feedwater Capability lost; l
4.
For Modes 1 and 2:
l The Reactor remains critical after receipt of a Reactor Protection Trip Signal or a manual Reactor Trip signal and the Plant is in an l
uncontrolled transient.
l 5.
For Modes 1-4:
The Control Room has been evacuated l
AND l
Control of shutdown systems has not been established from the local l
stations within 15 minutes.
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g
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= %.. w % -
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SAN,0NOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 i
UNITS 2 AND 3 REVISION 2 PAGE 24 0F 38 ATTACHMENT 8.1 LOSS OF SAFEY FUNCTIONS
~
46' GENERAL EMERGENCY r
TAB D4 EAL m
1.
For Mo8es 1-3:
Any combination of Loss of Safety Functions such that:
Significant fuel damage is imminent or in progress AND The loss of the reactor Coolant boundary has occurred AND The loss of the containment integrity is probable.
NOTE:
(a)
Significant fuel damage can be determined by:
Sample analysis of the RCS or Letdown Monitor High Alarm, both indicating the release of the Gap Activity to the primary coolant, OR High core temperatures indicated on the core thermocouples (>1200*F)
OR Inadequate subcooling margin (0* Subcooled)
~OR The core uncovered for a iignificant period of time.
i (b)
The Loss of containment integrity can be determined by status indication on containment penetrations OR Rapidly increasing containment pressure with a failure of the containment spray system, OR A stream line break downitream of the MSIV's with the MSIV's indicating open, OR A rapid decrease in containment pressure
=
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- n... 1..m - - - u - - -
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SAN.ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 25 0F 38 ATTACHMENT 8.1 CATASTROPHES
}
UNUSUAL EVENT M*
g4 TAB El EAL 1.
For Mo*es 1-6:
d Fire within the Protected Area which is not brought under control within 10 minutes after verification OR Any fire within the Owner Controlled Area which requires offsite assistance.
2.
For Modes 1, 2, 3 and 4:
Valid receipt of 61C21 " Seismic Recording System Activiation" alarm.
OR Notification by Unit I that Seismic Instrumentation has been activated.
3.
For Modes 1, 2, 3 and 4:
A tsunami that breaches the sea wall or any in plant floodir.g condition which causes damage that precludes the operation of any systems listed in Attachment 8.3.
4.
For Modes 1, 2, 3 and 4:
Any tornado striking site which causes damage that precludes the operation of any systems listed in Attachment 8.3.
5.
For Modes 1, 2, 3 and 4:
Site comes under hurricane force winds (i.e., sustained winds in excess of 74 mph) which causes damage that precludes the operation of any systems listed in Attachment 8.3.
6.
For Modes 1, 2, 3 and 4:
Aircraft crash onsite which causes damage that precludes the operation of any systems listed in Attachment 8.3.
7.
For Modes 1, 2, 3 and 4:
Train derailment which causes damage that precludes the operation of any systems listed in Attachment 8.3.
8.
For Modes 1, 2, 3 and 4:
An onsite explosion which causes damage that precludes the operation of any systems listed in Attachment 8.3 9.
For Modes 1, 2, 3 and 4:
Any flammable gas release which if ignited would damage any of the systems listed in Attachment 8.3.
OR Any gas release whTch prevents required access for safe operation of any system listed in Attachment 8.3.
1 I
May.m ee. s
--y m= ~ mm ~.,
- v. ~ **. w * -
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SAN DNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 26 0F 38 ATTACHMENT 8.1 CATASTROPHES
~
p UNUSUAL EVENT TAB E1 EAL 10.
For Modes I and 2:
A failure of turbine rotating equipment causing rapid plant shutdown as determined by:
a.
High vibration turbine trip, AND b.
Rapid loss of condenser vacuum; AND c.
Verified conductivity alarms.
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SAM ON0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 27 0F 38 ATTACHMENT 8.1 CATASTROPHES
{
% t-ALERT p:~
TAB E2 EAL 1.
For Modes 1-6:
A fire which damages equipment such that the capability to achieve or 1
maintain cold shutdown is lost.*
2.
For Modes 1-6:
An earthquake recording greater than.33 g. ground acceleration, OR
~
Valid receipt of 61022 " Operating Basis Earthquake Acceleration" alarm.
3.
For Mades 1-5:
A Tsunami or a hurricane surge that breeches the seawall or any other flooding that damages equipment such that the capability to achieve or maintain cold shutdown is lost.*
4.
For Modes 1-5:
Any tornado that damages equipment such that the capability to achieve or maintain cold shutdown is lost.*
5.
For Modes 1-5:
l Any sustained hurricane force winds (greater than 74 mph, but less than 100 mph) that damages equipment such that the capability to achieve or maintain cold shutdown is lost.*
l 6.
For Modes 1-5:
Any aircraft crash or any impact that damages equipment such that the capability to achieve or maintain cold shutdown is lost
- 7.
For Modes 1-5:
Any explosion that damages equipment such that the capability to achieve or maintain cold shutdown is lost.*
8.
For Modes 1-5:
Any toxic or uncontrollable gas such that the capability to achieve or maintain cold shutdown is lost.*
- The ability to achieve or maintain cold shutdown has been lost is based on the following:
Shutdown Cooling Capability is lost; AND Natural Circulation Cooling Capability is lost; AND Safety Injection capability is lost.
0
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND'3 REVISION 2 PAGE 28 0F 38 ATTACHMENT 8.1 CATASTROPHES
}
% f' ALERT TAB E2 EAL 9.
For Modes 1 and 2:
Massive turbine rotating component failure causing casing penetration and projection of turbine blading.
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SAN.ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2,AND 3 REVISION 2 PAGE 29 0F 38 ATTACHMENT 8.1 CATASTROPHES
% !l*
SITE EMERGENCY TAB E3 EAL 1.
For Mo8es 1-4:
Fire within the plant which damages equipment such that the capability to achieve or maintain hot shutdown is lost.*
2.
For Modes 1-4:
An earthquake which damages equipment such that the capability to achieve or maintain hot shutdown is lost.*
3.
For Modes 1-4:
Any flood, tsunami or hurricane surge, which causes severe damage to equipment such that the capability to achieve or maintain hot shutdown is lost.*
4.
For Modes 1-4:
Any tornado which causes severe damage to equipment such that the capability to achieve or maintain hot shutdown is lost."
5.
For Modes 1-4:
Hurricane winds (in excess of 100 mph) which cause severe damage to equipment such that the capability to achieve or maintain hot shutdown is lost.*
6.
For Modes 1-4:
Any aircraft, missile impact or explosion which causes severe damage to equipment such that the capability to achieve or maintain hot shutdown is lost.*
7.
For Modes 1-4:
Toxic or flammable gases that have entered the vital areas such that the Shift Supervisor has order a Plant evacuation.
- The ability to achieve or maintain hot shutdown has been lost is based on the following:
Reactor Trip Capability is lost (Modes 1 and 2 only);
AND Emergency Boration Capability is lost; AND Steam Dump Capability is lost; AND Feedwater Capability is lost;
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7.
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SAN QNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1
. UNITS 2 AND 3 REVISION 2 PAGE 30 0F 38 ATTACHMENT 8.1 CATASTROPHES
~
GENERAL EMERGENCY b*
TAB E4 1.
For Modes 1-3:
Any catastrophe (s) which cause:
The Loss of Containment Integrity AND The Loss of Safety Systems causing significant fuel damage AND The Loss of the RCS boundary is imminent.
NOTE:
(a)
The Loss of containment integrity can be determined by:
Status indication on containment penetrations, OR Rapidly increasing contaT6 ment pressure with a failure of the containment spray system, OR A stream line break downstream of the MSIV's with the MSIV's indicating open, OR A steam line break between the containment and the MSIV's.
OR A rapid decrease in containment pressure.
(b)
Significant fuel damage can be determined by:
Sample analysis of the RCS or Letdown Monitor High Alarm, both indicating the release of the Gap Activity to the primary coolant, OR High core temperatures iiIdicated on the core thermocouples
(>1200*F)
OR Inadequate subcooling margin (0* Subcooled)
OR The core uncovered for sTg~nificant period of time.
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S/11 ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 310F 38 ATTACHMENT 8.1 SECURITY COMPROMISE
[
% f-UNUSUAL EVENT p#
TAB F1 EAL 1.
For Modes 1-6:
Any Security threat, atterrpted entry or attempted sabotage such that security force notifies tste Operations Shift Supervisor of initiation of the Security Continge.1cy Plan.
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SAN,ONOFRE, NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1
. UNITS 2 AND 3 REVISION 2 PAGE 32 0F 38 ATTACHMENT 8.1 SECURITY COMPROMISE
~
g$:;
ALERT TAB F2 EAL 1.
For Modes 1-6:
Security force notifies the Operations Shift Supervisor of an Ongoing Security Compromise pursuant to the SONGS Security Plan.
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SAN ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-11.1 UNITS 2 AND*3 REVISION 2 PAGE 33 0F 38 ATTACN1ENT 8.1 I
SECURITY COMPROMISE
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r SiTEEMERGENCY N
(4 TAB F3 4
EAL 1.
For Modes 1-6:
i Security force notifies the Operations Shift Supervisor of the Imminent loss of Physical Security Control of the Plant.
i
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SAN GNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 34 0F 38 ATTACHMENT 8.1 SECURITY COMPROMISE sf CENERAL EMERGENCY i.f, fr*
TAB F4 EAL i
1.
For Modes 1-6:
Loss of physical security control of the facility.
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SAN.ONOFRE. NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 UNITS 2 AND 3 REVISION 2 PAGE 35 0F 38 ATTACHMENT 8.1 r -'s MISCELLANEOUS f
M UNUSUAL EVENT
$4 TAB G1 EAL Any one of the following conditions:
1.
For Modes 1-6:
Transportation of personnel that are both injured AND Externally contaminated from SONGS for treatment at a hospital.
2.
For Modes 1-6:
Plant conditions exist that warrant increased awareness on the part of:
The Plant operating staff, AND Local off-site authorities, or State off-site authorities.
3.
For Modes I and 2:
Other plant conditions exist which require' plant shutdown under Technical Specification requirements or involve other than normal controlled shutdown.
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-j t
ALERT TAB G2 EAL 1.
For Modes 1-6:
.I Other plant conditions exist that warrant precautionary activation of
'g Technical Support Center and placing emergency operations facility and other emergency personnel on standby.
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SAN 4N0FRE WUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-11.1
' UNITS 2 AND 3 REVISION 2 PAGE 37 0F 38 ATTACHMENT 8.1 MISCELLANEOUS
}
v 46
$ITE EMERGENCY TAB G3 k4 e
i EAL 1.
For Modes 1-5:
Other plant conditions exist that warrant activation of Emergency Centers and a precautionary notification to the public near the site is required.
e O
P
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ey *
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ee -
ee-
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SAN DNOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEOURE S023-VIII-11.1
' UNITS 2 AN0'3 REVISION 2 PAGE 38 0F 38 ATTACHMENT 8.1
~
MISCELLANEOUS t
GENERAL EMERGENCY I:k TAB G4 kJ EAL 1.
For Modes 1-G:
l Other plant conditions that make a release of large amount of Radioactivity in a short time period possible OR 2 of 3 fission product barriers (fuel cladding, reactor coolant boundary, containment) have been lost with a potential for loss of the third barrier.
l l
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SAN,0N0FRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE SO23-VIII-11.1
- VNITS 2 ANI) 3 REVISION 2 PAGE 1 0F 1 ATTACHMENT 8.2 l
LOSS OF RCS INVENTORY INSTRUMENTS gfb NOTE: To verify the Emergency Action Levels (EAL), on TABS B1 through B4, use any of,the following instruments:
FOR RCS'TO CONTAINMENT LEAKAGE 2(3)RT-7804-B1 Containment Particulate monitor 2(3)RT-7804-C1 Containment Gaseous Monitor 2(3)RT-7807-B1 Containment Particulate monitor 2(3)RT-7807-C1 Containment Gaseous Monitor 2(3)FR-5802 Containment Sump Inlet Flow 2(3)FR-5805 Containment Serp Inlet Flow FOR RCS TO SECONDARY LEAKAGE 2(3)RT-7818 Ccndenser Air Ejector Gas Monitor 2(3)RE-7870-1 Condenser Air Ejector Wide Range Monitor 2(3)RE-6753 Steam Generator Blowdown Monitor 2(3)RT-6759 Steam Generator Blowdown Monitor 2(3)RE-7874A1 Main Steam Line Low Range Monitor 2(3)RE-7875A1 Main Steam Line Low Range Monitor 2(3)RE-787481 Main Steam Line High Range Monitor 2(3)RE-7875B1 Main Steam Line High Range Monitor FOR RCS TO CCW LEAKAGE 2(3)RT-7819 Component Cooling Water Monitor FOR PRESSURIZER SAFETY VALVE LEAKAGE 2(3)TI-0107 Pressurizer Relief Line Discharge Temp 2(3)TI-0108 Pressurizer Relief Line Discharge Temp 2(3)LI-0116 Quench Tank Level 2(3)PI-0116 Quench Tank Pressure 2(3)TI-0116 Quench Tank Temperature w y-y..--_.___
y._
SAN -ONOFRE NUCLEAR GENERATING STATION EMERGENCY PROCEDURE S023-VIII-11.1 BAITS 2 AND 3 REVISION 2 PAGE 1 0F 1 ATTACl#9ENT 8.3
} (D UNIT 283 SAFETY SYSTEMS 9
9,p 1.
Boration Systems 3.
Reactor Protective Instrumentation l
4.
ESF Actuation System Instrumentation 5.
Accident Monitoring Instrumentaton 6.
Steam Generators and Main Steam System 7.
Emergency Core Cooling System 8.
9.
Containment depressurization and cooling systems 10.
Containment isolation valves 11.
Combustible Gas Control 12.
Auxiliary Feedwater system 13.
Condensate Storage Tank 14.
Component Cooling Water Systerr, 15.
Saltwater Cooling System 16.
Control Room Emergency Air Cleanup System 17.
A. C. Electrical Power Systems l
l 18.
D. C. Electrical Power Systems 1
0261F l
L l
_