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| number = ML20045F309
| number = ML20045F309
| issue date = 06/30/1993
| issue date = 06/30/1993
| title = Forwards Rev 25 to Limerick Generating Station Emergency Plan. Rev Reflects Changes to Table 4.2, Planning Basis Summary.
| title = Forwards Rev 25 to Limerick Generating Station Emergency Plan. Rev Reflects Changes to Table 4.2, Planning Basis Summary
| author name = Hunger G
| author name = Hunger G
| author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
| author affiliation = PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
Line 19: Line 19:
=Text=
=Text=
{{#Wiki_filter:.
{{#Wiki_filter:.
10 CFR 500 Appendix E PHILADELPHIA ELECTRIC COMPANY
10 CFR 50 Appendix E 0
                                                                                                ~
b PHILADELPHIA ELECTRIC COMPANY
b NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD.
~
NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD.
WAYNE, PA 19087-5691 (215) 640m
WAYNE, PA 19087-5691 (215) 640m
                                                                                                    ?
?
June 30, 1993 CTAT Jf r_PPORT DEPARTMENT Docket Nos. 50-352 50-353 License Nos. NPF-39       ,
June 30, 1993 CTAT Jf r_PPORT DEPARTMENT Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
NPF-85 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555                                                                       <


==Subject:==
==Subject:==
Limerick Generating Station, Units 1 and 2 Emergency Plan Revision, Revision No. 25 Gentlemen:
Limerick Generating Station, Units 1 and 2 Emergency Plan Revision, Revision No. 25 Gentlemen:
Attached is Revision No. 25 to the Limerick Generating Station (LGS), Units 1 and 2, Emergency Plan. This revision is being submitted in accordance with the         .
Attached is Revision No. 25 to the Limerick Generating Station (LGS), Units 1 and 2, Emergency Plan. This revision is being submitted in accordance with the requirements of 10 CFR 50.54(q),10 CFR 50 Appendix E, and 10 CFR 50.4(b)(5) as a result of changes which were effective on May 21, 1993.
requirements of 10 CFR 50.54(q),10 CFR 50 Appendix E, and 10 CFR 50.4(b)(5) as a result of changes which were effective on May 21, 1993. 10 CFR 50.54(q) and 10 CFR 50 Appendix E require that changes to emergency plans be submitted within         :
10 CFR 50.54(q) and 10 CFR 50 Appendix E require that changes to emergency plans be submitted within 30 days of such changes. These changes were submitted to the NRC within 30 days by way of controlled copy distribution; however, they were not submitted via docketed correspondence in accordance with 10 CFR 50.4(b)(5).
30 days of such changes. These changes were submitted to the NRC within 30 days by way of controlled copy distribution; however, they were not submitted via docketed correspondence in accordance with 10 CFR 50.4(b)(5). The delay in                 j submitting this revision of the Emergency Plan via docketed correspondence was             i the result of an administrative oversight. An investigation into this oversight           I is being conducted to preclude recurrence.                                                 i This revision reflects changes to Table 4.2, " Planning Basis Summary," of the Emergency Plan.       We have evaluated these changes and determined that they do not decrease the effectiveness of the LGS Emergency Plan. Furthermore, these changes have been reviewed by the LGS Plant Operations Review Committee.
The delay in j
submitting this revision of the Emergency Plan via docketed correspondence was i
the result of an administrative oversight.
An investigation into this oversight is being conducted to preclude recurrence.
i This revision reflects changes to Table 4.2, " Planning Basis Summary," of the Emergency Plan.
We have evaluated these changes and determined that they do not decrease the effectiveness of the LGS Emergency Plan. Furthermore, these changes have been reviewed by the LGS Plant Operations Review Committee.
If you have any questions or require additional information, please do not hesitate to contact us.
If you have any questions or require additional information, please do not hesitate to contact us.
Very truly yours, 9307070101 930630 PDR      ADDCK 05000352        h                                 . G. A. Hunger, Jr.
Very truly yours, 9307070101 930630 h
F                     PDR       v                                 Director Licensing Section
. G. A. Hunger, Jr.
PDR ADDCK 05000352 Director F
PDR v
Licensing Section
(
(


U.S. Nuclear Regulatory Commission                                       June 30s 1993 Document Control Desk-                                                         Page 2 l, Attachment.
U.S. Nuclear Regulatory Commission June 30s 1993 Document Control Desk-Page 2 Attachment.
cc:         T. T. Martin, Administrator, Region I, USNRC (w/ attachment, 2 copies)     ,
cc:
T. T. Martin, Administrator, Region I, USNRC (w/ attachment, 2 copies)
N. S. Perry, USNRC Senior Resident Inspector, LGS (w/ attachment) t f
N. S. Perry, USNRC Senior Resident Inspector, LGS (w/ attachment) t f
k I
k I
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O LGS EP I
O LGS EP I
THIS EMERGENCY PLAN SET                   1 HAS BEEN UPDATED TO                     :
THIS EMERGENCY PLAN SET 1
INCLUDE REVISIONS THROUGH                   .
HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH REV. 25 DATED 06/93 O
REV. 25 DATED 06/93                   !
n R-1 REV. 25, 06/93 O
O                                                     :
f* straw zoy.
n REV. 25, 06/93       !
R-1 O
f* straw zoy.                                   ,


. 'l LIMERICK CENERATING STATION UNITS 1 & 2                   .        .
'l LIMERICK CENERATING STATION UNITS 1 & 2 EMERCENCY PLAN
EMERCENCY PLAN                                         ;
^d PACE CHANCES 1he attached table is considered part of a controlled copy of the Limerick Generating Station Emergency Plan. This material should be incorporated into the Emergency Plan by following the instructions below.
^d                                         PACE CHANCES 1he attached table is considered part of a controlled copy of the Limerick Generating Station Emergency Plan. This material should be incorporated into the Emergency           :
l After the revised pages have been inserted, place the page that follows these I
Plan by following the instructions below.                                                 l After the revised pages have been inserted, place the page that follows these I
instructions in the front of Volume 1.
instructions in the front of Volume 1.
A list of effective pages has also been attached to simplify verifications after revision.                                                                                 :
A list of effective pages has also been attached to simplify verifications after revision.
VOLUME 2 REMOVE                                       INSERT PACE                       REVISION           PACE                       REVISION l Table 4.2                   23   11/92         Table 4.2                 24   06/93 0                                                                                                   .
VOLUME 2 REMOVE INSERT PACE REVISION PACE REVISION l Table 4.2 23 11/92 Table 4.2 24 06/93 0
O R-2                             Rev. 25, 06/93 l
O l
R-2 Rev. 25, 06/93


  .'    ,:                                                                            I LIMERICK CENERATING STATION               .          l EMERCENCY PLAN LIST OF EFFECTIVE PAGES VOLUME 1 PACE / DESCRIPTION                           REVISION NO.
I LIMERICK CENERATING STATION EMERCENCY PLAN LIST OF EFFECTIVE PAGES VOLUME 1 PACE / DESCRIPTION REVISION NO.
l R-1 thru R-4                                   Rev. 25 1 thru 10                                     Rev. 22 0-1 thru 0-2                                 Rev. 22 1-1 thru 1-4                                 Rev. 22 2-1 thru 2-4                                 Rev. 22 3-1 thru 3-7                                 Rev. 22 Figure 3.1                                 Rev. 22 Figure 3.2                                 Rev. 22 Figure 3.3                                 Rev. 22 4-1 thru 4-9                                 Rev. 22 Table 4.1                                 Rev. 22 l     Table 4.2                                 Rev. 24 f\
l R-1 thru R-4 Rev. 25 1 thru 10 Rev. 22 0-1 thru 0-2 Rev. 22 1-1 thru 1-4 Rev. 22 2-1 thru 2-4 Rev. 22 3-1 thru 3-7 Rev. 22 Figure 3.1 Rev. 22 Figure 3.2 Rev. 22 Figure 3.3 Rev. 22 4-1 thru 4-9 Rev. 22 Table 4.1 Rev. 22 l
5-1 thru 5-54                                 Rev. 22 Figure 5.1                                 Rev. 22 Figure 5.2                                 Rev. 22 Figure 5.3                                 Rev. 22 Figure 5.4                                 Rev. 22 Figure 5.5                                 Rev. 22 Figure 5.6                                 Rev. 22 Figure 5.7                                 Rev. 22 Table 5.1                                 Rev. 22                   ,
Table 4.2 Rev. 24 f\\
6-1 thru 6-25                                 Rev. 22 Table 6.1                                 Rev. 22 Table 6.2                                 Rev. 22 7-1 thru 7-10                                 Rev. 22 Table 7.1                                 Rev. 22 Table 7.2                                 Rev. 22 Table 7.3                                 Rev. 22                   i Table 7.4                                 Rev. 22 Table 7.5                                 Rev. 22 Figure 7.1                               Rev. 22 l                                 R-3                     .Rev. 25, 06/93
5-1 thru 5-54 Rev. 22 Figure 5.1 Rev. 22 Figure 5.2 Rev. 22 Figure 5.3 Rev. 22 Figure 5.4 Rev. 22 Figure 5.5 Rev. 22 Figure 5.6 Rev. 22 Figure 5.7 Rev. 22 Table 5.1 Rev. 22 6-1 thru 6-25 Rev. 22 Table 6.1 Rev. 22 Table 6.2 Rev. 22 7-1 thru 7-10 Rev. 22 Table 7.1 Rev. 22 Table 7.2 Rev. 22 Table 7.3 Rev. 22 i
Table 7.4 Rev. 22 Table 7.5 Rev. 22 Figure 7.1 Rev. 22 l
R-3
.Rev. 25, 06/93


4
4 l
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~          ~
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      ~
LIMERICK CENERATING STATION.
LIMERICK CENERATING STATION.               .        .
~
EMERGENCY PLAN
EMERGENCY PLAN (Q.
>                                                                                              l (Q.   /                           LIST OF EFFECTIVE PAGES (Continued)
/
PACE / DESCRIPTION                                 REVISION NO.
LIST OF EFFECTIVE PAGES (Continued)
8-1 thru 8-11                                       Rev. 22 Table 8.1                                       Rev 22 9-1 thru 9-2                                       Rev. 22 Appendix A                                         Rev. 22 Appendix B                                         Rev. 22 Appendix C                                         Rev. 21             ,
PACE / DESCRIPTION REVISION NO.
Appendix D                                         Rev. 22 Appendix E                                         Rev. 22 Appendix F                                         Rev. 22 VOLUME 2 Appendix C                                         Rev. 21 Appendix H                                         Rev. 21 Appendix 1                                       Rev. 22 Appendix J                                       Rev. 23 Questions and Responses                           Rev.18 i
8-1 thru 8-11 Rev. 22 Table 8.1 Rev 22 9-1 thru 9-2 Rev. 22 Appendix A Rev. 22 Appendix B Rev. 22 Appendix C Rev. 21 Appendix D Rev. 22 Appendix E Rev. 22 Appendix F Rev. 22 VOLUME 2 Appendix C Rev. 21 Appendix H Rev. 21 Appendix 1 Rev. 22 Appendix J Rev. 23 Questions and Responses Rev.18 i
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Is i
Rev. 25, 06/93 i                                    R-14
R-14 Rev. 25, 06/93


LGS EP TABLE 4.2 PLANNING BASIS  
LGS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
 
(Page 1 of 16) 1.
(Page 1 of 16)
HAZARDS 'M STATION OPERATION UNUSUAL EVENT 1)
: 1. HAZARDS 'M STATION OPERATION UNUSUAL EVENT       1) Aircraft crash onsite OR unusual aircraft activity over the site.
Aircraft crash onsite OR unusual aircraft activity over the site.
: 2) Train derailment within site boundary.
2)
: 3) Explosion within or near site boundary.
Train derailment within site boundary.
: 4) Nearby or onsite release of potentially harmful quantities of toxic, flammable gas or chlorine.
3)
ALERT               1) Entry of toxic, flammable gases OR chlorine into power block with subsequent habitability problem.
Explosion within or near site boundary.
4)
Nearby or onsite release of potentially harmful quantities of toxic, flammable gas or chlorine.
ALERT 1)
Entry of toxic, flammable gases OR chlorine into power block with subsequent habitability problem.
Indicated by:
Indicated by:
Visual observation, direct measurement OR notification received by Control Room.
Visual observation, direct measurement OR notification received by Control Room.
: 2) IF both units are in cold shutdown THEN:
2)
: a. Aircraft crash or missile impact on Reactor Enclosure, Control Enclosure, Turbine Enclosure, Diesel Generator Enclosure, Spray Pond Pump House.
IF both units are in cold shutdown THEN:
: 3) Known explosion damage affecting plant operation.
Aircraft crash or missile impact on Reactor Enclosure, Control a.
SITE AREA EMERGENCY 1) Entry of toxic, flammable gases OR chlorine into vital areas, where lack of access constitutes a reactor safety problem. Indicated bys
Enclosure, Turbine Enclosure, Diesel Generator Enclosure, Spray Pond Pump House.
: a. shift Supervision evaluation AND
3)
: b. Visual observation, direct measurement, notification received by Control Room.
Known explosion damage affecting plant operation.
: 2) IF either unit is not in cold shutdown THEN:
SITE AREA EMERGENCY 1)
: a. Aircraft crash or missile impact on Reactor Enclosure, Control Enclosure, Turbine Enclosure, Diesel Enclosure or Spray Pond Pump House.
Entry of toxic, flammable gases OR chlorine into vital areas, where lack of access constitutes a reactor safety problem.
: 3) Known explosion causing severe damage to safe shutdown equipment.
Indicated bys shift Supervision evaluation a.
GENERAL EMERGENCY   N/A
AND b.
                                                                                                        . 24, 06/93-
Visual observation, direct measurement, notification received by Control Room.
      ~ __
2)
IF either unit is not in cold shutdown THEN:
a.
Aircraft crash or missile impact on Reactor Enclosure, Control Enclosure, Turbine Enclosure, Diesel Enclosure or Spray Pond Pump House.
3)
Known explosion causing severe damage to safe shutdown equipment.
GENERAL EMERGENCY N/A 24, 06/93-
~ __


LGS EP TABLE 4.2 PLANNING HASIS  
LGS EP TABLE 4.2 PLANNING HASIS  


==SUMMARY==
==SUMMARY==
 
(Page 2 of 16) 2.
(Page 2 of 16)
ENVIRONMENTAL UNUSUAL EVENT 1)
: 2. ENVIRONMENTAL UNUSUAL EVENT         1)   Actual earthquake detected by seismic Monitoring System (00C693) at or below operating basis earthquake (.075g).
Actual earthquake detected by seismic Monitoring System (00C693) at or below operating basis earthquake (.075g).
: 2)   A tornado is observed within or near site boundary.
2)
: 3)   A National Weather Service hurricane warning is issued for Montgomery County.
A tornado is observed within or near site boundary.
ALERT                   1)   Actual earthquake detected by Seismic Monitoring System (OOC 693) beyond operating basis earthquake (.075g).
3)
: 2)   Tornado strikes: Reactor Enclosure, Turbine Enclosure, Spray Pond Pump House, Control Enclosure, Diesel Generator Enclosure.
A National Weather Service hurricane warning is issued for Montgomery County.
: 3)   Sustained high winds greater than 70 mph as indicated on OBC 699.
ALERT 1)
SITE AREA EMERGENCY   IF either unit is not in cold shutdown THEN:
Actual earthquake detected by Seismic Monitoring System (OOC 693) beyond operating basis earthquake (.075g).
: 1)   Sustained high winds greater than 90 mph as indicated on OBC 699.
2)
OR
Tornado strikes: Reactor Enclosure, Turbine Enclosure, Spray Pond Pump House, Control Enclosure, Diesel Generator Enclosure.
: 2)   Actual earthquake detected by Seismic Monitoring System (OOC 693) beyond safe shutdown earthquake (.15g).
3)
GENERAL EMERGENCY       N/A
Sustained high winds greater than 70 mph as indicated on OBC 699.
    ~
SITE AREA EMERGENCY IF either unit is not in cold shutdown THEN:
l*                                                                                                               24, 06/93
1)
Sustained high winds greater than 90 mph as indicated on OBC 699.
OR 2)
Actual earthquake detected by Seismic Monitoring System (OOC 693) beyond safe shutdown earthquake (.15g).
GENERAL EMERGENCY N/A
~
l*
24, 06/93


LGS EP TABLE 4.2 PLANNING BASIS  
LGS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
(Page 3 of 16)
(Page 3 of 16)
: 3. LOSS OF POWER UNUSUAL EVENT       1) Loss of all off-site power greater than 60 seconds.
: 3. LOSS OF POWER UNUSUAL EVENT 1)
: 2) Loss of all emergency AC power capability for greater than 60 seconds (e.g., offsite power is feeding station, but all 4 diesel generators unavailable) with fuel in reactor vessel.
Loss of all off-site power greater than 60 seconds.
ALERT               1) Loss of all offsite power for greater than 60 seconds.
2)
Loss of all emergency AC power capability for greater than 60 seconds (e.g., offsite power is feeding station, but all 4 diesel generators unavailable) with fuel in reactor vessel.
ALERT 1)
Loss of all offsite power for greater than 60 seconds.
AND Loss of all emergency AC power for greater than 60 seconds.
AND Loss of all emergency AC power for greater than 60 seconds.
: 2) Loss of al3 safeguard DC power for greater than 60 seconds.
2)
SITE AREA KMERGENCY 1) Loss of all offsite power for greater than 15 minutes.
Loss of al3 safeguard DC power for greater than 60 seconds.
SITE AREA KMERGENCY 1)
Loss of all offsite power for greater than 15 minutes.
AND Loss of all emergency AC power for greater than 15 minutes.
AND Loss of all emergency AC power for greater than 15 minutes.
: 2) Loss of all safeguard DC power for greater than 15 minutes.
2)
CENERAL EMERGENCY   1) Loss of all offsite power                                           *** PAR ***
Loss of all safeguard DC power for greater than 15 minutes.
AND Loss of all emergency AC power                     Evacuate 2 mile radius. Evacuate affected AND                                               sector (s) and 2 adjacent sectors for 2-5 Loss of RPV makeup capability                     ' miles, such that RPV level cannot be maintained above top of active fuel.
CENERAL EMERGENCY 1)
OG Q
Loss of all offsite power
*** PAR ***
AND Loss of all emergency AC power Evacuate 2 mile radius. Evacuate affected AND sector (s) and 2 adjacent sectors for 2-5 Loss of RPV makeup capability
' miles, such that RPV level cannot be maintained above top of active fuel.
O G Q


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LCS EP TABLE 4.2 PLANNING BASIS  
LCS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
 
(Page 5 of 16) 5.
(Page 5 of 16)
FIRE UNUSUAL KVENT Fires involving permanent plant structures in the protected area lasting 10 minutes or more.
: 5. FIRE UNUSUAL KVENT         Fires involving permanent plant structures in the protected area lasting 10 minutes or more.
ALERT 1)
ALERT                 1)   Fire which could make any of the following engineered safety (ESF) systems inoperable:
Fire which could make any of the following engineered safety (ESF) systems inoperable:
                                                                    - Class IE Power System
- Class IE Power System
                                                                    - Safety-Related Equipment Room Coolars
- Safety-Related Equipment Room Coolars
                                                                    - Drywell Unit Coolers
- Drywell Unit Coolers
                                                                    - MSIV-LCS
- MSIV-LCS
                                                                    - CAC
- CAC
                                                                    - RERS
- RERS
                                                                    - HPCI
- HPCI
                                                                    - SGTS
- SGTS
                                                                    - ESW
- ESW
                                                                    - ADS
- ADS
                                                                    - LPCI
- LPCI
                                                                    - Core Spray
- Core Spray
                                                                    - RHR Containment Spray
- RHR Containment Spray
                                                                    - RHR Suppression Pool Cooling
- RHR Suppression Pool Cooling
                                                                    - RHR Service Water
- RHR Service Water
                                                                    - Reactor Enclosure Isolation System
- Reactor Enclosure Isolation System
                                                                    - Habitability & Control Room Isolation
- Habitability & Control Room Isolation
                                                                    - Primary Containment & Reactor Vessel Isolation Control Systems
- Primary Containment & Reactor Vessel Isolation Control Systems
                                                                    - Control Enclosure Chilled Water System
- Control Enclosure Chilled Water System 2)
: 2)   Fire which could make RCIC inoperable.
Fire which could make RCIC inoperable.
SITE AREA EMERGENCY   Fire which compromises Function of a safety system which is required to mitigate the consequences of an accident OR is required to achieve or maintain safe shutdown AND for which there is no safety grade backup.
SITE AREA EMERGENCY Fire which compromises Function of a safety system which is required to mitigate the consequences of an accident OR is required to achieve or maintain safe shutdown AND for which there is no safety grade backup.
i.e.:
i.e.:
                                                                    - HPCI and ADS
- HPCI and ADS
                                                                    - All low pressure ECCS
- All low pressure ECCS
                                                                    - Loss of Suppression Pool Cooling GENERAL EMERGENCY     N/A 4
- Loss of Suppression Pool Cooling GENERAL EMERGENCY N/A 4
l'                                                                                                                                               . 24, 06/93
l' 24, 06/93
                                                                                                                                        -  _ _ _ - _ _ - - - - - _ _ _ _ _ - - _ ~
~


LGS EP TABLE 4.2 PLANNING BASIS  
LGS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
 
(Page 6 of 16) 6.
(Page 6 of 16)
-RADIOACTIVE EFFLUENT RELEASE UNUSUAL EVENT 1)
: 6. -RADIOACTIVE EFFLUENT RELEASE UNUSUAL EVENT         1)     Report indicates liquid release exceeds Offsite Dose Calculation Manual Section (I) 3.2.2 or 3.2.3.
Report indicates liquid release exceeds Offsite Dose Calculation Manual Section (I) 3.2.2 or 3.2.3.
: 2)     Calculated site boundary dose rates exceeds Offsite Dose Calculation Manual Section (I} 3.3.2.a or 3.3.2.b.
2)
ALERT                ***  Enter T-104 and execute concurrently ***
Calculated site boundary dose rates exceeds Offsite Dose Calculation Manual Section (I} 3.3.2.a or 3.3.2.b.
Calculated site boundary dose rate exceeds ten times Offsite Dose Calculation Manual Section (I) 3.3.2.a or 3.3.2.b.
Enter T-104 and execute concurrently ***
SITE AREA EMERGENCY   *** Enter T-104 and execute concurrently ***
ALERT Calculated site boundary dose rate exceeds ten times Offsite Dose Calculation Manual Section (I) 3.3.2.a or 3.3.2.b.
: 1)     North Stack Wide Range Accident Monitor reading exceeds 3.4E+06 uC1/sec for 2 minutes per recorder RR26-076 on MCR Panel 00C624 or RM-11 color console, excluding system noise.
SITE AREA EMERGENCY
: 2)     Calculated or measured site boundary whole body dose rate exceeds 50 mR/hr for 30 minutes.
*** Enter T-104 and execute concurrently ***
: 3)     Calculated or measured site boundary thyroid dose rate exceeds 250 mR/hr for 30 minutes.
1)
North Stack Wide Range Accident Monitor reading exceeds 3.4E+06 uC1/sec for 2 minutes per recorder RR26-076 on MCR Panel 00C624 or RM-11 color console, excluding system noise.
2)
Calculated or measured site boundary whole body dose rate exceeds 50 mR/hr for 30 minutes.
3)
Calculated or measured site boundary thyroid dose rate exceeds 250 mR/hr for 30 minutes.
GENERAL EMERGENCY
GENERAL EMERGENCY
                                *** Enter T-104 and execute concurren'ly c  ***
*** Enter T-104 and execute concurren'ly ***
: 1)     Calculated or measured offsite whole body dose rate exceeds 500 mR/hr.
c 1)
                                                                                                      ... PAR ***
Calculated or measured offsite whole body dose rate exceeds 500 mR/hr.
: 2)     Calculated or measured offsite thyroid       Evacuate 2 mile radius. Evacuate affected dose rate exceeds 2500 mR/hr.                 sector (s) and 2 adjacent sectors for 2-5 miles.
... PAR ***
l 5
2)
: 3)     Offsite doses are projected to exceed 1 Rem Whole Body or 5 Rem Thyroid.
Calculated or measured offsite thyroid Evacuate 2 mile radius. Evacuate affected dose rate exceeds 2500 mR/hr.
                                                                                                    ...  ,AR ...
sector (s) and 2 adjacent sectors for 2-5 miles.
: 4)     Actual or potential projected dose           Evacuate 5 miles radius, evacuate affected exceeding 5R WB/25R THY.                     sector (s) and 2 adjacent sectors for 5-10 miles.
l 3)
24, 06/93 i.
Offsite doses are projected to exceed 5
1 Rem Whole Body or 5 Rem Thyroid.
,AR 4)
Actual or potential projected dose Evacuate 5 miles radius, evacuate affected exceeding 5R WB/25R THY.
sector (s) and 2 adjacent sectors for 5-10 miles.
i.
24, 06/93


VAeS EP TABLE 4.2 PLANNING BASIS  
VAeS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
(Page 7 of 16)
(Page 7 of 16)
: 7. EVACUATION OF CONTROL ROOM UNUSUAL EVENT       N/A ALERT               Evacuation of Control Room anticipated or required, with control established at remote shutdown panel.
: 7. EVACUATION OF CONTROL ROOM UNUSUAL EVENT N/A ALERT Evacuation of Control Room anticipated or required, with control established at remote shutdown panel.
SITE AREA EMERGENCY Evacuation of Control Room AND control of shutdown systems not Esfablished from remote shutdown panel in 15 minutes.
SITE AREA EMERGENCY Evacuation of Control Room AND control of shutdown systems not Esfablished from remote shutdown panel in 15 minutes.
GENERAL EMERGENCY   N/A 1v e     -  .                              .
GENERAL EMERGENCY N/A 1v e
O                 .                    -- .
O O. u.
O. u. i ,
i,


LGS EP TABLE 4.2 PLANNING BASIS  
LGS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
 
(Page 8 of 16) 8.
(Page 8 of 16)
DAMAGE 'ID FUEL UNUSUAL EVENT 1)
: 8. DAMAGE 'ID FUEL UNUSUAL EVENT                           1)     Steam Jet Air Ejector Discharge radiation monitor exceeds 2.1E+04 mR/hr.
Steam Jet Air Ejector Discharge radiation monitor exceeds 2.1E+04 mR/hr.
: 2)     Steam Jet Air Ejector Discharge radiation monitor has an unexpected increase of 4000 mR/hr over 30 minutes.
2)
: 3)     I-131 dose equivalent in reactor coolant exceeds 4 uci/g or exceeds 0.2 uCi/g for more than 48 hours during one continuous time interval.
Steam Jet Air Ejector Discharge radiation monitor has an unexpected increase of 4000 mR/hr over 30 minutes.
ALERf                                   1)     Steam Jet Air Ejector Diccharge radiation monitor exceeds 2.1E+05 mR/hr.
3)
: 2)     I-131 dose equivalent in reactor coolant exceeds 300 uCi/g from sample AND main steam line high-high radiation with resultant scram.
I-131 dose equivalent in reactor coolant exceeds 4 uci/g or exceeds 0.2 uCi/g for more than 48 hours during one continuous time interval.
: 3)     Spent fuel damage resulting in a refueling floor area ventilation exhaust monitor alarm.
ALERf 1)
: 4)     Containment Post LOCA Radiation monitors greater than 1E+02 R/hr.
Steam Jet Air Ejector Diccharge radiation monitor exceeds 2.1E+05 mR/hr.
SITE AREA EMERGENCY                     1)     Major damage to spent fuel:
2)
: a. Observation of major damage to spent fuel OR
I-131 dose equivalent in reactor coolant exceeds 300 uCi/g from sample AND main steam line high-high radiation with resultant scram.
: b. Eater loss below fuel lavel in spent fuel pool.
3)
: 2)     Containment Post LOCA Radiation Monitors greater than 1E+03 R/hr.
Spent fuel damage resulting in a refueling floor area ventilation exhaust monitor alarm.
GENERAL EMERGENCY D/W Rad >1E+04 R/hr                                                     *** PAR ***
4)
Containment Post LOCA Radiation monitors greater than 1E+02 R/hr.
SITE AREA EMERGENCY 1)
Major damage to spent fuel:
a.
Observation of major damage to spent fuel OR b.
Eater loss below fuel lavel in spent fuel pool.
2)
Containment Post LOCA Radiation Monitors greater than 1E+03 R/hr.
GENERAL EMERGENCY D/W Rad >1E+04 R/hr
*** PAR ***
with containment intact.*
with containment intact.*
l Evacuate 2 mile radius, evacuate affected sector (s) l                                           D/W Rad >5E+04 n/hr                                 and 2 adjacent sectors for 2-5 miles, with containment intact.*
l Evacuate 2 mile radius, evacuate affected sector (s) l D/W Rad >5E+04 n/hr and 2 adjacent sectors for 2-5 miles, with containment intact.*
d
d
                                                                                                                                    *** PAR ***
*** PAR ***
                                                          *IF release is in progress OR containment failure imminent THEN PAR as indicated above         Evacuate 5 mile radius, evacuate affected sector (s) but shelter may be indicated for those areas         and 2 adjacent sectors for 5-10 miles.
*IF release is in progress OR containment failure imminent THEN PAR as indicated above Evacuate 5 mile radius, evacuate affected sector (s) but shelter may be indicated for those areas and 2 adjacent sectors for 5-10 miles.
that cannot be evacuated before plume arrival.
that cannot be evacuated before plume arrival.
l*                                                                                                                                             24, 06/93
l*
24, 06/93


ifs EP TABLE 4.2 PLANNING BASIS  
ifs EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
 
(Page 9 of 16) 9.
(Page 9 of 16)
INSTRUMENT OR COMMUNICATION FAILURE UNUSUAL EVENT 1)
: 9. INSTRUMENT OR COMMUNICATION FAILURE UNUSUAL EVENT       1)   Loss of all Main Control Room Communication.
Loss of all Main Control Room Communication.
: 2)   Significant loss of assessment capability in Main Control Room.
2)
: a. Indicated by simultaneous loss of plant process computer AND ERFDS for greater than 24 hours.
Significant loss of assessment capability in Main Control Room.
ALEMT               Loss of all annunciators.
a.
Indicated by simultaneous loss of plant process computer AND ERFDS for greater than 24 hours.
ALEMT Loss of all annunciators.
SITE AREA EMERGENCY All annunciators lost and plant transient initiated or in progress.
SITE AREA EMERGENCY All annunciators lost and plant transient initiated or in progress.
GENERAL RMERGENCY   N/A                                                                     ,
GENERAL RMERGENCY N/A 5
5
~
~
l' 24, 06/93
l'                                                                                                 . 24, 06/93


LGS EP TABLE 4.2 PLANNING BASIS  
LGS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
(Page 10 of 16)
(Page 10 of 16)
: 10. SCRAM FAILURE UNUSUAL EVENT           N/A ALERT                   Failure of the Reactor Protection System to automatically initiate and complete a scram as indicated by APRM's greater than 4%, one minute after scram signal has occurred OR 5hould have occurred.
: 10. SCRAM FAILURE UNUSUAL EVENT N/A ALERT Failure of the Reactor Protection System to automatically initiate and complete a scram as indicated by APRM's greater than 4%, one minute after scram signal has occurred OR 5hould have occurred.
!   SITE AREA EMERGENCY     Transient requiring manual or automatic standby liquid control system injection.
! SITE AREA EMERGENCY Transient requiring manual or automatic standby liquid control system injection.
(Due to high Suppression Pool temperature in T-101 or RRCS Setpoints exceeded.)
(Due to high Suppression Pool temperature in T-101 or RRCS Setpoints exceeded.)
CONERAL EMERGENCY       Transient requiring manual or automatic                           *** PAR ***
CONERAL EMERGENCY Transient requiring manual or automatic
standby liquid control system injection (due to high S/P temp or RRCS setpoints exceeded). Evacuate 2 mile radius, evacuate affected sector (s) and 2 adjacent sectors for 2-5 AND                                             miles.
*** PAR ***
standby liquid control system injection (due to high S/P temp or RRCS setpoints exceeded).
Evacuate 2 mile radius, evacuate affected sector (s) and 2 adjacent sectors for 2-5 AND miles.
The reactor is not made or expected to be made subcritical 45 minutes after SLC injection attempt 53.
The reactor is not made or expected to be made subcritical 45 minutes after SLC injection attempt 53.
l' 24, 06/93
l' 24, 06/93
Line 301: Line 403:


==SUMMARY==
==SUMMARY==
(Page 11 of 16) 11.
DOUNDARY DEGRADATION /LOCA UNUSUAL EVENT 1)
Failure of main steam relief valve OR ADS valve to close following reduction of applicable pressure.
2)
Reactor coolant leak rate exceeds 30 gpm total leakage.
a.
Indicated by surveillance test report.
ALERT 1)
Scram with leak.
Indicated by:
a.
Reactor level less than -129" OR unknown AND b.
Containment pressure greater than 1.68 psig.
2)
Containment pressure greater than 10 peig.
3)
D/W floor drain sump discharge >50 gpm for 1 hour.
4)
High airborne contamination in reactor enclosure indicated by RE exhaust RAD Monitor A/B or C/D Hi-Hi.
5) 1000 fold increase in general area radiation levels as reported by Health Physics.
6) 5000 MPC airborne activity excluding isotopes with half lives less than 2 hours as reported by Health Physics.
SITE AREA EMERGENCY 1)
Scram with LOCA indicated by:
a.
Reactor level less than -129" OR unknown.
AND b.
Containment pressure greater than 10 psig and increasing.
2)
Main steam line break _outside containment without isolation indicated by:
a.
High Main Steam Line Flow (108.7 psig)
OR b.
High Steam Tunnel Temp (165 deg F)
OR c.
Main Steam Line Low Pressure (756 psig) j' 24, 06/93


(Page 11 of 16)
LGS EP TABLE 4.2 PLANNING BASIS StHD4ARY (Page 12 of 16) 11.
: 11. DOUNDARY DEGRADATION /LOCA UNUSUAL EVENT      1) Failure of main steam relief valve OR ADS valve to close following reduction of applicable pressure.
BOUNDARY DEGRADATION /LOCA GENERAL EMERGENCY 1)
: 2) Reactor coolant leak rate exceeds 30 gpm total leakage.
Scram with LOCA l
: a. Indicated by surveillance test report.
AND ECCS unable to maintain reactor water level as indicated by:
ALERT              1) Scram with leak. Indicated by:
Failure to bring Reactor level above -161" after three minutes, l
: a. Reactor level less than -129" OR unknown AND
a.
: b. Containment pressure greater than 1.68 psig.
b.
: 2) Containment pressure greater than 10 peig.
AND Containment pressure greater than 20 psig.
: 3) D/W floor drain sump discharge >50 gpm for 1 hour.
2)
: 4) High airborne contamination in reactor enclosure indicated by RE exhaust RAD Monitor A/B or C/D Hi-Hi.
Scram with LOCA and D/W Failure.
: 5) 1000 fold increase in general area radiation levels as reported by Health Physics.
Indicated by:
: 6) 5000 MPC airborne activity excluding isotopes with half lives less than 2 hours as reported by Health Physics.
SITE AREA EMERGENCY 1) Scram with LOCA indicated by:
: a. Reactor level less than -129" OR unknown.
AND
: b. Containment pressure greater than 10 psig and increasing.
: 2) Main steam line break _outside containment without isolation indicated by:
: a. High Main Steam Line Flow (108.7 psig)
OR
: b. High Steam Tunnel Temp (165 deg F)
OR
: c. Main Steam Line Low Pressure (756 psig) j'                                                                                                    . 24, 06/93
 
LGS EP TABLE 4.2 PLANNING BASIS StHD4ARY (Page 12 of 16)
: 11. BOUNDARY DEGRADATION /LOCA GENERAL EMERGENCY 1)   Scram with LOCA AND ECCS unable to maintain reactor water level as indicated by:
l
: a. Failure to bring Reactor level above -161" after three minutes, l
: b. AND Containment pressure greater than 20 psig.
: 2)   Scram with LOCA and D/W Failure. Indicated   by:
Reactor level less than -129" OR unknown.
Reactor level less than -129" OR unknown.
AND l
AND l
Unexpected drop in D/W pressure or other evidence of D/W failure.
Unexpected drop in D/W pressure or other evidence of D/W failure.
                              *** PAR     ***                *** PAR ***                     *** PAR ***
*** PAR
*** PAR ***
*** PAR ***
Evacuate 2 mile radius, evacuate affected sector (s) and 2 adjacent sectors) for 2-5 miles.
Evacuate 2 mile radius, evacuate affected sector (s) and 2 adjacent sectors) for 2-5 miles.
I l
I l
Line 342: Line 463:


==SUMMARY==
==SUMMARY==
 
(Page 13 of 16) 12.
(Page 13 of 16)
UNUSUAL SHUTDOWN UNUSUAL EVENT 1)
: 12. UNUSUAL SHUTDOWN UNUSUAL EVENT       1) Shutdown initiated as required by any of the following Technical Specification limiting conditions for operation:
Shutdown initiated as required by any of the following Technical Specification limiting conditions for operation:
LCO 3.4.3.2 -    Failure to meet minimum reactor coolant system leakage limits.
LCO 3.4.3.2 Failure to meet minimum reactor coolant system leakage limits.
LCO 3.4.6.1 -
LCO 3.4.6.1 Exceeding reactor coolant system heatup or cooldown limito.
Exceeding reactor coolant system heatup or cooldown limito.
LCO 3.5.3 Failure to meet suppression chamber operability requirements.
LCO 3.5.3   -
LCO 3.6.1.1 Failure to maintain primary containment integrity.
Failure to meet suppression chamber operability requirements.
LCO 3.8.1.1 or 3.8.3.1 Failure to meet minimum A.C.
LCO 3.6.1.1 -
electrical power requirements while operating.
Failure to maintain primary containment integrity.
2)
LCO 3.8.1.1 or 3.8.3.1   -
Scram and automatic ECCS initiation with discharge to the vessel as a result of a valid aignal.
Failure to meet minimum A.C. electrical power requirements while operating.
3)
: 2) Scram and automatic ECCS initiation with discharge to the vessel as a result of a valid aignal.
Exceeding any Technical Specification safety limits.
: 3) Exceeding any Technical Specification safety limits.
ALERT N/A SITH AREA EMERGENCY N/A GENERAL EMERGENCY N/A m#
ALERT               N/A SITH AREA EMERGENCY N/A GENERAL EMERGENCY   N/A m#
p
p                                                                                                         . 24, 06/93
. 24, 06/93


4 LCS EP TABLE 4.2 PLANNING BASIS  
4 LCS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
 
(Page 14 of 16) 13.
(Page 14 of 16)
LOSS OF HOT OR COLD SHUTDOWN CAPABILITY UNUSUAL EVENT N/A ALERT Complete loss of ability to establish AND maintain plant in a Cold Shutdown condition.
: 13. LOSS OF HOT OR COLD SHUTDOWN CAPABILITY UNUSUAL EVENT       N/A ALERT               Complete loss of ability to establish AND maintain plant in a Cold Shutdown condition.
Symptomized by:
Symptomized by:
: a. Inability to establish Reactor Coolant Temperature of less than 200 degrees F in a timely manner OR
Inability to establish Reactor Coolant Temperature of less than 200 degrees F in a a.
: b. Loss of all means of Primary and Alternate Decay Heat Removal when shutdown, such that Reactor Coolant Temperature cannot be maintained below 200 degrees F.
timely manner OR b.
Loss of all means of Primary and Alternate Decay Heat Removal when shutdown, such that Reactor Coolant Temperature cannot be maintained below 200 degrees F.
SITE AREA EMERGENCY Actual inability to reduce Reactor Coolant System Temperature while the plant is Shutdown.
SITE AREA EMERGENCY Actual inability to reduce Reactor Coolant System Temperature while the plant is Shutdown.
Indicated by:
Indicated by:
: a. Inability to establish reactor coolant temperature less than 200 degrees F in a timely manner AND
Inability to establish reactor coolant temperature less than 200 degrees F in a timely a.
: b. Suppression Pool Temperature greater than 120 degrees F and rising.
manner AND b.
                                                                                                              *** PAR ***
Suppression Pool Temperature greater than 120 degrees F and rising.
: a. Inability to maintain Reactor level greater TAF                               Evacuate 2 mile radius, evacuate affected OR                                       sectors (s) and 2 adjacent sectors for 2-5 miles, substantial Fuel damage has occurred AND
*** PAR ***
: b. Inability to maintain Suppression Pool Temperature below upper limit of Heat Capacity Curves (SP/T-1 and SP/L-1) on T-102 procedure.
Inability to maintain Reactor level a.
greater TAF Evacuate 2 mile radius, evacuate affected OR sectors (s) and 2 adjacent sectors for 2-5 miles, substantial Fuel damage has occurred AND b.
Inability to maintain Suppression Pool Temperature below upper limit of Heat Capacity Curves (SP/T-1 and SP/L-1) on T-102 procedure.
l 4
l 4
['
24, 06/93
24, 06/93
['


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p-LGS EP TABLE 4.2 PLANNING BASIS  
p-LGS EP TABLE 4.2 PLANNING BASIS  


==SUMMARY==
==SUMMARY==
 
f (Page 16 of 16)
f                                                                           (Page 16 of 16)
TERMS AND DEFINITIONS SECURITY A security threat as illustrated by Plant parameters or other condition attempted entry or sabotage with the EMERGENCY ACTION which if met or exceeded the COMPROMISE intent to gain physical control of the LEVEL (EAL) emergency classification level and plant.
TERMS AND DEFINITIONS SECURITY           A security threat as illustrated by EMERGENCY ACTION Plant parameters or other condition                     COMPROMISE          attempted entry or sabotage with the LEVEL (EAL)            which if met or exceeded the                                               intent to gain physical control of the emergency classification level and                                         plant.
requires a declaration of emergency.
requires a declaration of emergency.
UNUSUAL EVENT      Events in progress or have occurred, that OPERABLE System, sub-system, train,                                                 indicate a potential degradation of the component, or device, and all                                               level of safety of the plant.       No auxiliaries required for their                                             releases of radioactive material operation, is capable of performing                                         requiring offsite response or monitoring its specified function in the                                               are expected unless further degradation intended manner.                                                           of safety systems occurs.
Events in progress or have occurred, that OPERABLE System, sub-system, train, UNUSUAL EVENT indicate a potential degradation of the component, or device, and all level of safety of the plant.
ALERT               Events in progress or have occurred that PROTECTIVE ACTION      Recommendation made to the state of                                         involve actual or potential substantial RECOMMENDATIONS (PAR)  action to be taken to avoid or                                             degradation of the level of safety of the reduce projected dose to the                                               plant.       Any releases of radioactive public,                                                                   material are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guidelines (PAG) exposure levels.
No auxiliaries required for their releases of radioactive material operation, is capable of performing requiring offsite response or monitoring its specified function in the are expected unless further degradation intended manner.
SITE AREA           Events in progress or which have occurred PROJECTED DOSE          An estimate of radiation dose which                 EMERGENCY           that involve actual or likely major affected individuals could                                                 failures of plant functions needed for potentially receive if protective                                         protection of the public. Any releases actions are not taken.                                                   of radioactive material are not expected to exceed EPA PAG exposure levels except near site boundary.
of safety systems occurs.
GENERAL EMERGENCY Events in progress or which have occurred SABOTAGE An act conducted by a person or                                             that involve actual or imminent persons with the intent of damaging                                         substantial core degradation or melting or impairing the operation of the                                           with potential for loss of containment plant,                                                                         integrity. Releases of radioactive material can be reasonable expected to exceed EPA PAG exposure levels offsite for more that the immediate site area.
ALERT Events in progress or have occurred that Recommendation made to the state of involve actual or potential substantial PROTECTIVE ACTION action to be taken to avoid or degradation of the level of safety of the RECOMMENDATIONS (PAR) reduce projected dose to the plant.
p
Any releases of radioactive
(,J. 24, 06/93
: public, material are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guidelines (PAG) exposure levels.
                !  J g
SITE AREA Events in progress or which have occurred An estimate of radiation dose which EMERGENCY that involve actual or likely major PROJECTED DOSE affected individuals could failures of plant functions needed for potentially receive if protective protection of the public. Any releases actions are not taken.
  -                        ^^
of radioactive material are not expected to exceed EPA PAG exposure levels except near site boundary.
                                                        ,, , , , , , _}}
Events in progress or which have occurred GENERAL EMERGENCY An act conducted by a person or that involve actual or imminent SABOTAGE persons with the intent of damaging substantial core degradation or melting or impairing the operation of the with potential for loss of containment
: plant, integrity.
Releases of radioactive material can be reasonable expected to exceed EPA PAG exposure levels offsite for more that the immediate site area.
(,J. 24, 06/93 p
J g
^^
,,,,,,, _}}

Latest revision as of 11:13, 19 December 2024

Forwards Rev 25 to Limerick Generating Station Emergency Plan. Rev Reflects Changes to Table 4.2, Planning Basis Summary
ML20045F309
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 06/30/1993
From: Hunger G
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9307070181
Download: ML20045F309 (2)
v • d • e


Text

.

10 CFR 50 Appendix E 0

b PHILADELPHIA ELECTRIC COMPANY

~

NUCLEAR GROUP HEADQUARTERS 955-65 CHESTERBROOK BLVD.

WAYNE, PA 19087-5691 (215) 640m

?

June 30, 1993 CTAT Jf r_PPORT DEPARTMENT Docket Nos. 50-352 50-353 License Nos. NPF-39 NPF-85 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

Subject:

Limerick Generating Station, Units 1 and 2 Emergency Plan Revision, Revision No. 25 Gentlemen:

Attached is Revision No. 25 to the Limerick Generating Station (LGS), Units 1 and 2, Emergency Plan. This revision is being submitted in accordance with the requirements of 10 CFR 50.54(q),10 CFR 50 Appendix E, and 10 CFR 50.4(b)(5) as a result of changes which were effective on May 21, 1993.

10 CFR 50.54(q) and 10 CFR 50 Appendix E require that changes to emergency plans be submitted within 30 days of such changes. These changes were submitted to the NRC within 30 days by way of controlled copy distribution; however, they were not submitted via docketed correspondence in accordance with 10 CFR 50.4(b)(5).

The delay in j

submitting this revision of the Emergency Plan via docketed correspondence was i

the result of an administrative oversight.

An investigation into this oversight is being conducted to preclude recurrence.

i This revision reflects changes to Table 4.2, " Planning Basis Summary," of the Emergency Plan.

We have evaluated these changes and determined that they do not decrease the effectiveness of the LGS Emergency Plan. Furthermore, these changes have been reviewed by the LGS Plant Operations Review Committee.

If you have any questions or require additional information, please do not hesitate to contact us.

Very truly yours, 9307070101 930630 h

. G. A. Hunger, Jr.

PDR ADDCK 05000352 Director F

PDR v

Licensing Section

(

U.S. Nuclear Regulatory Commission June 30s 1993 Document Control Desk-Page 2 Attachment.

cc:

T. T. Martin, Administrator, Region I, USNRC (w/ attachment, 2 copies)

N. S. Perry, USNRC Senior Resident Inspector, LGS (w/ attachment) t f

k I

4 t

. ?- ):

O LGS EP I

THIS EMERGENCY PLAN SET 1

HAS BEEN UPDATED TO INCLUDE REVISIONS THROUGH REV. 25 DATED 06/93 O

n R-1 REV. 25, 06/93 O

f* straw zoy.

'l LIMERICK CENERATING STATION UNITS 1 & 2 EMERCENCY PLAN

^d PACE CHANCES 1he attached table is considered part of a controlled copy of the Limerick Generating Station Emergency Plan. This material should be incorporated into the Emergency Plan by following the instructions below.

l After the revised pages have been inserted, place the page that follows these I

instructions in the front of Volume 1.

A list of effective pages has also been attached to simplify verifications after revision.

VOLUME 2 REMOVE INSERT PACE REVISION PACE REVISION l Table 4.2 23 11/92 Table 4.2 24 06/93 0

O l

R-2 Rev. 25, 06/93

I LIMERICK CENERATING STATION EMERCENCY PLAN LIST OF EFFECTIVE PAGES VOLUME 1 PACE / DESCRIPTION REVISION NO.

l R-1 thru R-4 Rev. 25 1 thru 10 Rev. 22 0-1 thru 0-2 Rev. 22 1-1 thru 1-4 Rev. 22 2-1 thru 2-4 Rev. 22 3-1 thru 3-7 Rev. 22 Figure 3.1 Rev. 22 Figure 3.2 Rev. 22 Figure 3.3 Rev. 22 4-1 thru 4-9 Rev. 22 Table 4.1 Rev. 22 l

Table 4.2 Rev. 24 f\\

5-1 thru 5-54 Rev. 22 Figure 5.1 Rev. 22 Figure 5.2 Rev. 22 Figure 5.3 Rev. 22 Figure 5.4 Rev. 22 Figure 5.5 Rev. 22 Figure 5.6 Rev. 22 Figure 5.7 Rev. 22 Table 5.1 Rev. 22 6-1 thru 6-25 Rev. 22 Table 6.1 Rev. 22 Table 6.2 Rev. 22 7-1 thru 7-10 Rev. 22 Table 7.1 Rev. 22 Table 7.2 Rev. 22 Table 7.3 Rev. 22 i

Table 7.4 Rev. 22 Table 7.5 Rev. 22 Figure 7.1 Rev. 22 l

R-3

.Rev. 25, 06/93

4 l

~

~

LIMERICK CENERATING STATION.

~

EMERGENCY PLAN (Q.

/

LIST OF EFFECTIVE PAGES (Continued)

PACE / DESCRIPTION REVISION NO.

8-1 thru 8-11 Rev. 22 Table 8.1 Rev 22 9-1 thru 9-2 Rev. 22 Appendix A Rev. 22 Appendix B Rev. 22 Appendix C Rev. 21 Appendix D Rev. 22 Appendix E Rev. 22 Appendix F Rev. 22 VOLUME 2 Appendix C Rev. 21 Appendix H Rev. 21 Appendix 1 Rev. 22 Appendix J Rev. 23 Questions and Responses Rev.18 i

?

Is i

R-14 Rev. 25, 06/93

LGS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 1 of 16) 1.

HAZARDS 'M STATION OPERATION UNUSUAL EVENT 1)

Aircraft crash onsite OR unusual aircraft activity over the site.

2)

Train derailment within site boundary.

3)

Explosion within or near site boundary.

4)

Nearby or onsite release of potentially harmful quantities of toxic, flammable gas or chlorine.

ALERT 1)

Entry of toxic, flammable gases OR chlorine into power block with subsequent habitability problem.

Indicated by:

Visual observation, direct measurement OR notification received by Control Room.

2)

IF both units are in cold shutdown THEN:

Aircraft crash or missile impact on Reactor Enclosure, Control a.

Enclosure, Turbine Enclosure, Diesel Generator Enclosure, Spray Pond Pump House.

3)

Known explosion damage affecting plant operation.

SITE AREA EMERGENCY 1)

Entry of toxic, flammable gases OR chlorine into vital areas, where lack of access constitutes a reactor safety problem.

Indicated bys shift Supervision evaluation a.

AND b.

Visual observation, direct measurement, notification received by Control Room.

2)

IF either unit is not in cold shutdown THEN:

a.

Aircraft crash or missile impact on Reactor Enclosure, Control Enclosure, Turbine Enclosure, Diesel Enclosure or Spray Pond Pump House.

3)

Known explosion causing severe damage to safe shutdown equipment.

GENERAL EMERGENCY N/A 24, 06/93-

~ __

LGS EP TABLE 4.2 PLANNING HASIS

SUMMARY

(Page 2 of 16) 2.

ENVIRONMENTAL UNUSUAL EVENT 1)

Actual earthquake detected by seismic Monitoring System (00C693) at or below operating basis earthquake (.075g).

2)

A tornado is observed within or near site boundary.

3)

A National Weather Service hurricane warning is issued for Montgomery County.

ALERT 1)

Actual earthquake detected by Seismic Monitoring System (OOC 693) beyond operating basis earthquake (.075g).

2)

Tornado strikes: Reactor Enclosure, Turbine Enclosure, Spray Pond Pump House, Control Enclosure, Diesel Generator Enclosure.

3)

Sustained high winds greater than 70 mph as indicated on OBC 699.

SITE AREA EMERGENCY IF either unit is not in cold shutdown THEN:

1)

Sustained high winds greater than 90 mph as indicated on OBC 699.

OR 2)

Actual earthquake detected by Seismic Monitoring System (OOC 693) beyond safe shutdown earthquake (.15g).

GENERAL EMERGENCY N/A

~

l*

24, 06/93

LGS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 3 of 16)

3. LOSS OF POWER UNUSUAL EVENT 1)

Loss of all off-site power greater than 60 seconds.

2)

Loss of all emergency AC power capability for greater than 60 seconds (e.g., offsite power is feeding station, but all 4 diesel generators unavailable) with fuel in reactor vessel.

ALERT 1)

Loss of all offsite power for greater than 60 seconds.

AND Loss of all emergency AC power for greater than 60 seconds.

2)

Loss of al3 safeguard DC power for greater than 60 seconds.

SITE AREA KMERGENCY 1)

Loss of all offsite power for greater than 15 minutes.

AND Loss of all emergency AC power for greater than 15 minutes.

2)

Loss of all safeguard DC power for greater than 15 minutes.

CENERAL EMERGENCY 1)

Loss of all offsite power

AND Loss of all emergency AC power Evacuate 2 mile radius. Evacuate affected AND sector (s) and 2 adjacent sectors for 2-5 Loss of RPV makeup capability

' miles, such that RPV level cannot be maintained above top of active fuel.

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'l

LCS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 5 of 16) 5.

FIRE UNUSUAL KVENT Fires involving permanent plant structures in the protected area lasting 10 minutes or more.

ALERT 1)

Fire which could make any of the following engineered safety (ESF) systems inoperable:

- Class IE Power System

- Safety-Related Equipment Room Coolars

- Drywell Unit Coolers

- MSIV-LCS

- CAC

- RERS

- HPCI

- SGTS

- ESW

- ADS

- LPCI

- Core Spray

- RHR Containment Spray

- RHR Suppression Pool Cooling

- RHR Service Water

- Reactor Enclosure Isolation System

- Habitability & Control Room Isolation

- Primary Containment & Reactor Vessel Isolation Control Systems

- Control Enclosure Chilled Water System 2)

Fire which could make RCIC inoperable.

SITE AREA EMERGENCY Fire which compromises Function of a safety system which is required to mitigate the consequences of an accident OR is required to achieve or maintain safe shutdown AND for which there is no safety grade backup.

i.e.:

- HPCI and ADS

- All low pressure ECCS

- Loss of Suppression Pool Cooling GENERAL EMERGENCY N/A 4

l' 24, 06/93

~

LGS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 6 of 16) 6.

-RADIOACTIVE EFFLUENT RELEASE UNUSUAL EVENT 1)

Report indicates liquid release exceeds Offsite Dose Calculation Manual Section (I) 3.2.2 or 3.2.3.

2)

Calculated site boundary dose rates exceeds Offsite Dose Calculation Manual Section (I} 3.3.2.a or 3.3.2.b.

Enter T-104 and execute concurrently ***

ALERT Calculated site boundary dose rate exceeds ten times Offsite Dose Calculation Manual Section (I) 3.3.2.a or 3.3.2.b.

SITE AREA EMERGENCY

      • Enter T-104 and execute concurrently ***

1)

North Stack Wide Range Accident Monitor reading exceeds 3.4E+06 uC1/sec for 2 minutes per recorder RR26-076 on MCR Panel 00C624 or RM-11 color console, excluding system noise.

2)

Calculated or measured site boundary whole body dose rate exceeds 50 mR/hr for 30 minutes.

3)

Calculated or measured site boundary thyroid dose rate exceeds 250 mR/hr for 30 minutes.

GENERAL EMERGENCY

      • Enter T-104 and execute concurren'ly ***

c 1)

Calculated or measured offsite whole body dose rate exceeds 500 mR/hr.

... PAR ***

2)

Calculated or measured offsite thyroid Evacuate 2 mile radius. Evacuate affected dose rate exceeds 2500 mR/hr.

sector (s) and 2 adjacent sectors for 2-5 miles.

l 3)

Offsite doses are projected to exceed 5

1 Rem Whole Body or 5 Rem Thyroid.

,AR 4)

Actual or potential projected dose Evacuate 5 miles radius, evacuate affected exceeding 5R WB/25R THY.

sector (s) and 2 adjacent sectors for 5-10 miles.

i.

24, 06/93

VAeS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 7 of 16)

7. EVACUATION OF CONTROL ROOM UNUSUAL EVENT N/A ALERT Evacuation of Control Room anticipated or required, with control established at remote shutdown panel.

SITE AREA EMERGENCY Evacuation of Control Room AND control of shutdown systems not Esfablished from remote shutdown panel in 15 minutes.

GENERAL EMERGENCY N/A 1v e

O O. u.

i,

LGS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 8 of 16) 8.

DAMAGE 'ID FUEL UNUSUAL EVENT 1)

Steam Jet Air Ejector Discharge radiation monitor exceeds 2.1E+04 mR/hr.

2)

Steam Jet Air Ejector Discharge radiation monitor has an unexpected increase of 4000 mR/hr over 30 minutes.

3)

I-131 dose equivalent in reactor coolant exceeds 4 uci/g or exceeds 0.2 uCi/g for more than 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> during one continuous time interval.

ALERf 1)

Steam Jet Air Ejector Diccharge radiation monitor exceeds 2.1E+05 mR/hr.

2)

I-131 dose equivalent in reactor coolant exceeds 300 uCi/g from sample AND main steam line high-high radiation with resultant scram.

3)

Spent fuel damage resulting in a refueling floor area ventilation exhaust monitor alarm.

4)

Containment Post LOCA Radiation monitors greater than 1E+02 R/hr.

SITE AREA EMERGENCY 1)

Major damage to spent fuel:

a.

Observation of major damage to spent fuel OR b.

Eater loss below fuel lavel in spent fuel pool.

2)

Containment Post LOCA Radiation Monitors greater than 1E+03 R/hr.

GENERAL EMERGENCY D/W Rad >1E+04 R/hr

with containment intact.*

l Evacuate 2 mile radius, evacuate affected sector (s) l D/W Rad >5E+04 n/hr and 2 adjacent sectors for 2-5 miles, with containment intact.*

d

  • IF release is in progress OR containment failure imminent THEN PAR as indicated above Evacuate 5 mile radius, evacuate affected sector (s) but shelter may be indicated for those areas and 2 adjacent sectors for 5-10 miles.

that cannot be evacuated before plume arrival.

l*

24, 06/93

ifs EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 9 of 16) 9.

INSTRUMENT OR COMMUNICATION FAILURE UNUSUAL EVENT 1)

Loss of all Main Control Room Communication.

2)

Significant loss of assessment capability in Main Control Room.

a.

Indicated by simultaneous loss of plant process computer AND ERFDS for greater than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ALEMT Loss of all annunciators.

SITE AREA EMERGENCY All annunciators lost and plant transient initiated or in progress.

GENERAL RMERGENCY N/A 5

~

l' 24, 06/93

LGS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 10 of 16)

10. SCRAM FAILURE UNUSUAL EVENT N/A ALERT Failure of the Reactor Protection System to automatically initiate and complete a scram as indicated by APRM's greater than 4%, one minute after scram signal has occurred OR 5hould have occurred.

! SITE AREA EMERGENCY Transient requiring manual or automatic standby liquid control system injection.

(Due to high Suppression Pool temperature in T-101 or RRCS Setpoints exceeded.)

CONERAL EMERGENCY Transient requiring manual or automatic

standby liquid control system injection (due to high S/P temp or RRCS setpoints exceeded).

Evacuate 2 mile radius, evacuate affected sector (s) and 2 adjacent sectors for 2-5 AND miles.

The reactor is not made or expected to be made subcritical 45 minutes after SLC injection attempt 53.

l' 24, 06/93

LGS 2P TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 11 of 16) 11.

DOUNDARY DEGRADATION /LOCA UNUSUAL EVENT 1)

Failure of main steam relief valve OR ADS valve to close following reduction of applicable pressure.

2)

Reactor coolant leak rate exceeds 30 gpm total leakage.

a.

Indicated by surveillance test report.

ALERT 1)

Scram with leak.

Indicated by:

a.

Reactor level less than -129" OR unknown AND b.

Containment pressure greater than 1.68 psig.

2)

Containment pressure greater than 10 peig.

3)

D/W floor drain sump discharge >50 gpm for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

4)

High airborne contamination in reactor enclosure indicated by RE exhaust RAD Monitor A/B or C/D Hi-Hi.

5) 1000 fold increase in general area radiation levels as reported by Health Physics.

6) 5000 MPC airborne activity excluding isotopes with half lives less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> as reported by Health Physics.

SITE AREA EMERGENCY 1)

Scram with LOCA indicated by:

a.

Reactor level less than -129" OR unknown.

AND b.

Containment pressure greater than 10 psig and increasing.

2)

Main steam line break _outside containment without isolation indicated by:

a.

High Main Steam Line Flow (108.7 psig)

OR b.

High Steam Tunnel Temp (165 deg F)

OR c.

Main Steam Line Low Pressure (756 psig) j' 24, 06/93

LGS EP TABLE 4.2 PLANNING BASIS StHD4ARY (Page 12 of 16) 11.

BOUNDARY DEGRADATION /LOCA GENERAL EMERGENCY 1)

Scram with LOCA l

AND ECCS unable to maintain reactor water level as indicated by:

Failure to bring Reactor level above -161" after three minutes, l

a.

b.

AND Containment pressure greater than 20 psig.

2)

Scram with LOCA and D/W Failure.

Indicated by:

Reactor level less than -129" OR unknown.

AND l

Unexpected drop in D/W pressure or other evidence of D/W failure.

Evacuate 2 mile radius, evacuate affected sector (s) and 2 adjacent sectors) for 2-5 miles.

I l

l

LGS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 13 of 16) 12.

UNUSUAL SHUTDOWN UNUSUAL EVENT 1)

Shutdown initiated as required by any of the following Technical Specification limiting conditions for operation:

LCO 3.4.3.2 Failure to meet minimum reactor coolant system leakage limits.

LCO 3.4.6.1 Exceeding reactor coolant system heatup or cooldown limito.

LCO 3.5.3 Failure to meet suppression chamber operability requirements.

LCO 3.6.1.1 Failure to maintain primary containment integrity.

LCO 3.8.1.1 or 3.8.3.1 Failure to meet minimum A.C.

electrical power requirements while operating.

2)

Scram and automatic ECCS initiation with discharge to the vessel as a result of a valid aignal.

3)

Exceeding any Technical Specification safety limits.

ALERT N/A SITH AREA EMERGENCY N/A GENERAL EMERGENCY N/A m#

p

. 24, 06/93

4 LCS EP TABLE 4.2 PLANNING BASIS

SUMMARY

(Page 14 of 16) 13.

LOSS OF HOT OR COLD SHUTDOWN CAPABILITY UNUSUAL EVENT N/A ALERT Complete loss of ability to establish AND maintain plant in a Cold Shutdown condition.

Symptomized by:

Inability to establish Reactor Coolant Temperature of less than 200 degrees F in a a.

timely manner OR b.

Loss of all means of Primary and Alternate Decay Heat Removal when shutdown, such that Reactor Coolant Temperature cannot be maintained below 200 degrees F.

SITE AREA EMERGENCY Actual inability to reduce Reactor Coolant System Temperature while the plant is Shutdown.

Indicated by:

Inability to establish reactor coolant temperature less than 200 degrees F in a timely a.

manner AND b.

Suppression Pool Temperature greater than 120 degrees F and rising.

Inability to maintain Reactor level a.

greater TAF Evacuate 2 mile radius, evacuate affected OR sectors (s) and 2 adjacent sectors for 2-5 miles, substantial Fuel damage has occurred AND b.

Inability to maintain Suppression Pool Temperature below upper limit of Heat Capacity Curves (SP/T-1 and SP/L-1) on T-102 procedure.

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f (Page 16 of 16)

TERMS AND DEFINITIONS SECURITY A security threat as illustrated by Plant parameters or other condition attempted entry or sabotage with the EMERGENCY ACTION which if met or exceeded the COMPROMISE intent to gain physical control of the LEVEL (EAL) emergency classification level and plant.

requires a declaration of emergency.

Events in progress or have occurred, that OPERABLE System, sub-system, train, UNUSUAL EVENT indicate a potential degradation of the component, or device, and all level of safety of the plant.

No auxiliaries required for their releases of radioactive material operation, is capable of performing requiring offsite response or monitoring its specified function in the are expected unless further degradation intended manner.

of safety systems occurs.

ALERT Events in progress or have occurred that Recommendation made to the state of involve actual or potential substantial PROTECTIVE ACTION action to be taken to avoid or degradation of the level of safety of the RECOMMENDATIONS (PAR) reduce projected dose to the plant.

Any releases of radioactive

public, material are expected to be limited to small fractions of the Environmental Protection Agency (EPA) Protective Action Guidelines (PAG) exposure levels.

SITE AREA Events in progress or which have occurred An estimate of radiation dose which EMERGENCY that involve actual or likely major PROJECTED DOSE affected individuals could failures of plant functions needed for potentially receive if protective protection of the public. Any releases actions are not taken.

of radioactive material are not expected to exceed EPA PAG exposure levels except near site boundary.

Events in progress or which have occurred GENERAL EMERGENCY An act conducted by a person or that involve actual or imminent SABOTAGE persons with the intent of damaging substantial core degradation or melting or impairing the operation of the with potential for loss of containment

plant, integrity.

Releases of radioactive material can be reasonable expected to exceed EPA PAG exposure levels offsite for more that the immediate site area.

(,J. 24, 06/93 p

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