ML20204F863
| ML20204F863 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 03/20/1987 |
| From: | Denise Wilson IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML112240927 | List: |
| References | |
| EPIP-1.1, NUDOCS 8703260287 | |
| Download: ML20204F863 (45) | |
Text
TRANSMITTAL / ACKNOWLEDGEMENT
, MEMORANDUM f~~) 0"Y Ma ch 2 .' 1 7
SUBJECT:
EMERGENCY PLAN IMPLEMENTING PROCEDURES MANUAL X Procedures ( NA Series) Manual No . f Revisions to your controlled copy of the manual, as checked above, are attached.
As indicated below, please remove and discard the supers.eded material and insert the revised material, or perform the changes as directed herein.
REMOVE INSERT MANUAL CONTENTS Rev Date Rev Date Revision Control Sheet 40 12/19/86 41 3/20/87 EPIP 1.1 (DCF87-P-0315) 7 11/10/86 8 3/20/87 O
L ,)
P5ase acknowlodge that the above action has been taken by signing below end returning this memorandum to lowa Electric Light & Power Co., P.O. Box 351, Cedar Rapids, Iowa 52406, Document Control of the following organization: ,
Design Engineering Department X OAEC Support Services ,
Nuclear Licensing & Nuclear Generation Olvision Emergency Planning Department
{} I have inserted the above revisions in th'e Manual.
1
\s' l
l NG-013X* Rev. 4 Signed Date (106.4) i 0703260PB7 070320 PDR ADOCK ODOOO331 F PDR
REVISION CONTROL SHEEI Paga 1 cf 1 EMERGENCY PLAN IMPLEMENTING PROCEDURES Revision No. 41 Revision Date: 03/20/8/
PROC. DATE REV. PROC. DATE REV. PROC. DATE REV.
INDEX 4/23/85 15 4.1 DELETED 1.1 03/20/87 8 4.2 //14/83 1 1.2 11/3/86 9 4.3 5/2//83 2 1.3 12/19/86 1 4.4 DELETED 4.5 3/15/83 1 2.1 12/19/86 5 2.2 11/3/86 / 5.1 DELETED 2.3 DELETED 5.2 10/15/84 2 2.4 3/30/85 3 C 2.5 11/10/86 3 6.1 6.2 6/16/86 DELETED 4
2.6 5/20/86 2 6.3 DELETED 2.7 7/25/83 0 6.4 DELETED 3.1 12/19/86 4 7.1 12/6/83 2 3.2 3/2//86 6 3.3 11/10/86 2 3.3a DELETED 3.3b DELETED O
EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Pag 2 1 of 43 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 8 Date$R 2 0198L ,
- 1. 0 PURPOSE This procedure provides guidelines for determination and revision of an energency classification.
2.0 APPLICABILITY This procedure shall be used by the Operations Shift Supervisor and the Emergency Coordinator.
3.0 RESPONSIBILITIES 3.1 Operations Shift Supervisor / Emergency Coordinator 3.1.1 Evaluate plant conditions to determine if an EAL has been reached.
3.1.2 Ensure requisite notifications are made, per EPIP 1.2.
3.1.3 For events classified as an ALERT or greater, initiate assembly and accountability of all DAEC personnel, per EPIP 1.3.
3.1.4 Review and approve the energency classification.
3.1.5 Ensure activation of the Emergency Response Organization, as required.
4.0 INSTRUCTIONS 4.1 Emergency conditions are classified in an ascending order of severity as follows:
a) N0f!FICAT10N OF UNUSUAL EVENT (Condition Classification A) b) ALERT (Condition Classification B) c) SITE EMERGENCY (Condition Classification C) d) GENERAL EMERGENCY (Condition Classification D)
The above classifications are defined at the top of each page of Attachment 1. " Emergency Action Levels".
4.2 When a suspected emergency condition occurs, the Emergency Coordinator shall make the initial analysis and determination of the classification, referring to Attachment 1, " Emergency Action Level" (EAL) and Attachment
- 2. " Emergency Action Level Classification Guidelines". The Emergency O Coordinator shall review the classification for concurrence or revision, either when notified of the condition, or upon arrival at the site.
, s EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Pag 2 2 of 43
^
DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 8 Date .NAR 2 0198F I
G l NOTE The symptoms listed under "Possible Indications" in Attachment 2 may serve as possible indicators of an EAL; all inclusive.however, the list should not be considered as 4.2.1 Attachment 1 contains three flow charts covering Emergency Action Levels, formatted in three categories; Radiological, Operational, l
and Other, 4.2.2 Attachment 2, " Emergency Action level Classification Guidelines",
is arranged according to the type of event, plant condition, possible indications and Emergency Action Level codes.
4.2.3 To determine an EAL, the Emergency Coordinator shall:
- a. Categorize the general type of event, referring to Attachment 1 for quick reference, as appropriate.
- b. If necessary refer to Attachment 2 to identify l
instrumentatlonorindicatorsusedforinterpretationof I plant conditions.
- c. Identify the specific plant condition
- d. Declare the emergency classification.
4.2.4 Upon declaring the emergency classification, the event, the time declared and the action (s) taken shall be logged in the Shif t Supervisor's Log.
4.3 Other events not specifically included in this procedure may be classified as a NOTIFICATION OF UNUSUAL EVENT, ALERT, SITE EMERGENCY or GENERAL EMERGENCY at the discretion of the Emergency Coordinator. The l
i primary consideration for classification of these events shall be to protect the health and safety of site personnel and the pubitc.
4.4 Notification and activation of the Emergency Response Organization to the extent required for the classification shall be accomplished as follows:
l 4.4.1 The Emergency Coordinator shall initiate the notification process as prescribed in EPIP 1.2, " Notification".
4.4.2 For all events classified as an ALERT or greater, the Emergency Coordinator shall initiate plant assembly and accountability as prescribed in EPIP 1.3, " Plant and Site Evacuation".
4.5 Reclassification shall be authorized by the Emergency Coordinator. The Emergency Response and Recovery Director should be consulted, if
\ possible, prior to upgrading, or downgrading to, or from, a SITE EMERGENCY or GENERAL EMERGENCY.
l l
i t EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 3 of 43 DETERMINATION OF IHE EMERGENCY ACTION LEVEL Revision 8 Datel54R'2 01987 O
4.5.1 Reclassification should be based upon the guidance provided in Attachnents 1 and 2.
4.5.2 The Emergency Coordinator should consult with the following personnel during such evaluations:
- a. Site Radiation Protection Coordinator
- b. Control Room Coordinator
- c. Technical Support Center (TSC) Supervisor
- d. Emergency Response and Recovery Director 4.5.3 The Emergency Coordinator shall ensure that off site agencies are notified of the reclassification in accordance with EPIP 1.2. If the EOF has been activated, this responsibility shall be assuned by the Emergency Response and Recovery Director.
4.5.4 Reclassification of an event shall be docunented in the Shift Supervisor's Log or the TSC Log as appropriate.
4.6 As plant conditions change, the Emergency Coordinator shall ensure Os that plant status is monitored in order to change the emergency classification, as appropriate.
4.6.1 Criteria for Downgrading As plant conditions change, consider:
- 1. The probability that plant conditions will continue to improve.
- 2. The probability that plant conditions might worsen, thereby necessitating upgrading the energency class once the energency has been downgraded.
- 3. The need to staff all or some of the energency response facilities.
! 4. Evaluating existing conditions with respect to the criteria established for each emergency class per the EALs in this procedure.
! 5. The control or termination of non-routine releases of
- radioactive material to the environment.
- 6. The control or cessation of any fire, floort, earthquake, or similar energency conditions.
l 7. The specified corrective action has been taken or the plant has been placed in the appropriate operating mo,de.
l
, 3 EMERGENCY PLAN IMPLEMENTING PROCEDURE EPIP - 1.1 Page 4 of 43 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 8 Dat)AR 2 01987
- 8. All required notifications are completed.
- 9. The TSC technical staff has evaluated the plant status with respect to the Technical Specifications and recommends downgrading the emergency classification.
4.6.2 An emergency condition can be considered resolved, and a recovery organization established (if necessary) when the following guidelines have been met or addressed:
- 1. Existing conditions no longer meet the emergency classification criteria and it appears unlikely that conditions will deteriorate further.
- 2. No surveillance relative to offsite protective actions is needed, except for the control of foodstuffs, water, and offsite contamination, or environmental assessment activities.
- 3. Radiation levels in affected in-plant areas are stable or decreasing to below acceptable levels.
', 4. Releases of radioactive material to the environment greater
.i than 10 times 10 CFR 20 Appendix B limits are under control or have ceased.
- 5. The potential for an uncontrolled release of radioactive material is at an acceptably low level.
- 6. Containment pressure is less than 2 psig operating band.
- 7. The reactor is in a stable safe shutdown condition and long-term core cooling is available as required.
- 8. Any fire, flood, earthquake, or similar energency conditions are controlled or have ceased.
- 9. Any contaminated / injured personnel have been transported offsite, and are receiving appropriate medical care.
- 10. All emergency action level notifications have been completed.
- 11. Of fsite conditions will not limit access of personnel and support resources.
- 12. Discussions have been held with the Nuclear Regulatory C's Commission, state and local organizations (with FEMA input),
G' and agreement has been reached to terminate the emergency.
EPIP -
1.1
- ' EMERGENCY PLAN IMPLEMENTING PROCEDURE Page 5 of 43 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 8 DatqMAR 2 0 1987
,e S V
- 13. The TSC technical staff has evaluated the plant status with respect to the Technical Specifications and concurs with termination of the emergency.
5.0 REFERENCES
- 1. Duane Arnold Energy Center Emergency Plan
- 2. NUREG-0654, Revision 1.
- 3. DAEC Technical Specifications
- 4. Updated Final Safety Analysis Report 6.0 ATTACHMENTS
- 1. Emergency Action Levels
- 2. Emergency Action Level Classification Guidelines Approved by: nidh. lh ErAergency panningCo5rdinator Date 3. Et/-f 7 Approved by: M Date #dYO Manager, Nuclear Licensing and Emergency Planning Approved by: 8N W/4/. Date ~2/t 4/f 7.
Operations Supervisor Reviewed by: .
22m, Date I ff!87
' 5 OperationsfCdndittee Ch' airman Approved by: N Date 2 Abd7 '
Plant Superintendent - Nuclear O
l.
i EMERGENCY PLAN IWLEENTING PROCEDURE EPIP - 1.1 l Page 6 of 43 DETERMINATION OF THE EMERGENCY ACTION LEVEL Revision 8
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C-2 O this colasta ney serve as a possible NWL SITE MwEW Indication, tast ther are act necessarily EVEET ALERT EEGO E*IE G C EVENT TYPE PLANT CONDITIONS suf fielent cause to detereine an EAL. LOCA Reactor Coolant System lask rate Lap Pug timers on TC21 resulting in one or Al greater than either the unidentiff e:: more of the f oll osi ng a la res e 1034 (5 goal or combined Tech Spec 11elts "Drywell Floor Druin kap h1 Lesk* (25 gas), but less than 50 gom.
- Dry. ell Eauf pnent Drain Sug hi Leek" a a nc/cr W
3 One or more of the t olI o.1 mg a la rus cn ICD 4 W "DryweII Floor Drain km hi ht level
- x "Drywell Eauf pment Drain Leo ni ni level =
S W 5 "DryweII Ecut;ssent Drain kw h1 Teep * [ and g g Flos rate calcolation tram FlQ 3707 on 1019 vs
- c. time is grester than 5 gom 9 9 1 O C The f l os rate calculati on f rom Fig 3738 on W IC19 vs time a dded to f t o rate calcs tation
{ g g f ran FlQ 3707 cn IC191s greater tm o 25 gpe. w w J g Other cassible indications 3 g Dry ell Tomeratare Incrosse as Ind cated on TR 4383 A, B, & C cn IC29 5
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LOCA LOCA grester than sekoap capacity ECCS systers and etwer aus11able se kaap C1 (Conti rwed) capacity uredle to selatain/ recover RPr ester level as InScated on LI 4539, 4543 on 1005 and LI 4565, LR 4566 on TCD3.
> Cther ladestices to const e g "j lacreasing CryweII Pressare as i nd cateJ ty:
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a No 4 Q-5E rg g C Note: The instrweentation I!sted in this column may serve as a possible U%'SUAL SITE GENERAL cL eo o e i n di cati on, tut they are aat necessar1Iy EWENT ALERT EMECE C EME%EC
" ' " EVENT TYPE PLANT CONDITIONS suf f!cient cause to cetermine an EAL.
LOCA LOCA, with f allare of ECOS to RDY level decrossin2 and less than + 46.5 as C1 (Conti nued) perfore. Loss of contal nnent Indicated on LI 4539 and 4540 on TCC5 Integrity projected, and RPV pressure decreasing and less than 450 psig as Indicated on Pt 4563, 4%4, 4%5, PR 4563,
-.J a n d 4564 on TCDS w
> or g '^j Roy level less than + E.5" as Indicated on cr o LI4565 and LR 4566 c o and C Containment pressure projected to exceed 56 CL S psig as Indicated on l y a) Ccreuter Points B103 and B104 e o c) PR 4334 and 4385 on 1029 z
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w w a) Drywell pressare >10 psig f or more then 30 w et rutes witnast Containnent Spray I r ca pa bi li ty.
= m b) TR-4333 A, B and C on "~29 , < o c) TR-5713 A, B and C cn TC25 1
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, MSLm J.
_ CE E R A4
- . l ,
T SE t ; Eu e m m ES s I CC t iT H
' EE 8
0T C CT s u a { g (( t j, E Gm u MG t L , EE 0E EV N LE - le L H
,
- 4 ,
WE L
],
S s E ~
N m e $
- EPIP 1.1 o ATTACmENT 2 EMERGENCY ACTION LEVEL
% co cq PAGE 6 of 35 CLASSIFICATION GUIDELINES e C 8 e-4 O M Note: The Instrumentation listed in SO c.
g ] to c) as g this column rey serve as a possible Indication, but they a re not necessari ly UNUSUAL SITE EVENT ALERT EMERGENCY EMERGENCY GENERAL W 0- " O EVENT TYPE PLANT CONDITIONS suf ficient cause to determi ne a n EAL. LOCA LOCA, contai nment perf orna nce is Containment pressure projected to exceed 56 D2 (Conti nued) unsuccessf u l psig as Indicated on a) Corvuter Points B103 and B104 b) PR 4384 and 4385 on 1C29 or Drywell temperature prVected to exceed 281*F g as i ndicated by: us a) Drywell pressure > 10psig f or more than 30
$' minutes withojt Containment Spray y ca pa bi lity
- ) z b) TR-4383 A,B and C on IC29 O 3 c) TR-5713 A and B on 1C25 8 $
a nd y RDV level decreasi ng and less than +46.5" as
>- Indicated on Li 4539 and 4540 on 1C05 g
z z and [ Z
$ RPV pressure decrest.Ing and less than 450 pstg
$ as Indicated on PI 4563, 4564, 4565, PR 4563
$ and 4564 on IC05 and
~
Potential exists f or loss of ECCS dae to a) Torus level decressing as Indicated on Z LL-g TR4386 A and B on IC29 J or
" b) Torus wster terverature increasing and 8
y [ greater than 170*F as indicated on TR 4386 z < A and B on TC29
$ E $ h Msi n Steam Ms i n steam 11 ne break wi th MSi v Group I 1 solation caused by Steam Tunnel h1 B2
{ f Line Break ne lfunction causing leakage. temperatu re g Ou+stde g Secone ry Turbi ne bui l di ng h1 toeverature Contai nment g Msi n Stearn Li ne h1 F l or a nd/or (see next page) l
ts Q h EPIP 1.1 ATTACHMENT 2 EMERGENCY ACTION LEVEL O
$m PAGE 7 of 35 Ct.ASSIFICATION GUIDEllNES in C M I W O 4
- M g g .,_ e Note: The Instrumentation listed in gggg c. m o this column my serve as a possible UNUSUAL SITE GENERAL w Indication, but they a re not necessa ri ly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf f1cient cause to determine an EAL.
% 1 n Steam Mst n steam line Dreak w1th MSlY Ra dia tion levels do not decrease back to near Line Break ro lfunction causing leakage, norm t f ollowing Isolation as Ind1cated on Outside (Conti nued) Tur91ne Bl dg ARM's on 1C11 Contai nment W1 i Steam 11ne rad monitors RC 4448A,B,C,D (Conti nued) IC36 and RR 4448 on TCO2 g Reactor Building ventilation Exhaust Rsd w Monitoring System y a) Nornel Ibnge Monitors 4,6 and 8 g Z g b) High Range Monitors 3,5 and 7 w - and/or 8 C Steam tunnel temeratures or Turbine Bldg g 4 temperatures do not decrease af ter 1 solation, g
=
]
z Possible Indicators mi n Stean Li ne f i os nn y st i l l exist on [ c F1 4408, 4409, 4410, or 4411 on ICOS a f ter
- y. "
w
- c I solati on.
w w a % 1 n Steam 11 ne brea k wi th oat Groep I 1 solation caused by C2 9' 1 sola ti on. Steam Tunnel n1 Temperature a larm on 1C35 a nd/or g 'g Tu rbi ne B l dg h 1 Temp e ra tu re a la rm on 1C05 a and/or C-5 Ma i n Steam L1 ne h1 F l ov a la rm on 1C05
] [ . and g g The 2 MSIV's on one or more stasm lines fall to e - c l os e. Msi n Stean Li ne Fl ow wi l l renn i n Sigh @ h W
as Indicated on FI 4408, 4409, 4410 or 4411 g er, 1C03 f or af f ected steam lines. w o Other Possible Indications and Inf orwetion The Steam Tunnel and/or Turbine BI dg Tegeratures will remsin h1 f ollowing attemted I solati on. (see next page) O O O
N m
- 8 EPIP 1.1 ATTACHMENT 2 EMERGENCY ACTION LEVEL O PAGE 8 of 35 CLASSIFICATION GUIDELINES M
O CD OQ
~ N to e A 9 e-4 O
'u, Note: The f rstrumentation listed in this column my serve as a poss1ble UNUSUAL SITE GENERAL S$$[ i ndi cot t on, but they are not necessari ly ggyy EVENT TYPE PLANT CONDITIONS suf ficient cause to determine an EAL.
EVENT ALERT EMERGENCY EMERGENCY h l n Steam Msi n Steam li ne break without Rx vessel pressure will decrease rapidly as Line Break isolation (Continued) Indicated by P1 4563, 4564, 4565, Ou tsi de PR 4563, 4564 a nd PR 4542 on 1C05. Contai nment (Conti nued) RX vessel level my be hard to mintain; j radiation levels and releases my require a
> higher emergency level.
w w J cr i 8 5 U I Envi ronmenta l Al rborne of fluents exceed As reported by Radiation Protection Department A2 O N Releases 10 CFR 20 Appendix B limits. based upon the results of are lyses conducted. ' 1 y (Related to Airborne Ef fluent Release Indicators g g 10CFR20) Turbine Bldg. Ventilation Exhaust Rad Monitor System I
.-. w
- l z $ a) Noral Range Monitor 2 b) High Range Monitor 1 M y ,
j W Reactor Bldg Ventilation Exhaust Rad Monitor l System j g W r a) Norml Range Monitors 4,6&8 i g b) H1g1 Range Monttors 3,5&7
=
c:t O Of f Gas Stack Rad Monitoring System N Z a) Norel Range Monitor 10 x 3 b) Hig.i Rsnge Monitor 9 N k Alrborne ef fluents greater than 10 As repoded by Rsdlation Protection Dapartment B3 l g ce r times 10 CFR 20 Appendix B limits. based upon the results of analyses condJcted, d W b Airborne Ef f luent Release Ind1cators l [ O
- ', . (Same as above)
{ l l O O O
m 5cn
~
4 EPIP 1.1 O ATTACt94ENT 2 EMERGENCY ACTION LEVEL D . co CQ PAGE 9 of 35 CLASSIFICATION GUIDELINES
.: e i D54 M - Note: The Instrumentation listed in
- o. e .$ as this column ney serve as a possible UNUSUAL SITE GENERAL
[ uJ
,n 0-oc o PLANT CONDITIONS Indication, but they a re not necessarily EVENT ALERT EMERGENCY EMERGENCY suf ficient cause to determine an EAL.
EVENT TYPE Envi ronmenta l Liquid D1scharge Et fluents greater As reported by Radiation Protect 1on Department A3 Releases thar.1(EFR20 Appendix B limits, based upon the results of analyses con &cted. (Related to 1(EFR20) L1 quid Ef fluent Reiease Indicators (Conti nued) Liquid Process Rad Monitors - a Pa nel 1C10** ( Ala rm H1) y Ra diation Rate Meters
- w 1997 - RHR Service Water - (H1 Alarm)
$ 3972 - Fb dwaste - (H1 Ala rm)
@ @ 4767 - Service Water - (H1 Ala rm) l W p Radiation Recorders
- o o 4820 - Reactor Buildi ng Closed
' E >- Cooling eter O N p a 5 $ L1 quid Discharge Ef f luents greater As reported by Radiati on Protection Department B4 [ J 6 than 10 times the 1(EFR20 Appendix based upon the results of analyses conected. B limits. S
~
$ Llould Ef fluent Release Indicators L1qu id Process Ra d Monitors -
y 'o- Pa nel 1C10** ( Ala rm H1) J 7 Ra diati on Ebte Meters
- o 1997 - RHR Service Water - (H1 Alarm) o [ 3972 - Eb owaste - (H1 Ala rm) 5 @ 4767 - Servi ce Water - (H1 Ala rm) c.D = Fb diation R6 con ders' g &
W 4820 - Reactoi Buildi ng Closed Cooli ng % ?e.-
, g t w l O
- These meters and recorders indicate the existence of a possible problem. Actua l conditions are determined by sample are lysis.
** This Instrumentation only directs your attention to 10CFR20 Ilmits and the need to take a sample to actually determine plant condi ti ons.
i O O O
N m <n
- SD EPIP 1.1 ATTACtNENT 2 EMERGENCY ACTION LEVEL
-. o co PAGE 10 of 35 CLASSIFICATION GUIDEllNES ca
.-e CO C' CC e & O 4 ,
'"m 5
- n. c) - 4)- Note: The Instrumentation listed in
[ $$% m Q- % O this column my serve as a possible Indication, but they are not necessarl ly UNUSUAL EVENT SITE ALERT EMERGENCY EMERGENCY GENERAL EVENT TYPE PLANT CONDITIONS suf f1cient cause to determine an EAL. Envi ronmenta l Measured dose rates and estimted NOTE C3 Releases dJration of release Indicate Hea lth Physics personnel woul d take radiation (Related to Integrated dose at Site Boundsry (or rea di ngs a t the si te boJ n ds ry a nd f u rther EPA PAGs) beyond) shall be between 1000 and downwi nd as appropriate. The dose rates they a 5000 mrem, would find would be multiplied by the y est1mted dJration of release, as determined W by the Emergency Coord1 rutor, and a n
$ Integrated dose would be obtaIned f or mch l@ $ l oca ti on. If this dose f ell withIn the range l w p of 1000 to 5000 mrem at any location, then ' o o class 1tication C-3 wou t d apply.
e < Q-3 e u
= Z e -e LLJ y w 5
i:J e r w z Z LL-
- e o d g t
m z g .-e
' cr: E i w
$ b Q
t 4
?
O O O
co Q 522 EPIP 1.1 O ATTACrNENT 2 EMERGENCY ACTION LEVEL I co N PAGE 11 of 35 CLASSIFICATION GUIDELINES A cc e Co o., E c3 - c; Note: The Instrumentation listed in { *
,, $% this column my serve as a poss1ble UNUSUAL SITE GENERAL W C- E O Indication, but they are not necessari ly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf fic!ent cause to determi ne an EAL.
1 Envi ronmenta l Calculated dose rates and estimeted NOTE C4 l Releases dJration of release Indicate Personnel using either the nanua l or (Related to Integrated dose at Site Bounery (or conputerized method of dose assessment wou t d EPA PAGs) bayond) sha ll be between 1000 and calculate a projected release rate f or the a (Conti nued) 5000 mrem. site boJnds ry and ve rlois other dornw1nd y l oca ti ons. The dose rates they would find W woul d be mu ltipiled by the estimated dJ rati on e of release, as determined by the Emergency W
$ Coord1 mtor, a nd a n I ntegrated dose wcul d be obtained f or each locati on. if this dose fell l
[ with1n the range of 1000 to 5000 mrem at any o O locati on, then classi ficati on C-4 woul d apply. e o Z
] High Radlologica l Indications: Of fgas stack rolese rate = KAMAN Ch 9 & 10 C25
>- e p lu s s ta ck f l or y $
E Of fges stack release rate of 1.4 t o Rector / Turbine building vent release rate = y w 53 C1/secg KAMAN Ch 1-8 plus vent f lov
-J g Reactor / Turbine Building vent Of fgas monitor rea ding = KAMAN Ch 9 & 10 S I rolese rate of 9.5 x 10-5 to.185 Rea ctor/Tu rbi ne bu i l di ng ve nt moni t or rea di ng C1/sec or = KAMAN Ch 1-8 Q 'o Of fges Ent tor reading of .75 t o 28 Drywell monitor readi ng = Instrument RIM-9134A l g g pci/cc or &B o Rea ctor/Tu rbi ne bui l di ng vent Torus monitor rea di ng = I nstrument RIM-918% &
U [ monitor reading of 5 x 10-5 to 2 x B
! Z
@ 104 pct /cc g g y Drywell monitor rea ding of 800 to g g 3,000 R/hr g Torus monitor reading of 1.4 to l
t r
!w t
$ 50 R/h r.
t i o O O O _ - _ - _ - _ . _ . _ . -__ - - _ _ _ ~ _ - - _ . _ - - - _ - _ - - _ _ -
N m $
*
- EPlP 1.1 ATTACMENT 2 EMERGENCY ACTION LEVEL
% O PAGE 12 of 35 CLASSIFICATION GUIDELINES M O CO y s
N Note: The Instrumentation 11sted I n O C' this column my serve as a possible UNUSUAL SITE GENERAL
' " y- Indication, but they a re not necessari ly EVENT ALERT EMERGENCY EMERGENCY g y, EVENT TYPE PLANT CONDITIONS suf ficient cause to determi ne an EAL.
- cn > u ci- 9 e e En vi ronmenta l Nesured dose rates a nd estimated NOTE D3
* *
- Releases duration of release Indicate Health Physics personnel would take ra diation (Related to I ntegrated dose at Site Bounds ry rea di ngs a t th e s i te b oJ n ds ry a n d f u rther EPA PAGs) (or beyon d) sha l l b g reater tha n dcwnwi nd as appropriate. The dose rates they (Conti nued) 5000 mrem, would f1nd would be multlpfled by the est1mted dJration of relasse, as determined by the Emergency Coordinator, and an integrated dose wouid be obtained f or each locatlon. If this dose f ell was f ound to be in excess of a 5000 mrem at any location, then classification y D-3 wou l d apply.
w w J NOTE D9 O z O Calculated dose rates and estleted Personnel using either the enual or aJration of release Indicate conputertzed method of dose assessment would U o [ O Integrated dose at Site Boundsry calculate a projected release rate f or the site
# (or beyond) sha l l t e g reater tha n bou nds ry a nd va ri cus other dcw nw i n d l oca ti ons.
E > 5000 mrem. The dose rates they would f1nd would be multiplied by the estimated dJration of the w release, as determined by the Emergency
- Coordi nator, and an Integrated dose woul d be
$ $ obtained f or each location, if this dose was g y w
f cund to be in excess of 5000 mrem at any locati on, then classI fication l>-9 woul d apply. w J S' High RadlologIcal Indications: Of fgas stack release rate = KAMAN Ch 9 & 10 D10 Of fgas stack rolesse rate of > 53 plu s sta ck f l os z u_ C1/sec or- Reactor / Turbine building vent release rate =
< O Reactor bullding vent relosse rate KAMAN Ch 1-8 p lus vent f icw d =
O of >.185 Cl/sec or Of fgas monitor rWding of Of fgas monitor rea ding = KAMAN Ch 1-8 Drywell monitor read 1ng = Instrument RIM-9184A U [ > 28 pel/cc or &B z < Reactor Bul Eng vent monitor Torus monitor rea ding = I nstrument RIM-9185A & y 3 reading of > 2 x 10* pcl/cc or B cr: E Drywell monitor readi ng of Rea ctor/Tu rb1 ne bu t I dt ng vent monitor rea di ng = i$w w l > 3,000 R/hr or - KAMAN Ch 1- 8 l [ Torus monitor Teadi ng of > 50 P/hr l o 4 l O O O
I 1 i ts I m
~
EPIP 1.1 ATTACMENT 2 EMERGENCY ACTION LEVEL o PAGE 13 of 35 CLASSIFICATION GUIDELINES M O CO (\1
# E l ~ c-
! I N O l' E - Note: The Instrumentation listed I n Q- ggS y this column may serve as a possible Indicatlon, but they are not necessari ly UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY g EVENT TYPE PLANT CONDITIONS suf f1clent cause to determine an EAL. Degraded Fuel Reactor coolant activity greter Reactor Coolant chemistry sample results as A4 I ntegri t y tha n Tech nl ca l Speci fi cati on reported by the Radiation Protection limits of 1.2 ucl/gm of dose Depa rtment ba sed u pon a na ly ses c ond> cted i n equim lent 1-131 which requi res accorence with appl 1 cable cps. shutdoe n. j Other Pms1ble indications
> Increasing Reactor Coolant condJctivlty as w d Indicated on Recorder 2738, 2737 1C04
@ z increas1ng radiation levels as I ndicated on:
l O $ a) MSL Ra diati on Monitors RC 4448A,B,C&D on i o H 1C36 and RR 4448 on 1C02 O N b) Of f Gas Pretretment Rsdiation Monitor 3 4104 on TC10
@ g c) MSL HI Ra d a la rm m 1C05
- w
$ $ Air Ejector monitor activity Indicated air ejector activity rato > 1 x 103 A5 y y greater than 500,000 uct/sec or an mR'hr as I ndi cated on Of f gas Pre-treatment Ra d W ' increase of 100,000 uct /sec withi n Mo11 tor 4104 ai 1C10.
g w a 30 mi nute time peri od. or
- r Indicated ai r ejector activity rate increase i
= w of 200 mFV h r wi th i n 30 mi nu tes a s i n di ca ted on
' O
$ Of fgas Pre-tretment Ra d Monitor 4104 m 1C10 Q-l
- Other pms1ble indications i
@ Q in::ressing ra diation levels as I ndicated on:
a) MSL Radlation Monitors RC 4448A,B,C&D on l y 5 a: E IC36 and RR 4448 on TCO2 y $ b) Of fgas Post-treatment Ra d Monitors W
- 4101 A&B on TC10 w
Q c) Of f Gas Stack Ra d Monitors RI 4116A & B j on TC10 i d) MSL H1 Ra d a la rm os 1C05 I e O O O
s EPIP 1.1 m c:) ATTACHMENT 2
* @ EMERGENCY ACTION LEVEL PAGE 14 of 35 CLASSIFICATION GUIDELINES
% O
.-* o CO
- M Note: The Instrumentation listed in
# thls column ney serve as a possible UNUSUAL SITE GENERAL m c- cg: Indication, but they are not necessari ly N O EVENT ALERT EMERGENCY EMERGENCY 8 *C EVENT TYPE PLANT CONDITIONS 5 suf ficlent cause to determi ne a n EAL.
'm CL G) " F Degraded Fuel Reactor coolant activity greater Reactor Coolant chemistry sarnple results as B5 E
w CL
,*o E O
$$ i nteg rity than 300 uc1/gm of dose reported by the Rad 1ation Protection (Conti nued) equiva lent I-131 Department based upon analyses cond2cted in accordsnce with applicable cps.
Other Possible Indications i nc res s 1 ng Res ct or Coola nt con duct i vi ty a s Indicated on Recorder 2738, 2737 on 1C04 increasing ra diation levels as Indicated on: a) MSL Radiation Monitors RC 44484,B,C&D on 1C5 and RR 4448 an IC02 b) Of f Gas Pretrastment Ra dlation Monitor w 4104 cn IC10 w [J c) MSL H1 Ra d a larm on 1C05 ct , Ai r Ejector monitor activity Indicated al r ejector act1vity rate > 1x104 B6 w - 5 greter than 5 cl/sec corresponding mR/hr as Indicated on Of fgas Pre-treatment Rad to 16 Isc+coes decayed 30 mi nutes. Monitor 4104 on TC10 S c:
$< Other possible Indications incressing radiation levels as indicated on:
>- a) MSL Ra diat1 on Monitors RC 4448A,B,C&D on 52 5;?
1C36 and RR4448 on TCO2 O C b) Of fgas Post-trastment Rad Monitors
- O 4101A&B on 1C10 5 $ c) Of f Gas Stack Rad Monitors Rl 4116 A&B lE
$ on TC10 d) MSL HI Rsd ala rm 1C05 r ~_,,
Degraded core with possible loss of Resctor level below the TAF at a ny time as C5 coolable geometry. Indicated on LI 4564 a nd LR 4566 (IC03) Q o and J
- 1) Greater than 55 cla ddi ng f ailure as
$ i ndicated by P.A.S.A.P. 7.2, 7.3 a nd/or 7.5 w
=
Z
- 2) MSL radiation great than three times
' norun I as I ndicated on RC 4448 A,B,C,D
@ E cc (IC36) and RR 4448 (1CO2) g " or w 3) DW or Torus radiat1E exceeds Site W
l g Emergency limits as Indicated on t F RIM 9184 A,B RIM 9185 A,8 (1C09) or
- 4) DW 2H In excess of "7f as Indicated on AR 43318, AR4381B ( 1C09) t (see next page) 9 O G
o% EPIP 1.1 m CD ATTACm ENT 2 EMERGENCY ACTION LEVEL
* @ PAGE 15 of 35 CLASSlFICATION GUIDELINES w O -* O CD gg
- Note: The I nstrumentation !1sted in m c CE this column ney serve as a possible UNUSUAL SITE GENERAL s N o j I ndi ca ti on, bu t th ey a re n ot necessa ri l y EVENT ALERT EMERGENCY EMERGENCY Ee EVENT TYPE PLANT CONDITIONS suf ficient cause to determine an EAL.
a., c) - as EE$% w Q- % C Degraded Fuel I ntegri ty Degraded core with possible loss of coolable geometry. Other possible Indications SRM, I RM, or T I P d et ect ors ta l l t o t ra nsi t the ( Conti nued) ( Conti nue d) core f ul ty. Core R ate dP, with rect roulation f l ov, Is low or high f rom its expected w lue as Indicated by PDR/FR 4528 (1C05). Loss of 2 of Any 2 of the f olloring 3 conditions LOCA D5 3 Fission with potential loss of the th1rd: Fuel Integrity - see B-5 Prod 2ct 1) LOCA greter than 50 gpm Conta1nment Integrity d Bsrriers with 2) Degraded fuel Integrity potential loss 3) Loss of prise ry conta1nment a) See A-12, or b) Drywell Pressure >56p sig, or
" I nteg rity c) Drywell Temperature >281*F w of the third e
5 w 5 System / Equipment Stuck open safety or relief elve " ADS Sa f ety Va l ve Leki ng" a la rm e 1C03 High rellef va lve discharge pipe tegerature A6 8 e Fa1 lure or
% lfunction or hi gh sa f ey e l ve ta l I pipe temperatures as I ndicated on TR 44004,B,C and D on 1C21 Q- White press lite of f IC21 f or one or more of g g the respective w tves. - w $ $ Other Possible Indications y y increasing Torus water tenperature as w w Indicated on TR4386A/B a 1C29 w increasing Torus water level as Indicated on 5 LR 4384 and 4385 m 1C29 g g increasing Containment pressure as I ndicated cc O on iE' = a) Computer Points B103a nd B104 3 3 b) PR 43SS and 4385 a 1C29 y Q increasing Drywell temerature as I ndicated on g Z TR 4383 A,B, and C a IC29 or TR 5713A and B on 1C25.
e :2-M W
$ "Prlan ry Containment H1/Lo Press" a la rm on l [
C 1C05
" Prise ry Containment Hi Press Trlp a la rm on 1C29 Generator Imd decrease as I ndicated on WR 1100 1C31 ard Gen Megawatts e 1C08 Main Steam Line f f or decrease on FI 4408, 4409, 4410, 4411 a nd FR 4450A e 1C05.
i e O O O
t~ E EPIP 1.1 O 4 ATTAC m ENT 2 EMERGENCY ACTION LEVEL "j O
- N PAGE 16 of 35 CLASSIFICATION GUIDELINES c E
<r in i S O, 5
- Note: The Instrumentation listed in
@ g g* $ this column my serve as a pmstble UNUSUAL SITE GENERAL Indication, but they are not necessarily EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE . PLANT CONDITIONS suf ficient cause to determi ne an EAL.
System / Any ECCS actuation that results in HPCI i nt tlati on A7 Equi pment uster being discharged to the IC05 a la rm" HPCl Auto initlation" a 1C03 Fa l lu re or Reactor W ssel that is either FIC 2309 I ndicates f lov. Ms I f uncti on unexpected or Is required to recover CV 2313 Indicates open. d (Conti nued) a nd m 1 ntai n RPV wa t er l eve l. Possible response on Neutron Monitoring, w LPCI I n1 tla ti on
! $ z (Inject 1on possible only If Rx press is less C3 g 3 than 450 pstg) on ICO3 g *-
o " ADS Core Spray or LPCI pump running" a la rm. cc < FI 1971 A/B I ndi cates f I or.
~
>- CV 2002 or CV 193 Indicates open.
@ bl or y Core Spray initlation z e (Injection possible only If Rx press is less E
W E than 450 pstg) e 1CO3
" ADS Core Spray or LPCI pump running" a la rn.
g y FI 2110 or FI 213) Indicates f lov.
- >- CV 2118 or CV 2138 Indicates open.
z LL
< O
$ 8
- g =
l e r i !E $
!w t; o
I f e O O O
N N EPIP 1.1 O ATTAC* ENT 2 EMERGENCY ACTION LEVEL
". O
- N PAGE 17 ct 35 CLASSlFICATION GUIDELINES
~
i .n c *
' N
.3 m
D$$$ Note: The Instrumentation listed i n
@gy$ this column ney serve as a possible UNUSUAL SITE GENERAL Indication, but they are not necessarl ly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficient cause to determine an EAL.
System / Loss of a fi re suppressi on function Loss of both the Ele'etric and Diesel F1,re A8 Equi pment requiring shutdown by Technical Purnps as Indicated by annunciators a *1C40 Fa i lu re or Spec 1 f icatl ons. AND Ms i fu ncti on Irnb111ty to provide a backup water source g' (Conti nued) within 24 h ou rs. w w -J
$ z Complete loss of any function needed Operations Shlf t Supervisor judgment. 87 i
3 H f or plant cold shutdorn. o O N Corrplete loss of a ny function needed Operations Shif t Supervisor judgnent. C6
>- f or pla nt hot shutdown,
".c t
z o z
' Cz cr M
W W Turbine rotating component fal lure Turbine Trip when >30% power die to high caus1ng rapid plant shutdown. vl bration as I ndicated on Tu rbi ne Vi bration A9 g y Recorder 9019 or annunciated on Panel TC07
~ w
= in l j O Turbine failure causing casing Turbine Trip when >30% porer die to high cL g penet ra ti on. vibration as Indicated on Turbire Vi brett on Recorder 9019 or annunciated on Pa nel 1C07 B8 N $
Z A ND Possible condenser vacuum decrease as { y
' cc E Indicated on PRf 479 m IC07 E w I w t i {
i i O O O
N
- co
@ 522 EPIP 1.1 o ATTACtNENT 2 EMERGENCY ACTION LEVEL
$ co g PAGE 18 of 35 CLASSIFICATION GUIDELINES
$28 -
'E
=
a m $ <$3 Not e: The instrumentation listed in ggyy this column any serve as a possible UNUSUAL SITE GENERAL uJ CL e Q i n di ca ti on, bu t th ey a re not necessa ri l y EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDIT10NS' suf ficient cause to determine an EAL. System / Shutocnn ocoJrs but requisite decay Group 1 Isolation with total loss of RHR D6 Equ i pment heat remova I system fe.g., Rm) or sysem Fallure or non-saf ety systo.s best remova l means a nd/or Ms i f uncti on a re rendered unaw11able. Core Tota l loss of RHRSW system g (Conti nued) degra dstl on or me lt occu r i n a baa t a nd/or y ten hours with subsequent contai nment Tota l loss of ESW system i.u f al lu re, a nd/or y " Tota l loss of RWS system g g a nd/or l uJ p Any conb1nati on of the above systems that o o prevent decay heat remom 1. e < cu g C System / Loss of HPCI and either ADS or RCIC Failure to satisfactorfly conplete A10 Z Z Equi pment survelllance testing in accord 3nce with the
>- e Fa l lu re or Loss of ADS logic or loss of more applicable STP Z
E E Ms I f uncti on thm 1 ADS e ive - OR y (Loss of Vi sual obserwstion
-.J sa f et y Total Loss of any of the f ollowing ~
r systems or Core Spray other Possible Indications f eatu res LPCI SBLC - Loss of Squb Va l ve conti nul ty a s Z requi ri ng Indicated by: g $ RHRSW _a shutdown in ESW a) Loss of Indicating lites a 1C05 5 a ccords nee SBLC b) "Conti nuity Loss to Squlb Va i ve" a 1 rm 9 U [ with Techn1- Standby Gas Treatment a 1C05 g g ca l Speci f 1-e
- catt or.s Loss of Containment Spray capablilty SBGTS- Charcoa l bed tenverature > 255* , with e nenua l spray I nitlated or, if not, >310* on w Loss of both H2 and 02 Ana lyzers 1C24 l g Diesel Generators 'Olesel Generator Trouble" ! Loss of both Emergency Diesel a la rms a 1C08 01esd Generator Auto-Sta rt ; Generators Fa l lu re a la rns on 1C08 Loca l a la rns a t Diesd Generators 1C93 and 1C94 O O O
N Q EPIP 1.1 ATTACtNENT 2 EMERGENCY ACTION LEVEL _, I m o PAGE 19 of 35 CLASSlFICATION GUIDELINES
- ca
. D8= -g a e $F Note: The Instrumentatlon listed in
[ @$% W 4 % O this column enny serve as a possible UNUSUAL SITE GENERAL Indication, but they are not necessarily EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf f1clent cause to determine an EAL. System / Any combirntion of saf ety system As specified in the appl 1 cable Technical All Equ i pment failures that regul re shutdcwn by Specificatlon Limiting Conditions f or Fa l lu re or Technical Spec 1tication. Operation (LCO) sta tements. Ms i f u ncti on a (Loss of g sa f et y w systems or e f eatures ' @ $ requiring ) shutdown in y ~ g O O a ccords nce E with Techn1-e Z Z ca l Speci f1-cati ons H c (Conti nued)
= 1 m m = LL < O O
i3 ?
= $ b 5lE 5
w W t w
' o l
O O e
N Ob O E o EPIP 1.1 4- ATTAC
- ENT 2 EMERGENCY ACTION LEVEL
# O *
. PAGE 20 d 35 CLA50lFICATION GUIDELINES
- QC m c 8 N O b$ h Note: The Instrumentation 11sted in A
w 2 e*g $ this column ney serve as a poss1ble UNUSUAL SITE GENERAL Indication, but they are not necessari ly EVENT ALERT EMERGENCY EMERCENCY EVENT TYPE PLANT CONDITIONS suf ficlent cause to determine a n EAL. System / Loss of prinary contal nment Both ve lves in one or more vent or purge li nes A12 Equi pment integrlty t o the drywe l I a re open a n d a re requi re d to be Fa l lu re or - closed. Msifunct1ons or d (Loss of Any Auto Isolation elWthat is falled in the g Contai nment non isolated conditi on, w J I ntegrity) or O z Both doors I n the Dryw21 el e lock are not w 3 sealed / closed (at least one door nust be g C closed and sesled). cc 4 or
>- One or more blind flaths and/or nenwsys not @ M W
closed. p e a nd/or
= m 1C35 Alarms w
E E a Drywell Torus f or SP" W "
" Standby AP Al r Compressor Running" g W H
a nd/or
- 1C05 AIarms z
u_ O "Contai nment h1 H2 and 02 Content A and/or Pone r Fa 1 lu re" c' Z "Contal nment h12H and02 Content 8 and/or
>- - Powe r Fa i lu re" N $ a nd/or y Z AR 4381/4382 on 1C09 Indicating increasing 02 g g concentrati on E w a nd/or
- w Torus level < 40% or > 60% on LR 4384, 4385 O
on TC29 Other items to consider; see next page l 4 e O O O
N m e O EPIP 1.1 4- ATTAC* ENT 2 EMERGENCY ACTION LEVEL
. PAGE 21 o* 35 CLASSIFICATION GUIDELINES
- 0:
R ;8 :7 b *cn > b Note: The Instrumentation listed in
@ E. $ $ this column way serve as a possible UNUSUAL SITE GEt4ERAL Indication, but they are not necessarlly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficlent cause to determl ne an EAL.
System / Loss of pr1pe ry containment Other Itens to C onsider Equi pment Integrity (continued) " Prine ry Contai nment H1/Lo Press" a la rm on Fa l lu re or IC05 Malfunctions Drywell and Torus pressure as Indicated on: J w (Loss of a) Computer Pol nts 8103a nd B104
]
, Contal nment b) PR 4384 and 4385 ci 1C29 w J i nteg ri ty) Drywell tenperature as I ndicated on:
- 3 z ( ContI nued) a) TR 438M,B ard C ai 1C29 O 3
+
b) TR 5713A and B on IC25 u o o cz: <
>- Loss of secone ry contai nment Both doors In any alrlock cannot be closed A13 @ @ I ntegri ty or y Both SBGT systems inoperable Any autonatic Isolatto elve failed In the W W non Isolated position.
g W or
- H Failu re to satisfactorily conplete = ta_ surveillance testing in accorence with the < O applicable STPs.
a 5 O & Z < e r N W 4 D o i O O O
co m - _ 4 o EPIP 1.1 ATTACtNENT 2 EMERGENCY ACTION LEVEL o co PAGE 22 of 35 CLASSIFICATION GulDELINES
. Q:
.-e o c I M O .
- I a a;
$ c) Note: The Instrumentation listed in w
m $%
%C this column ney serve ts a possible UNJSUAL SITE GENERAL Q- Indicati on, but they a e. not necessa ri ly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficient cause to determine an EAL.
System / Total Loss of of fsite power Loss of Startup Transf orner as I ndicated by: A14 Equi pment a) Startup transf ormer OCB 5550 open m IC08 Fa t lu re or b) "Sta rtup Transf ormer Lockou t Trip" a larm
% If uncti on en 1C08 a (Loss of W Power) and W Loss of Standby Transf ormer as i ndicated by:
$ a) Standby Transformer CCB 8490 cpen cn TCOB l@ w
$ b) " Standby Transf ormer Lockoat Tripa a la rm l p cn IC08 O o
' E and
,3 $ Both Diesel Generators running and supplying Z j I A3 a nd 1 A4 a s I ndicated on 1C08 s-~ r3 5 $ Other Indications of Tota l Loss of Of f site
{ & Poner J S
~
^ 1A1 a nd 1A2 poser avallable lights are
' off on 1C08 z t.L
<:t O g g 1 A1 and 1 A2 voltmeters cn TCOS re ding c3 zero volts.
u &
= <
t e b z
' w e E LaJ 1
w W I LAJ f t i e O O O
co 9 su O EPIP 1.1
% ATTACmENT 2 EMERGENCY ACTION LEVEL 1O OG PAGE 23 of 35 CLASSIFICATION GUIDELINES .-s c E I MO en S$$3 Note: The Instrumentation listed in ggy$ this column erny serve as a possible UNUSUAL SITE GENERAL I n di cati on, but they a re not necessarf ly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf fIclent cause to determi ne en EAL.
System / Loss of onsite pcwer capability Failure of both diesel generators to coglete A15 Equi pment surveillance testing In accordsnee with the Fa l lu re or applicable STP. MsIfunctIon or d (Loss of Observa ti on
> Power) or W ._s (Conti nued) Fa l lu re t o sta rt when Tequi red O
z or 3 Loss of one or more ofThe f ollori ng Busses g y lA3, 1A4, 183 or 184 as Indicated by: e <:t a) Power supply lights on 1C08 a re not il t
> b) Voltage f or Bus Is zero
@ M c) IC08 a la rms y "4KV Bus I A3 Loss of Voltage" z e "4KV Bus 1A4 Lass of Voltage" T W W "CB EL 757-6LC Trans IX31 4KV Bkr 1 A303 _J Trip" g g "C8 EL 757-6LC Tra ns 1x414KY Bkr 1 A403 - >- Trip" z u_ d) Bkr 1A303 gen O $ e) Bkr 1A403 open 5 u 5 e r W 2 E W W W LAJ Q O O O
m su Q EPIP 1.1
% ATTACHMENT 2 EMERGENCY ACTION LEVEL
-o co N
- PAGE 24 of 35 CLASSIFICATION GUIDELINES CE
~ c <
M gO g j Note: The Instrumentation listed in ggo y this column rey serve as a possible UNUSUAL SITE GENERAL I n di ca ti on, bu t th ey a re n ot necessa ri l y EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficient cause to determi ne an EAL. System / Loss of a ll AC Power; restoration 1A3 a nd 1A4 Power Ind1cating lights on 1C08 Equi pment f rcm Control Room not pmstble. not on 89 Fa i lu re or and Ms i f uncti on IA3 and 1A4 Volt meters reding zero cn IC08
,j (Loss of and
> Power) " Di esel Generatcr 1G31 Sta rt Fal lure" a la rm w
d d (Conti nued) 1C08 z and o O " Diesel Generator 1G21 Start Fai lure" a larm ' H u 1C08 a M Other Indications 3 Th e f ol l ow1 ng Bkrs I ndi ca te cpen on IC08 g g 1A301 1A401 1A302 O w 1A311 1A411 1A402 y @ Other Indicators y y w J Bkr (8490) to Standby trans. w M Bkr (5550) to Sta rtup trans. _.a
~
O 3 Loss of all AC Power; restoratlon not Same as above f or > 15 mi nutes. C7 z g possible within 15 mi nutes.
< O d z 3 3 Total Lcss of 125v DC Power Loss of RCIC I ndicating lights B10 g Q and , g = Lcss of all Control Room Annunciators e E and y $ Lms of ability to open a nd close 4160V a nd ', W
[ o 480V brekers f ran Control Room l e Total Loss of 125< DC Power; Same as above f or > 15 minutes C8 l restoration not possible within l 15 minutes l l e O O
m co
- SD EPIP 1.1 ATTACtNENT 2 EMERGENCY ACTION LEVEL o
o co g PAGE 25 of 35 CLASSIFICATION GUIDELINES m c Oc
?
ct, c) O c) Note: The Instrumentation llsted In E W
,C" o
C-
%O this column rey serve as a poss1ble I n d1 ca t i on, bu t th ey a re n ot necessa ri l y UNUSUAL EVENT SITE GENERAL ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf flclent cause to determi ne an EAL.
System / Fa i lu re of RPS to I nitia te a n d Both of the f ollowing a larms on 1C05 B11 Equi pment complete a reactor shutdan. " Trip System -'A' Rx Auto Scram" Fa l lu re or and Msifunctlen "Trlp System 'B' Rx Auto Scram" a (RPS and W
, Fa t lure) APRM/lRM !s not dcwn sca le af ter short perlod W of time.
ce RPV pressure on PE 4563, 4564, 4565 on 1C05 5 w 5 rems i ns stes dy. a W o y Other Indications et All rods not fully Inserted as Indicated on e o green "fi ll I n" lights on 1C05 a nd CRD 5
+
5 o pcsttlon I nd. 5 Transtent Requi ring Operatt on of Both of the f ol i cwi ng a la rms on 1C05 C9 w O Shutdovn Systems with Fallure to "Trl p System ' A' Rx Auto Scram" g w Scram (continued power generatt on, and 3 3 but no core darrege 1mnedtately evi de nt) .
"Trl p System 'B' Rx Auto Scram" and 5 'o No control rod motlon (red f ulImt 11ghts g z reneln on, no new green lights on) on 1C05 o Other Indications b [ No decrease as Indicated on:
d $ a) APRMs on 1C05 g y b) Steam f l ow a nd Feed f l ov on 1C05 g d c) Generator oJtput on 1C08 w r 1C05 a la rns Indicate shutdown should have f $ occu rred,
~
i l O O O
N m ro e $Z! EPIP 1.1 g ATTACmENT 2 EMERGENCY ACTION LEVEL
% co PAGE 26 of 35 CLASSIFICATION GUIDELINES
~
e c 2: g g 3h j q; Note: The Instrumentatlon listed in pgy this column rrey serve as a possible UNUSUAL SITE GENERAL w cL e o Indicati on, but they a re not necessa ri ly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficient cause to determi ns an EAL. System / Transient (e.g., loss cf of fsite Same as preceding, plus: Inablitty to D7 Equi pment p ower) plus fal lure of requisite initiate SBLC Fa l lu re or core shutdorn systems (e.g., scram
% l f uncti on or standby liquid control system).
(RPS Coul d lead to core melt I n several w Fa l lu re) hours with containment failure w (Conti nued) likely. More severe consequences if y " pump trip does not f unction. o z .t 8 C Na tu ra l Earthquake of suf ficient negn1tude Seismic Alarm on Panel 1C35 A16 g Occu rrences to actuate the Seismic Monitoring (0.01g) Green V Light g yz System.
=
=
Ue w w E E g Ea rthquake greater than OBE. Seismic Alarm on Panel 1C35 B12 J (.06g) Yel l ow Li ght
$' I
= tn
< O
- , Earthquake greater than TE with Seismic Ala rm on Panel 1C35 C10 o plant not in cold shutdorn. (.12g) Red Light 0
e 5 E w b
; t; O
l
}
O O O.
EPIP 1.1 ATTACFMENT 2 EMERGENCY ACTION LEVEL N PAGE 27 cf 35 CLASSIFICATION GulDELINES m to
- S
% O e-4 O CO
. CQ Note: The Instrumentation IIsted in m e g this column may serve as a possible UNUSUAL SITE GENERAL
' " Indication, but they are not necessarily EVENT ALERT EMERGENCY EMERGENCY g
y ,g
.O EVENT TYPE PLANT CONDITIONS suf ficient cause to determine an EAL.
- en > a
$$$o Natural Cedar River level greater than 753' as measured at the DAEC Intake Intake Structure Level Recorder on Panel 1C102 A17 Occurrences (Continued) Structure. Computer generated river level printout Corputer Point M010 w" Cedar River level greater than 757' Intake Structure Level Recorder on B13 C as measured at the DAEC Intake Panel 1C102 g J Structure. Computer generated river level printout Computer Point M010
' o z o o d
o o cr: < Cedar River level greater than 767' Visual Observation C11
~
=
m as measured at the DAEC Intake Structure, or loss of f lood g E E protection for safety related W " structures with plant not in cold a n shutdown.
= u_
< o
@ Cedar River flow less than 200 CFS Cedar Rapids 8th Ave Bridge USGS Monitoring A18 y ~ as measured by the 8th Ave Bridge Station. Monitored daily by Nuclear Licensing z < (Cedar Repids) USGS Monitoring i
$ 3 Station. Monitored daily by Nuclear I gd @ Licensing.
t E w f w Cedar River flow less than 50 CFS. Cedar Rapids 8th Ave Bridge USGS Monitoring B14 U I as measured by the 8th Ave Bridge Station. Monitored daily by Nuclear Licensing (Cedar RaplJs) USGS Monitoring l Station. Monitored dally by Nuclear 1 Licensing. O O O
c . * *E my zb N <= .gJw$ =w.zO 10 o0omw wuS e
~+M _
Lo$ $ O *-* Q ct e ea$Tn 5 oC E E :<Uoz otn y w$mcwzoy Ne3= J~N.- s 0 3 s _ oou n
- OO G 5
% e
( ON Cca E oct V nuu E trr N ira T
. nel un T ec de Y
P
) s E dT p i W LS( mwC ao T l i tCeie mr o an caeat d etdsh a an r nd r
g a n ts n iau a sorrp
.e od d ng ign .n Rdai el R s o or te a nv t o a . p bt e P r n it Miy n
r L i ner od A k s nstof N e i c i) h ti T s t lot t e iw c C
.e h oU O f da rS8n a n eGt l N _
D c s dShCe _ i h1 os l u0 dMAl s IT i t 0 aovd I t d l ne t O y ora l i Sh N wp y tBh a S c nh orun a . brit y idd 1 u w s i ng o3 i t Ng ew n h u nC g c F l aS e s a r N V V M SC o i e t e t ss i s t ad e y u u e t a sa a o i r o tl l r sI tT PA e mob o ol .n pR a unh h A T b o f die GTE as s gi i f is EAP l e e Md I c I C I ar r c os n cacntos 2 8 )M P rv v a l E ma a l i8 eil t o N .1 st t t t nourmu f T1 I oh i o i o n r t ,n c nme 32 n s eA
.n t d v ab mn 5 a r e uuat sty a n u d d m aB l r e tsi t e
a n l i th eo s t a y d g oerny v s be d el o t y ea i c i U t ras i o NS eest a n u G r e t e , o cS mnad n io d leM ao ntp e on i P ns a rn n i aes e Lt nci eb t io c r Esl I ei Ase C n n sg .L ar 2 i i 1 n y l g U E N A V U 1 ES 9 NU TA L A CE L L M B E AE 1 5 R SR T SG I E E F N M I C ES CY C C RI A 1 1 GT ITA 3 2 EE C N OT C NI Y O GN E U MG I L EE DE R N E V GE LE E R I L N N A CL E t S
N co m CE! w EPIP 1.1 O ATTACtNENT 2 EMERGENCY ACTION LEVEL
$ co CQ PAGE 29 of 35 CLASSIFICATION GulDELINES
.: N c-m 4
35 l a a3
~ *
$ c3 Note: The Instrumentation listed In l
W CL 2 O
$% this column eny serve as a possible I n di cat i on, tu t th ey a re n ot necessa rI l y UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficient cause to determi ne a n EAL.
I Natu ra l Tornado which danages safety related Visual obseretion and associated C14 Occurrences structures and compromises the system a la rms (Conti nue d) f u ncti ons of sa f ety s ystems a y Other Unusua l ai rcra f t a cti vi ty over Comcun1 cations frcn Security A20 w Haza rds f acility or crash on site , 4 W Experienced f g y or Projected w e o >-- o
' o ' ce <
cu
! g U Ai rcraf t crash or missile T@act Communications f ran Security B16 Z Z which causes facility darege. Visual Obserett on and Associated
>- o System Alarns Z
E z w w
- N_ '. Q 'o Al rcraf t crash or missile Imact Communications f ran Security C15 ; which daneges safety related systems Visual Obserett on and Associated o or structures with plant not in cold System Ala rns l a* [ shutdown. ; = 5 t
ce
.~-.
I t
' E w
s-- Train derallment onsite Concunications f ran Security A21 I f e O O O
N M EPIP 1.1 i._ O ATTAC*ENT 2 EMERGENCY ACTION LEVEL
". O
- 03 PAGE 30 of 35 CLASSIFICATION GUIDELINES co Oe, M e M in DUm$* Note: The Instrumentation listed in ggyy this column rey serve as a possible UNUSUAL SITE GENERAL Indication, but they are not necessarily EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficient cause to determi ne a n EAL.
Other Nea r or onsi te exp l osi on Comnun1 cations f rom Security A22
, Hsza rds visual Obseretion Experi enced or Projected d
(Conti nued) w w a o z Explcslon onsite which causes Comnunications frcm Security 817 3 fucility dsnege a f fecting plant Visual Obseretion and Associated g [ operati on. System Alarms ce < C u z z
- w b-- O z :r W
W Explosion onsite which dsneges Comnunications f ran Security C16 safety related systems or stractures Visual Obseration and Associated
- n. y with plant not in cold shutdown. System Ala rms
= u_
< O N 8 M $ Onsite release of to<tc or Portable Detectors A23 y Z f lamnn ble ga ses. Possible Odors.
, ce r Visual Obseretion
$ b
- W ;;
; o t
t i e O O O
3 Q SD O EP I P 1.1
% ATTAC* ENT 2 EMERGENCY ACTION LEVEL
~
. PAGE 31 c,f 35 CLASSlFICATION GUIDELINES & c U '~s& $$$ Note: The Instrumentation 11sted in dE$$ this column vray serve as a possible I ndi ca ti on, bu t th ey a re not necessa ri ly UNUSUAL SITE GENERAL EVENT ALERT EMERGENCY EMERGENCY EVENT TY % PLANT CONDITIONS suf ficlent cause to determi ne a n EAL.
Other Uncontrolled entry of toxic or Portable Detectors B18 Haza rds flamnable gases into the facility Possible Odors. Experienced envi rons. Visual Obserett on or Projected d (Conti nued) w w a o Z O w - 8 e [ Uncontrolled entry of toxic or f lamnn ble ga ses i nto c ri ti ca l p la nt Portable Detectors Possible Odors. C17
>- arass where lack of access to Visual Obserwstion
$ S the area constitutes a saf ety ~ y problem. Plant not In cold shutdown Z M con di t1 cn. E E j " Release or Any uncontrolled i ncrease i n d1 rect As reported by the Ra diation Protection B19 g y Loss of radiation levels greater than 1000 Depa rtment based upon the results of surveys - H Control of times norna i condJcted i n accordsnce with a ppli ca ble Z w Ra di cm etI ve RPPs. < O Pa teria ls Other Possible Indicators a Q- y within the ARM I n di cat ors >- - P la nt CAM recorders a w Z 4 w Z c.D - cc E k w b O O O O
S 0 se EP I P 1.1 O ATTACmENT 2 EMERGENCY ACTION LEVEL
". O
- N PAGE 32 of 35 Cl.ASSIFICATION GUIDELINES
~
o e 2 w - h 3$53 Not e: The Instrumentation listed I n
@E$$ this column ney serve as a possible I n di cati on, but they are not necessarl ly UNUSUAL EVENT SITE GENERAL ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficlent cause to determi ne an EAL.
Release or Fuel handling acc1 dent that results V1sual obserwitlen B20 Loss of in fuel danage with the release of and Control of radl mctivity to the Rx BIdg. As reported by the Radlation Protection Ra d1 met t ve (Secone ry Contai nment) Department based upon the results of surveys d Ms teria ls within the and a nalyses conected I n accordsnce with applicable RPPs. w
]J Pla nt Other Possible Indicators
$ z (Conti nued) ARM I n di cators
$ 3
+
CAM recorders t u 0 N Major danage to spent f uel In Rx Visua l obserwstion C18
> Bldg. (Seconds ry Contai nment) and
{:2 M As reported by the Ra diation Protection p y Depa rtment based upon the results of surveys
= and analyses conWeted In accor&nce with $ ]
z applicable RPPs. W W Other Possible Indicators a 9 y ARM Indicators
- H CAM recorders z u O $ Uncontrolled decrasse In Fuel Pool Water level Indicator on Panel 1066 C19 1 Z g water level belos fuel level. 37 f t. 6 I n. mininum level >- - Fuel Pool Cooling Clearup F1 Iter Trcuble w
Q z Annunciator Panel on 1C04 O *-* c2:: E
- w N b t;
- o I -
i e e e
di ali 4 m . 4 ' O l F'
*t - \
,1 ATTA >NE W EMERGENCY ACTION LEVEL
- $ co- 0:
PAGE 33 c+ 35 Ct.ASSIFICATION GulDELINES
+3
- c-:g _.
. - a e . . s e
a, ca - c3 Note: The ins +r. .wntation liste.d i n , E E' $ Y f g T M s col a.: eay serve a t a poss!ble UNU%S.L Si1E. GENERAL U Q- ?O Indicati on, but they a re not necessari ly E dNT ALERT EMERGENCY E*ERGT'CY , EVENT TYPE DLAf 6T COeBITIONS - suf ficient cause to determi ne a n EAL. d 7 Eve n+s -!:.Yeatt s.o pe Ala rus on Process or System Ala rm/ Recorder A24 Atfecting Et! snt far e+4rs in the Control ,
,0pe.qti nne l Room which regair6 dlant shutdown.
- gC .ritrol 's _
w l. > Loss of if sual alarm sys*49
,- Loss of a l t safety related a larra B21
', $$ and annunciaticc ; ,wa bt I
- t y; rest or- or
- l
$ o att on not possi';te within Loss of Visual andNdt ble alarm system y [ 15 minutes.
o o er < Q.
' ms of a ll saf ety related s torm a nd Lost of U s el a la rm s ystem C20 s ,
hey' - , Z ; an'er:!ation capability colt.cident or H O ! with pla nt transient. t oc s o' Y!sua l a nd au di ble a la rm s ystes z x ; , w L; and hg a 6 ,. y R cor not I n >te=U+ ate condit1,,
+
h I Significant loss of assessment or conra nications capability. Operati ons Shi f t Super <12cr ju dgement concerning the operatt el cdequacy of A25
$ 'o phones, ra di os, cor'puterc 6- ,5vens, a nd the g = l oca l rea d network.
O b' sN Mher plant conditions exist that Operations Shif t Supervisor judgement A26 b 4 r ' " v3 rrant increased awa reness or *
-I require plant shutdoen under
@ . 'f' ,
w
~
g 3 . Technical Specification or i nvcive w H - l other than pcN 8 controlled .
$ ' #;Jnhe n.
o
=
O O O
co EPlP 1.1 O . ATTAC
- ENT 2 EMERGENCY ACTION LEVEL o co N PAGE 34 of 35 CLASSIFICATION GUIDELINES
- cx
, e .a-
,3 c.
c) $ c3 Note: The instrumentation listed i n u.
,o c.
m o this column my serve as a possible UNUSUAL SITE GENERAL Indication, but they are not necessari ly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf f1clent cause to determi ne a n EAL. Events Other plant conditions ex1st that Emergency Coordi nator ju dgent B22 Effecting usrrant precautiona ry actiett on of Operationa l TSC and placing EOF and other key Control emergency personnel on standby. g (Conti nued) w Other plant conditions exist that Emergency Coordi nator ju dgent C21
$ warrant actimtlon of emergency W
$ centers and monitoring teams or a
[ precautlora ry notification to the o y public near the site.
~
c.D o
= z C $
Control Room Ewcuation of the Control Room Control Room emosated and action inttlated B23 6 w Ha bita bi lity requi red f or a ny reason. Shutdown in accordsnee with Operatirg ProcedJres E w 6 outside Control Room inttlated. W h y EvaoJation of the Control Room Fallure of System Comonents to Function C22 requirad f or any reason. Shutdown f ran Remote Shutdown Panel y $ ; outsida Control Room not inplemented
-a withIn 15 minutes.
o O >- ' 5 @ Situations Tra nsportaG on of contami nated Comtrunications f rom Hea lth Physics A27 g g Requi ri ng injured Indivi dJal to the hospf.w a g g Off-Site ' w & As91s ta nct Security threat, attenpiod saletaga, Comnunications frcm Security A23 d; or umuthorized .? m comb 3 84 *-; ry [ ' Confi rme d on goi ng see r. s v Comeanications iPan Security or Operations s24 coh.promi se
/
s O .. x
- r, .- .
i
+
N m EPIP 1.1 Q ATTACm ENT 2 EMERGENCf ACTION LEVEL o co cq PAGE 35 of 35 CLASSIFICATION GulDELINES N G; e OE% o, e - as Not e,: The instrumentation IIsted in
" * ,o W Q-
%O this column nny serve as a possible UNUSUAL SITE GENERAL Indicatl on, but they are not necessarl ly EVENT ALERT EMERGENCY EMERGENCY EVENT TYPE PLANT CONDITIONS suf ficient cause to determl ne an EAL.
Si tua ti ons in mi nent loss of physical control Comnu nications f ran Security or Operations C23 Requi ri ng of the plant Of f-Site _ 8ssista nce a (Conti nued) y Loss of physical control of the Communications f ron Security D8 y plant ca z o l W p Comnunications f ran Fire Brigade o o Fi re within the secured ares that A29 ' $ cannot be extinguished wittCa 10 e z z mi nutes by the Fi re Briga de 5
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5 E w Fi re not ext i np i shed i n 10 mi nutes Comnu nicat7 ons f rom Fi re Briga de B25 g w i n a n a rea that coul d a f f eet saf ety E related equipment Lr
.J k b O Fi re conpromising the f unctions of Comnu n1 cation f rom Fi re Briga de C24 u [
sa f ety s yst ems Associated System and Ala4rms - Panel 1C40 5 c.c z Observa ti on 'zbW i w l w
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