ML17333A314
| ML17333A314 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 02/21/1996 |
| From: | John Hickman NRC (Affiliation Not Assigned) |
| To: | NRC (Affiliation Not Assigned) |
| References | |
| NUDOCS 9602260248 | |
| Download: ML17333A314 (53) | |
Text
I 5t'P,S RKgI
+4 po Cy I
0O I
I!
9
~O
++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 February 21, 1996 LICENSEE: American Electric Power Company FACILITY: D.C.
Cook Nuclear Plant, Units 1 and 2
SUBJECT:
MEETING SUHMARY EMERGENCY PLAN REVISION TO INCORPORATE NUMARC EALS A meeting was held at NRC Headquarters on January 24,
- 1996, between American Electric Power Company (AEP, licensee) and the NRC to discuss the licensee's proposed change to the D.C.
Cook emergency plan to incorporate the NUMARC EAL
[emergency action level] classification methodology.
Jim Feinstein, with the licensee's Nuclear Production Support and Administrative Services
- Section, provided opening remarks indicating a willingness to address our concerns.
Gordon Arent, with the licensee's Nuclear Licensing Section, provided most of the presentation.
Significant discussion issues and comments are provided below:
1 Emergency Condition Category (ECC) R-1:
Discussion on clarifying notes; licensee (AEP) will have operations staff review for clarity; may consider rewording similar to Zion.
AEP will also look into appropriateness of monitor setpoints, in particular ODCH [Offsite Dose Calculation Manual] vs.
[total effective dose equivalent] limits.
ECC-R-3:
AEP will revise Unusual Event EALs to improve human factors usability.
Bases will include rationale for selection of radiation monitors under Alert EAL.
AEP will reevaluate water level under Alert-EAL to provide adequate margin for pool level.
ECC S-2A:
AEP will include specific breaker indications.
ECC S-6:
AEP performed a significant revision to include 0737 instrumentation as critical.
AEP will revise to address human factor concern with logical and/or connections.
AEP will provide guidance on what quantifies most in "loss of most safety system. annunciators."
ECC N-1.5:
AEP will change Alert EAL from missiles which penetrate all areas to any areas.
N ECC N-1.6:
EAL will be reevaluated to consider cause of flooding.
ECC N-1.7:
AEP will reevaluate wording to clarify distinction between unexpected and other explosions.
ECC H-3:
AEP will revise note on what constitutes "control" of a process to
,'clarify.
960226024S 960221 lV F.PDR ADOCK 050003i5 L
PDR1
5 II f
'I
Fission Product Barrier Classification Table; Containment Barrier:
AEP will revise the containment pressure level for potential loss to design vice expected failure pressure.
AEP will reevaluate need for list of excessive leakage rate under potential loss.
A list of attendees is provided as Attachment 1.
Attachment 2 contains the discussion slides used at the meeting.'f there are any questions regarding this meeting
- summary, please contact me at (301) 415-3017.
Docket Nos.
50-315 and 50-316 Attachments:
As stated (2) cc w/att:
See next page r
ohn B. Hickman, Project Manager Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear. Reactor Regulation
Indiana Michigan Power Company CC:
Regional Administrator, Region III U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attorney General Department of Attorney General 525 West Ottawa Street Lansing, Michigan 48913 Township Supervisor Lake Township Hall P.O.
Box 818 Bridgman, Michigan 49106 Al Blind, Plant Manager Donald C. Cook Nuclear Plant 1 Cook Place Bridgman, Michigan 49106 U.S. Nuclear Regulatory Commission Resident Inspector's Office 7700 Red Arrow Highway Stevensville, Michigan 49127 Gerald Charnoff, Esquire
- Shaw, Pittman, Potts and Trowbridge 2300 N Street, N.
W.
Washington, DC 20037 Fayor, City of Bridgman Post Office Box 366 Bridgman, Michigan 49106 Special Assistant to the Governor Room 1
State Capitol Lansing, Michigan 48909 Nuclear Facilities and Environmental Monitoring Section Office Division of Radiological Health Department of Public Health 3423 N. Logan Street P. 0.
Box 30195 Lansing, Michigan 48909 Donald C.
Cook Nuclear Plant Nr. S.
Brewer American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, Ohio 43215 Nr.
E.
E. Fitzpatrick, Vice President Indiana Michigan Power Company c/o American Electric Power Service Corporation 1 Riverside Plaza
- Columbus, OH 43215 April 1995
NAME MEETING ATTENDEES January 24, 1996 AFFILIATION J.
Hickman L. Cohen J. O'rien W. Maier S. Klementowicz D. Mihalik G. Arent R. Krieger R. Steele
=K. Toth R. Begor J. Feinstein NRC NRC NRC NRC NRC AEP AEP AEP AEP AEP AEP AEP Attachment 1
NRC MEETING:
RESPONSE
TO NRC QUESTIONS REGARDING APPLZCATXON OP NUMARC EALS TO COOK NUCLEAR PLANT JANUARY 24, 1996 AEP COOK NUCLEAR PLANT EAL ORE GROUP REPRE ENTATIVES GORDON ARENT:
ROLAND BEGOR:
JXM FEINSTBXN:
(principal NUCLEAR LICENSING SECTION spokesperson for EAL.activity)
COOK PLANT OPERATIONS DEPARTMENT Coordinator)
(EOP NUCLEAR PRODUCTION SUPPORT AND ADMINISTRATIVE SERVXCES SECTION (chairman EOPCOPS
[emergency operating procedure committee on oversight and practical support])
ROD KRIEGBR:
COOK PLANT EMERGENCY PLANNING COORDINATOR DAN MIHALIK:
RANDY STEBLB:
KARL TOTH:
RADIOLOGXCAL SUPPORT SECTION (corporate emergency planning coordinator)
XNSTRUMENTATION AND CONTROLS SYSTEMS SECTION NUCLEAR LXCENSING SECTXON AGE~A INTRODUCTION:
ABNORMAL RAD LEVELS/
RADIOLOGICAL'PPLUENT:
HAZARDS AND OTHER CONDITIONS:
SYSTEMS MALPUNCTIONS:
PISSXON PRODUCT BARRIERS:
Jim Feinstein Gordon Arent Gordon Arent Gordon Arent Gordon Arent Attachment 2
pA'.C G~rn~ 8s ~~
/~op~~~ ~
i/~~ ~g M-/
/p 4k'>~~ f8< A/~~ ~g ce Lc'H /SA/gd l8 kPa5 u~ ew roc'~ Ad~~~
R-I uc Z~ '~/~
g- 0 LIE rn ADD.ass wiser ~8 ~m w~~~z ZiE&P/20Lc5hrS D
COCAtldm Qq~~~)
'CS>
St'C-'I Svi~~+e/ge/
- Eggs, c+cCn Pod/C Spcwi~C + 3
~>~~ ~~a4e's a~~ 5A ~~icRccy Aa~~~-ms's Z-4
~ DW~v'87784 0< ~~4=6 g~g gqp~iu~
gtgrg ~6'k W l2IL5. (X-9 use&~)
B
~MAXNC/g6
+VAN ~~~ ~~gp~~j~
lD/YIICgk5E~i~ &Vlu.Serc~&unlu<
pr.'-y -gc.)
$8lnPLc~ AnJA~ySiS
~><~ bu~~a Addwd ro Dowz +ie
/Mud&EV~~i g "Q /~~ ~y-gg+ ~ p++ k~g~c)
S EM 8-~
4'</A'L.
RDuaD ~D Mm)zm/'&dzmwxM
~ ~~ />><Wnc~/oss~mvRriaQ
~
E-D
>a/wc.
geruarioQ ezi~iw am g~ soom
1
~A 4oks l'lo 'e.4eut aced cf 4 BoQ R-'
SA jGF-Pcc' cdck~ m+4
< h>> Ks~uwteckdh.re% vt~
Md-+4 lS yn~~4 C(c~s4.c ~ cr~Mi~.
I l
u
EMERGENCY CONDITION CATEGORIES Pill'.> 20et).EPP.101.
Attachment A REcoGNmoN cATEGGRY: Fuel Damage / Abnormal Radlologlcal Conditions MODES'S DEFINED ECC R-1:
RADIOACTIVE EFFLUENT RELEASE MODES: ALL UNUSUALEVENT
'ANYtINPLiANNED,i';EFFLUENT>7<"'n~",I (RELEA'SE:GREA<<TER;;THAN:.',2x',THK.::;;
(oFFsITE:0 osE'cd'cULATIDN'<<~@~
~iM'ANUAL'lL'IMITS~'LrAS<<TINGSOP:-Y,:."'~
Note: lf the monitor reading(s) ls sustained for longer than 60 minutes and the required assessments cannot be completed within this period, then declaration must be made baaed on the valid reading.
~ Valid reading of at least 2x the high alarm setpolnt on any of the following:
~ VRS-1500/2500
~ SRA-1 800/2800
~ SRA.1900/2900
~ R.20 e R28 4R-Confl/med sample analyses for gaseous or liquid releases Indicates concentrations or release rates exceeding 2x the ODOM maximum Instantaneous release limitfor a 60 minutes.
ALERT
'ANY:UNPLANNED,'~SF<<FLUENT<~,s~~~:,;.~y a OFFSITEIOOSE:,CALCUL'ATION,'"-.').".',:.g>~<<'g:,.';.'"..
'"<<MANUAL';.LIMIYS;FOR)46'MINUTES.,;,';
Note: Ifthe monitor reading(s) Is sustained for longer than 15 minutes
-and the required assessments cannont be completed within this period, then the declaration must be based on the valid reading
~ Valid reading of at least 200x the ODCM limits on any of the following:
~ VRS 1500/2500
~ SRA-1800I2800
~ SRA.1 900/2900
~ R 20
~ R.28
-OR-Confirmed sample analyses for gaseous or liquid releases indicates concentrations or release rates exceeding 200x the ODCM release limit for a 15 minutes.
4R-Field teem suNey results or Dose Assessment indicate does rates of 2: 10 mrem/hr at or beyond the site bounds/y and are expected to continue for a 15 minutes.
SITE AREA EMERGENCY g@:<<<<<<pg 5.'@ c A>p +yp; ypjggqcy4y+ e'p+
~SITE::.SOUNDA'RY...,DOSE,:FROM,::AM';;;
- "".AciuAL'-;OR
- ,IMMINENT,;=EFFLUAT.."
- :
9+'>SOQiriiemiCDE'<THYROlD-:.I/i".ig Note: The monitor reading(s) are based on an assumed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> event duration.
Ifthe monitor reading(s)
Is sustained for longer than 15 minutes and the required assessments cannont be completed within this period, then the declaration must be based on the valid monitor reading Avalid reading on one or more of the following monitors that exceeds or Is expected to exceed the value showm
~ VRS-1500/2500 > 4.20E'i ycUce
~ SRA.1800/2800 > 9.10E'ci/ce
~ SRA.1900/2000 > 1 955's Iic//
4R-Avalid dose assessment Indicates greater than 100 mR TEDE or 500 mR CDE thyroId at the site boundary 4R-Flefd survey results Indicate site boundary dose rate exceeding 100 mR/hr /f-yor a CDE thyroid exceeding 500 mR for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of Inhalation at the site boundary.
GENERAL EMERGENCY
~wp%.r. <<g<<<,'.coro<<p.> >,,,>:g~~y.~yg~ y,y@y
,"SITE;:BOUND<<ARY,:D'OSE,FROM",'AN/.;.
>~aeTUai.,::Oj;IMMINENT.':EFFLUENJ, ~-.';
p ~+~<<~~g~js:i~p~~'r+gp+"
JAN Note: The monitor reading(s) are based on an assumed 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> event duration.
Ifthe monitor reading (s) Is sustained for longer than 15 minutes and the required assessments cannont be completed within this period, then the declaration must be based on the valid reading Avalid reading on one or more of the following monitors that exceeds or Is expected to exceed the value shown:
e VRS.1SOO/2SOO > a.20E'cVce
~ SRA-1800/2800 > 5.85E 'cUce
~ SRA-1900/2000 > 5.78E'~ Pdlce 4R-Avalid dose assessment Indicates greater than 1000 mR TEDE or 5000 mR CDE thy/old at the site boundary 4R-Reld sutvey results Indicate site boundary dose rate exceeding 1000 mR/hr p y or a CDE thyroid exceeding 5000 mR for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of lnhalatlon at the site boundary,'nplanned means the release occurred without a Release Permit or the conditions speclfled on the Release Permit have been exceeded.
IF actual release assessment is less than the speclfled limit, THEN E-Plan activfatlon Is not required.
IF the release ls terminated within the time limit,THEN &Plan activlatlon/upgrade ls not required.
However, IF the starting time of the release Is unknown, THEN the time limitIs not applicable and event dedaration should be made as soon as the RMS reading ls validated.
Pageos of Rev.
1
EMERGENCY CONDITION CATEGORIES PMP 2080.EPP.101 Attachment A REcoGNITIDN cATEG0RY: Fuel Damage / Abnormal Radiological Conditions MODES: AS DEFINED ECC R-2:
INCREASING IN-PLANT RADIATION LEVELS UNUSUAL EVENT
- .,
- UNEXPECTED';'INCREASE,IN'::,",::,g:,,--:',;:~
KIANT%AbIATI6N~'LEVELS~Of
>'AiRiiORN'E".CON'O'EN'TRATIO'N';:".":::.:;'X""
ALERT g>RADIATIOgLEVEL'S".WITH(N"<THEa'/~i:.-
- "',FA'C'IL1TY~THAT',
IMPEDE)OPERATION:;:e"-'~"OFISYSTEMS,REQUIRED;TO.":-:".',.!.',.,'4,',"),=,,'.
~MAINTAINSAFE::OPER'ATION'!OR'TO'imp~
- ESTAIILISH;
- ,OR,MA'lNTAIN',COLD;":!,':4.'..',"'<
SITE AREA EMERGENCY GENERAL EMERGENCY g w'"kk<AK@+z'@g~'%&~ ( 4C? 'w$Q Avalid, unexpected reading on an area monitor 1000x higher than the 244our average,
~
Unexpected radiation levels
>15 mrem/hr in any of the following areas:
~ U1 Control Room
~ U2 Control Room
~ Central Alarm Station Not Applicable Not Applicable
~OR-
~
General area radiation level of
>100 mR/hr at any manned local operating station.
Page 2 of Rev.
1
EhtlERGENCY CONDITION CATEGORIES
~
~
Phi'.P'2080.EPP.101-Attachment A, REcoGNmoN cATEQDRY: Fuel Damage / Abnormal Radlologlcal Conditions MODES: AS DEFINED ECC R-3:
LOSS OF WATER LEVEL IN ANYAREA HOLDING IARADIATED FUEL IC UNUSUALEVENT
.";,'AN'NCONTROLi WATER<:".".:j~-':;:
- dhL'EVnEL'DECREASE'lN!A'NmY'AREA'~5
.".,jjOLDINQ.",iRRADIATED,:,FtiELt>;;".~",.:;.
Valid unexpected reading of
>15 mrem/hr In the Spent Fuel area on RS.
ALERT
<pm<pe:.....xg Ihg<<o:.~p" <dms.am mr 'e 'p.&d. ~:
'"'MdAJOmR DhA'M<AdQE:,'TOhIRRAOmIAmTEho'h."".
- ,"
- FUEL'."ORfOSSYOFrWATERaL'EVEL.";,';:::$
'","LRRA'OIATED,";FI)EL."OtITdSID8'OATHS'cW~
Report of visual observation of irradiated fuel uncovered In the spent fuel pool or transfer canaL SITE AREA EMERGENCY g< X<aj<;:;:< dome< >q( C;:o4@Y.;..<oh:,P.
oh:hdtv'<:.).$ Io5
~NOT'.APPUCnASLE 'dpi'm~g~'gg~<":ji~'d'<,: ~r GENERAL EMERGENCY An uncontrolled water level decrease In tho spent fuel pool and fuel trartsfer canal as IndloaIIIIIIIy the receipt of a low low spent fuel pit level annunciator (annunciator 105, drop 27), with all Irradiated fuel assemblies remaining covered by water.
An~on ranned alarm on one of the followlna monitors:
a VRS-1101/2101
~
VSR-1201/2201
~
R-5
~
Manipulator Crane (Portable Monitor)
NR-Inabilityto maintain water level In the spent fuel pool and/or transfer canal at a 643ith all spent fuel assemblIes covered Report of visual observation of irradiated fuel uncovered ln the refueling cavity or transfer canal, Inabilityto maintain refueling cavity level a 64323 feet above the top of the fuel - technical specification limit)with Irradiated fuel ln containment.
Water level < 620or the spent fuel pool and/or transfer canal that will result ln fuel unoovery.
Page 3 of Rev.
1
cia/8c./M
~c.,/zathe Q~ ~three k ~mk(r~
- Wie, W~P(A'r.A;~ g r~/18.
Ac&EZ Adl&~g-07g7 ~cd
~
ucftcnh~.s, LwduQctl.
CUAK CkctSes Q.s dpp.&cats.lht
+ p"Ct~~~ Odd(ea'W pchtI-%reer~(-
lmtce..
Vchll~gevaheS.~e be~< Chzyzg4, 720<a)l 5c
(&9 t.tc/wt)
It.~t~. ~ ea.tQ t~hccthtcwq ct( chvwmavtt~l-LK.p~4ol Pl ttLAcS. ~
ZlOth ROT&7LJ 'tkN Ec%Q M
~~~ <h=~</ch~ pi~ mChwr,~/-/ns 8~/c/oem ECC
~rvtsz54ed 4&rli A~'(i'Q/'5 &i~"~
/Ae.
M~
reyhhhsc 4 6-CP ~ $~ ClarcSie& W ccrc((N5+ ~s ct+ &8<&ch//~$ +5$ dr gzlrhG5'c
/ych/he//rhhtJ Czhie
+< c,h>h /rhhu'~R5g HN ~45/c Ji /4 jrgdres'5'Z,S mD 9 hlus'eeei
/ushered W cc Dimr@zan h" hth~~~ng<
~ED/=irAI/dJ
/~ D 8, jfcfc(kenMcl thhD leap.
gctll~ o$ ZZG /Lttt 4vftL'Leehtht mckudtccst..
0 AcB +St u,tht~~
g.cbee,~
Cggect! 4)
Vt )At ISA m ADDRe~
Q5seRVRmM M~ c~~L..
0 1) 4
EMERGENCY CONDITION CATEGORIES Pb.P'2080.EPP.101-Attachment A ECC UNUSUAL EVENT ALERT REcoGNITloN cATEGCRY; System Malfunctions SITE AREA EMERGENCY MODES: AS INDICATED GENERAL EMERGENCY s-1:
FAILURE OF REACTOR PROTECTION
.";:.NOV)i,iCAik,.",'>.~'~,'-~':,,:;,':. ':.FAILURE OF;.REACTOR;PRO>>TECTIOM-"'l'",SYSTEM'fMsTRUNiENTATIo@<i'o,",-:;~:::4.
"'O'OMj;L>>ET'EO'R:.'IN'ITIATEaN:::.",.',',"-!~:',"',:"",,<
-AUTOMATIC','fIEA'CTOR:".S'CRA>>.M'OMCS.':
PA:REACTOR'PROTECTION.'SYSTEM,,".<,'-".'i
- ":.'.'SEfPOINT.','IfA'O'SEEM'g(CEEDED~A'Nb>
'MANUAL';,SC>>RA'M:;V7AS.:,:SUCCESSFUi,:::,;,'
FAILURE'OF..REACTOR~:";~: ~@~i.Jib>>>
COMPLITE:,'OR;.INITIATE";Al4 UT>>,OMATIC>>REACTOR::SCRAIVI.'.
':'ONCE 'A;REACTOR!'PROTECT>>JOIE@,
- .'SYSTEM,.';SETPOXNT,.;:HAS,SEEM@-,.'-','I
SCRAM:.:VIA'S,:~oT.:,SUCCESSFUI.',"'".FAILURE;OF,REACTOR:
PROTECTI>>ON,+
".,.':SYSTEM';INSTRUMENTATION,"To,", ",",.";
."COMPLETE!AICAUTOMATIC'SCRAIVI
<g
'.;: A'ND.:O'AIIIVAI'.:SCRAIIjtWA'S."~NO
~".~~'":,4-
- ,
- ,succESSFuI~>>AND;,THE>>REIS.,'.=:,,g:;">',-,:,;-'..-',
I,,::CHAL!ANGE",TOUCHE,"ASILITYTO,:P;:,:-j,:.::
gP
'c~
~. ': ~,.; '3p.~'-',>>:,;."< P, Not Applicable AVOWS terminated by manual reactor trip from the control room.
ATWS NOT terminated by manual reactor trip from the control room.
Subcrltlcallty~o Core Cooling CSFSTs are'ED.
Subcrlticallty~o Heat Ink CSFSTs are RED.
Subcrttlcaiity CSFST ls REDID Wide range level In at least 3 SGs Is less than minimum for RCS feed and bleed initiation.'dverse containment values are applicable if adverse containment conditions exist.
Page 1 of Rev.
1
11 1
EMERGENCY CONDITION CATEGORIES PMP 2080.EPP.101-Attachment A REcoGNITloN cATEGCRY: System Malfunctions MODES: AS INDICATED ECC S-2A:
LOSS OF AC POWER'odes 1Q:
IC UNUSUAL EVENT Wibc "<~+d<~P Pvg@lrg@&FN'4Ã'%YFpg:.<"<
",,LO'SS,".OF. ALL'"OFFSITB POWER"TO,;.,'ESSENTIAL":.BUSSES,:FOR,":,~ggj:,';-'",'"-:
jF+rP<r'rj++k)<<<:g7gj@+<~~+j+jp,'.~)P<+gp/i
~ME ~HE switchyard~NSg KV power supplies available to the T-buses for >15 minutes, ALERT
,': ACPONKR~CAPABILITY,,'TO.'g<j',::.,"<oj,";:."
~ESSENTIAL'USSES" REDUCED!TO."A'":".9
- ."SINGLE..'POM/ER."SOURCE;
- I,"Off@.~~;;$4
<".GREATER:%HA'N(16',lNINUTE8:SUCH~<
- fPA'fP'NY
- AbblTIONA'L'"'SINGL'E;'"'",,-<,'".-':"~',
I,FAILURE,.ViOULilRESULT.".IN~,:::',.;"~'."';;::,"',,';,:;',
kSTAT'Iaii'Bi'A'CKOui;:,;".<Yg:.>P"...'-.-,,;::!="-,:;:.,,~
AnyAC power alignment for
>15 minutes that could allow a single failure to cause a loss of all T4uses.
SITE AREA EMERGENCY (LOSS'.:OF ALL':,,'OFFSITE:POWEPf$$
~.
- AND
- :LOSS,'.OF,,:ALL::ONSIYEA'C,:..'Ql
""POIIER~TO:ESSENTIAL'.BUSSES;":<(
Loss of all T4uses for >15 minutes.
GENERAL EMERGENCY
.'..PROLONG'ED,'LOS'S;"OF.'.',OF.,A'Li!Z,-,-.gap
~OFFSITE'Pblh%8iAND,. PRdLONG ED~+i hl.'OSS':.OF<ALL'ONSITEAC;:;POthIER~pg<
~Pc~j,$$';rp~P~+, +i< Ã'w)j~'~~/(4%+@8/4 Loss of all T+uses with Core Cooling CSFST - ORANGE, Loss of all T4uses which Is expected to last for >4 hours.
S-2B:
'."L'Ossa~OF,':"'ArL'L'.",OFFS(TS POW<ER".<T<O,;-:,;-";.
KESSENTIAL.:BUSSES'FORM'S~: '-'.j+'":j
~.GREATER THAN.:.'16'.,MINUTES,;.".";jF>
(LOSS(OF;"AUPOFFSITE: POWER...AND
';.;'.L<OSS'.,OF."A'LL'."<ONSIT'E",A'C!POWER:.;TO',:.-:;
'iESSENTIALrBUSSES,"9URING;:COu).".'j3.
- -'NOT,"'AP<PI.ICABLE :~"""'":: '"'"::""""""'"'-
- ?~? '; <, <<'~~,,:.~;.",:,~'4;;'.;:-'k.;,.'
"',,:;.," ~
NEITHER switchyard ~MR 69 KV power supplies available to the T4uses for >15 minutes.
Loss of power to all T4uses for
>15 minutes.
Not Applicable Not Applicable Evaluate each unit's power supplies separately.
Page 2 of Rev.
1
EMERGENCY CONDITION CATEGORIES PMP. 2080.EPP:1O1 Attachment A REcoGNmoN cATEGQRY: System Malfunctions MODES: AS INDICATED ECC 84:
LOSS OF DC POWER UNUSUALEVENT jUNP'LANNE'D,,LOSS,,O'".."R CUIR ED~~'DC'I, OWER;:DURiNG;COl D >~jp ggv'~<'~ q
- .SffUTDOWN,
- OR:REFUEUNG" ~~&:<,.:<
- MODE;FOR
- GAFFER'!THAICj1 6>%54 ALERT
'"'.':,:<'): ',:,"",," CRt 'a<@N48j"..4?Q<)XV~Q+i F807APPLICA'BLE'~?iPj"j~i'jpgj)"".j~jpj SITE AREA EMERGENCY
,L'OSS"::OFA'U.<VlTAL'"DC':P<OW<ER'gg<
GENERAL EMERGENCY UNPLANNEDloss of DC buses AB
~D CD as indicated by e 220 volts DC.
Loss of DC buses AB AND CD as indicated by bus voltage s 220 volts DC.
Page 3 of Rev.
1
EMERGENCY CONDITION CATEGORIES PMP-2080,EPP.101 Attachment A REcoQNmoN cATEQDRY: System Malfunctions MODES: AS INDICATED ECC SP:
INABILITYTO MAINTAINA UNIT IN COLD SHUTDOWN LC UNUSUAL EVENT ALERT j'!N'aiiiiTY-.'To,kA'iNTAI'N.P'L'ANT:Iii4..':
SITE AREA EMERGENCY
<<L'OSS:,OFjWATER lkVEL';;IM;THE>>,":,
'jREAC1 Ott;VESSEL'-'.YHATgHAS OR::;,::.
-"WILL';VNCOVER'.FUEL',"INj7fiE'@4'.
GENERAL EMERGENCY Mode 6,6 Not Applicable UNPIANNEDloss of shutdovm cooling for >15 minutes.
Inadvertent criticalitywith a concurrent loss of RCS boration capability.
Not Applicable Loss of shutdown cooling resulting in an uncontrolled Increase In RCS temperature that Is expected to exceed 200'F.
Loss of shutdown cooling resulting in core uncovery':
RVUS NR <44% - 0 RCPs IF RVUS ls not operable, THEN core uncovery should be assumed Ifvessel level Is less than 613 feet 6 inches by any available Indication.
Page 4 of Rev.
1
EMERGENCY CONDITION CATEGORIES PtJP 208f',.EPP.<Ot Attachment A REcoQNmoN cATEGQRY: System MalfunctIons MODES: AS INDICATED ECC S-S:
LOSS OF SYSTEMS NEEDED TO ACHIEVE OR MAINTAINHOT SHUTDOWN IC UNUSUAL EVENT ALERT Ng'NP.,~s
.'x '~.pea
. +: ~'.j, pxi j,",:">~.;, ". >cp(
-::.,NOT,'APPUCAeL'E:,-.";:.BP<i-"-'"'~'::"-"::-:;:"::~
SITE AREA EMERGENCY
.".;.COMPLETE::,LOSS.:OF,FUNCTION,;;~:.:;.'NEEDED,:TO ACHIEVE:,OR.;,.',.-,,.:y.'.-.-.':.',.:::'.;.:,MAINTAINiHOT<SHUTD OWNS&4 GENERAL EMERGENCY Modes 1P Not Applicable Not Applicable Inabilityto feed any SG~O all wide range SG levels <29% (43%
adverse containment)'.
Loss of both CCW trains AND RCP seal Infection flowfor >15 minutes.
inadvertent criticalitywith a concurrent loss of RCS boratlon capability.
Not Applicable Page 5 of Rev. t
EMERGENCY CONDITION CATEGORIES PhlP 2080,EPP.101 Attachment A Ecc UNUSUALEVENT RECGGNmoN CATEGGRY: System Malfunctions ALERT SITE AREA EMERGENCY MODES: AS INDICATED GENERAL EMERGENCY S4:
LOSS OF ALARMS OA INDICATION
',i'UNP'LA~iiiiLo's's';OF.,'Mo'sioR'a+V:;:-;."'".-.
,FSAF ElY,sysTEM ANNVNclAlTONOR""';:.,".g~.
I'9/DicATIoN;I/fTt/E',coNTRDL'lRO'ohfgoR~I L'UNPLANNEDLOSS;:OF MOST>OIIALL,"SAFEIY:;""r~~l":;i/
iSYStEM'ANNVNCJATlONORINDICATIOII'gf THE,~:,'
~CONXTROt.:,ROOM;Wjjl,SIH@;tfjA:ekiNIFIrCA'til":,
,,:iNA'e'I'L'ITY':,TO',MON/F'R'.'AQoffiRCANT,.':.i::,".,;j Unplanned loss of most safety syst<<n
~nnundetas h a unit for >15 mbutes.
Unplennd loss of most safety system ennundatas In ~ unit for >15 minutes.
A loss of most safety system onnundetors h
~ unit for > IS niinutes.
Not Appecabl ~
~ Panels 104-114, 119, 120
~ Panels 204-214, 219, 220
~ Panels 104.114, 119, 120
~ Panels 204-214, 2 I9, 220
~ Panels 104-114, 119, 120
~ Panda 204.214, 219, 220
~OR.
A known loss of ell bdications assodetd with tho Mowing per<<neters:
~ Neutron fkrx monitoring
~ Cont<<nment Area High Range Monitor
~ RCS Pressure
~ S/G Level
~ S/G Pressure
~ Pressurize Level
~ Continment Pressure
~ AFWRow
~ CCP, Sl Pump end Sleeker Status end Row Indication
-OR.
A knovm loss of ag hdications associetd with the fogowing parameters:
~ Neutron flux monitoring
~ Containment Area Ifigh Range Monitor
~ RCS Pressure
~ S/G Level
~ S/G Pressure o Pressuizer Level
,, ~ Containment Pressure
~ AFWRow
~ CCP, Sl Pump end Sreaker Statue end Row Indication
~OR.
A kilowilloss of eg bdicatlons assoclat<<l with the fogoviing p<<<<neter<<
~ Neutforl flUxmonitabg
~ Containment Area High Range Monitor
~ RCS Pressure
~ S/G Level
~ S/G Pressure o Pressurizer Level
~ Ccntinment Pressui ~
~ AFWRow
~ CCP, Q Pump and Breaker Status and Row Indication
-ANO.
Compensatory non e4ming bcficatbns for the above annunc/ator panda <<e avegeblo
-AND-h the openion of the Qift Supervisor, tho loss of ennunciators or indications rocpiires haeased survdhnco to safely operate tho unit Annundator/lrxficator loss does not result from a plannd action.
ANO-The plant remains h steady.state corxlitions.
-ANO-In tho opbion of the Qift Supervisor, tho lose of annundetors or bdicetions requires bcreesed surveigence to safe/y operate the unit.
-AND-Annundator/indicator loss does not resuh from a pfennd action
-AND-The plant Is not or does not rernab in ~ ste<<fy-state conditions.
-OR.
Compensatory non.al<<mbg indications for tho
~bove <<urundata penA <<e ~NO av<<labia
.ANO-4 Compensatory non.a4rrring hdicetions for tho above annundator panels ere t/OT evegeblo A significant transient ls b progress Page 6 of Rev.
1
it
EMERGENCY CONDITION CATEGORIES PMP. 2080.HAPP.101 Attachment A ECC UNUSUAL EVENT REcoaNITICN'ATEaoRY: System Malfunctions ALERT SITE AREA EMERGENCY MODES: AS INDICATED GENERAL EMERGENCY S-7 FUEL CLAD DEGRADATION IC
,'~ INDlCATIONl'OF~FUEL'~CLAD~~m~,'"<.:~
- =.DEi'RADATiON';),rA'CTIVk:FUEL'-:,,-':,;'..
Any Indication of fuel clad damage
~
ActMty->1.0pCI/gram I-1st dose equivalent for o 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> In the RCS.
':N01APPLICA'SL'8 '"'-j:>~p<~g<~FNc~"'> "~>j";
Not Applicable Not Applicable Not Applicable
~
RCS acttvlty >too/8 pCI/gram.
Page 8 of Rev.
1
1 P
CI P
EMERGENCY CONDITION CATEGORIES PMP 2OSO.EPP.~Ot
'ttachment A REcoewmow cATEGoRY: System Malfunctions MODES: AS INDICATED ECC 8-8:
EXCESSIVE RCS LEAKAGE UNUSUALMNT pg~p~R zjF~"i7vv":<H'p'cY~~y.'N ~~~vrY~~+pF~p
~REACTOR'COOLANl'rSYST@II.~:~",
~
Pressure boundary leakage >10 gpm.
~
SG tube leakage >t0 gpm.
~
Identified leakage >25 gpm.
~
Unidentified leakage >10 gpm.
ALERT
,'rwz~'<<v+4~~~"'. 'w~;~~.gj,'ev~mgss~;~ N~
.,",SoT::.'APPLicASLE~'~-:j".;..-';;~gg',.;,:.,": $~.':
~prg~x'@ger. g~g>0~5 <~R', r';?Ãr1,':..""'jjgz~ >yj>>
Not Applicable SITE ARSL EMERQENCY
~'.NOT.-,'APPLICABLE',::,;:.y".;,.';",.",",;."'; ',",."":
Not Applicable QENERAL EMERQENCY 4% W%>>:.+~iEr;g"',<w<py8 Not Applicable Page 9 of Rev.
1
J
EMERGENCY CONDITION CATEGORIES PMP 208q.EPP.1O1 Attachment A ECC S-S:
TECH SPEC COMPLIANCE Modes: 1A UNUSUALEVENT
~p yy~r~wyzi>>.@gal.,x~p.pc>, q@~crig.<~p.
.;;;INASILITY,,TO'REACH::REQUIRED>>;:::.-';::
- SHUTDOWN,.VhiHIN;TECHNICAt;-';.
- ,';
ALERT Unit ls NOT placed ln required MODE wlthln Technical Speclflcatlon LCO action time limit.
REcoGNITIQN cATEGQRY: System MalfUnctfolls SITE AREA EMERGENCY MODES: AS INDICATED GENERAL EMERGENCY
'NOTAPPUCABLE-",.:~"'g<ji-'""
~~~""~~":"';,~'"'age 10 of Rev.
1
EMERGENCY CONDITION CATEGORIES PMP 2080.EPP.101 Attachment A Ecc UNUSUALEVENT ALERT REcooNION CATEaoRY: System Malfunctions SITE AREA EMERGENCY MODES: AS INDICATED GENERAL EMERGENCY S-10:
LOSS OF COMI?IUMCATION SYSTEMS Modest ALL Ic gii'N'PtA'N'N'EO!'L'OS'S'.O'F?A'ii<<"."':-"':.",:..'.;"..-:.,."i Unplanned loss of ALLonslte electronlo communication capabilities:
~
Telephone
~
Page system
~
Radios 4R.
Unplanned loss of ALLoffslte electronlo communication capabilities:
~
Telephone (offsite)
~
Microwave transmission
~
NRC phone
~
Load dispatch line
~
Cellular telephones of PM and APMs
- "NoT'APPUcASLe.;"
- -"'",:".,'"".~~a""..':~>:.;::ill
>4.. ~PP4~g,.<
P~ rq/PPPg~i'~f4(g:I;,
Not Applicable
>w, 83
>cj~j+?? Jz>?g+>>'..',8xgyjp'"."q<..?
<<>i>
"NO'f:APPLICABL4~)PP~"~:.";@~'.:gP:;g>'?~~",
.g:;y,>)"v,'x,>"I"..". vpZ>o p'?r?'j.<<~>;c~.v$
Not Applicable w~"4+??~r
<'~"4'j%>"~4?'<%V ~j~g'()4@p( 5'>
Not Applicable Page 11 of Rev.
1
l+-788~
r AIC-EL~~7lDQ 0
pgWWr Z~Zc.
ll 4 l.~
AL has been vwis o* wet.cue.
~ cegerAm g$ +acbv>x QiSS4S Q~Q g.maw ~~~g ~(eg q~~d c~gun~, col Is
~ g mer
~+@Bc.s
EMERGENCY CONDITION CATEGORIES PMP 2080.EPP.10$
Attachment A.
UNUSUALEVENT RECOGNmON CATEGORY: NaturaIIDeetructlve Phenomena (page 1 of 1 )
SITE AREA EMERGENCY GENERAL EMERGENCY N-1 NATURAU DESTRUCTIVE PHENOMENA MODES ~ All EAL
~1 SEISMIC ACTIVITY f.HENOMENA:,INSIDEiTHEiPROTECTEDii r'AIIEA;;OR'ATjTHE RADfOACTIVE..,:";-':;"~~j~~+g SBSMIC ACTIVITY AS INDICATEDBY ACTUATIONOF THE SEISMIC RECORDER (ANN 123 DROP 42)
UNEXPECTED VIBRATIONNOT ATTRIBUTABLETO OPERATING EQUIPMENT CONFIRMED BY CONTACT WITHTHE NATIONALEARTHQUAKEINFORMATION CENTER AT (303) 236-1500 SEISMIC ACTIVITY AS INDICATEDBY ACTUATIONOF THE SEISMIC RECORDER (ANN 123 DROP 42) 4HBjOR UNEXPECTED VIBRATIONNOT ATTRIBUTABLE TO OPERATING EQUIPMENT AND UNEXPECTED PLANT SHUTDOWN DUE TO VIBRATIONAND/ORVISIBLEDAMAGE~ THE PtANT STRUCTURES USTED IN EALIU4 AND CONFIRMED BY CONTACT WITHTHE NATIONALEARTHQUAKEINFORMATION CENTER AT (303) 236-1500 NOT APPUCABLE
,",.NOT>'APPUCA'SLY':~g,,'.ii(~;.
NOT APPUCABLE EAL N-1.2 TORNADOI HIGH WIND TORNADO TOUCHES DOWN WITHIN THE PROTECTED AREA OR ATTHE RADIOACTIVEMATERIALBUILDING REPORT OF ATORNADO STRIKE IN A PLANT VITAI.AREA OR SUSTAINED HIGH WIND GREATER THAN90 MILES PER HOUR NOT APPUCABLE NOT APPUCABLE
. Page1 of Rev. 1
EMERGENCY CONDITION CATEGORIES PMP. 2080IEPP.101 Attachment A ECC N-1 NATURALI DESTRUCTIVE PHENOMENA icontlnuadl EAL N-1.3 VISIBLE STRUCTURAL DAMAGE UNUSUAL EVENT NOT APPLICABLE RECOGNITION CATEGORY: Natural/Destructive Phenomena (page 2 of 3 )
SIGNIFICANTVISIBLESTRUCTURAL DAMAGERESULTING FROM ANYEAL USTED IN THIS ECC TO ANYOF THE FOLLOWING:
CONTAINMENT,AUXIUARYBUILDING, RADIOACTIVEMATERIALBUILDING, ESSENTIAL SERVICE WATER ENCLOSURES, PORTIONS OF TURBINE BUILDING CONTAININGAUXILIARYFEEDWATER STRUCTURES, SYSTEMS, AND COMPONENTS, REFUEUNG WATER STORAGE TANK, CONDENSATE STORAGE TANK SITE AREA EMERGENCY NOT APPUCABLE GENERAL EMERGENCY NOT APPUCABLE EAL N-1.4 VEHICLE COLUSION VEHICLE COLUSION INTO A STRUCTURE CONTAININGSYSTEMS NECESSARY FOR SAFE SHUTDOWN WITHINTHE PROTECTED AREA VEHICLE COLUSION AFFECTING AVITAL AREA NOT APPUCABLE NOT APPUCABLE VEHICLE COLUSION INTO STRUCTURES, SYSTEMS, OR COMPONENTS REQUIRED TO CONTAIN RADIOACTIVEMATERIALAT THE RADIOACTiVEMATERIALBUILDING EAL N-1.6 MAIN TURBINE ROTATINQ COMPONENT FAILURE MAINTURBINE ROTATINQ COMPONENT FAILURE CAUSING VISIBLE DAMAGEOR DAMAGETO THE GENERATOR SEALS MAINTURBINE ROTATINQ COMPONENT FAILUREWHICH PENETRATES THE CASING AND GENERATE MISSILES WHICH PENETRATE ALLAREAS CONTAININGSAFETY RELATED EQUIPMENT, CONTROLS, OR POWER SUPPUES.
NOT APPUCABLE NOT APPUCABLE Page 2 of Rev.
1
EMERGENCY CONDITION CATEGORIES Pi~iIP 208P.EPP.101 Attachment A ECC N-1 NATURAL/
DESTRUCTIVE PHENOMENA (contfnu ed)
MODES N ALL EAL N-1.6 PLANT FLOODING UNUSUALEVENT NOT APPLICABLE RECOGNITION CATEGORY: Nsturai/Deetructlve Phenomena (page 3 of 3)
AlERT FLOODING IN AN AREAAFFECTING SAFETY RELATED EQUIPMENT.
SITE AREA EMERGENCY NOT APPUCABLE GENERALEMERGENCY NOT APPUCABLE EAL N-1.7 EXPLOSION AN UNEXPECTED EXPLOSION WITHINTHE REACTOR PROTECTED AREA OR AT THE RADIOACTIVEMATERIALBUILDING UNEXPECTED EXPLOSION IN AVITALAREAOF THE PIANT, NOT APPUCABLE NOT APPUCABLE Page G of Rev.
1
J/ re~~
~
t II/C 43 ~
AQPFdl pyavrI gPÃCLcerzg Q rpwrr~ ~k~lcdzrrtig /M~~~~
EMERGENCY CONDITION CATEGORIES PMP 208CrEl P.101-Attachment A
~
RECCGNITICN CATEGCRY: Hazards and Other Condftfons MODES: AS INDICATED ECC H-1:
RRE UNUSUALEVENT
'.",FIRE:WITHINPROTECTEtI
'.AREA~P'"::-
>SOVNOA'RYrNOT EXTIN'GUISfiE5,;:;:,;:
Qygg~y~ "+ '@/ger. ~g+r,~wv g's~
P
~~" ~'~'@: '::'i~'; map V.,
~ m~:
ALERT
';;..,FI'R'i.'iFFE'cTINGii'f'E':;o'iEmiiiiir'Y'i'-,:::.:
'.,bF',PLANY...,SAFE,:;SYsTShs,':~;::::.:P;';
"<REQUIRE6 FCRgtIE,"cURRENT.,':.'~~4"~:.
SITE AREA EMERGENCY GENERAL EMERGENCY p4~~%(~4pg'~p~+
%A+N~ i4i4/VQ+QQJNpAC
@:;..w',
Fire within the Protected Area or at the RMB~NT extinguished within 15 minutes of detection.
Rre that affects the operability of systems required for the current operating mode or for safe shutdown.
Fire that causes significant visible damage to plantstructures.'ot Applicable Not Applicable Plant structures refer to the oontslnments, auxiliary buildings, radioactive material building (RMB), ESW enclosures, AFWpump rooms, RWST and CST, Page 1 of Rev.
1
EMERGENCY CONDITION CATEGORIES PplP 208rl.EPP.101.
Attachment A.
REcoGNmoN cATEGCRY: Hazards and Other Conditions MODES: AS INDICATED ECC H-2:
TOXIC OR FLAMMABLE GASES'NUSUAL EVENT (RELEASE,:OF@TOXIC'OR:;::>+PA>~::","..
":;FLAMM>ASL'E:.'.GA'SES,DEEMEti<::;;;";.;:;
',"OETRIMENi'AL",TO'iA'FE;-:;.'.;:~:-'::-',":C~'.,'".,'.
ALERT
,:';RELEA'SE":,OF.,TOXIC!OR','%LA'MMABLE!,i,,:
'j!'GASES,.'VNTAIN'A'.FACILITY,-;",'.8"":;:::;k'..
<'.STRUCTVREQVif1CH,JEOPj4'RDIZES';~".i.-',:
- ,O'i.'ERAT'ION'.
- .;OF,""aYSTEMS,:~iaiiiREO'-";
(TO!ESTABLISH<'OR:.MAlNTAlH'COLDi4'i,::
SITE AREA EMERGENCY GENERAL EMERGENCY Release of toxic or flammable gases wlthln or near site boundary that may affect normal phnt operation.
Report by recognized authority of the need for a partial site evacuation because of off-site toxic gas release.
Toxic gas ln areas that impede safe operation such as:
~
Ut Control Room
~
U2 Control Room
~
Central Alarm Station
~
Other areas based on the actual conditions.
Flammable gas at a concentration near its flammability limitlocated In an area containing safe shutdown equipment.
Not Applicable Not Applicable Asphyxlators such as carbon dioxide are not toxic, but it can be lethal ifentry is required into the area that is oxygen4eficlent.
Thus, oxygen4eficiency Is not a basis for classlfication unless access,to the area ls required for safe operation and access cannot be made because of the personnel hazard.
Page 2 of Rev. 1
EMERGENCY CONDITION CATEGORIES PhllP 2080.f PP.<01.
Attachment A.
REcooNmoN CATEaoRY: Hazards and Other Conditions MODES: AS INDICATED ECC H-3:
CONTROL ROOM EVACUATION UNUSUALEVENT
.;;iOT"'A'i.ijCA'SLEg:,::,:,':".~':,-',,'.,P'-j.:~
ALERT N:.,?~(w~<:y. Ec, jj(,,'MY'???.. gpp 'QAv;?gw~p~ Q?? /',,'r
'.'CONTROL"::.,ROOM:,EVACOAT?IOP;::HAi,.':.,'ITE AREA EMERGENCY
.CONTR'Oi':ROOM:EVACUATION-:.,
".HAS'BEEN;INITIATED:AND>?:"':Yg)+>j:"",",';,
- ."ESTAS'LI'S'jEi'
- :.';::,',.',:;-'::,","-::'.;":::,".;."::;,$~';;
GENERAL EMERGENCY Not Applicable Control Room evacuation has been Initiated.
Control Room evacuation has occurred ANDcontrol'f the following processes is not established within 15 minutes Not Applicable
~ Reactivity
~ RCS Inventory
~ RCS temperature
~ SG heat sink A process is under control Iflt ls stable even Ifdirect operator controls have not been established provided actions have been Initiated to regain direct oontrol of the process.
Page 3 of Rev.
1
J
EMERGENCY CONDITION CATEGORIES PMP> 208'.EPP.iot:
Attachment A.
REcoGNITloN cATEGoRY: Hazards and Other CondItIons MODES: AS INDICATED ECC H4:
SECURITY EVENTS IC UNUSUALEVENT
':::CONFIRMEO<,sECVRITYjEVENT~P@~"
~VNtcH;INblcATEs>",APOTENTIA't;;~
- DEGRAD'ATION3INqTI'fE'L'EIFFEL",'OF.'ij
$ sgljFETY PFITIfEPiL'ANT '":;(jg>':">>'"Ã'~~
+ ".;:'">>,","~:::,~!:::.j:::::.5:;
-:;,j'LERT
'SECURIT>YorEVENT~IN,.;A>PLA'NTkjY SITE AREA EMERGENCY
~jSECURIT>Y:."EVoENT.'IN:A'PL'ANT"."i"';<",.
'gQ~N4~~'~g'+~>""'>>4'k~'xQ>c'>~'
'"~',>wx~<.
GENERAL EMERGENCY Qg'C
~
~ >~
-< %~
P g>>~ cp
'.v>
,':.SECtefcRSI>T>,Y:;EVE>Nut::RmViSNe.'IN":g";,':
~f.CiSS..O>8:"ABLITY,:;:T>O:REACH:ANbj"-.-.:
Any security event which represents a potential degradation In the level of safety of the plant such as:
~ Recommendation from pcotoor>on superintendent or designee'hat ongoing events warrant a UE declaration.
Any security event which represents an actual degradation In the level of safety of the plant such as:
~ Intrusion Into the Protected Area by a hostile force.
~ Discovery of a bomb device within the Protected Area or at the RMB.
~ Recommendation from protection suponnconcronc or designee~ that on-going events warrant an ALERT declaration.
Any security event whfch Indicates likelyor actual Jeopardy to safety systems intended for protection of the public such as:
~ Intrusion into any Vital Area by a hostile force.
~ Discovery of a bomb device within a Vital Area
~ Recommendation from protection supocu>ton>feet or designee~ that ongoing events warrant a SITE AREA EMERGENCY declaration.
Any security event which results In:
~ imminent loss of physical control of a control room.
~ Imminent loss of physical control of a unit's remote shutdown capability.
Recommendation from procoouon suponnconcront or designee~ that on~ofng events warrant a GENERAL EMERGENCY declaration.
Shift Security Supervisor ls desfgnated to act for the Protection Department Superfntendent whenever IMpersonnel are not available.
Page 4 of Rev.
1
QT t
EMERGENCY CONDITION CATEGORIES PMP.2080,EPP.101 Attachment A, RECOQNITION cATEQoRY: Hazards and Other Condjtjons MODES: AS INDICATED ECC H-6 SEC JUDQEMENT Ic UNUSUAL EVENT
- ",:."OTHdEgR,.:'cco'ND'ITIooN'Sr"sEx'I'STINQ<'"::::P'"'WHICH!
IN,'THE'JtrDQEMENT:,OF':~m~
fTHeE::;EMERQENnCY',a(RECTnOR',;-:d)>~/>>
~WARJI'ANTDECL'Al&TIONtOFo."AM':~>>
d <<d.$')~PE'/j. g~~..:N$.'co$Q'v:><<'yj+>go %dog ALERT
- ,OoTHER';CONDITIONS;,EXISTINmQ::;..'~";;,':,,'~.".,
';-;.WHtcH::IN.:.THE':JilDQEMENi;;OFTHE<~
>>qEINERQENCYj DIRcHCTcOR!WARRA'NTj",-<>>,"4
<'0ECLrARA504,'.OF...,'Ag,'ALERT~,',",>>'$g,jj SITE AREA EMERQENCY N"t<t'"'-"'<<'".P4%%'"'. sm"dP';::YmKN!: >:P
"'.OTHERicoNDmONS LEXieSTl'N'0',,';.:d,';
- ,".WHlCH':IN;:.THErJIIOGENlENTOF...',:.;:
i':T'H'E.'EM"ER'Q'ENcCY."riiijECTOR~>>~>>'~
~!WARRmAN7,,,5~CL'AnRnnAe. TIONxOF,,"A":";
.d'SITE<ARcEA;EMERQENCY,',:w~ kPg QENERAL EMERGENCY
';",OoT'HER."CON'DI'T'IO'Ns"",eEXI'ST<<IN'Q,';',".:.',"'.:-.'<<WHICH,,
- IN:.TIE:JmUDQEMENTrOnF.,;TtHE ~
'>>iEMEROEN<<CmY~>DclRECTOII';WARRAIIIT~~>>~<
'~::DECLdARATIObl>~gOF.'A'4ENNAK%<jjj,'~$>',
grggddg
~ oenta )pal)(+ 4~Mt>>gts In the judgement of ths Site Emergency Coordinator, conditions tndtcate atmtentrat degradatton ot the level of safety of the plant.
In the Judgement of the Site Emergency Coordinator,
~
conditions Indicate that plant safety systems may be degraded,
~
Increased monitoring of plant functions Is needed.
In ths Judgement of the Ste Emergency Coordinator, conditions Indicate~tike or actual major failures of plant functions needed for the protection of the public health and safety.
In the Judgement of the Sts Emergency Coordinator, conditions indicate an actual or tmmtnent angstanttet core degradatton wtth tmtenttet toss ot containment from BTHER unit.
Page 5 of Rev.
1
EI
74
&4
~6 &a'az.5'r7r~a rrMMHc:7tneru'c~
h 8~7 SIR/g 6/rrrra C~
Wk'm ~r7 fr 77tLs pekrwrce m re'ZAN
+n'ome ~~e jfg5i'~QIV~7 jf&5 ~E+ ~Wnvc i-7.
+Zcfrl rr'reed~~
YSrc 4c rdu~ Arrl~re mQ A~ 8~r' ~ Er7~cl~~g
<<~ 4~m beenr ~e./eA.cl ~msgr 49 iC//7f'c+rrrFberrr r 'dpgjrcs(aC er ~J4<<~S m~ rue
<CS N~r~w
/~~us CCnS~Skr.l ~rr~
nl~u~aC <u~~Ce (t e>
/res ~as~ ) Aneeup us grdrer 4zp< lirrsoCggeJ )
7fiz p~rdiCl LOSS GFC. ~ 7F~ rPLJ Z~&reM r7eeS gAen7 ~(scD MsrW4-Atrvv Au.'lh'HAÃ8 Q(dence-N k~h~p nWS ~
/C'eP e,p 74, Ze sS mC. ~ ~
A'QS 84rMr~ Aasgeeer
~lseo 4 c44ckck Mre
'7d77-r~geer sperm LUrr7d~g rnnd Ck&@f /eg~nnree A
r
/~M WG'
W Pok~48) Loss m( hz='oeen (+<<seo
< ~~<>>~~<~mq "s Cbsi~k ycgKdi-~
4~ KA(
hho+J'P W added'~>
'Pr~arg 4,S'e~8eg Lcr Wgg ) 'M c A wwc~4o(ied r~t~(.ns. $
&usM~~ G~%~.
lh pok~oE leon ($ Q~~~yy~~g v)c~~w hc c b~z~
V+ 'gggg~Q ~aV~~
~ x&uul S VYlUAVZLQ
I
EMERGENCY CONDITION CATEGORIES PMP 2680.EPf.101 Attachment A FUEL CLAD SAIt/QOI Rrslon product esrrhre I4ference TOMO MODES I, 2. 3, 6 c CONTAINMENTBAfc/QOI Rce BAfc/gDI LOSS SEC Judgamorc'ore Cocrrng CSFST
~ RED CNTMT aaa larristien > 200 R/lv Assessment ol coro damage >6% dsd Iscut ~
RCS ActiwtyLevel > 300 pCI/cc I~ 131 aqciv Vent 0
POTENTIAL LOSS SEC Jtsfgomenc'ao Cooling CSFST -ORANGE
~R Hest Sink CSFST s RED LOSS Urisdsb4 broach of cont Vnmenc
~R Contslnmenc preestxe/sump 4vel NOT pail<<ising Cocle>>tent with expected coAdillor>>
Rapkf ts>>xplss'nsd containment preserve or
~ump level deaease fogowkrg prcsstee Increase caused by LOCA Enny Into ECA 'l.2. LOCA OUTSIDE CONTAINMENT
~R Primary to second<<y 4ak rate > T.S. rimit ANDtx>>ontrd4d rs4ese of secondary codsnt from the associated SG to the
. environment ls occtsrlng O
I OTENTIALLOSS Contdrvt>>nc Crhlcsl Safety Funcclon Ststw Tree ~ REO
~R-Hr greater than CTI
~R-Both CTS Trains Inoperab4 OR lail to
~utomsticslly st<<t on HATHI cont Vnment pfseers o
~R-Both CEO I<<>> inopasb4 OR fail lo
~utematlcsgy actuate oA KI&lccntdninent piesslso
~R Contsevnent piseerxe exceeds 30 peig
~h Conc ainrnant Kr conosnu stion
> 0.6IC ANO H, conud eqdpment Inopcr sbre EXCESSIVE/E leakage rate es Indicated by
~ Pressteo Bound<<y > 10 Qpm
~
SG Tube 4sksge > 10 gpin
~ Indaxirrad Leakage > 26 gpnt
~ UridenQied 4skago > 10 gpm-0 LOSS RCS 4ak rate Qrasta than
~vsilsb4 makeup cspsdty ss faceted by ~ comp4lo lose of RCS eubcoosng Entry Into SGTR IE.SI A nonisdsb4 eecandsry bne break or ~ pro4nged ro4sse of contamhated secondary coolant iootf&lgIn ~ r<<rrosctlvo re4aso 'lo the environment fran tho affected sto<<rl gar>>rata Contdnrnant'Area Radiation > 10 R/hr WR-SEC Iudgement po'TENTIALLoss RCS Incegrity Critkd Safety Function Statw RED OR Hest Sink Crhicd Safety Function - RED OR-UNISOIABLERCS leakage gros'tor tl>>n CapoCrty of oAO ccnuifugsl charging ptsnp In norm V charging mode Rupttxod ate <<rl Qeflofster greater then capadty ol cna d>>igfng ptsnp In normal chagbtg mode SEC Iudgement SEC Judgement Contdnmsnc aoa l<<rrst4A > 1000 R/hr
~R Asseesmenc ol cae damage > 20IC d<<l far%re Coro Coerrng Cndcel Safety Function Status Tree RED ANO Rsstast4n procedtses ere not etfactive within 16 riinutes SEC Judgemenc Once a barrier has been dedared lost, the symptoms of the loss may disappear.
SEC judgement should be used to determine whether to continue to carry the barrier as lost. Ifthe abilityto monitor a barrier is degraded, the SEC must use judgement to determine the barrier status.
Ifno turnaround In safety system performance is expected and escalation to Site Area Eme/gency or General Emergency is expected within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, then IMMINENTbarrier degradation should be determined and the SEC should make the appropriate emergency dassification.
I Page 1 of 6 Rev.
1
r b
0 DONALD C.
COOK NUCLEAR PLANT BASIS FOR EMERGENCY ACTION LEVELS ECC CATEGORY NAME, EMERGENCY CLASS, AND DESCRIPTION S.3:
UNUSUAL KVENT -
Loss of Vital 250 Volt DC Power INITIATINGCONDITION Loss of +11 250 Volt ESF DC power during Cold Shutdown OR Refueling mode.
MODE APPLKABILITY Cold She%down Refuel$ ng EAL-THRESHOLD VALUE 250 VDC Battery buses 1A, 1B, 1H, 2A, 2B, and 2H less than or equal 220 volts.
BASIS (References):
The threshold valve was chosen to recognize a loss of ESF DC buses compromising the ability to monitor and control the removal of decay heat during the Cold Shutdown and Refueling modes.
lhetbceshold valuu. was chosen to recognize a loss of DC power at a voltage level low enough to be indicative of a severe contr+1 system problem.
The value is high enough to provide reasonable assurance that the 250 volt batteries will last at least 15 minutes prior to reaching a designed minimum voltage of 210 volts.
TERMINATION/RECOVERY CONSIDERATIONS Power is restored to at least one 250 volt ESF DC bus and an investigation as to the cause is underway.
S3 UNUSUAL EVENT
February 21, 1996 Fission Product Barrier Classification Table; Containment Barrier:
AEP will revise the containment pressure level for potential loss to design vice expected failure pressure.
AEP will reevaluate need for list of excessive leakage rate under potential loss.
A list of attendees is provided as Attachment l.
Attachment 2 contains the discussion slides use at the meeting.
If there are any questions regarding this meeting
- summary, please contact me at (301) 415-3017.
r a
Docket Nos.
50-315 and 50-316,- ',
'ttachments:
As stated (2)i',
cc w/att:
See next page DISTRIBUTION::
sDocket File- (wJatts 1
& 2)
PD 3-1 Reading.(w/atts 1
& 2)
ACRS (w/att 1)
E-NAIL W. Russell/F.
Miraglia J.
Roe J.
Hannon C. Jamerson L. Cohen W. Maier B.
McCabe Original Signed By:
John B. Hickman, Project Manager
, Project Directorate III-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation PUBLIC (w/atts 1
& 2)
OGC (w/att 1)
R.
Zimmerman E.
Adensam J.
Hickman E. Jordan J. O'rien S. Klementowicz W. Kropp, RIII cc:
Licensee
& Service List (with all enclosures)
DOCUMENT NAME:
G:iWPDOCSiDCCOOKiC089878.SUM To receive a copy ot th/a doctanent, In&cate In the box:
C' Copy withorrt attachment/enctoeue E'
Copy with attachment/enctoerae k'
ko copy OFFICE DATE LA:PD31 N
CJamerson 2/ lS/96 BC'RB L-PM: PD31 C
JHickman 2/ lW/96 2/ZL /96 0
CIA CORD COP D: PD31 JHannon 2/>< /96
II J
I I
I'I h
I t'I, I
t I
I.
n, (I
I r,
Il tt t
tt 0 p' I
I I
>(
ttt
,I I
i II i,
Ji I
ft
,I I
tt I
I
'J '
I tt I
I, tt 't I