ML20081B680
| ML20081B680 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 01/10/1984 |
| From: | Cooney M PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| PROC-840110-01, NUDOCS 8403090285 | |
| Download: ML20081B680 (93) | |
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~ ,,'c Uf6tTED STA1 E L 1
5'*,., NUCLEAR REGULATORY COMratsstON !
; .g - ' ,' 'g p W ASHINGTON, D. C. 205M 4((%
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,/ 11 arch 7,1984 i
50-277/278 Peach Bottom MEMORANDUM FOR: Chief, Document Management Branch, TIDC FROM: Director, Division of Rules and Records, ADM
SUBJECT:
REVIEW 0F UTILITY EMERGENCY PLAN DOCUMENTATION The Division of Rules and Records has reviewed the attached document and has determined that it may now be mAde publici available.
/ / I
. M. Felton. Director I -
ivision of Rules and Recor Office of Administration
'['/[
Attachment:
As stated / 8403090285 840110 PDR ADOCK 05000277 PDR l F l l I l r
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February 10, 1984 Re: Docket Nos. 50-277 50-278 Dr . T. E. Murley, Administrator Region I , Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
Dear Dr. Murley:
Enclosed are two copies of additional revisions to the Peach Bottom Atomic Power Station Emergency Plan Implementing Procedures. These procedures are submitted, within 30 days of the change, per regulations in 10 CFR 50, Appendix E, Section V. The procedures being submitted are the following: EP-101, Rev. 8 EP-209 App. D-3, Rev. 9 EP-102, Rev. 8 EP-209 App. D-5, Rev. 6 EP-205A.12, Rev. 3 EP-209 App. D-7, Rev. 10 EP-206A, Rev. 6 EP-209 App. E, Rev. 10 EP-209 App. C, Rev. 10 EP-209 App. H, Rev. 8 EP-209 App. D-1, Rev. 7 EP-209 App. I-1, Rev. 12 EP-209 App. P, Rev. 8 Pursuant to Section 2.790 of the Commission's regulations, it is hereby requested that the telephone numbers listed in procedures EP-102; EP-209, App. C; EP-209, App. D-1; EP-209, App. D-3; EP-209, App. D-5; EP-209, App. D-7; EP-209, / App. E; EP-209, App. H; EF-209, App. I-1; EP-209, App. P, be withheld from public disclosure. An affidavit setting forth the g -._ grounds in support of this request is attached hereto.
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i Dr. T. E. Murley Page 2 i e Two copies have been sent under separate cover to the Document Control Desk. i Very truly yours,
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M. J. Cooney Manager, Nuclear Production Electric Production Depar tment 9 KWS:mlh Enclosure U cc: Document Control Desk U.S. Nuclear Regulatory Commission Nashington, DC 20555 Site Inspector - Peach Bottom bcc: V. S. Boyer w/o attachment J.S. Kemper w/o attachment E. J. Bradley w/o attachment R. H. Moore w/o attachment R. S. Fleischmann w/o attachment L. B. Pyrih w/o attachment R. H. Logue/RAK w/o attachment DAC
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~En Index-
, .2DKCCY PLAN PIOCIDURES INO#f Pnqe 1 i RECEIVED Rev. 30
- py3c3g atymy. t& LIT 12 AND 3 01/10/94
- C Wurt>cr JAtt 171984 neyic. . nny, u nyir.icn Title nate ' lo . natn R.A.KANKUS EP-101 Classification of Emergencies 01/10/84 R 01/10/94
- 1;P-102 Unusual Event Response A 01/10/'d
- 01/10/P4 EP-103 Alert Response 08/01/93 9 09/01/83 EP-104 Site Emergency Response 08/01/83 0 08/01/83 EP-105 - General Emergency Response 08/01/G3 4 08/01/83 t;P-110 Personnel Assembly and Accountability OG/20/83 1 Of./20/83 t
' ~ EP-201 Technical Su;riert Center ('niC) Activation 06/01/93 6 08/01/03 EP-202 Operations Support Center (030) Activation 10/27/03 5 10/27/93 :
#-z0.$ b:.nrgency Operations Pacility '
y (liDF) Activation OR/01/93 6 OR/01/03 r.P-205 Radiation Protection Tea Activation 04/25/R3 4 04/25/93 1 EP-205A Chemistry Sampling and Analysis Group 05/25/02 4 DV25/92 l , UP-205A Operation of Post Accident
.1 sampling Station 11/24/93 4 11/29/93 EP-205A Obtaining Drywell Gas Samoles
.2 from Containment Atmosphere Dilution Cabinets 05/26/02 0 05/26/92 ,
EP-205A Retrieving and Changing Sample
.3 Filters and Cartridges from the Drywell Radiation Monitor During Emergencies 04/25/n3 1 04/25/83 EP-205A Obtaining Drywell Gas Samoles
.4 from the Drywell Radiation Monitor ~ q, Sampling Station 05/25/P2 0 05/25/12 t.P-20SA obtaininq Reactor Water Samples
.5 from Sample Sinkn Following Accident Conditions 05/25/n2 0 05/25/P2 -
iT-205A Obtaining Canal Discharge Water
.6 damples Follcwing Radioactive Liquid .
Rolcaces After Accident conditionn 05/25/R2 05/25/87 4
^ 5&. .;C- . -
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- EP Inilex *
*, 1:MElGE:JCY PIAN P!OCEDURES INDPX Pagm 2 !
i , Rev. 38
- i j PEACH DOfICH UNITS 2 AND 3 01/10/84 *.
- Review Rev. Revision j Ntrrber Title Date Mo. Date
*'S
! iP-205n obtaining the Iouine and , p .7 Particulate Sa..ples frca the !'.ain Stack and Hoof Vents Following l ACx:ident Conditiano 11/21/03 2 11/21/83
. EP-205A Obtaining T,,iquid Itadwaste Samples
.8 from Radwaste Sample Sink Following Accident Conditions 05/25/32 0 05/25/02 EP-205A Obtaining Samples from Condensate
.9 Sample Sink Following Accident Conditions 05/25/02 0 05/25/82 EP-205A obtaining Off-Gas Samples from
. .10 the Off-Gas Hydrogen Analyzer vollowing Accident Conditions 05/25/82 0 05/25/82 CP-205A Sample Preparation and
.11 standling of Highly Radioactive Liquid Samples 11/21/83 1 11/21/83 de-205A Sample Preparation and Handling
.12 of liighly Radioactive Particulate Pilters and Iotline Cartridges 01/10/84 3 01/10/84
- 1
/ EP-205A Sample Preparation and Handling of
.13 Hig'n ly nadioactive Gas Samples 11/21/83 1 11/21/83 1:.e-205a offcite Analysis of High
.14 Activity Samples 11/23/83 0 11/23/83 EP-2053 Icxliation Survey Grcups 04/25/83 4 04/25/83 .
-<-a w Personne,1 Dostmetry litoassay -
and Hespiratory Protection Group 04/08/82 2 04/08/82
' EP-206 DELETdD DELRTED i.;P-206A Fire Fignting Group 01/10/04 6 01/10/84
- EP-206u Damage hepair Group 05/31/83 3 05/31/83
. 1:P-207 Perconnel Safety Team Activation 04/25/33 5 04/25/A3 i i EP-207A Searcn and Rescue 04/13/83 3 04/13/83
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EP-2073 DaLETED DELRTED EP-207C First Aid 04/25/83 3 04/25/83 EP-207D dvacuation Ascombly Group 04/25/83 3 04/25/83 E
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-- .__.. .~ _ _ _ _ .j EP Irxlex
.' EMERGEA'."I PIAN PROCEDURES INDEX Page 3
! . Rev. 38
- l PFAC11 Dor 101 UNITS 2 AND 3 . 01/10/,84.*
3 . j Review Rev. Revision j Numocr Title Date No. Date t i EP-207E Vehicle and Evacuee Control ' I Procedure 08/01/83 2 08/01/83 1 EP-2071' Vehicle Decontamination Procedure 05/31/03 1 05/31/83
- EP-208 Security Tean 05/31/03 1 05/31/83 EP-209 Telephone List For Emergency Use 12/23/82 6 12/23/82 EP-209 Intnediate Notification Call List Ar)cndix i A 08/23/83 8 06/24/83
- t EP-209 DELETED DELETED Appendix 3 EP-209 Peach Bottom Station Supervision Appendix C 01/10/84 10 01/10/84
- EP-209 On Site c2aergency Team Leaders A14)endix D-1 01/10/84 7 01/10/84
- EP-209 Radiation Protection Team Appendix D-2 11/23/83 11 11/23/83 EP-209 Fire and Damage Team
.sppendix D-3 01/10/84 9 01/10/84
- EP-209 Personnel Safety Team
- Appendix D-4 11/23/83 11 11/23/83 5 EP-209 Security Team
. Appendix D-5 01,'10/84 6 01/10/84 * -
EP-209 Ite-Entry' and Recovery Team
. Appendix D-6 08/23/83 3 04/11/83
, EP-209 Technical Support Center Group Appendix D-7 01/10/94 10 01/10/84
- EP-209 Corporate Emergency Team Leaders and Appendix E Support Personnel 01/10/84 10 01/10/84 2
^
EP-209 U. S. Government Agencies
.%)pendix F 08/23/83 5 06/24/83 EP-209 cergency flanagement Agencies Appendix G 08/23/83 3 04/11/83 b EP-209 Company Consultants ~
<4)pendix 11 01/10/84 8 01/10/84
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. , EP Index th2O2CY PT.W4 PIOCf2XIItES INDEX Page 4
" *' Rev. 3R
- PEACH B7ITG1 UNITS 2 AND 3 01/10/84 *
. ~'a -
Review Rev.'Revicion Numoer Title Date No. Date
~"g EP-209 Ficld Support Personnel Appendix I-l
- 01/10/84 12 01/10/04
- EP-209 Cnemistry & Health Physics Contractor Appendix I-2 Call List 11/23/83 9 11/23/83 EP-209 Nearby Public and Industrial Users
- , Appendix J Of Downstream Waterc 08/23/83 5 06/24/83
- EP-209 Miscellaneous appendix K 08/23/83 6 06/24/83
%o EP-209 Incal Plro Phones Appendix L 09/19/83 4 09/19/83 EP-209 DELUTED DELETED Appendix M
, he-209 Medical Support Groups Appendix N 08/23/83 6 06/24/03 SP-209 Staffing Augmentation - 60 Mirrte
appendix P Call Procedurc 01/10/84 8 01/10/84 * ( EP-210 Dose Assessment Team 04/25/03 0 04/25/83 i:.P-301 Operating the Evacuation Alarm and Pond Page System 12/23/82 1 12/23/82 I EP-303 Partial Plant Evacuation 06/20/83 2 06/20/83 'f 8P-304 DELETCD -
- P-305 Site Eva*cuation 06/21/83 5 06/21/83 i:.P-306 Evacuation of the Information Center 05/25/82 2 05/25/82 rP-307 Reception and Orientation of Support Personnel 04/12/02 0 04/12/82 cP-311 11andling Personnel with Serious
- i Injuries, Rodioactive Contamination
- 8xposure, or Lxcessive Radiation .
j Exposure Dnergency Director Functions 04/08/82 3 04/08/82
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CP-312 Racioactive Liquid Release (Emergency '. Director Functions) 04/13/83 1 04/13/R3 EP-313 Control of Thyroid Blocking (KI) Tablets 04/08/82 0 04/08/82 - r e
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- EP Index
., ?, DEHGdNCY PTR4 P10CEDURES INDCX Paq2 5 Rev. 38 * .
PF121 DOMQ4 UNITS 2 AND 3 , , 01/10/84 * { I Review Rev ' Revision l Number Title Date No. IMte i ~ j') _ EP-316 Cumulative Population Doce Calculations 05/31/93 3 05/31/83 EP-317 Direct iteccanenuations to County Emergency W ement and Civil Defense Agencies 05/31/83 2 05/31/R3 EP-318 Liquid Itelease Dose Calculation Method for Intake Water at
. Downstream Facilities 04/13/83 1 04/13/R3 ,
i EP-319 Liquid Release Dose Calculation
- Method for l'ish 04/13/83 1 03/13/83 '
dP-320 Procedure for Leaking Chlorine 03/12/82 1 03/12/82 , EP-325 Use of the Containment Radiation .tanitor to Estimate Jelease Source Term 06/09/82 0 06/09/82 EP-401 Entry for Emergency nepair and ~ Operations 04/13/83 4 04/13/83 s EP-500 Revisi and Revision of Emergency Plan (FSAR Appendix 0) 04/01/81 0 04/01/81 1
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,_ '. CONTROLLED Appgoir.? COPY-
- EP-101 101D F Ci1005 I g gj Pag 3 1 of 3, Rev. 8 ggy RLG:1 jpc DIST3!aUTION: '
l l Centr 31 N2 .,,. _..__ PHILWELPHIA ELECTRIC COMPANY jg y j g ,cp,9
* ;-u t e S.:pe r . . . . .. PEA 31 BOTIOM UNITS 2 AND 3 Cflice --C -ENC ( PLAN IMPLEMENTING PROCEDURE
( I EP-101 CLASSIFICATION OF EMERGENCIES t 1 -t PURPOSE To define the method of classification of an event or condition into one of four emergency classifications as described in the Emergency Plan. Additionally this procedure details the method of de-escalation from one emergency action level to another. d REFERENCES 0
- l. Peach Bottom Atomic Power Station Emergency Plan
- 2. NUREG 0654 Criteria for Preparation and Evaluation of Radiological Emergency Response Plans and Preparedness in Support of Nuclear Power Plants.
- 3. EP 102, Unusual Event Immediate Actions
( 4. EP 103, Alert Immediate Actions ,
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- 5. EP 104, Site Emergency Immediate Actions
- 6. EP 105, General Emergency Immediate Actions ACTION LEVEL
; Implemented this procedure whenever Shift Supervision detects conditions . ; which meet the Emergency Action Levels in Appendix EP 101, Classification Table.
IMPLEMENTATION OF THIS PROCEDURE DOES NOT CONSTITUTE IMPLEMENTATION OF THE EMERGENCY PLAN. =* PRECAUTIONS THE JUDGEMENT OF THE EMERGENCY DIRECTOR IS VITAL IN PROPER CONTROL OF 1 AN EMERGENCY AND TAKES PRECEDENCE OVER GUIDANCE IN THE EMERGENCY PLAN PROCEDURE. _ _ . , r IMMEDIATE ACTT03 , 1.0 Shift Supervision or Emergency Director shall: 1.1 Select affected categories related to station events e or conditons. :
,l EP-101 j Paga 2 of 3, Riv. 8 N '
l i 1 IMMEDIATE ACTIONS (cont'd) - s 1 Reference ! [] " Pages in 4 Appendix , Category EP-101 a Unplanned Shutdown 1 Personnel Injury 2 J Primary Containment Integrity 3 Radioactive Material Release 4 I Fire 5 t Environmental 6 I Loss of Power 7 Secondary Containment 8 Instrument Failure 9
'% Fuel Damage 10 s
f Hazards to Station Operation 11 Control Room Evacuation 12 i See Contingency Plan Security 1.2 Beginning at the indicated page in Appendix EP 101, review - 't the Emergency Action Levels for all categories selected. 1.3 If the more severe events or conditions are classified as an Unusual Event, implement EP 102, " Unusual Event Response." 1.4 If the most severe events or conditions are classified as an Alert, implement EP 103, " Alert Inunediate Response." i 1.5 If the most severe events or conditions are classified as a Site Emergency, implement EP 104, " Site Emergency Response." , 1.6 If the most severe events or conditions are classified as a _ _ _ - . General Emergency, implement EP 105, "Ceneral Emergency Response." e 9
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* . CP-101 Pags 3 of 3, Rzv. 8
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FOLLOW-UP ACTIONS ' i 1.0 If event is classified as Alert, Site Emergency, or General Emergency, ( Shift Supervision or Emergency Director shall: 1.1 Periodically evaluate the event classification as listed on j attached Appendix EP-101. Based upon results of corrective - action taken to recover from the emergency situation, escalation or de-escalation of the emergency action level classification will be decided upon by the Emergency Director or Interim Emergency Director. (It is preferable, but not mandatory, to ; obtain concurrence from the Site Emergency Coordinator and Corporate Headquarters prior to classification reduction). The NRC and appropriate off-site authorities at the Emergency Operations Facility all be informed of the decision to move
; from one emergency class to the next. All agencies or personnel listed in checkoff lists of EP's 102, 103, 104, and 105 shall i be informed as a minimum. ! 1.2 Provids written summary within eight hours to the NRC concerning i basis and circumstances surrounding reduction of emergency action level or closeout of the emergency.
2.0 If event is classified as an Unusual Event, Shift Supervision or Emergency Director shall periodically evaluate the event classifi-cation as listed on attached Appendix EP-101 and escalate or de-escalate the emergency action level if necessary. All appropriate agencies or personnel shall be notified using the appropriate check-
,. s off lists of EP-102, 103, 104, 105.
3.0 When the emergency has been mitigated and the power plant and auxiliaries have been placed in a safe shutdown condition, only then will a decision be made as to whether a recovery phase is justified. To enter the recovery phase after the emergency or accident situation is considered
; no longer in effect, the concurrence of the Site Emergency Coordinator, Emergency Director, the Emergency control Officer at d Corporate Headquarters, and Federal and State Government Liaison
/ is required. The recovery phase is a departure from an emergency a situation. The Site Emergency Coordinator and' Emergency Director
' evaluates plant operating conditions as well as the in-plant and out-of-plant radiological conditions in this dccision. Notifications to the various individuals and agencies that the recovery phase has been implemented is the responsibility of the Site Emergency Coordinator.
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. . . Page 1 of 12, nev. 8 UNPLANNED SHUTDOWN
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UNUSUAL EVENT ALERT
} '. UNPLANN1;D SilUTDOWN -
SCRAM WITH TRIPLE g LEVEL
- 1) controlled shutdown due to failure 1) scram alarm and
, to moot L.C.O. 2) double low level alarm (-48") and
-! 2) any scram other than planned 3) triple low level alarm (-130") and
- 4) increase in containment pressure to greater than 1 psig but less than 2 psig on PR-2/3508 SCRAM WITH SMALL LEAK
, 1) scram alarm and
- 2) double low level alarm (-48") and
- 3) triple low level alarm (-130") and i
- 4) containment high pressure alarm (2 psig) and
- 5) containment pressure 2 psig or greater on PR 2/3508 4 9 t
g SITE EMERGENCY GENERAL EMERGENCY
. SCRAM WITH LOCA SCRAM NITH LOCA & NO ECCS
- 1) scram alarm and 1) scram alarm and
- 2) double low level alarm (-48") and 2) double low level alarm (-48") and
- 3) triple low level alarm (-130") and 3) triple low level alarm (-130") and
- 4) containment high pressure alarm 4) active fuel range level indicatiion (2 psig) and shows less than -226" on LI-2/3 Sa) containment pressure 10 psig or 3-91A, B and greater on PR 2/3508 g 5) failure to reset triple low level l
Sb) containment dose rate greater than alarm after 3 minutes and 105 R/hr on RI-8/9103A/C ar.J 6) containment high pressure alarm RI-8/9103B/D (2psig) and
. 7) containment pressure greater than 20 psig on PR-2/3508 or
- 8) containment dose rate greater than
. 106 R/hr on RI-8/9103A/C and .
RI-8/9103 B/D __ _- . 9 2 9 up
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. ___ _ . . . - _ _ . . _ . ._ .. _ _ _.._._ _ ~_ _ _ _ . . 1Z T I AIPEND I X Eli- 1 O I Paga 2 of 12, R2v. 8 h' -
P E R S O N N E L I N J.U R Y' i UNUSUAL EVENT ALERT l l (h. . l l r } i 's N/A f INJURY WITH EXCESS RADIATION EXPOSURE OR ) CONTAMINATION ? 1) Contaminated injury warranting off-
. site medical treatment or
- 2) an acute whole body exposure j greater than 3 R i
e 4 d t +
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I SITE EMERGENCY GENERAL EMERGENCY I
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- i N/A N/A t
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Page3of12,1kov.g i PRIM ARY CONTAINMENT .
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l t l UNUSUAL EVENT ALERT l l ( LOSS OF PRIMARY CONTAINMENT INTEGRITY l 3 NON-ISOI.ABLE LEAKAGE , Ls) l) Primary containment leakrate 1) Reactor Building vent rad effluent I is greater than 0.5 percent of high rad alarm and inability to i volumo per 24 hrs. at 49.1 psig or, maintain pressure greater than
- 2) N2 makeup system is not capable of 0.25 psig on narrow range
- maintaining pressure (not due to PR-2/3508 oJ_
, lack of N 2). 2) Torus Room flood alarm with level decrease in torus I FAILURE TO ISOLATE PENETRATION WHEN ISOLATED BY A TRANSIENT e
' 1) incorrect valve position during
; Group I, II, or III isolation alarms a
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SITE EMERGENCY GENERAL EMERGENCY l LOSS OF PRIMARY CONTAINMENT INTEGRITY
} WITH LOCA i ; 1) erratic containment pressure N/A fluctuations above alarm setpoints of 1.5 psig, and
- 2) Group II and III isolation alarms, and
. 3) Containment dose rate greater than 105 R/hr on RI-8/9103A/C and RI-8/9103B/D and SITE EMERGENCY
- 4) Reactor Building area high temper-MM SS O R R NTA M M HIGH
. Mo tor P 2 3- 8 RADIATION i abnormally high, and Reactor Bldg.
i vent rad effluent high alarm, o_r r 1) containment high pressure alarm. Main Stack Rad effluent on PR 0 (2.0 psig), and
- 051 increasing due to SGTS opera- 2) scram, and ._'
tion. 3) containment dose rate greater tnan 105 R/hr on RI-8/9103A/C and RI-8/ 9103B/D, and
- 4) Reactor BTdtf Area Rad Monitors Alarming, and _
- 5) Vent Stack Rad Effluent moniter high alarm l
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APPENDIX EP-101
' I l Paga 4 of 12, R3v. 8
'. l 1
R ADIO ACTIVE R.ELEASE .
]
j UNUSUAL EVENT ALERT l l' ,) INSTANTANEOUS RELEASE EXCEEDING TECH ACTUAL OR POTENTIAL RELEASE 0.01 REM SPECS WHOLE BODY OR 0.05 REM THYROID 5 1) A spiko on rad offluent monitors: 1) Uncontrollable release for more than i a) Main Stack greater than 6 x 103 20 minutes from the:
- cps on RR 0-17-051, or a) main stack greater than 1 x 103 cps b) Reactor Bldg vent greater than on RR 0-17-051 or 4 x 104 cpm on RR-2/3979 or b) Reactor Bldg ve d greater than F 2) Analysis of particulate filth s or 5 x 104cpm on RR-2/3979 g charcoal cartridge: 2) Continued particulate or iodine re-a) Main Stack greater than 5 x 10 1 lease such that analysis of particu-uC1/sec, or late filter or charcoal cartridge b) Reactcr Bldg vent greater than results in the following estimated 4 x 101 uCi/sec release rates:
a) main stack greater than 5 x 102 uci/ sec or i RELEASE EXCEEDING TECH SPEC b) Reac Er Bldg vent greater than QUARTERLY LIMIT 3 x 103 uCi/sec g
- 3) Containment dose rate greater tran
- 1) A report of the summation of 104 R/hr on RI-8/9103 A/C and individual release data within RI-8/9103 B/D the quarterly period.
( SITE EMERGENCY GENERAL' EMERGENCY
'! ACTUAL OR POTENTIAL RELEASE 0.1 REM ACTUAL OR POTENTIAL RELEASE 1.0 REM WHOLE BODY OR 0.5 REM THYROID WHOLE BODY OR 5.0 - REM THYROID '
1 i
- 1) Uncontrollable release for more 1) Uncontrollable release for more than than 20 minutes from the: 20 minutes from the:
a) main stack greater than 1 x'105 cps a) main stack greater than 1 x 104 cps on RR 0-17-051 or on RR 0-17-051 or b) Reactor Bldg. vent greater than b) Reactor Bldg vent greater than 5 x 105 cpm on RR-2/3979 g 5 x 106 cpm on RR 2/3979 or_
- 2) continued particulate or iodine re- 2) continued particulate or iodine re-
- lease such that analysis of particu- lease such that analysis of particu-late filter or charcoal cartridge late filter or charcoal cartridge l'
t results in the following estimated results in the following estimated i release rates: release rates: I' a) main stack greater than 5 x 103 a) main stack greater th:r 5 x 10 4 uci/ I cCi/sec or sec or . I b) Reactor Bldg vent greater than b) Reactor Bldg vent greater than 3 x 105 uCi/see or 3 x 104 uCi/sec or I 3) containment dose race greater than 3) containment dose rate greater than 105 R/hr on RI-8/9103A/C and 106 R/hr on RI-8/9103A/C and RI-8/9103B/D RI-8/9103B/D S
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APPEND 1X EP-101 t
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- Paga 5 of 12, Rsv. 8
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l- . FIRE .. - UNUSUAL EVENT ALERT
', 1 PIRC IN PFarCCTUD AREA LASTING 10 MIN. FIRE WHICH COULD MAKE AN ECCS INOP CR MORE AFTER INITIAL ATTEMPTS 'IO EXTINGUISH IT 1) Fire alarm and verbal report from SSV ; 1) Alarm and verbal report from SSV i
I e 4 .I i 's - ( .~,, SITE EMERCENCY GENERAL EMERGENCY FIRE WHICH MAKES AN ECCS INOP FIRE WHICH CAUSES DAMAGE TO PIANT SYSTEMS SUFFICIENT TO LEAD TO OTHER GENERAL
- 1) Fire alarm and verbal report EMERGENCIES from SSV
- 1) Fire alarm and verbal report from SSV, and LOCA sympt. oms, ECCS, 'or
, containment failure 1
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- 1
. _ _ . _ _ . - - - ---- - -- - . -- - Z_ ,T APPENDIX EP-101 Pago 6 of 12, Rev. g E N V I R O N M E N T.A L .--
! UNUSUAL EVENT ALERT L
.Q CAlti'llt,)UAXC EARTIfQUAKE a
Q .
- 1) An actual carthquake detected by 1) An actual earthquake beyond the ,
soismic instrumentation systents Operating Basis Earthquake (OBE) ABNORMAL POND LEVEL ABNORMAL POND LEVEL
- 1) Conowingo Pond level on LI-2/3278A, 1) Conowingo Pond level on LI-2/3278A,B,
- B,C: C a) greater than 113 feet or a) greater than 115 feet o_r_
b) less than 104 feet without prior b) less than 98.5 feet without prior -' notification by L.D. notification by L.D. TORNADO TORNADO
- 1) A tornado is observed on site 1) A tornado strikes the Power Block with identifiable plant damage HURRICANE HURRICANE
- 1) Hurricane is expected tr cross 1) Station is experiencing a hurricane the station with winds greater than 100 mph
,m
.s SITE EMERGENCY GENERAL EMERGENCY EARTl! QUAKE
- 1) An earthquake greater than Design Earthquake as detected on seismic instruments ABNORMAL POND LEVEL
- 1) Conowingo Pond level on LI-2/3278A,B,C exceeding the following limits:
a) greater than 116 feet E b) less than 87 feet
. - 0 i
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' APPEhuix EP-LOA l Pagt 7 of 12, Rev. 8
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LOSS OF POWER- -+ UNUSUAL EVENT ALERT
.E) LOSS OF OFFSITE OR ONSITE. LOSS OF OFFSITE AND ONSITE AC POWER FOR POWER LESS THAN 15 MINUTES i
- 1) turbine generator trip with Startup 1) turbine generator trip with Startup ,
Auxiliary transformer SU2 and SU3 Auxiliary transformer SU2 and SU3 l unavailable for service for more unavailable for service and than 60 seconds or 2) failure of all diesel generators to
- 2) loss of voltage on the four 4160 energize their busses.
volt emergency busses or 480 volt load centers supplied from the four LOSS OF ALL DC POWER FOR LESS THAN 15 MIN. 4160 volt emergency busses for more
, than 60 seconds. 1) less than 105 volts on the 2/3A,B,C
& D distribution panels as indicated
- on Panels 2/3AD03, 2/3CD03, 2/3BD03, 2/3DD03 and
- 2) less than 21 volts on the 24 volt distribution panels as indicated on Panels 2/3AD28, 2/3CD28, 2/3BD28, 2/3DD28 and
- 3) loss of all alarms V,3::
SITE EMERGENCY GENERAL EMERGENCY LOSS OF OFFSITE AND ONSITE AC POWER FOR LONGER THAN 15 MINUTES
- 1) turbine generator trip with SU2 and
. SU3 unavailable for service for longer than 15 minutes and .
1- 2) failure of all diesel generators to energize their busses for longer than 15 minutes
. LOSS OF ALL 125 VDC POWER FOR IONGER THAN 15 MINUTES
- 1) less than 105 volts on the 2/3A,B, C&D distribution panels as indicated on Panels 2/3AD03, 2/3CD03,2/3BD03, .
' 2/3DD03 for longer than 15 minutes
- _a-,
and i
- 2) less than 21 volts on the 24 volt distribution panels as indicated on
(', Panels 2/3AD28, 2/3CD28, 2/3BD28 , 2/3DD28 for longer than 15 min. and - l
- 3) loss of all alarms for longer than 15 min. ,
i
- . - .- - - . . . . . . . . . , . . . _ _ _ _ _ _ _ _ . _ . _ . . ,1 Avec wAA Le*-Awa
- Page 8 of 12, Rev. 8 f f
~+
. S E C O N D A R Y C O N T A.I N M iE N T ._
', UNUSUAL EVENT ALERT q]) LOSS OF Sl;CONDARY CONTAINMENT INTEGRITY I loss of secundary containment 1)
", integrity for greater than 12 hours N/A 9
s D t ( (. SITE EMERGENCY GENERAL EMERGENCY i 1 N/A N/A t 9
- ." I 1
1 s 1 e 9 l A
_ _ ,{1 m.m ,usx eg-sui Page 9 of 12, Rev.8
~+-
j . I N S T R U M E N T F A l.L U R E _ _ l ? l UNUSUAL EVENT ALERT i I 6 _. , () , SIGNIFICANT LOSS OF ASSESSMENT OR COM-MUNICATION CAPABILITY IN THE MAIN CONTROL ROOM
- 1) complete loss of all Main Control Room communication equipment
' N/A 6 1 f SITE EMERGENCY GENERAL EMERGENCY i . N/A N/A O m E 9 8 h
=
9 o
- o
, f APPENulX EP-lua
- Pago 10 of 12, Rev. 8
. FUEL D AM AGE l
UNUSUAL EVENT ALERT l f I.C)
, V POSSIBLE FUEL DAMACE a FUEL DAMAGE
- 1) Air ejector discharge rad monitor 1) Air ejector discharge rad monitor high alarm and an increase of 500mR/ indicating greater than 2.5 x 10 4mR/
hr within 30 minutes or a level of hr on RR 2/3-17-152, or
! 2.5 x 103 mR/hr as in5cated on 2) High coolant activity7 f 300 uCi/gm RR-2/3-17-152, or dose equivalent I-131, and main steam
- 2) high reactor coolant activity as line high-high radiation alarm with
, determined by sample analysis equal resultant scram alarm, or to or greater than 2 uCi/gm dose 3) spent fuel damage resulting in a equivalent I-131 refueling floor area radiation monitor
. alarm or a high radiation alarm on refuel floor exhaust rad monitor h
4 SITE EMERGENCY GENERAL EMERGENCY l FUEL DAMAGE FUEL DAMAGE
- 1) rollowing conditions occur 1) When at least 2 of 4 containmert rad a) failure of control rods to fully monitors indicate levels greater insert on a scram and than 106 R/hr on RI-8/9103A/C and b) higher than normal readings on RI-8/9103B/D and containment pressure LPRMs adjacent to not-fully- exceeds 10 psig on PR 2/3508 inserted rods and c) at least 2 of the 4 containment rad monitors indicate levelc.
greater than 10 5 R/hr on RI-8/9103A/C and RI-8/9103B/D.
- 2) Major damage to spent tuel in fuel j
pool or uncovering of spent fuel as confirmed by a fuel pool area radiation monitor alam and: - a) refuel floor exhaust radiation : a, monitor high alarm, E b) refuel floor area radiation monitor alarm or
" 3) Observed major damage to spent fuel -
M e O i . _ _ _ __ _ _ _ . ___-___m._______ _ _ - . _ _ _ _ _ - _ . - - _ - _ _ _ - _ - _ . _ - _ _ - - _ - _ _ - _ _ - - - - _ . - _ _ - _ _ - _ _
~ ~ _ m_..... . , _
, ,j
- Pago 11 of 12, Rev. 3 j .
' -~ .-
- s HAZARDS - -x-1 UNUSUAL EVENT ALERT l
,) MODERATE HAZARDS SEVERE HAZARDS
- 1) Aircraft crash on or near site 1) Aircraft crash on the facility or as datormined by Shift Supervision missile impacts into the Reactor or Bldg. Diesel Generator aldg. or
- 2) Significant explosion on or near HPSW pump structure as determined site as datormined by Shift by Shift Supervision g Supervision or 2) Explosion damage to facility affecting
- 3) Toxic gas release on or near site plant safety as determined by Shift as determined by Shift Supervision Supervision or
- 3) Chlorine gas detected in the i Control Room
,3 SITE EMERGENCY GENERAL EMERGENCY O
r
~
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. _ ._.. ,1 na auman u.-sv.
* * *' '
- l'49C 12 Of 12, 1(ov. g
, e* ' C O N T R O L R O O M E V A C U A T I O N__ - > l b UNUSUAL EV121T ALERT I I. ) REMOTE CONTROL ESTABLISHED
- 1) Evacuation of Main Control Room anticipated or required and control established at remote shutdowr panels as determined by Shift Supervision i
o SITE EMERGENCY GENERAL' EMERGENCY REMOTE CONTROL NOT ESTABLISHED
- 1) Evacuation of Main Control Room and control of shutdown systems not established at remote shutdown panels in 15 minutes as determined N/A .
by Shift Supervision 4 s , e s l l l 9
- - . . .~.,w.. ..
. . . . .V i.
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,,. CONTROLLED APPROVED COPY-VOID P.P.EVIOUS IS:,'Z ?
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,. 'iX) define site renc.onse to an Unusual -'; vent. 'j ID'ETCCES ~
- 1. ?each Bottom Ata.ic Power Staticn 2', ergency Plan
- 2. I E 0554 4
- 3. tocal Evacuatien GP-15 -
- s
- 4. -EP-101 Classification of c' scrgencies
$, s 37., ..o
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.!/ 102-1 Lnusual Event ::ctificatien Checkoff List
.l 2P l2-2 L'nusual Ivent CM calation Checkoff List m.
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- 1. .' .if t .iugcrvisien shall:
1.1 Jr.:.:.2 the role of Interi.12.ergency r'irector. 3
% 1. ".. .4:tivate 2.crgency .'.ic..s as r.ece sary. ,
. 1.3 Direct the evacuatien of aff?cted arean as nonn.w.;v.
.'d er to the follering p::codure:
sD-15 Lccci r:v ::::icr.
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- sys %102
. . ~)m a 2 of 9, .ev. - PM. 3 ;
-p O Cmtrunicator shall:
2.1 Usin'j t'.e Stardarci Prc.pt *1ctificatien = erst.ge -ntify the approcriate parties in Acperdix E?- 102-1 or 102-2. (see Appercix A for additional telephone nrJbers) . sLI41.~-UP AC"IOt.3 ,0 rcrgency Director shall: 1.1 ?crio'.ically evaluate the event classification in accordance with E? 101, Classification of S:ercencies an1 escalate or deescalate the classification as necessary. If claulfication is dMacalated, fill out Appendix E?-102-2, and direct the consnunicator to notify the appropriate parties. DO N . OT USS TIS BLUE RING-DOL 21 PHCtFw R')R THESE CALLS. E 1.2 Direct the Shift Clerk to contact additional succort 5 personnel that are necessary for emergency func't' ions. ,0 Shif t Clerk shall: 2.1 tiotify aiiitional supocet personnel to report to the plant as directed by the Energency Director. e m eu. .
~
i l l l e l A ' s
, _ _ . . . . _ . . ~ . _ _ _ . . . . , . . . . _ . . . _ = _ _ _ _ . . _ _ . . - ~ . _ -
_:.. p ! . . "'-102
%M 1 of 5, "ev. i
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APPOrn CP 102-1 (Ccnt id) ? 4 ,
.. m L*G76 EVC.':' !TIFICrI21 CEX'CEF LIST
' V' NBC Opetations Center ) F.cd ? hor.e
- anager-?uulic
**- Information l (91-4122 or 215/G49-4732 er in3er ; 300/502-2500) e P3A?S Guard Sergeant (4292)
- (Cnly make this call if an a.Mance or the fire oormany has been
', calleo). Time :;otifications of above parties empleted . Verified By Cate ] i 9 r
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ed nIC P!7..'t.R STATIGJ CELI';G 'IC .U3R:' TE TC".II:ATIO'I OF N! L*.; USUAL D/ :'??. r.. .3 I.; :.o 77ti;f:IE Foa .3.m C3CRA:'ATIal. Off ::xi:: IS . TI: .: N:D .' Arc IS . 'I'.*IG (IS) (IS ?!OT) A D'.III.
- .otifications:
Nare of Ti:e of Ccm.inica tor 's Party Person Rescendim '.*.ctification Initials Station Supt. Ind Dis ster.er Per.nsylvania .' ar4-
.. er.ev "',a cnent A ;er.: /
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- EP 205A.12 , ,
. . Cor:TaelI.D APP i0VD Cm. Paga 1 cf 5, Rev. 3 .
y :::, mvv.r ua . , G n sic -; \
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, f ,' O n > h.h.~ : .,, .,[~PIIIL\DILP1 IIA 11TCPRIC C04PANy i ' , a: . . . _ . . . d EP 205A.12 - SN4PTE PREPARATION AND HANDLING OF H1'UILY BADIOACTIVd .PARTICUIATt: PILf1E AND IOIQn_ CAT 1TRIDGPS PURIO3d: *
- The purpose of this procedure in to provide cone guidelinen for concideration ouring sample preparation (sample reduct. ion) and isotopic analysis of highly radicactive pcrticulate filters and iodino cartridges following accident i, conditions with major fuel damage.
APPNtATUS: j Extremity docimetry
; Appropriate 11ealth Physics survey equipment Air Sampler (lcu voltvae) if required lespirator protection equipment if required Anti-C clothing if required Appropriato lead shielding
' (,- )
'~
Pid)CAUrItJIS: A. In all steps of tais proced1re, an ALA1W concept is mandatory. This procedure provides some philosophy in pre-planning for sample preparation and handling of highly radioactive samples. In addition to reviewing this procedure, an AIAlm review of the
; sample preparation methoos should be performed prior beginninq
- preparation (sample reduction) . If an analysis ".c not really
~
needed or a lower dose method is possible to obtain the came -
data, do not perforal the analysis. .
i ;
B. at no tine may Nic exposure limits (either airborne or body dose) be exceeded during the cam?la preparation r.nd analysin.
If it appears that an over exposure could reascnsely occur ducirx3 sample preparation or analysis, 03 Or proceed without written NIC approval.
PIOCEDUl]s or other remote tooling durinq caapic preparation.
- 5. Determine the contact dose rate from the particulate filter and the charcoal cartridge at the time of samplinq.
If thr contact dose rato in < 200 mRern/hr the samole should be analyzed directly by the Coli analysis on the 3 cm or 30 cm shelf.
- 6. Consider the use of more elaborato shielding during sample j preparation if doco rates merit its uso.
- 7. Connicer the use of silver zeolite cartridges in the place
, ,, cr chcrcoal cartridges to reduce the noble gas interforence
() during icotopic analycic. The une of silver zoolite will allow samples which contain more I-131 (as empared to
, clurcoal) to be counted with less dead time.
l 3. Jacples with high noble gas bacxgrourris can be flushed to reduce the noble gas interference my one of the
, following methois:
; a. Insa a filter /cartriage holcier with the " hot" cide toward the inlet quick-disconnect as -
, stown in figure EP 205A.12-1. Flow nitrogen or .
clean, air through the cartridqc. Line up the i diucharac to a suitable ventilation exhaur.t. 1 Conunce t.4e pur.je f1w until tne radiation level
! no longer decreases, t
D. Liro up a vacuum pump to take a suction on a cartridge leider with the exhaust to a suitable 1 l ventilation exhaust as shown in Figure EP 205A.12-2. !i Place the cartridge in the holder observing proner j, flow direction through the cartridge. Turn on the ., vacuum pump and establish flw until the radiation
- . level no longer decreases. _. .
j>
, Q/
e E
-. - . . . . . -._. . ~ . --_ ~ _ _ . _- , . _ _ _ _
-. .-. . -- . . - -. . - - ~ . - >.. -.. . -. - .. ~ . ..- - - . - - . - - - . . . . . . .- - . - - - -. . - +
o.
. . F.P 20",.%. l?
. ,, Page 3 of 5, Rev. 3 g
i I 9. Consioeration slall be given to tne final disMition or d
} the sxples, the remainder of the original smpic ano tne waste produced.
t 'a lu. Saapleu and tie romainder of the original cample which are kept for additional analysis shall be stored in an j' appropriate location based on their dose rate awi radiological hazard. t 8
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*it. li: PEVIN ." ~ P e 1 of Rev. 6 SRil:clb r: 7R:20T*G'; g f ,, - p 4
l l / cW. %is.. , 7 1*:.i7'*<[ l !
';l /1 d'IUpF.LPIIIA ELECfRIC COtPANY J hil I O M'1
! t' '; "
... .. "PEAGI D01'104 UNITS 2 AND 3 l
- . " ' ~' ' ' 34SIENCY, PLN2 DiPLFMHPINC PROCCrXIIE ~
s
! EP-206A FILE FIGiffING G!OUP f
PURPCGE
- i To cefine the actions of ;he Fire Fighting Group.
REFSIENCCS l. Peact Bottom Atomic Power Station Emerge.Ty Plan
't , Section Title 5.2.1. 5 B' Fire and Damaqe Team
- 2. EP 401 Entry for F.Tergency Repair, Operations, and Scarch and Rescue.
- 3. SUEG 0654 Criteria for Preparation and Evaluation of Radiological Emergency Responso Plans and Pre- ,
7 , paredness in support of Nuclear Pouct Plants.
. 4. 10C M50 Appendix R, Section K
- 5. EP-209 Appendix l}-3 Fire anu Damtyle Team Notification List APPdNDIX
. CP-2 -1 Fire Fighting Group Organization am! !!cmon'ibilitter by Jot; Title IP-206A-2 Fire' Fighting Group Standard Actions
*.: 'P-20 6A-3 Automatic Fire Protection System Initiation and Roset EP-206A-4 Classes of Fires and Types of Extinguishants Fd-206A-5 Pottable Fire Fighting Papipncat Available On Site EP-206A-6 Emergency Exposure Levels (Rmergency Plan Tablo C.1)
EP-205A-7 Availacle methodc of safe shutdown
=-
ACTIOS LLNdL
- The Fire Fighting Group will be activated whenever there in a situation onsite which, in the judgement of the E:rergency P
- - - . . = _ - - - - - -. - - .~ .. V EP-206A
. . Page 2 of 24, llev. 6 y
Director or Shif t Supervision, requires their services. IThe
! Fire Fighting Group shall also be activated upon any initiation ; Qfthefiresystem.
PitrAuriuNs i 1. Team member's exposure should be limited to tha adminis-trative guide levels in Appendix T:P 206A-6, Emergency Exposure Limits. The Emergency Director shall approve
, any team member exceeding Peach Gotte quarterly exposure limits. The Fire an'd Damage Team Leader should ensure that all team members are controlling their own exposure in accordance with AIN M con cpts. ; 2. The Outside Shif t Supervisor or other member of shift super-j vision, as' determined by the shif t Superintendent, Interim Fire e and Damage Team Leader until relieved by the Fire and Damage Team Leader for fire-fighting and damage repair duties.
- 3. The Engirner-M;11ntenance and the Assistant Engineer-Maintenance
, are qualified in fire-fighting techniques which allows -
tnem both to be Fire and Damage Team Leaders if required. newever, as a general rule, the site maintenance personnel are not fire-fighting qualified. These personnel can only assist in fire-fighting activities with the shif t operators if requested by the operators due to an in-extremis situation. 7
- 4. If oft-site assistance is required, ensure a representative
- of the fite-fighting group meets the fire department at the entrance to the site to infor:n them of the situation and provide guidance to the fire location. Pcqaest Security , and Dosimetry support for off-site fire companies.
- 5. hequirements of HP0/CO-4, Radiation Work Permits, are not applicable. The llP ac W nying the Fire Fighting group .
will s:crve as the 1n.7. '
- 6. If team members are required to enter a hazardous area, i there shall be a minimum of two people per group entering.
- 4 PiOCCDURE:
1.0 Personnel who identify fires shall: 1.1_ imnediately determine iC the fire can be extinguished by a quicx action such as using a nearby fire extinguisher. j Attempt to quickly extinguish the fire, and in all instances, i notify shif t Supervision (ext. 4220, 4221, 4222, 4223 or P.A.)
, of the fire location and type and actuate the nearest fire
,, alarm station. Waraing: For a fire in fuel storage areas, flooding nea
- fuel with water or applying a water fo) chould
!~ s ce avoided to prevent a pousible criticality in new fuel. , i e
._ . - f
, D*-?OfiA Page 3 of 24, Rev. G
- y t .
l 1.2 Af ter souMing the alarm remain close to the area, at a g).
%, safe distance from smoke, fumes and fire, to provide direction to the fire location to the fire fightinq qroup.
. 2.0 Snif t personnel who receive report of fire shall: 4 2.1 If a fire is reported to the control room via phone or i P.A. the inrlividual who receives the report shall advise 1 c the chief opera, tor of the location and fire description. r 2.2 If the fire notification was initiated via the fire alarm annunciator pariel the chief operator should obtain the exact words on the annunciator window, and use them j in the announcement. 2.3 The Cnief Operator should make repeated announcements of the fire type (if knwn), location, and fire fightinq group assembly area. He may at this time, or later, if requested to do so by the Team Leader, announce an assembly area for general plant personnel. This assembly area should be chosen based upon the additional' r.a<ds of the fire fightinq group as indicated by the leader. (E.G. manpower - at fire locatiorVportable fire fighting equipnent - per locations irrlicated in Appendix EP-206A-5/ turnout coats, boots, gloves, scott 4.5 SCSA - cage located at Unit 313 KV area.) 2.4 Consider evacuation using the follwing procedures: Q
, G? Incal Evacuation EP-303 - Plant Svacuation t:P-305 - Site Evacuation 3.0 Emergency Director shall:
3.1 Call the fire and damage team leader. If the sit.uation i permitu, discuss the problem with the fire and damage team .
. leader so he can assess the situation and determine how '
- many and what, type of team members will be necessary to
! correct the problem.
3.2 If necessary, direct the designated co:mtunicator to contact fire and damage Team members; refer to EP 209 Appendix D-3 for telephone numuers. Inform the team itembers where to accomble. i 3.3 If necessary, contact off-site agencies for assistance. The
- site emergency coordinator should be consulted if outsido
. a;uistance is desireo before contacting any off-site agencien.
3.4 In the event that the fire has the potential to completely - . ._' disable all equip:ent in ud cablinq passing through the s fire area, reference the 'P' procaiare for the area and j Appendix EP-206-A7 to obtain guidance in determining the remaininq available systems to accomplish safe shutdown of the affected unit. .
-uw. e a- -.
en
__l._ _ _ _ _ _ . _ _ . . _ . .. _ _ _ - _ . . _ - - - - -- - - -- - - - - - . - RP-20GA Pago 4 of 24, Rev. 6 I i F }
.- 4.0 Interim Fire and Danugo Team Leader (Shif t Supervisor) shall:
( ~) 4.1 Obtain known information frcxu Chief Operator. [ 4.2 If time permits, review the applicable "F" procedure for the affecte' fire zone. - 4.3 obtain all necessary keys for the fire zone in the event of doors are locked
- or the security keycard device does not function.
4.4 Obtain two radios; one for the leader and one for the inspection team leader. 4.5 Call the Auxiliary Operations Support Center and request
; an HP to report to the assembly area. ~
4.6 Proceed to the fire scene and assemble the fire fighting
. group. .
{ 4.7 1::xplain the situation and what has to be done in detail to the fire fighting group. Also inform them of any hazardn , or precautions encountered on way to fire. 4.8 Prior to leaving the assembly area decide the number of , personnel necessary (minimum of 2 plus an li.P.), designate I ( ">.; equipnent to be used (sco P.P-20G-A Appendix 1), ensure team memuers have adequato protection to fight the fire, and ensure the team leader and group have portable radios. 4.9 If entry into a hazardous area is necessary, do so in accordance with EP 401, entry for emergency repair, operations
- and search and roccue.
h 4.10 Direct the fire-fighting efforts in accordance with appendix EP-206A-1, fire and damage team organization . and repensibilities and appendix EP-206A-2, fire fighting group standard actions. Use portable and installed fire protection equipnent in t.ccordance with EP-206A-3, auto-matic fire protection system initiation and reset, Appendix i EP-206A-4, classes of fires and types of extinguishants, and Appendix EP-206A-5, portable fire fighting equignent available on-site.
; 4.11 Advise the Control Room concerning the need for de-energizing or reaoving equirnent or systems from service and the significance 3 of damage sustained and the impact on plant operations and safety.
. Request as required the shutdown of ventilation system (s) .
4.12 Se alert to radiological, electrical, and toxic hazards to per onnel involved in fire fighting. Seek advice fran the Fire J and Damage Team Leader on radiolcNical or toxic agent hazards. 4.13 Periodically update the emergency uitector or interim - _ -__ _-__--_._____________m _ _ _ _ _ _ _ _
_ _l _ . ._ . _ _ _ . _ _ . _ _ _ _ _ _ . _ . . _ _ __..,y i EP-206A Page 5 of 24, Rev. 6
- p emergenc/ director of the status of the situation, request
~,. the emergency director or interim emergency director to ask l
,d for acsistance from the Delta-Cardiff fire and ambulance
( company, if necessary. 4.14 Coordinate the activities of off-sito fire fighting support l groups. - i . i 4.15 Advise the Interim Emergency Director or Emergency Director l concerning Emergency Exposure Limits for team members involved in emergency wcfrk and repairs, attempt to minimize radiation (;
- expc.sure and contamination as much as possible. (See Appendix 12-206-8 for exposure limits). .
5.0 Fire Fighting Group Members shallt k
, .1 Iteport to the assembly area with equipnent, as assigned in Appendix EP-206A-1, assume the responsibilities assigned in Appendix EP-206A-1, and fight the fire under direction of the p team leader.
I 6.0 Fire and Damage Team Leader shall: 6.1 Iteport to the technical support center (when activated) . Contact Emergency Director when on-site and obtain status of the current situation. ('i ' G.2 Establish ccmnunications with the Interim Fire and Damage Team Leader and obtain status of the fire fiqhting group. 6.3 Provide additional personnel support if necessary. Use EP 209 Appendix D-3 for additional qualified fire fighters or maintenance support perconnel. Contact them and provide 1, information on where to report. Assign designated plant staff
; to direct one or more Fire Fighting Teams as necessary.
Assign at least threc personnel to cach team, as rcquired. Direct the team to relieve or assist the Interim Team members . j as necessary.
; 6.4 Periodically provide fire and damage group leader with plant status changes and significant radiation exposure ana radioactive contamination problems which may affect the functions of the team. Assign a member of the Fire Fighting Group to man the SCBA syntom on the First Floor of Unit 1.
7.0 Auxiliary Operations Support Center Coordinator shall:
; 7.1 Assign an !!P Technician to each fire fighting group. I j 8.0 IIP tecnnicians shall:
j 8.1 Obtain required equipment and report to assembly area. Octain information from and inform interim team leader of any known radiation hazards associated with the situation. -
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- Paqo G of 24, Itcv. 6 j ,
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i 8.2 dnsure safe radiological conditions in the fire fighting 2 y,j area. e l e 4
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EP-206A Page 7 of 24,1(ev. 6 l APPc;NDIX EP-206A-1 - 1
] Pile e*1GFCING GIUJP OICWJI'/ATIUN AND IESPONSIBILITIPS BY JO*1 TITU',
A. Tne Fire Fighting Group should report to the assembly area with the following assigned equipnent: Shif t Supervisor: Two radios and necessary keys Plant Operator No.1: 032 portable fire extinguisher Plant Operator No. 2: Purple K dry chemical fire extinguisher Ass't Plant Operator: Purple K dry chemical fire extinguisher
; Auxiliary Operator: Imuodiately proceed to the fire fighting '- group equipnent cago,116' P,1. by joy air compressor or cart i El. 165' by Unit 2 turbine shield wall and obtain one Scott 4.5.SCBA and proceed to assembly area. Immediately obtain additional Sala if requested to do so by leader.
H. Tne following are guidelines which should be used to assign resp)nsibilities to the Group members: Shif t Supervisor: Interim Fire and Damage Team Leader Plant Operator No.1: 1) Inspection Team Leader
- 2) Ass't Interim Fire and Damage Team Leader (i.e. Shif t Supervisor designated alternate)
- 3) Nozzle man on No. 2 Pire Hose
- 4) Extinguishant with CO2 Plant Operator No. 2: 1) Nozzle man on No.1 Fire llose .
, 2) Extinguishment with purple K dry chemical
- 3) Lighting and Snnke itemoval Ass't Plant Operator: 1) Inspection Team (along with P.O. No.1)
- 2) Nenup aua on Nca. 2 c' ire iiwe
- 3) Extinquishannt using purple K dry chemical Auxiliary Operator:
1} 1:quipnent Manager (inside)
- 2) Backup man on No.1 Fire 11ose
; 3) Extinguishment using CO2 9
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,' Page 3 of 24, llev. 6 , ~b APPENDIX EP-206A-2 f .
I FIRE FIGlff1NG GIGIP WPANDARD ACPIONS dAUrIUM Talt: PlORUCrG UP GIOU:TruaN O'/ CG!frAIN MATditIAtli (e.g. SCM: ELOCIRICAL CABLES, PLASTICS, OILS) AIE VERY 'IOXIC, IP llIGli
'10XIC GAS LLVdLS AIE SUSPECTED, IF Ti!S OXYCSN LEVEL IS LUIS
( TilAN 19.5%, OR IF T!!C CARDOX SYSTFM llAS' GREN ACPIVATED, i scuff 4.5 AIR PACKS MUST BU USED.
- 1. Comunications should ce established with the Interim Emergency Director or Emergency Director, or his designee (via phone, P.A.,
or radio) .
; 2. Fire Assessment 5
- a. Prior to entry by the inspection team, if the access to the fire zone is unopened, look for abnormalities such as physical
; deformation, discoloration, peelirs paint or other evidence of
( high temperature in an attempt to determine the proximity of the fire to the access. Use extreme caution to open door. If door is hot or flash over is expected, nove a charged line in prior to opening door. D. The Fire Fighting Group Leader should direct the Inspection Team to enter the area of the fire. The Inspection Team should nave portable fire extinguishers. Dependent upon the size of
, ~ . the fire area and smoke conditions the inspection team may use
( j, a Scott 4.5 SC3A radio, lifeline, or portable life lines at the Leaders discretion (or use of a charged line by inspection team) .
- c. Tne Inspection Team should stand to the side, (charging line must be available) while remaining low, and slowly crack open, then open the access. (If required, the site forcible entry tool is located in the security building, Auxiliary SAS, under the windows of the North Wall),
- d. If the fire is determined, by the Inspection Team Leader, to De otniously extinguishable, with their portable extinguishers, -
; immediate action shall be taken to do so.
If the fire is of such magnitude that immediate extinguishment is ceyond the capabilities of the Inspection Team, the Inspection Team Leader shall repart, to the Fire Fighting Group Leador, the nature of the fire, its location and severity, equipment adjacent to and involved with the fire hazards in the vicinity (e.g. oil tanks or lines, cornpressed gas lines, cylinders, or tanks, prooane lines or tanks), and any apparent effects of the ventilation system on the fire, i
- l 3. Upon the report of the Inspection Team, the Fire Fighting Grou;) _ _ - .
Leader sh:x21d direct the manual initiation of installed fire i , suppression equipment described in Appendix EP-206A-3, if appropriate, and direct fire fighting equipment preparation and associated actions. Also cnecK for fire extensions and extinguish name. _ 1 l 3
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IW-20bA Page 9 of 24, Itov. 6
- y 1 4. At this time and periodically thereafter the Fire Fighting Group Leader should report the fire scene situation to the Interim ^
I ']
\ Dicrgency Director or F.mergenc/ Director. (The Interim 7.mcrgency .
Director or the r:ncryoncy Director, banc<l upon Control lloam indi- I cations, and review of the applicaole "F" procedure should make
, reconinerdations as deemed necessary) . .
1
; a. Ventilation - The "F" procedure for the firo zone indicates normal
- ventilation flow rates. This data, along with Inspection Team observations should be evaluated to determine degree of impact from the normal fire zone ventilation. In general, direct the shutdown of the supply ventilation system servicing the fire area j to isolate and help smother the fire. Exhaust ventilation may 3 remain in service to either aid in increasing visibility (smoke
, remaval), renovo potential toxic or explosive fumes, or :r introduce cool air. Otherwise, supply and exhaust ventilation should both be shutdown initially. If ventilation is completely shutdown the Fire Fighting Group Leader should direct (e.g.
J General Plant Personnel Leader) that areas serviced ty/ the same ventilation system be surveilled to assure amoke is not migrating into those areas. If so, exhaust fans should be sequenced on periodically to alleviate this condition.
- 5. The Fire Fignting Group should then, under the direction of the tire and damage team leader, enter and extinguish the fire. The guidelines presented in Appendix EP-206A-1 should be used to aid in coordination of this effort. The guidelines presented in
(- Appendix EP-206A-4 should be used to employ the proper extinq-uishant for the type of fire which is present.
- 6. If deened necessary, the Firo Fighting Group Leader should direct additional general plant personnel either directly or via the Interim anergency Director or the Emergency Director. Ile should request additional portable fire fighting equipment, as listed in Appendix IT-206A-5 and additional personnel to fiqht the fire. -
- 7. Upon extinguishment of the fire or as is necessary designated -
plant personnel should " ventilate" the area using guidance con-tained in the applicable "F" proceduro. Instructions for use of the portable smoke renoval equipment are contained in Procedure S.13.1.
- 8. Upon extityjuishment of the fire, a fire watch shall be estaclished, in the area, in the event of a reflash of the fire.
The duration of the fire watch shall be proportional to the saagnitude of the tire, bat in no case shall be less than 1/2 hour.
- 9. Fire fighting equiptent shall be inventoried, replaced and returned to its proper storage location. If Scott airpacks :-
have oeen used, the cylinders must be refilled and then inspected by t!.o hespiratory Protection Ad;ainistrator throu@ performance of ST 17.2.a.
-- .V IT-20GA Page 10 of 24, Riv. 6 i
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- 10. At somrt tium after tte fire Piro Form No. 196-64002, "lMport of Fire" Form, should be completed and forwarded to the Safety I
Q IJepart:nent by the Interim Fire and Damago Team Leader. l 0 1 i T t 4 A
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+ ! APP &JDIX 8P-206A-3 ,
s j {} AUlu4ATIC PIIC PICfECff0N SYSTC4 INITIATION AND REGW
$ Taoso arcan in the plant which nave their own fire protection
; systems are listed below with a brief description of system
, actuation and resetting. Auto actuation of any of these systemn
~
- will initiate a coded signal and a Main Control acam alarm.
1.. The following equipnent is protected by open head sprinklers supplied by Water Deluge Valves which are initiated automatically
- upon heat detection or manually by opening and pushing the lever in the manual station located at the Deluge Valve in the Conden-sate Pump Room. After a fire is out or urvler control, reset these valveu per Procedure S.13.2.1.G.
- u. Main transformers 2AX01, 2aX01, and 2CX01 (3AX01, 30X01 and 3CX01)
- b. Auxiliary transformer 20K02 (30K02)
- i, c. Condensate pump transformers 2AX07, 23XO7, 2CX07 (3AX07, 33X07, 3CA27)
- d. Start up and emergency auxiliary transformer 00X03 n
- 2. The folloaing equipnent is protected by open head sprinklers
( supplied by Water elooding Valvon which are initiated auto-matically upon heat detection or manually by opening and pushing
,; the lever in the manual station located at the Deluge Valve near tne protected equipment. After a fire is out or under control, reset these valves per Procedure S.12.3.2.1.I:
- a. ilydrogen seal oil unit (Units 2 & 3)
- i
- u. A am! 3 standby gan trcatment system filterc .
- c. A and B recombiner Duilding ventilation filters ,
t
- 3. The Turbine !!atch Area (COMJN) is protected try a 11 eat 3ensitive Closed llead " Nitrogen-filled dry sprinkler system."
!! eat breaks the sprinkler head (s), releases the nitrogen pressure, and causes a fire alarm. The sprinkler system for the Turbine liatch Area must then be manually initiated by one of the following methods:
i c. Pushing the rennte puchbutton located on panel 20C01 in ,; the Control toom. ,: o. Opening the local electro-manual box-mounted next to -__'
! the '.'uruine .suilding Cardox unit. j V c. Opening ami pushing the lover in the manual station l located at the celugo Valve Cl.116' near Turbine rlldg. l m-
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o- ^tter the rire is out or uacer controt, reset ents vatve per procedure S.13.2.1.G.
?
3 4. Tne following areas are protected by ileat Sensitive closed
;' head sprinklers supplied Sprinkler Alarm Valves (SAV) which j initiate upon actuation of the heat sensitive ~ sprinkler . < heads. If a heat nensitive sprinkler head breaks but the Sprinkler Alarm Valve fails to open, the local manual station located at the individual SAVs may be used to open the SAV.
i After a fire is out or under control, reset these valves per Procedure S.13.2.1.II: i a. Turbine Lube Oil Heservoir Room (Unit 2 & 3)
- b. Turbir.e Lube Oil Storage Room (Unit 2 & 3)
- c. Main Steam Stop Valve Area (Unit 2 & 3)
- d. East and went feedwater heater service platforms (Unito 2 & 3).
- e. Areas under cast and west main turbine generator plat-
. forms (Unit 2 & 3) . . f. 1.axiliary noiler Building ; ~g i d 5. Tne followiry rooms are protectw by sprinkler systems t which, upon actuation of a heat sensitive sprinkler head, give a direct spray on the equignent in the room. After a fire is out or under control, reset these systems by closing 1 the corresponding Manual Block Valve, replaciw; the actuated sprinkler head, and restoring the block valve to an open 3
position: 1
- i. . A, 3, and C RFP Turbine Lube Oil Reservoir ikxxns (Units .
; 2 & 3) .
j ! D. Diesel Fire Pump Room (CCWON)
- c. El.116' lube oil storage room Unit No. 3 Turb. Bldg.
- d. El. 116' lube oil storage room in Mimin. Bldg.
1
- e. El.135' lurlwaste Compaction Area 2
- 6. We turnine bearing oil line uelow the pedestal (Unita 2
{ & 3) are protected by a " Heat Sensitive Closed liead Nitrogen- l filled dry sprinkler system." llast breaks the sprinkler head (s),
- rolcases the nitrogen pressure, and initiates a fire alarm. Tho -
dry sprink1cr synton for the turbine bearinq oil lines telou
- . f. I pedestal i.uy then uo inanually initiated by one of the followinsi '
methods: 9
.T KP-20tas
. Page 13 of 24, Itev. 6 i
s
- a. At the local stations located at North and Soutb ends of turbine.
h b. Opening and pushing the lever in the manual station lcxtated at the Deluge Valve (165' elevation near generator). Af ter the valve in out or under control, reset this valve per procedure S.13.2.1.G.
- 7. The Diesel Generator Cardox System, if not disarmed, will
- initiate automatically upon heat detection in each of the I irxlividual Diesel Compartm 'ts. If heat detection initiation does not occur, ,ae system may be manually initiated usinj.the pushbutton station outside each Diesci Conpartment door. Upon failure of the pushbutton station,
, manually initiate the Cardox System by breaking the front
, glacc of the appropriate Electro-Manual Pilot Valve (located _, outcido of the noontor Pump Itoom) and n' ave the lever to tha
. OPdN position to open the Master Select Valve for 60 seconds, then cloce the pilot valve. When initiated manually, the Electro-Manual Pilot Valve lever must be naved i to the Cu1ED position to stop the discharge of CO2 to the Uicsel Conpartment. After initiation of the Cardox system, I reset the system per Procedure S.13.2.2.B. The Diesel Generator CO2 tank, located in the Booster Pump 11oom holds 5500 lbs of CO2. A single sixty second discharge to any of the Diesel Generator rooms uses 2200 lbs. Therefore " double shat" protection is provided.
b ,. 8. The itPCI itcom Cardox System can.be initiated in any of the tnree manners described above for the Diesel Generator Cardox System. Tne Electro-Manual Pilot valve for the ilPCI room is located at the Unit 2(3) Turbine 3169 . Cardox Storage Tank. Manual discharge is perfortred by moving the Electro-Manual Pilot Control (dMPC) luver to the OPEN position for 60 seconds, then closing the DtPC. Reset of the system per i Procedure S.13.2.2.D, Section A. Each Turbine 3uilding CO2 Tank (Unit 2 and Unit 3) holds 12,000 lbc. of CO2. A single . 60 second discharge to either of the HPCI Rooms uses 2100 los. Therefore " multiple shot" protection is provided.
- 9. The computer Itoo:n Cardox System is initiated at the pusnoutton stations on either side of the Computer Room.
If pushbutton initiation fails, the Electro-Manual Pilot Control (DiPC) levers for the Master Select Valve and the Select Valve muct be moved to the OMJ position for 125 seconds. The EMPC for the Master Select Valve is located at the Unit 2 Turbine Duilding CO2 Storage Tank. The EMPC for the Select valve is located outside the Cable Spreading 1<com. Wnen initiated manually, both the DIPC levers must be returned to the CLOsa3 position after 125 seconds. System ' reset per Procedure S.13.2.2.D may then be acccmplished. - :m Upon Coaputer 1(oom CO2 injection, the tie valve between the Unit. 2 x.J Jnit 3 tanxc opunu, providir>J a total CO2 capacity of 24,000 lun. A singlo 125 cocond diccharge to , O l j
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_ m. - - EP-206A Page 14 of 24, Imv. 6
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-j the computer room uses 1100 lbs. of CO2. Therefore -
! " multiple shot" protection is provided.
l h~ 10. Tne Cable Spreading Room Cardox System in initiated a autunatically by actuation of both channoic of a two 3 channel sacke detector matrix in the Cable Spread Room. 1 If snoke detector automatic initiation does not occur, the system may be actuated manually by using 'the pushbutton . stations cutside either Cablo spreading 14aam door. If
,' pushbutton initiation fails, the 1::MPC levers for the Master ?
Select Valve and thei Select valve must be moved to the l . OPEN position for 125 seconds. The !!NPC for the Master
- Select valve is located at the Unit 2 Turbine Building
', CO2 storage tank. The EMPC for the Select Valve is y located outside the cable spreading room. When initiated
> manually, the twC levers must be returned to the CIAEu ! position after 125 seconds. System reset per Procedure j S.13.2.2.D may then be accomplished. ; Upon Cable Spreadin) Itoom CO2 injection the tie valve between the Unit 2 and Unit 3 tanks opens, providing a total s CO2 capacity of 24,000 lbs. A single 125 second discharge to tne Cable Spreading Room uses 9600 lbs. of CO2.
p Toernfore " double shot" protection in provided.
- 11. Tne main control Hoom and the Unit 2 and 3165' El. lif t pump areas are equipped with CO2 hose reels, hhen the
!! hose nozzle is removed from its holder the hose reel and ( ^> header automatically pressurize. Discharge is acconplished 1 by depressing the nozzle hand lever. If hose reel header fails to prescurize, at the Unit 2 Turbine 314 .3 Cardox Tank, acve the !!OSS REEL 11tPC valve to the OP@l position to
!! pressurize. When use of the hose reel is canplete, return the .. c.PC valve to the CLOGED position.
M
'; 12. Yne uoaring casings for turbine bearings 1 throa)h 0 (Units 2 & 3) are protected by dry chemical furnished through a series of nozzles. In the event of a fire at the casings:
u -
!?
- a. Move the 350-pound wheeled Ansul dry chemical unit to
, the appropriate tearing.
, c. Connect the quick connect hose from the Ansui unit to the quick connect fitting at the bearing.
4
- c. Discaarge dry chemical by opening the manual valve to i charge the cylinder and actuating the hand lever for
' discharge. .t
- 13. Tine .C Set Room -(Unit 2 & 3) and the !C Set Lube Oil Pump Room (Unit 2 & 3) are protected by a " Heat Sensitive :-
(( Clo:cd .5prinnler Head" Nitrr>Jen Filled, Smoke Detector
) Prescurized Sprinkler System. Smoke Detection causes fire alarms and pressurizes the sprinkler header with water b opening the flooding valve. Heat breaks the sprinkler head, ,
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. t' j sprayinj the area of the fire. The system can be pressurized
, with water nunually by operation of the manual station located
. at tre flocx2in3 valve. The system is then reset per procedure 4 S.13.2.1.K.
- 14. The No. 6 fuel cil tank and the auxiliary boiler building I are protected by a manually operated foam sys. tem. To apply foam inside the No. 6 oil tank open the foam solution tank inlet and outlet valves. To apply foam using the manual y hose reel and nozzle, unreel the entire hose, open tbo foam e solution tank inlet Valve, the hose reel isolation valve,
. and appiy foam using the " Pistol Grip" shutoff valve. 4 When fire is out, close valves and restore the system per j procedure S.13.1.1. $ 15. The west corridor of the Unit 2 and Unit 3.RX nldg. Bl.135 I are protected by manually operated water curtains. The
} purpose of ttese water curtains is to provide a " fire barrior"
- between cables of two different Safe Shutdown methods. Cables
- for one method.are located North of the curtain and cables for i the other method are located South of the curtain. To initiate
'! these water curtains, pull the mcnual pull station at the floodinq valve which is located in the southwest stnirwell or remove frangible lock from the remote station in the el. 135 Rx Bldq. t elevator stairwell and actuate the pullbox. These water curtains can only be initiated manually. These systems must be initiated if, in the opinion of the Shift Supervisor, the fire cannot be controlled with noruol manual fire suppression equipnent and 1 {') has the potential to offect cables in those areas. l. 'l 't 1 1 1 i i I
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P.P-2tmA Page 16 of 24,ltcv. 6
. t APPtNDIX RP-206A-4 CIASSiE O? f' IRES AND TYPES OF EXrINGUISilACS EXTINGUISilANTS Hose Station Portable Fire Extinguishers Purple K Prensurized Classes of Fires Fog / Stream CD2 Dry Chemical Water . Class A .Yes No, except Yes (Heat of Yes (Defined as wood, very small Combustion may paper, cloth, etc.) (See Note 4) fires remain)
Class a (Defined as flam- Yes,IMG ONLY Yes Yes No {, mable Liquids) (See note 1) i
; Class C (Defined as ener- No Yes Yes No (Sec gized Electrical No Yes Yes No (See Equignent) (See Note 2) (Note 3) Note 2) . Note 1: When using . water to canbat a Class 3 fire special 3 techniques are necessary. The Use of'a direct hose stream
(# ) should be avoided to minimize spreading the fire. Ilowever, t " cooling" may be provided via hose stream to heat sensitive equipment in the vicinity of the fire. If necessary, due i to the size of the fire being beyond the capabilities of
, multiple Purple K dry chemical extin]uishers, a water " fog" application NOT DIRBCPLY APPLIED to the fire
- may be used for additional suppression.
Note 2: In the case of High Voltage Equignent, the Associated i Cabling and Control Devices shall always be de-energized ,- prior to the use of water as a suppresant. liigh dennity . j cable runs of generally lower voltage are a specific concern at P3APS. Water ONLY in the form of a IOC
' My be used. Water should be used only in maximum fog form at the maximum effective distance (to eliminate electrical conduction) when fighting a fire in low voltage energized cable. Fog should first be established, not in contact with the fire, and separation distance should slowly be decreased.
When electrical equignent is de-energized then, the fire may ne considered an Class A and may be fouqht an such. Note 3: Due to the highly corrosive characteristics of Purple K dry chemical extinguishant usage on electrical ecui r. t ant -- -__,
, should ce minimized.
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.40te 4: WAINING: EOit A PIIG3 IN d'U2L fi1GIACS A!EAS, FIDODIIKI l
NIM Furi Wral WAT?Jt Olt APPLYING A WATER EtXi () StuJLD Br: AVOIDitD *10 PIUNuif A POSSIBLC , CitITICALIh IN nim r'JEL. 6 E h 4 4 i e 8 4 L
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ADPENDIX EP-206A l t) PJ1TABIE t' IRE PIGifflNG EOUIPMMt' AVAItXIIS ON SITE d 5. Piro 3rigade Personnel IOluipment C.vje and Cart 3 (Cage located on El.116', Turbine Building, adjacent y' to the joy air compressor. Cart located on El. 165' inshore shield wall for Unit 2 turbine). Contents incitrie y' Scott 4.5 one hour colC contained breathing apparatus, turnout coats, boots, gloves, and phoenix hard hats.
- B. Emergency Fire Cabinets
- 1. Cabinet No.1 (Imcated at 165' El. adjacent to Unit 2 control room shield wall) . Contents include smoko renuval blower, instruction manual, flexible duct, and l Vent dtx:t to flexible duct adapter, masking, duct, and electrical tapes, tools and fittings, door bar back
. txguignent, extension cord.
- 2. Cabinet No. 2 (Same location as No.1) . Contents include halt mile rays and Chemox canisters.
- 3. Cabinet No. 3 (Incated at 11G' El. adjacent
- to plant entrance chield wall) . Contents incitxle two snoke rencval blowers plus same items as Cadinet No.1.
Additional in-plant llose Carcs: ("' C.
, 1. Unit No. 2 Reactor Bldg:
- a. !!ose Cart No.11-137 El.165', southeast corner near hatch,
- o. Iloso Cart No.11-135 El.195', northeast corner of fire tower.
- 2. Unit No. 3 Reactor Oldg:
~
- a. 11o30 Cart No.11-138 El.165', northeact corner near hatch. ,
- b. Hose Cart No. E-136 El.195', southeast corner by fire tower.
~3 t D. 350 lb. Wheeled Ansul Units: i
- 1. Elevation 11G':
- a. Unit No. 2 Turb. Bldg. southwest corncr.
- b. Turd. Bldg. Center SWGR. Area South.
- c. Turb. Bldg. Center SHUR. Area North.
, d. Unit No. 3 Turb. Bldg. Northwest Corner.
- 2. Elevation 165':
- a. Unit No. 2 Turbine Hall: _: .
- 1. xiverside wall North'
- 2. Riverside wall South I;
- 3. Downriver Southwest corner. -
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- 4. Adjacent to Control Room entrance. -
m. (') ,
- b. Unit No. 3 Turbirn !!all:
- l. Itivorsicle wall lJorth
! 2. Riverside wall South
- 3. Northwest Corner -
. 4. Center near generator ,
E. Portable wall mounted CO2, Purple K Dry Chemical, pressurized water fi're extinguishers and self-contained breathirv3 apparatus. 4. 9 s f* 6
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EP-20fiA
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i . APPidDIX EP 20GA-6 E CO'.tCY EXPOSJ10-; LIIRTS l Projected i Whole Body Thyroid Authorized Function Dose Dose By . 1. Life Saving and Frergency** Reduction of Injury 75 rem
- 375 rem Director
. 2. Operation of Equipnent to Mitigate an. Fa rgency**
Emergency 25 rem
- 125 rem Director i
- 3. 1.~Otection of llealth
! arkt Safety of the Emergency Public 5 rem 25 ren Director
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! APPiLLIX 206A-7 2 j AVAIUGLS M IODS OF SAFE SHUrDOWN ,
Twenty-five methods of providing reactor shutdown and decay heat renoval were utilized as the basis for a safe shutdown analysis. The individual "F" procedure for each fire zone indicates those methods which would remain available if the fire zone of interest were to be subjected to a denign basis fire. A design basis fire is assumed to disable all equipment located within a fire zone and all equigstent associated with cabling passing throuqh the fire zone. This analysis assumes ccrnplete loss of equipnent function even if a coaponent is not required to charge its normal line up status to perform satisfactorily. Cach of these methods includes a system by which water can be added to the
, reactor vessel, a system by which energy can be renoved from the reactor vessel, and any support systems needed to accumedate energy removal to an ultimate heat cink or to return water to its supply source. Additionally, each methcyl has several alternatives derived from multiple flow paths, redundant loops, or alternate power supplies.
Folloaing is a description of these 25 methods of providing reactor shutdown. Methods utilizing the condensate pumps or condensate pumps and reactor feed-pumps: ( l. Water is supplied from the condensate storage tank (CST) by the condensate and reactor feed pumps to the reactor vessel. Energy is renoved via the turbine bypass valves (TGV) to the condenser and water is returned to the CST. The conseaser is cooled by the circulating water system / This is a non-safety related method.
- 2. Water is supplied from the CST by the condensate and reactor feed pumps -
to the reactor vessel. Energy is removed via the main steam relief ', valves (MSRV) to the torus. the torus is cooled using the residual heat removal (RHR) punps and the high pressure service water (HPSW) pumps and water is returned to the CST. This is a non-safety related
. method.
- 3. Water is supplied from the CST by the condensate and reactor feed pumps
, to the reactor vessel. Energy is rennved via high pressure coolant injection (IIPCI) steam drag to the torus. The torus is coaled using the tuin and dPs'a pumps and water is returned to the CST. This is a run-safety related method.
- 4. Tne reactor is depressurized to 650 poig or less us'ing the Tav. Water 4 is supplied frcra the CST by the condensate pumps to the reactor vessel.
Energy is reroved via the T3V to the condenser and water is returned to the CST. The condenser is cooled by the circulating water syst.'m. "' This is a non-safety related method. l
- 5. The reactor is depressurized to 650 psig or less usinq the MSRV. Water is supplied from the CST by the condensate pumps to the reactor vencel. .
1
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! EP-206A Pago 22 of 24, Rev. 6
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- , 1 Energy is removed via the MSIN to the torus. 'Nw torus is' cooled using I g the RHR and itPSW pumps and water .is returned to the CST. Thin is a j ; ;r non-safety related metin1.
j Met!als utilizin) the ICIC pump: I
$ 6. Water is supplied from the CST by the- reactor core isolation cooling l i (!CIC) pump to the reactor vessel. Energy is re:mved via the TBV to the condenser. Tne condenser is cooled oy the circulating water l
i system. the tor w is cooled by the RHR and HPSW pumps. Water is j returned to ths CST. This is a non-safety related method. I 7. Water is supplied frcm the CS:' by the ICIC pump to the reactor vessel. Energy is removed via the MSRV to the torus. The torus is cooled by b the lufR and HPSW pumps and water is returned to the CST. This is a
;. non-safety related method, h 8. Water is supplicci fro:n the CSr by the TCIC pump to the reactor vessel. - Energy is renoved via HPCI steaT. drag to the torus. The torus is . Cooled bf the Ri!R and llPSW pumfr and water is returned to the CST.
This is a non-safety related stethod.
- 9. Water is supplied from the torus by the ICIC pump to the reactor vessel. Energy is re:mved via the Tav to the condenser. The condenser is cooled ()y the circulating water system. The torus is cooled usinij tne RHR and dPSW pumps and water is returned tc the torus. This is a non-safety related method.
' (. . 10. Water ir .3upplied fraa the torus by the ICIC pump to the reactor vessel. Energy is recoved via the MSRV to the torus. The torus is cooled using the IUIR snd HPSW pumps. Althcugh the DCIC system is not considered a safety related system, it is designed to satisfy class I i seismic criteria. Because of this design, this method can be considered a safety related method. ? 11. Water is supplied from the torus by the iCIC pump to the reactor i vessel. Eurgy is removed via ICIC steam drag to the torus. The torus .
is cooled by the RiiR and HP3M pumps. Although the RCIC system is not
', considered a* safety related system, it is designed to satisfy Class I j seismic criteria. Because of this design, this method can be considered a safety related method.
f
- Methods utilizing the 11PCI pump: '
t
; 12. Water is supplied fran the CSr by the 11PCI pump to the reactor vessel.
Energy is removed via the T3V to the condenser. The condenser is
,' cooled by the circulating water system. The torus is cooled using the tulit and ilPS4 pumps and water is returned to the CST. This is a non-
- cafety related method, y
- 13. Water is supplied frara the C9P by the HPCI pump to the reactor vennM .
ener.jy is rc:noved via the RilW to the torus. The torus is coole's i>y .{ ( ~) ,the R!!R and I!PSU pumps and water is returned to the C9f. This is a non-safety related me*.hed. i E 1 v F
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EP-206A - J . Page 23 of 24, Itev. 6 ! i
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p ! I 14. Water is supplied from the CM by the IIPCI pump to the reactor vennel. 4 m Energy is removed via llPCL steam drag to the torus. The torus is
; h:) cooled ttf the it!!R aryl !!PSW pumps 'aryl water is returned to the C91'.
2 Tnis is a non-safety related mothcx1.
- 15. Water is supplied from the torus by the HPCI pump to the reactor vessel. Energy is removed via the T3V to the condenser. The condenser 1
is cooled by the circulating water system. The torus is cooled by the i Hilu and !PSW pumps and water is returned to the torus. This is a non- .; . safety related method.
- 16. Water is supolied from the torus by the IIPCI pump to the reactor vessel. Energy is rem 3ved via the MSRV to the torus. The torus is cooled by the Hr!R and HPSW punps. This is a safety related method, s 17. Water is supplied from the torus by the !!PCI pump to the reactor vessel. Energy is removed via HPCI steam drag to the torus. The torus
; is cooled by the WIR and !!PSW pumps. This is a safety relatcd method.
Methods applicable af ter the reactor is depressurized to 300 psig or less: 1
- 10. The reactor is depressurized using the TBV. Water is supplied from the torus by an RRR pump to the reactor vessel. Energy is removed via the TGV to the condenser. The condenser is cooled by the circulating water, system. Water is returned to the torus. This is a non-safety related method.
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- 19. The reactor is depressurized using the MSRV. Water is supplied fron the torus Lif an Riln pump to the reactor vessel. Energy is removed via the MSRV to the torus. The torus is cooled using the RilR and IIPSW pumps. This is a safety related method.
Methods applicable after the reactor is depressurized to 350 psig or less:
- 20. The reactor is depressurized unira tr.0 TBV. Water is supplied from the
. CST by a coro spray pump to the reactor vessel. Energy is removed via' the TBV to the concenser. Tiie condenser is cooled by the circulatin.)
water system. Water is rci.urned to the CST. This is a non-safety related method. This method is an alternate to ruethod 22 below, i.e., water is supplied from the CST in place of the torus. Use of this water supply requires opening a manual valve in the core spray punp suction line.
- 21. The reactor is depressurizing using the .*t3RV. Water is supplied from the CST by a core spray pump to the reactor vessel. Energy is removed via the MSRV to the torus. The torus is cooled by the Ri!R and IIPSN pumps c.nd water is returned to the CST. This is a non-safety related uethcx1 This methcx.1 is an alternate to method 23 below, 'i.e. water in
; supplied from the CST in place of the torus. Use of this water sucoly requires openin) a manual valve in the core spray pump suction line. _.,
- 22. Tne reactor is depressurized using the TBV. Water is supplied from the
- s. _ 4 torus by a core spray pump to the reactor vessel. Energy is rennved via the Ta1 to the condenser. The caxienser is cooled by the .
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h e * ~L ' i . f circulatityJ water system. Water is returned to'the torus. Thin 10 a j ,
- non-safety related method..
- 23. Tne reactor is depressurized usity; the MS!N. Water is supplied from
, the toruc.by a core spray pump to the reactor vessel. Energy is ? removed via the !ti1W to the torus. The torus is cooled by the n!!R and 5 11PSW pumps. This is a safety related method. i
- 24. The reactor is.deprecsurized using the TIW. Water is supplied from the river by a !!PS'n pump to the reator vessel. Energy is renoved via the TBV to t.he condenser. The condenser is cooled by the circulating water system. Water is returned to the CST which overflown to radwaste.
This is a non-safety related method. I
- 25. The reactor is depressurized using the mr&. Water is supplied from the river by a IIPSW puap to the reactor vennel. Snergy in removed via time MSIN to the torus. The torus in cooled by the Ill!!! and ilPSW pumps.
) This is a safety related method. t 9
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I Station Superintendent Scme p h e > R. S. F1ciSC-Mr.n i 1 l Assistant Station Suoerintendent D. C. l
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^* McDaniel Kmrad , ,
Ward Constantini acoinson Capoferri e i l e
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# . , EN 209 4 -
CONTROLLED APPROVED CCFY. CIX D-5 VOID PPE'lI0t'3 IfG'? Page 1 of 6, Rev. 6 q, RIS:cib '
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"~~ ~~~ PhLADELPHIA ELTI'RIC CCMPNTI I DF)Of BCrfl01 UNITS 2 & 3 EP-209 APPENDIX D-5 SECURITY 'IT:AM -
Security Team Leader ' Telephone No. S.O. Tharpe (Security Supervisor) Alternates C.W. Myers (Capt. of the Guards) K.L. Kncuse (Training Lt.)) Security Team - Sergeants L.C. Kissirger L.D. Smith Sr. S.A. Spencer W.F. Strauser Assist. To PECo Security Suoervisor Lt. J.C. Ta is Clerk D.S. Watkins L o _ __ ___.m._.,._____-_ -- - ' ' - - - ' ' - - - - - -
l I i < r :s ED-209
, : , APPENDIX D-5 O Page , 2 of 6, Rev. 6 g
3 . Security Team Members - Guards Telechone No.
.g.
), 1. Altland, Eugene R.
l 2. Ashoy, Dewey D. ,
- 3. Biggs, James Z. 4 i 5
- 4. BucKingham, Charles L. J
- 5. Clay, Kathleen M. ,,
- 6. Dallas, Richard O. .t 4
- 7. Dennison, Tcbert L.
- 8. Edwards, Perrilee T.
- 9. Frazier, George H.
- 10. Hess, Martin R.
- 11. HhMrt, George R.
- 12. Mutton, William R. ,
3
- 13. Maltx:ci, Paul C.
- 14. Merryman, Jeffrey B. +
r f~
- 15. McLain, Lester S.
- 16. Morris, Lawrence A.
) #
- 17. Murphy, Priscilla A.
- 18. O'Shell, Dcnald R. I l 19. Salamo, Jorge i 20. Shaw, Iouis L. }
- 21. Smith, Steven M.
- 22. Stewart, Ralph E.
- 23. Taylor , Roger L. [
]
- 24. Warner, Bradley E. ~.4
- 25. Willians, Urlo C. ,.
- 26. Wilson Jr., James P. f JI .
- 27. Wyatt, Alan R.
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. Aso-T. DIX D-5
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_. s. t . 5achityTeam:'.e.oers-Natchperson Telechone No.
- s .
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- 1. ;lcan, A Renee L. I 1
i
;. hen., Carl T.
- 2. *dreece, Karen J.
- 4. -Brennan, Joann i:.
j ..;ristol, ::evin *I.
- i. Brown, Essell E.
. .Bacxing.u ., .1111am C.
- 2. ~Cos; rove, David L.
, L. b.nison, Gregory L. t
- 10. Dressler,:'ichael C.
- 11. 'Freelano, Arne L.
e (
;;. Jialstec, Carol L.
i i
- 13. Harrirgton, Julia . ;
i . ! _,. Jor an,.nriene u. i f _5. [Knignt, '.,arocra A. i
- 15. *0ssiasoff, Donna,A.
- 17. Aforc, Ja vis ".:.
1s.:ajor,Ja.T.er.:;.
;9. :brnin .::ar , h0;.crt L.
;J. Parthree, Diarr.3 D.
- 11. Risser Jr. , kotert G.
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.t. co wrts, L1rna .
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_4. Searle Jr . , Ric . ara 2. - - - 1 9
.5. 5egain, ic. ro C.
_G. Sna f f er , .c:;.r.'
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, y EP-209 APPENDIX D-5 Page 4,of 6, Rev. 6
_E
- 27. Sipe, Steven P.
- 20. Smith, Cnristopoer A.
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- 29. S.nius Jr. , Larry D.
- 30. Taylor, Dwayne D.
- 31. Taylor, Jacalyn f 32. Testerman, Pauline 11.
33.Testerman, Tina L.
- 34. i.bisner, Jean F.
- 35. Willic.rson, Denise M. -
. i
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E"d-209 APPS4 DIX D-5 Page 5,of G, Rev. 6 Seconcary Alarm St. & Ccntrol Alarm St.
,sttonannts Telephone No.
G 'd 1. ar.mntrout, Treva C.
- 2. Bar,er, Paul N.
- 3. Deal, Norna J.
- 4. Brooks, r(11xcely A.
- 5. Casey, Willia.T. L.
- 6. Duh, Anita F.
- 7. Gu11cault, Denisc A.
- 8. liaga Jr. , Crarels L. :
- 9. llaga, Leisa
- 10. Kunkle, Drian K.
- 11. McLaughlin, Carol A.
- 12. Willia:rs, Teresa C.
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CP-209 APP!2CIX D-5 l3" E Page 6,of 6, Rev. 6 _ s_ Part Ti.ne Security Team Members - Guards Telcohone No, j b l l. Cantler, Ronald A. l l
- 2. Green, RODert A.
- 3. Icoinson, Ja:nes 11.
Part Time Security Teram Members - Watcheerson l l
- 1. 3rce , noward M.
- 2. Gross, Donald E. ,
l
- 3. liesps, William A. l
- 4. Johnson, Donald P.
- 5. Loathian, Rorald D.
0
- 6. Wilh a;rs, Tho: ras 9.
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-. 3 urns International Security Services, Inc.
J , l. ti42 ilamilton I'.all, Suite 8 Allentown, Pa. 10101 i l ,- Sarns District Manager - Allentown l l Phil liyde 1 i ham , l Burns Area Su!rrvisor Ja:xs N. luynond m h l 9 e l l l w- - _. - - - - - . . - - _ - - - _ . _ _ _ - _ _ _ - - - _ _ _ - - _ _ - - - _ . . -
~---t--- - - - - - -.
CONTROLLED APPROVED C::PT- EP-209 VOID PRIVI0'JS 1000C APPENDIX D-7 Pags 1 of 3, Rev. 10
. D!STP.!3UTION:
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, EP-209 APPDIDIX D-7 J AN 101984 orn e. - . . . -
~ ~ '5b. . . . - - -ergency Director Ek m Centrex R. S. Fleischmann Alternate l D. C. Smith Technical Engineer J. E. Winzenried Alternates ,
i S. R. Roberts S. A. Spitko A. A. Fulvio G. F. Dawson
- F. W. Polaski A. J. Wasong Supervising Engineers & Alternates j Outage Planning Engineer F. W. Polaski Achinistraticr. Engineer S. J. Kovacs Results Engineer J. F. Mitman Alternate
- J. Jordan I & C Engineer G. F. Dawson Alternate: J. L. Clupp e
. _ _ _ . . . _ _ _ _ . . . . . . - . . . _ . - . .-.--..-- - __ _...... ,i F
j i EP-209 APPDCIX D-7 N'
}!
Pega 2 of 3, R:v.10 y
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j! 3 a. actor ersineer 7~ A. J. Wasang , Alternate: J. T. EJdzynski Plani. Chemist 1I H. L. Watson i Alternate: G. Barley ) l Quality Assurance i'ygineer ,f l 1 A. A. Fulvio { h i Alternate: R. M. Sware i l Maintenance Engineer *** l l J. K. Davenport Alternates D. B. Warfel Senior Health Physicist *** A. E. Hilsmeier $1 Alternate: N. F. Gazda f
)
Applied Health Physicist *** :) N. P. Gazda h i Alternate: C. S. Nelson A Record Keeper and Comunicator, a See EP-209 Appendix I-l for pe 1 to fill this positico.
+ -
Data Display Operators - 2 recuired i Notify cne of the five personsdn the order listed below. The perscn notified will contxt two Data isplay Operators.
- 1. R. O. Carr j
- 2. K. T. Voight p
- 3. C. E. Andersen f
- 4. D. A. Davridge J.
- 5. D. D. Burguard ,.
*** Beguired to report to the when activated. '--
t . I
_ _ . . _ . . . . _ -_ ,_.m_. . . .
. . _ __ --- ~ ..._ _ ________
EP-209 APPENDIX D-7 Page 3.of 3, Rev. A0 __ E Secretaries
~]) 2 required % Centrex L. McCleary L. Davis W. Felts T. Huttcn C. Brainerd S. Holgate J. Hoopes J. Williams )
J. Wiley ' , l t l l l i U g, l l 4 e
CONTROLLC 1FFF.7tD COPY- EP-20' VOID *'FPri:003 ISS'JC AP"'I ! DIX E ) D .:.. . .:
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Page 1 of 9, Rev. 10
,e 73
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N, 9 -. . .... EN209 APPiNDIX E - CCFFIVJd FJERGDCY TFXi IZADERS AND Jpy 1 o gg^ea
. .:. SUPPORT PERS22;EL j
Hcre Phone Centrex Site Emergency Coordirator -
't. J. Cooney Sept. Generation / Nuclear Site E;tergency ' crdinator Alternate i;. T. Ullrich l Supt. Suclear Services '
Site Emergency Coordinator Alternate G. M. Leitch' l Supt. Lbnerick l
\
HP&C Coordinitor W. J. Knapp Director, Rad. Prot. Sect. HP&C Coordinator Alternate J. G. Fcogneiser Physicist, Rad. Prot. Sect, i nviron. ental Sa :clinc Coordina*wr G. F. Deabler ScP/. Eng. , Enviror rental Brarch
- .nviron. ental Sa:mlina Coordinator Alter R. H. Ingue Eng. in Charge, Nuclear & Env. Sec.
Planning & Scheculing Coordinator F. i;. Polaxi _ _ . Outage Planning Coordinator _- J 9 C
,.a...---. - _ _. . _ _ _ _
^%~~^LT .^ ' '^ . : . - . . . . _ -
20-209 APPS' DIX E Paqe 2 of 9, Rev. 10 t . Procedure Supoort Coordinator
.7 W. C. Direly s.; .ior 2.;ineer , ,icensing Frocedure Ju;xort Coordinator Alternat J. B. Cottor.
7.aintenance Engineer, Lirerick I (
-:mer:- Succort Officer /Recove Offi l
S. L. Daltrof f V.P. Clectric Producticn l Emergency Sucport Officer / Recovery Officer Alt. J. W. Call v.her '
' Mgr. E.lectric Production Emergency Medical Diretor_
,~ W. F. Hushicn Mecical Director Emergency recical Director Alternate A. J. Circc ta Med. Disp. Physician j
ZDergency security Officer I J . C . S'cGol .r ic < M.a.vger, Clairs-Secarity I hrsanc/ Scarity Officer Alter:ute ,
- h. J. Denee.
Directer, Sec.rity Insurance Ocordina*.or W. G. Holberg hager Ir.surree Division
~ .
l e
- - _ _ . . ~ . _ _ _ _ . . _ __ _ _ _ _ . ___ _ _ _ _ _ _ _.__ ____ _ _ _ __ ____,
_ . . . . . . . . . 3 '
& 200 APDNDIX E
., Page 3 of 9, Rev.10 __ ,
o < - I s l .a t. \ .l
- Insurance Cccrdinator Alternate _ -
\ A. L. Saltiel Insurance Actninistrator . I4 Core Pnysics Cocroinator_ I \ i ( L. F. Ruoino g l I Supv. Eng. Fuel Mg .t. ; I L Ccre Physics Ccordinator Alternate _ L H. J. Diamorr! ).
+
8b 271 ! Eng. Fuel Mgmt. ; i r \
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'l AMinistrative and Logistics Manager , i i J. M. Friderichs - D.recter, Corporate Analysis Adt anistrative and 'mistics Mana:er Alt l - ! A . s' . .'iilllas Manager, Rate Division t l- . lI , 1 4 .Winistrative anc istics ".ana:er Al . J. V. Mannicn ' {
.rager, TLD 5ervices l Suaort Personnel Procurement Coordina I
i .. a. Aloen ~ Eng. in Charge, Licensing Section l f Ja n:rt Person..el rrocure. ent Coordinator Alt. _ _ - . l-R. C. Brcv. rNineer, Licensing Section l l
. =.m l
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,g EP-209 APPCIDIX E
-, Page 4 of 9, Rev. 10
- L r
'I
', Support Personnel Au.ci.ulations Coordinator J "
J. C. O'Brien l .9;r. Area Develornent l9 Scroort Personnbl Aa.unadations Coord. Alt. 1 J. J. Bevan ; % Supt., Sares Analysis l l l . t rt Personnel A m i.uiations Coord. l
)
G. C. Linthicum Staff Asst. Business Services i P i !u Western Divisico - Ac.u.a.6.ciations ; I i.1 -.i A. W. Horrocks , l r' Supv., 3usiness Services
~
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' Western Divisicn - Accw. uiations Alt. i S. F. MarKley
- i. .~
Bus. Services Rep. 4 1 Purchasing Coordinator l I H. B. Winitsky'- i
.%3r., Purchasing Purchasing Coordinator Alternate
! R. A. Nones i: I Supervising 3uyer Transoortation Coordinator E. L. Dold Gen. Supt. Trans. Div. }i (l Transportation Coorcinator Alternate R. T. Melvin
--- Supt. Operations -
- .c i
5
. r. .. . . . . .'
W 209 APDCCIX E Page 5 of 9, Rev.10 _E Camunication Equignent Coordinator
-}
B. C. Czarkowski Gen. Supt. Office Systems and emication Camunication SqJiment Coordinator Alt. j C. W. Aldrec l Supt. Office Systems and Ccrmunicat l f I i Stores Divisicn Coordinator I i j T. C. Stapelford Gen. Supt. Stores Division Stores Divisicn Coordinator Alternate i i H. A. CcrtTr Supt. Stores Divisico l T & D Sup:crt Cocedinator f
' A. G. Mikalauskaus
.I . Mgr. T O Operations l T & D Suoport Ccordinator Alt _. i
- h. J. Nhy .
Asst. to V.P. T&D s 1 hlign and Construction Supoc:t Officer
- 2. C. Kistner Chief Mecn. Eryg. .
Desi=n'ard Construction Suotort Offiar G. N. DeCows<y Cnief Elec. Eng.
' ' 'ocrai'sto: -- _ .y; R. H. Moore I
{ Sept. Electric Production /CA -y'? ; l
'b.
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EP-2C9 APPENDIX E Page 6 of 9, Rev. 10 _k
~g 0;/QC Ccordinator Alternate
. s' P. K. Pavlides Eng, in Charge E&R/CA Ra:! waste Coordinator
- l S. J. Kowalski Eng. in Charge Power Plant Service Radwaste Coordinator Alternate A. C. Caprara Supv. Eng. Power Plant Services Engineering Design Coordinator 1
J. W. Siefert Chief Design Engineer ; En:;ineering Design Coordinator Alt.
)
A. R. Lewis Asst. Chief Design Engineer { 1 l i I&C Ccordinator R. T. Jones i i Supv. "ng. Power Plant Control Systers Branen - I&C Coordirntor Alt. W. W. Bowers Eng. Poer Plant Control Systems Br Licensirn Coordinator
- h. 'i. Lo;;-1 Eng. in Charge .4uclear & Env. Secti Licensiry Coordinator Alternate L. 3. Pyrih g
Supv. Engineer Nuclear Branch k e e l .-
EP-209 APPDOIX E
?D9e 7 of 9, Rev. 10
_p q Systen Engineering - Mechanical Coordinator
.)
J. Moskw itz Eng. in Charge, Power Plant Design Systems Ergireering - Mechanical Ccorinator alt. T. E. Shannon Sr. Eng. Power Plant Design Syste.m Engineerirg - Electrical Coordinator J. T. Ferenesik i~ ' Eng. in Charge,.4uc.-Gen. Branch ' Systems Ernineering - Electrical Coord. Alt. J. Lees g..
<^
Su;n. Eng. , Nuc.-Gen. Branch s Cmstruction Coordinator J. G. Weisheit Gen. Supt. Construction Division Construction Gmrdinator Alternate Tm Gotzis Asst. ,en. Supt. Construction Division taintenance Coordinator W. C. Whitfield Gen. Sept. Maintenar.ce Division Mainter.ance Coordinator Alternate E. J. Orday Supt. trical ".aintenance " l Federal and State rn,' err. ment Liaison - - - V. S. Boyer 3r. V.P. Nuclear 4 _ _ _ _ _ _ _ _ _ _ _ - __-----._ _ - - - - - - - - l
EP-209 APDD3 DIX E Page 8 of 9, Pav.10 o . s
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Federal and State Government Liaisen Alt.
- 1 ,
A C. Brenner D* - - V.P. Coraorate Ccrmunicaticns ;, - ', D ,.',. .
& 74,,4 :n.C 6.a 'T'An - - NY ' ' '
.f q q. *[p QW Ccrpany Sockeskan
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9 J. Kenper
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V.P. Dyg[Research '
! M h'. . ;mh . ,fw . e. A.-
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2 w igs! 7}g.g>M'.Sqi, . s
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Puolic Inforration Officer .~.', .. - 4 @,.. . .. C. Brenner l , 4 ' V.P. Corporate Comunications -
?
v - ' .; c ; , a Puclic Infor atico Officer Alt. I ~' * [ S. J. Boyle I
*R. ; .) '
Q; . , Asst. to .P. Corporate C .
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4xkly Run News Media Ccordinator 4
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4 :. R. L. Harper * ' - -
. 5; a
Nr. Puolic Inforration
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Midy Run News; Media Coordinator Alt. - -
'sD :
> Mc C. J. McDer ott ' - - %ty# ,%
Public Infor ation Rep. f*%[UI' o %. : gf. f- .t..(.
'L
.' 'p ' ' 3. . r, 2DF Liaison -
. . A%p L3 ..V..-
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W. R. Taylor T [~ $, ,, Mgr. Corp ~ orate Ccrrunications ' o e
, ,~- .j.[, ,
, 9.M;h I EOF Liaison Alt. ' -
. .ir + ^ (k ~v'. %
q 1. . h M. D. McCorr.lck W ' - ea'
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Corporate News Media Cccrdinator ! V - J . .Q* .
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* . '?J. fy 7A 4q:;)-" . 3-:f
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P. G. Byrne - p.y, . ;.'. _: . - y e Mgr. Editorial Services
- T.'i L.' -'~i < n 7. .
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' 1 l
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. Corporate News Media Coordinator Alt.
L. H. Perri Dir. E@loyee Info. I i M.nical AWisor 'tc ".dy Ran !;ews Center l l 3. L. Clars Sr. Eng. !;uc. Sect. Gen. Div. l M.nical Advisor (to !bddy Run !;ews Center) Alt J. Daer m3 Operaticns Engineer, Limerick i Ventilaticn Coordinator l S. H.I4ng l l ndustrial Secticn l Ventialtion Ccordimtor Alternate I G. M. .'brley l
! 3uilding ."acilities Branch I
' l I
i Civil Engineering Ocordinator D. .v.irano l Industrial Se: tion i l Civil Engineerina Coordirutor Al*arrute l l .-i. A. Vollraer Industrial Secticn Drergercy Planninc Coordinator R. A. Kannus E:ergency Pre:aredness Section .; M r Energerc/ Planning Coordimtor Alternat - - y,l y K. ii. Schlecker , C'ergency Preparedness Section R w l 1
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CONTROLLC APPP.0V~.3 CCFY- En-709 V0:3 FP VICUS !SSCE P&PMIX H Page 1 of 2, Rev. 8
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lb 3* l . EP-209 APPDOIX H - C3@ANY CINSULTNTPS J A N 10 108Y' l L g . j Phone
- 1. General Electric Carpany General Electric Emergency Supprt Program
- 2. Sout.%est Research Institute
- 3. Underwater Tecnnics, Inc.
Mr. D. R. Stith Mr. R. T. Ban.m s
- 4. Radiation .42 nag m t Corp i
Suite 400 Science Center Bldg 2 (Dr. Boger E. Linre.an)
- 5. Bura.s Detective Agency Burns Detective Agency
- 6. Institute for Nuclear N r Operaticns (INPO) 7 Secntel Wr Corporation
?e y-4
C3-209 I APPCiDIX H 4 Pace 2 of 2, Rey, a
, 8. Ra W k and Wilcox C .s s i
Mr. J. P. Doran Dbrk)
- (!+xe) i Mr. A. F. Olsen , &brk) l
,1 (Home) l l
- 9. Pooled Inventory Management (PIMS) t
. Brtre Elintic ..
- - f
- 1 4 (Off hours) r 1 Jim G. Bogue e E I h
~T (Off hours)
Milind Korde { I - I 1 7
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? - EP-209 ~APPI2OIX I-l ' FILID SUPPORT PEPScmEL 1
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CP-209 APPBCIX I-l Page 3 of 3, Rev. 12 _E r3 M. S. Sattler T. Bltraa R. A. Brower G. H. Gellrien J. E. I!cssler, Jr. S. J. ?'.innix F. F. Itascitelli G. Siefert S. L. h <ey J. Troiano 1 e e
EP-209 CONTROLLD AFFROVE, Ch5 APPD; DIX P ( . Pace 1 of 4, Pev. 8 i e* VOID FFIVICU3 IS!"!E O ' ~ DISTRIBUTION: uns.
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,74 PRIIADELPHIA ETTRM CD PRJY J AN 101984 PrAca actrIod UNITS 2 M D 3
.... o a:QRCDCY PIRi IMPLDIEN JG PPCCEDURE p
1 -- y s 4 . EP-209 APPD; DIX P - STAF?II.'C A?TtOTTATIOti - 66 MDUrE CAU., PmJJP2 l i PU:@DSE: [1 Tnis apoendix provides tne method of contactibg key staff personnel wno wil.1, in-turn, notify sufficient support personnel to meet tne one-hour staffing requirement. It is used if an Emergency Plan Alert, Site Emergency, or General Emergency is declared.
- 1. The folicwing steps shall be performed, id, sequence,
~ by the Shift Clerk or other assigned perschnel. t
- 2. Inform each person contacted of the eventI lassification and that 60 minute staffing is required.
! 3. Call pager nnoer if the phone is busy, i . there is no answer, or if you know that the individual is " ,he-pager". Individuals
- .. may, of course, supply temporary numbers $ich should be called first. j
- 4. Contact t'c staff senior engineers. R. Sf Fleischmann is contacted by the Ccmmu.nicator and counts as cce cont $nct. Do not call R. S. Fleisch:unn if the Commicato? has successfullv reached him. Attempt to contact the "Dut( and " Interim Site Ccord." engineer
- first. If you are unsuccessful, continuetocallorpagepersonnelonthepistuntilyou ccntact two irdividuals who can be at thepite in less than 60 minutes, y s
Time Dibposition Called Na e Phone Called N6 Ans.-3usy-Contacted g i Dick Fleischmann 5 Drw Smitn Jack '4inzenriec $ Steve .toerts i Allen Hilcmeier e John Davenport f Steve Kovacs , [ Pred Polasu . l . e e e
. . ._ t d ED-204 h
APP:23 DIX P
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Page 2 of 4, Rev. 8 g i l , . p , b
- 7) 5. Contpt one of the representatives frczn the Personnel Safety Team
listqd below and request the call-in of required Personnel Safety Team taerrbers. Make the calls in the listed order unless individuals are nnt to be available.
Ti:re Disposition Called Phone Called No. Ans.-3csv-Contacted g Name 3 i Bill KrAllister Art 3 ewald Steve Grosn Bill Dcubey GlenFAign Ted Hocpes 4
- 6. Contict cne of the representative frcrn the Radiation Protection team listed below and regaest the call-in of requ{ red HP and Cher.istry, TAs and Technicians. Make the calls in the listed order unless individuals are known not to be avainhie. Tnis step may be crnitted if A. E. Hilsmeier was ccn*M in step 4.
Time Disposition Called Same n Phone Called No Ans.-Busv-Contacted g
.~. 4 .
(,2 Allen Hilsocier Noro QM Harry Watson Stewart pson Jim Valinsni Da.e Barren k
- 7. Contact t% on-shif t Maintenance Sun-Foreman via phone (at Ext. 317/319) or p'lant page system and request a call-in of two maintenance mechanics (pre (erracly one electrician and one fitter or eachinist) from theit cwn su;5crt personnel call list.
Maintenance Sud-Fore an Time tacted by L
- 8. Ccntet the co-shift I&C technician via plant obone (at ext.
4D8), or plant cagits systern and request a call-in of two additional It,C technicians from their own succort eersonnel call list, k IEC Technician contacted t __ _ T& &WL Tf 7 s 1 . ~
;- EP-209 APPCCIX P # Page 3 of 4, Rev. 8 p
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.D 9. Contxt one of the representatiye of the Engineering Support Group below and request the call-in of required Engineers and TAs Call in the lis*.ed order unless irdividuals are krown not to be available. ' Itis step may be cgitted if J. E. Winzenried was ccotacted in step 4. {
=a Time Discosition Called Name Phone Called ?M Ans.-3asy-Contacted By Jac4 Winzenried Fred PolasKi Geoff Dawson Jim Mitman Tcny Wasong Joe Clupp Tcn Niessen Jim Jordan
. ./
- 10. Ccntact one PO or APO on list hided by SS/SSV and call-in for sock as Baivaste Operator. (If the person is contacted, he is required to ecme to plant) . This step may be waived tri Shif t Suipervision if an extra PO or p for Radwaste is already on shif t.
PO or APO Ccntacted f Est Arrival Tine fr s Time Contacted by
- 11. At the discretion of she Shif t Superintendent, call in a Shif t Supervisoi to act as OSC Coordinator.
Use EP-209 AFP. C for phone nuters. Supervisor Contac -3 3 Estimated Arrival Tire Tine Contac '* ; Contacted 9y i
- 12. Ccntact the .e Supervisor (or the Electrical Superviwr, ced, at the discretion of the Snif t Superinu ' e help l'n responding to s
the plant condition, f Time Disposition Called Na e Phone (3 tiled No. Ans.-Busv<ontacted By,
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- 13. Atte pt to cantact all other Senior engineers listed in Step 4. Document in step 4. 3 i --
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-iA' EP-209 I r APPENDIX P
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Page 4 of 4, Rev. 8 ._ ,
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- 14. Notify Interim Emergency Director (Shist Supterintendent) when notifications are couplete and inform p of any discrepancies.
t Notified at t Discrepancies '[, . E
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