ML20024B958
| ML20024B958 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 05/17/1983 |
| From: | Bailey G, Barkhurst R LOUISIANA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20024B952 | List: |
| References | |
| PROC-830517, NUDOCS 8307120048 | |
| Download: ML20024B958 (106) | |
Text
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WATERFORD 3 SES
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PLANT OPERATING MANUAL LOUISIANA POWER & LIGHT SYSTEM EP-2-030 REVISION 1 PCM VOLLME 18 APPROVAL DATE:
POM SECTION 2 EFFECTIVE DATE: Fuel Load yjjpg EMERGENCY PLAN IMPLEMENTING PROCEDURE EMERGENCY RADIATION EXPOSURE GUIDELINES AND CONTROLS LP&L W-3 RECORDS CONTROLLED COPY i
NO-
- o g.,., ... .
PORC Meeting No. f3 -02 J Reviewed:
'RC ' 7.an (
Approved: u W.
Plant Manager-Nuclear l
1 O
8307120048 030624 fDRADOCK 050003gg PDR
e, .
WATERFORD 3 SES
- PLANT OPERATING MANUAL
, CHANGE / REVISION / DELETION REQUEST Procedure No. d& 1.can Title Andn.nc.y hb ro rmd drAu us a Ga>&fjs,JaS
- Effective Date firs t imA (if di NerinY Irom approval date)
'lon el a te A. B. e r- C A. Change No. I B. Revision No. / ,
C. Deletion M4 RFAMON FOR CHANOE. REVISION. OR DFLETTON 1,rm.at4b 1ae afdls '" c Nh. A.9 (Lush AM memih A.
REQUTRED SICMATURF3 Originator llY JJ '~~ Date Yller93 Technical Review NN Date 'N/4 SAFETT EVALUATION ,
Does this change, revision, or deletion: YES NO
. Change the facility as described in the FSAR7 g
, 2. Change the procedures as described in the FSAR7- v'
< 3. Conduct tests / experiments not described in the FSAR7 _.zg;,
- 4. Create a condition or conduct an operation which ex- w ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Eva uation checklist.
b[
Safety Evaluation w Date N-/1-dh Group /Dep't. Head Review bO[bh U Date I -/1' '8%
I Temporary Approvale Date (NOS)
Temporary Approval
- Date QC Review #4 4( W- Date M-*r/
PORC 11eviewMN bb Da !t-L W 3 MeetingNo. f'Fird PlantManagebNuclearApproval Nu- 1 Date b@
' Temporary approval must be followed by Plant Manager-Nuclear approval
.ithin 14 days.
UNT-1-003 Revision 6 Attachment 6.9 (1 of 1)
_ . _ . . _ . . _ _ . _.,..___-_,.__,m._ ..m.,_.,v._.,,__,__,m_,.,__.___,_.._,,._m.___ _ _ _ _ _ . - , _.. .r . _ _ ,-
T 4
- l l
WATERFORD 3 SES
% PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST N -6 3 0 Title 7 ^<wa My by r- nd/[/m/.
Procedure No.
Effective Date (if diffe/end from PM-N approval date) d d./
Camolete 1. B. or C A. Change No. N/4
/
B. Revision No. I C. Deletion WM 9FASON* TOR CM1NCE. REVTSION. OR DELETION IYY'/Wl SO t/M( kh9tl--b- J* d 4: /tN?NW ~~
h p' d &
- k n i#p ^&
- s -A-ir W/.s,,rr,t.) buswiw 'N- ~ lY~ ' -- -~
-/ // -/
REOUTRED SIG!!ATUREE /
Originator NN Date ) )~I b3 ' ---
Technical Review U
f bb i M - -
Date - N ' ND- '-
i SAFETY EVALUATION J Does this change, revision, or deletion: YES NO
't-
- 1. Change the facility as described in the FSAR?
'L
- 2. Change the procedures as described in the FSAR?
~L-3 Conduct tests / experiments not described in the FSAR?
- 4. Create a condition or conduct an operation which ex- __9 i
ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safet- Evaluation checklist.
G Date
- M-7 Safety Evaluation Group /Dep't. HeadRevib 9u O bd -
Date b/7O '-
1 (NOS)
Temporary Approval
- Date -
Temporary Approval *
~~
~~ ~~ --- Date - -'
QC Reyiew - d W Y Y u P -- - -------
Date - '/~).5-*9-1-~---
PORC Review h k- Dat
- I -l 9-I 3 ' - - Meetin No. f3 011 --'
PlantManager)NuclearAppEoval MD - -- Date b- - " - -
' Temporary approval must be folicwed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
y g - e Emergency Plan Implementing Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 1 l and Controls i
TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
30 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Emergency Exposure Authorization Form (2 pages)
LIST OF EFFECTIVE PAGES Title Revision 1
. 1-7 Revision 1 l
1 l
f Emergency Plan '.mplementing Procedure EP-2-030 Emergency Radiation Exposure Guicelines Revision 1 and Controls 1.0 PURPOSE To provide guidelines and administrative controls for radiation ex-posures in excess of 10CFR20 limits during life saving or accident-mitigation activities.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan
~
2.2 Title 10, Code of Federal Regulations, Part 20, Standards for Protection Against Radiation 2.3 National Council on Radiation Protection Report No. 39, Basic Radiation Protection Criteria 3.0 RES PON SIBILITIES The Emergency Coordinator is responsible for ensuring that the actions outlined in this procedure are carried out.
4.0 INITIATING CONDITIONS This procedure is to be initiated upon reaching the following condition:
4.1 Defined emergency response actions to perform life saving or ac-cident-mitigating functions are expected to result in radiation ex-posures in excess of the 10CFR20 limits.
5.0 PROCEDURE NOTE l
The Emergency Coordinator is the only indivi-dual who can authorize emergency exposures in excess of 10CFR20 limits.
1 i
2 l
F e 8 Emergency Plan Implementing Procedure EP-2-030 E=ergency Radiation Exposure Guidelines Revision 1 and Controls 5.1 The Emergency Coordinator will determine the need to perform specific tasks which are anticipated to result in exposure in excess of 10CFR20 limits by evaluating the risk of not performing the tasks against the anticipated exposure.
5.2 The guidelines for emergency exposure are:
Organ Corrective Action Life Saving Whole Body 25 rem 100 rem Extremities 100 rem 300 rem Thyroid 125 rem No limit 5.3 Personnel selected to perform the task should be chosen in ac-cordance with the following guidelines:
5.3.1 Individual is a volunteer or professional rescue person.
5.3.2 Individual is generally familiar with the radiological consequences of the exposure.
5.3.3 Fertile females shall not be used. l 5.3.4 Individual has not previously received emergency exposure.
5.4 Personnel shall not enter any area where dose rates are unknown or unmeasurable with dose rate instruments.
5.5 All reasonable precautions fer minimizing the radiological ccasequences of the emergency action shall be taken (i.e. ,
protective clothing, respiratory protection, thyroid prophylaxis, etc.).
5.6 The Emergency Coordinator (or designee) will complete Section A of Attachment 7.1.
3
o .
Emergency Plan Implementing Procedure EP-2-030 Emergency Radiation Exposure Guidelines Revision 1 and Controls NOTE
- 1. The Emergency Coordinator is the only indivi-i dual who can sign Section A authorizing the emergency exposure.
- 2. Although it is preferable to perform and doc-ument these steps prior to the exposure, the Emergency Coordinator may verbally authorize the exposure and complete the documentation l
at a later time, l
a 5.7 The individual who will receive the emergency exposure will complete Section B.
l 5.8 The Radiolcgical Controls Coordinator will complete Sections C and D. Follow-up medical evaluation will be in accordance with the following guidelines:
5.8.1 If an individual's dose equivalent exceeds 10 rem for the whole body, 30 rem for the thyroid, 60 rem for the skin, and/or 150 rem l to an extremity, the details of the exposure incident shall be brought to the attention of a physician. The physician shall determine the need, extent, and nature of any clinical, biological, or biochemical examinations.
5.8.2 If an individual's dose equivalent exceeds 25 rem for the whole body, 75 rem to the thyroid, 150 rem for the skin, and/or 375 rem for an extremity, the individual shall be examined by a physician. The physician shall determine the need, extent, and nature of any clinical, biological, or biochemical examinations or necessary medical surveillance.
5.9 The Radiological Controls Coordinator shall designate an individual responsible to complete the exposure evaluation and complete a full 4
}
o .
Emergency Plan Implementing Procedure EP-2-030 )
Emergency Radiation Exposure Guidelines Revision 1 and Controls report on the emergency exposure, including necessary reports in ac-cordance with 10CFR20.403 6.0 FINAL CONDITIONS All sections of Attachment 7.1 are complete and assignments have been made for completing necessary exposure reports.
7.0 ATTACHMENTS 7.1 Emergency Exposure Authorization Form I
5
l
. - l EMERGENCY EXPOSURE AUTHORIZATION FORM SECTION A
- 1. Name (to receive exposure):
Soc. Sec. No.:
- 2. Individual TLD Number: Employer /LP&L Department:
3 Task (s) to be Performed:
- 4. Date of Authorization: Authorized Limit:
- 5. Conditions:
Individual is a volunteer or professional rescue person.
Individual is broadly familiar with radiological consequences of ex-posure.
Fertile females shall not take part (Reg. Guide 8.13).
Individual has not received an emergency exposure before.
Dose rates in area are known/ measurable.
Life saving Action?
Corrective Action?
- 6. Emergency Coordinator: (signature)
SECTION B I have been briefed in the radiological consequences of the proposed emergency exposure, and I have volunteered to perform the emergency measures during which I will receive the emergency exposure.
7 Signature: Date:
I l
EP-2-030 Revision 1 6 Attachment 7 1 ( l of))
[' l EMERGENCY EXPOSURE AUTHORIZATION FORM SECTION C (Attach exposure evaluation)
- 1. Dose equivalent assigned for entry:
- 2. TLD/ Dosimeter Results:
3 Bioassay Results:
- 4. Medical Evaluation / Action:
Doctor:
5 Radiological Controls Coordinator: Date:
SECTION D
- 1. Disposition (Allow additional exposure, restricted access, etc.):
l
- 2. Individual assigned to follow up reports (s):
3 Radiological Controls Coordinator: Date:
t l
EP-2-030 Revision 1 7 Attachment 7 1 (a of 62)
9* .
WATERFORD 3 SES PLANT OPERATING MANDAL LOUISIANA POWEFI & LIGH T NNNsb EP-2-033 -
PCM VOLUME 18 REVISICN 1 j ;a PCM SECTION 2 APPROVAL DATE: s ETFECTIVE DATE: Fuel Load .
'lllfE t EMERGENCY PLAN IMPLEMENTING PROCEDURE ADMINISTRATION OF IODINE BLOCKING AGENTS LML W-3 RECORDS CONTROLLED
' COPY NO. bbb gh PORC Mee ing No. f3-C28 ' __
Raviewed: '
a Ch i n Approved:
Plant Manager-Nuclear
WATERFORD 3 SES
~
PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST trocedure No. 50 on Title Akvan Twwdes Zehw; 11 s e spe gga#1 Effective Date fuit > 0A 5 (if different from approval date) ;
1 Comolate 1. B. or C A. Change No. I B. Revision No. /
, f C. Deletion N/4 l i
RF1 MOM FOR CHANGE. REVJSION. OR DELFTION Je ts-vad drh.:s ., + A d eli i t MR E.A L !~/1 1 kdd T%cT'ibe NWe "
REQUIRED SICMATURF3 Originatot~ b WY Date * /]
Technical Review NII Date N/4 SAFETY EVALUATION ,
Does this change, revision, or deletion: TES NO l 1 Change the facility as described in the FSA57 '
l . Change the procedures as described in the FSAR7- '
l
- 3. Conduct tests / experiments not described in the FSAR7 /
- 4. Create a condition or conduct an operation which ex- '
ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Eva untion checklist.
Safety Evaluation kb Mt Date N'/A-3 3 Group /Dep't. Head Review Y 18 b b Date V -/1 -9 k U j Temporary Approvale Date (NOS)
Temporary Approval
- Date QC Review N4 m af8 M - Date #-'(-F7 PORC Review NNI Date 4-1 T-il Meeting No. 73-Af8 PlantManagehNuclearApphoval bbM Date U/ N 3 CTemporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1) g -e- -
,.,,,-p-.-.-y-, -e, - - - - p-m+- --- . ,,q_----,w--.,---,w-- - - - - -m____m - - - _ m -.---m -__---e---ir, --
WATERFORD 3 SES A PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No.
~
'l-6 M - Title NWM/sh4rxhbrW eMe ed Effective Date (if different from $b-N approval [ ate)
Comolete 1. B. o r- C A. Change No. NM '
B. Revision No. / j C. Deletion #4 [
l :
RFASON*FOR CH1MGE. REVISION. OR DELETION b h/ fA:dfbf buh/ /lb hW 2 / O & lN!/N $ ~~
a'rwkw dms Aweo / AL,i!v - &nd n -- -
9 1 ~/ -f
, REOUTRED SIGNATtfR]f' _
Originator # - / Date //- 19'~ U- - '---
Technical Revi kh '
~~ Da te - l!- I 4 ' 2 '- - -- -
Q 4 SAFETY EVALUATION
, revision, or deletion: YES NO f w)DoesChange s
this change, the facility as described in the FSAR?
w
. 1.
- 2. Change the procedures as described in the FSAR? u
~-
- 3. Conduct tests / experiments not described in the FSAR?
- 4. Create a condition or conduct an operation which ex- <-
ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
Safety Evaluation M bd - - --
~-' Date b Y~8 L --
Group /Dep't.HeadReybew MOO U i
-~~ Date - //'/ f- f' --
Temporary Appr. oval *
~-- ~~ ~ -- Da te - (NOS)
Temporary Approval * - --
- - - - --- Date - --
QC Revieu Y W b6s$ct# ~ -~ - ------
D a t e - l4 3 -' f"3 - '* - - -
PORC Review k d- Date I 2 3 ' ' - - Meetin No . -fM'2 4 - --
PlantManagerSuclearApphoval N Ob,NwY- -~~ ' Da te d81 - - - - -
,. ' Temporary approval must be folicwed by Plant Manager-Nuclear approval
's / within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
- -- _.-e
O '
Emergency Plan Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 1 l TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
I 3.0 RESPONSIBILITIES !
4.0 INITIATING CONDITIONS i F
5.0 PROCEDURE ,
6.0 FINAL CONDITIONS 7.0 ATTACHMENTS
. 7.1 Thyroid Dose Graph (1 page) 7.2 KI Issue Record (1 page) 7.3 Potassium Iodide Administration Form (1 page) 7.4 Potassium Iodide Precaution Leaflet (1 page)
LIST OF EFFECTIVE PAGES Title Revision 1 1-9 Revision 1 l
l l
l 1
Emergency Plan Zmplementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 1 1.0 PURPOSE To provide the guidelines for determining when potassium iodide (KI) should be administered to site personnel to minimize I-131 intake and for implementing and recording the administering of potassium ;
iodide (KI). I l
2.0 REFERENCES
i, 2.1 Waterford 3 SES Emergency Plan 2.2 NCRP Report No. 55, Protection of the Thyroid Gland in the Event of Releases of Radiciodine 2.3 IAEA Technical Report No. 152, Evaluation of Radiation Emergencies and Accidents 2.4 Patient Package Insert for Commercial Packaged Potassium Iodide 2.5 EP-3-040, Emergency Equipment Inventory 2.6 Appendix I, Waterford 3 Emergency Medical Assistance Plan (EMAP) to Waterford 3 Emergency Plan 2.7 EP-2-020, Contaminated Injured /Ill Personnel 2.8 EP-2-150, Emergency Records 3.0 RES PONSIBILITIES The Health Physics Coordinator is responsible for the implementation of this procedure.
4.0 INITIATING CONDITIONS This procedure shall be initiated upon reaching the following condition:
The Health Physics Coordinator determines that exposure to I-131 may .
result in quantities sufficient to cause a thyroid dose equal to or greater than 10 rads.
2
Emergency Plan Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 1 5.0 PROCEDURE 5.1 Determine the need for KI administration by using Attachment 7.1, Thyroid Dose Graph.
r NOTE l KI is not to be used in lieu of proper respira- i tory protection (i.e., as a prophylactic). XI is to be used only to block the thyroid gland prior to/after unavoidable exposure or after acci-dental exposure to radioiodine.
5.1.1 Verify and record the calculations / measurements / estimates on At-tachment 7.3, Potassium Iodide Administration Form.
5.1.2 Report the results to the Emergency Coordinator.
5.2 If the thyroid dose is estimated to be 10 rads or greater (the minimum dose for KI administration), the identified physician at Ochsner (see Emergency Call List) and the Emergency Coordinator must be consulted to determine the need to order administration of KI.
NOTE If communication cannot be made to the Ochsner physician, proceed to determine the need to order administration based on verified calculations and consultation with the Emergency Coordinator.
5.3 Upon authorization by the Emergency Coordinator, for the administration of KI to the appropriate individuals, perform the following steps.
5.3.1 Note the authorization in the Control Room Log.
3
- ' Emergency Plan Implementing Procedure EP-2-033 Administration of Iodine Blocking Agents Revision 1 5.3.2 Direct the First Aid Team to report to the KI Administration Area to administer KI. (KI is located in the First Aid Area and First Aid Kits.)
5.3.3 Notify the consulting physician at Ochsner of the administration [
t order. j I.
NOTE This may be unnecessary if consultation was recently completed and/or the notification must be delayed due to conditions / duties.
5.3.4 Assign one or more escorts to transport and assemble the individual (s) at the KI Administration Area.
5.3.5 Verify the above transport.
5.4 Have the First Aid Team direct the exposed individual (s) to read At-tachment 7.4, Potassium Iodide Precaution Leaflet and sign At-tachment 7.3, Potassium Iodide Administration Form. This is to verify that the individual (s) read and understand the leaflet and understand the taking of KI to be voluntary.
5.5 Issue one KI tablet to each individual each day for a minimum of six (6) to a maximum of ten (10) consecutive days and record on At-tachment 7.2, KI Issue Record.
NOTE Unless medical personnel are available, cnly the First Aid Team administers KI. KI shall not be administered to anyone suspected of iodide allergy.
5.6 Forward all completed forms to the Emergency Coordinator for keeping.
4
. Emergency Plan Implementing Procedure EP-2-033 4 .
Administration of Iodine Blocking Agents Revision 1
! 5.7 Direct a whole-body count and/or bioassay analysis be performed on each individual at the earliest opportunity and that the consulting Ochsner physician (s) provide supervision and verification of its completion to the Emergency Coordinator.
i 6.0 FINAL CONDITIONS l
- I
.6.1 Each individual whose estimated exposure to radioiodine exceeded 10 {
rads has been identified and administered KI. -
6.2 All Potassium Iodide Administration Forms and KI Issue Records are completed, signed / initialed and in keeping by the Emergency Coordinator (in accordance with EP-2-150, Emergency Records).
~6.3 Each exposed person has been scheduled for bioassay analysis.
7.0 ATTACHMENTS 1
7.1 Thyroid Dose Graph 72 KI Issue Record 7.3 Potassium Iodide Administration Form 7.4 Potassium Iodide Precaution Leaflet
I 5
l
AftbiMULIIUtt5 tUK Ubt.
......;..- - s g--=m.-_-- -=
- -----=u_---
1,. Determine (estimate er actual) the I-131 airborn2 conct
_-___u-= tration in the area (s) cf intercst. Divide this by the :
w h4-1
- m m y._ -T~ +-==-a
= . = - --
9 protection factor of the equipment used (if unknown.
a___-_rs. =y --* use 1). Locate this number on the Horizontal Axis.
- 2. Follow that line vertically until it intersects with tt
- - - - - Horizontal Line from the duration of exposure in minute (Vertical Axis).
l \ l- 3. If this point of intersection is to the left or below t t o """ , J ;'L . ..z '- line curve, the thyroid dose is less than 10 rad.
e ---- ; -
__ u..e I_-_iiM M M Aist M 19EB
- 4. If this point of intersection is to the right or above
..-__ f -
+3e line curve, the thyroid dose is greater than 10 rad.
.c==_wEm---
m=e- f - - "w=:U=1'9 =. 5. If this point is on the line, then the thyroid dose is !t mrm-
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u-s u-a it-r it-e u--s it-4 st-s , t-I-131 Concentration Factor / Protection Factor EP-2-033 Revision l' . I 6 Attachment 7.1 (1 of 1)
- K'1 ISSUE RECORD e
)
KI Administration 7 8 9 10 j 2 3 4 5 6 1
Date Date Date Date /
Date Date Date Date Date ! Date Int. ;r Int. Int.
Int. Int. Int. Int. L Int. Int. Int.
i Nome: { ,
I h
SS No.: l i . [
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liime:
SS Nc.: '
l Name SS 8c.: ! I
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SS No.: l ! g l l ! ,
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SS No.: !
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L 033 Revision T- _
1 Attachment 7.,2 (I of
. POTASSIUM IODIDE ADMINISTRATION FORM Name of Exposed Individual Last Middle First Social Security Number - -
LP&L Badge Number Duration of Exposure Minutes
. i I-131 Concentration JACi/cc in Air {
l Estimated l Thyroid Dose 110 RAD / <10 RAD (Check One)
Date of Exposure Respiratory Protection Worn During Exposure Yes N o_- ~F Known Iodide Allergy / Previous Allergic Reaction Yes No I verify that I have read and understand the precaution leaflet and understand that taking thyroid blocking agent is voluntary.
/
Signature of Exposed Individual /Date Potassium Iodide tablets issued by:
/
Signature of First Aid Team Member /Date NOTES:
I EP-2-033 Revision 1 8 Attachment 7.3 (1 of 1)
F '
' POTASSIUM IODIDE PRECAUTION LEAFLET HOW POTASSIUM IODIDE WORMp Certala fenns of lodiae help year thyroid gland work right. Most p.,,,,, p ., no ,, p, ,, people got the iodine they need from foods, like iodised salt or fish. The thyroid cas " store" er hold only a certaan amount of
' i. dame.
!~ " In a r=diatioa *==seacr. rad *cua I*diaa =ar k r=3=ad !=
THYRO BLOCK" the air. This matarial may be breathed er own!! owed. It may
, estar the thyroid gland and damage it. The damage would pro.
(PCTAsssuns 00:03 bably not show itself for yeam. Chadres are most M to havo (pronouncess pee.TASSwm EYt.<eewyee .
thyroid damage.
,latitarewesteam: K4 TASLgTS ans SOtamON U.S.P. If you take P' lodida, it wiD Elhap your thyroid gland.
' This reduces the chance that harmful radioactive iodine win enter the thyroid gland.
t WHO SHOULD NOT TAKE POTASSIUM IODIDE
' TAKE POTASSIUM IODIDE ONLY WHEN PUBLIC The only people who should not take potassima lodido are people :
-!EALTH OFFICIALS TELL YOU. IN A RADIATION who haow they are allergic to iodide. You may take potassium !
sMERGENCY. RADIOACTIVE IODINE COULD BE ledido even if you are taking medicanes for a thyroid problem (for l' i ?LELEASED INTO THE AIN. POTASSIUM IODIDE .
(A example. a thyroid hormone er satitbyroid drugl. Pregnant and FORM OF IODINE) CAN HELP PROTECT YOU. aursing womes and behies and chDdren any also take this drug.
IF YOU ARE TOLD TU TAKE THIS MEDICINE. TAKE IT HOW AND WHEN TO TAKE POTASSIUM IODIDE j 3NE TIME EVERY 24 HOURS. DO NOT TAKE IT MORE Potassium Iodido should be takes as soon as possible aber !
OFTEN. MORE WILL NCYr HELP YOU AND AIAY IN. pubuc health officials tan you. You should take ooe dose every 24 ' '
OREASE THE RISE OF SIDE EFFECTS. DO NOT TAKE hours. More wG1 not hip you because the thyroid can " hold" om.
7"ctI3 DRUG IF YOU KNOW YOU ARE ALLERGIC 70 17 limited amounts of ladine. Larger doses win increase the risk IODfDE. ISEE SIDE EFFECTS BELOWJ of side effects. You win probably be told not to take the drug for .
mere than 10 days.
SIDE EFFECTS UsuaBy. side effects of potassium iodide happen when people INDICATIONS take higher doses for a long time.You should be careful not to t
' THYRCID BLOCRING IN A RADIATION EMERGENCY take man than the recommended does er take it fu longer Gaa '
ONLY* you are told. Side effects are unlikely beause of & Iow dose and b short time you wGI be taking the drug.
OIRECTIONS FOR USE .
directed by Stats or local public health authorities la Possible side effecte Include skia rsshes, swelEng of the se!! vary
- Use m the eve of a radiatlos emergency. glanda, and " iodism" (metallic taste, burning mouth and throet, sore tese and gums, symptores of a heed cold and somethnes DOSE se -eh upset and diarrheel.
Tahlets: ADULTS AND CHILDREN 1 YEAR OP
~
ACE OR OLDER: One (1) tablet once a A few people have an eBargic reaction with more serious symp.
toras.These could be fever and joint pe*ma. or sweDing of parts of day. Crush for sman chDdren.
h fece and body and at tirees severe shortness of breath resguir.
i BABIES UNDER 1 YEAR OF AOE:
I One. ham (1/23 tablet ones a day. Crush Ing immodante needical attenties.
5mt. Taking Iodide may rarely cause overactivity of h thyroid ADULTS AND CHILDREN 1 YEAR OF gland, underactivity of the thyroid gland, or enlargement of the Solution: thyroid gland (gentert.
AGE OR OLDER: Add 6 drope to one.
half glass ofliquid and drink each day. ,
BABIES UNDER 1 YEAR OF ACE: WHAT TO DO IF SIDE EFFECTS OCCUR Add 3 drepe to a small amovet of lictund If the side effects are severe or if you have en aDergic reaction, onceaday, stop taking potassiusa lodidos Then. If possible, cau a doctor or For e# dosage forma Take for 10 days unless directed otherwise public beelsh authority for instructaone, by State or local public health authorities.
HOW SUPPLIED
'bre'tt conta eDed room temperetare between 1&* and 30*C l&S*
~ THYROwBLOCKM TABLETS (Potassium Iodide. U.S.PJ bot.
to 86'F1. Keep container tightly closed and protect from Eght. ties of 14 tablets (NDC 0037 04T2 20.1 Each white round, scored De not tse the solation ilit appears brownish in the nozzle of h tablet contains 130 mg potassium iodide.
gg,3,, ,
THYRO.B14CKM SOLUTION (Potassium Iodide Solution.
l WARNING U.S.PJ 30 ml(1 fL a J Ught resistant, measured-drop dispenslig Pzrasdam lodide sAemld noe 6e used by people eHergic to fedids- units (NDC 0037-4287 251. Each drop contains 21 mg potassium I
iodade, Keep out of the reach of chDdres. In case of overdose or aDergic i
reaction, cootect a physicina or the public health authority. WALLACg LA80RATORigt DESCRIPTION osoien es CARTEpall. ACE. lNC.
Each THYRO.BLOCKN TABLET contains }30 mg of Ctantnery. New Jersey CSS 12 I talum iodide.
- k. ,of THYRO.BIACKW SOLUTION contains 21 mg of , , , ,
poi . iodide.
T Attachment 7.4 (1 Of 1)
EP-2-033 Revision [
- I e w-l l
l
~
WATERFORD 3 SES PLANT OPERATING MANGAL LoulSIANA POWER & l.lGHT MM EP-2-090 PCM VOLDE 18 REVISICN 1 , ,
g %,/
2 APPRC7AL Dl:Z:
PCM SECTICN ETTECTIVE DATE: Feel f.cnd V//4/68
. i
. EMERGENCY PLAN IMPLEMEITING PROCEDURE ACCIDENT ASSESSMD.i W&L W'3 RECORCs
-CONTRo; LED -
~
COPY NO. k 94.-
s:
PCRC Meeting No, fJ .02 d i Baviewed: I .
CRC Chairman Approved: _@ "\
Planc Manager-Nuclear l
WATERFORD 3 SES
~ '
PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 50 3 - t/W Title Atc Ihint AMissmic Effective Date hil IcA 5 (if different from approval date)
Cemelete A. B. o r* C A. Change No. I I B. Revision No. I C. Deletion #l4-HrAMOM FOR CHAMCE. REVISION. OR DELETION Jet'swrJ NiG E w d drh.xh //A65.kA m k l m Y '
Ad) Eh i ,4- ' b t-d_
REOUTRED SICMATURES
- Originator M & Date C 3 Technical Review N/M ' Date Bl4 SAFETT EVALUATION ,
Does this change, revision, or deletion: TES NO
. Change the facility as described in the FSAR? d
- 2. Change the procedures as described in the FSAR7- M
- 3. Conduct tests / experiments not described in the FSAR7 Z
- 4. Create a condition or conduct an operation which ex- M ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
Safety Evaluation N MCli1% Date Y/l"9 %
Group /Dep't. Head Review 6 VO N Ctt k Date 9-/ 2 -M l
Temporary Approvale Date (NOS)
Temporary Approval
- Date QC Review #d ' M/ d- Date '--C PORC Review U N b N Dat 4-li~Y3 Meeting No. P4-irl PlantManageNNuclearApprbval M*D Date#ID /8 \
' Temporary approval must be followed by Plant Manager-Nuclear approval ithin 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1)
\
l
9 e WATERFORD 3 SES ,
% PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No.
-696 Title - et *(/ -/ r2^:'wed - -- - -
Effective Date (if different from PM-N approval date)
Camolete 1. B. or C A. Change No. NN B. Revision No. /
C. Deletion d4 MFASON' FOR CMMGE. REVISION. OR DELETION
//2 # mur' do..r,4 lNs had- A-b?-- febrin#s M --
cita,e - 6vw%waMs,,, ins4 Avsan#-- u- - - --
Tl/ Y -*/
REOUTRED SIGNATUDES Originator N M r At 5-
- Date Ir ~ 14 ~ ~ N* ~
Technical Rev[ewU' - b O bJ Da te d N-O -- --
SAFETY EVALUATION YES NO
,-y Does this change, revision, or deletion:
- 1. Change the facility as' described in the FSAR?
- ~
h
- 2. Change the procedures as described in the FSAR? L_
Conduct tests / experiments not described in the FSAR7
- j;
- ::_
3.
Create a condition or conduct an operation which ex- u 4.
ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Sar *y Evaluation checklist.
Safety Evaluation A' - -- -
Da te - l N 9-3 ' - __
-- Date N -l TP Group /Dep't. HeadRevhew N V t
- - ~'
Temporary Approvala Date - (NOS)
Temporary Approval * -- ~~ --- Date - -'
QC Revieu - A M kwW - -------
Date - - l~ / 3- 9 t - - - -
PORC Review NYO .-. Date I f'l- - - Mee tin No . h-02 # - -Y PlantManager$NuclearApphval NNN_tM'- Date 94/dV - - - -
- Temporary approval must be folicwed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
30 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 7.1 Plant Status Checklist (2 pages)-
7.2 Containment Radiation Plots (1 page) 7.3 Containment Radiation Plots General Guidelines - Containment Radiation Plots Table (2 pages)
LIST OF EFFECTIVE PAGES i
Title Revision 1 1-12 Revision 1 l
t I
1
- _ . _ _ . _ - . - .)
i .
Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 l 1.0 PURPOSE 1.1 This procedure describes necessary actions to be taken by the technical and engineering emergency response personnel following a l major off-normal event at Waterford 3 involving the reactor systems.
1.2 This procedure provides a Plant Status Checklist to assist in the coordination of the shift in responsibilities from the Control Room to the Technical Support Center.
1.3 This procedure provides guidelines for the use of the Emergency Plan Containment Radiation Plots.
I
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.3 Waterford 3 SES Final Safety Analysis Report 30 RESPONSIBILITIES .
31 The Technical Support Center (TSC) Supervisor shall be responsible for the implementation of this procedure under the Emergency Coordinator.
32 The TSC Lead Engineer shall provide recommendations on technical assessment to the TSC Supervisor.
3.3 The Technical Support Center Engin2ers shall provide recommendations to the TSC Lead Engineer involving problems affecting plant safety or operation during an emergency, including all areas related to design and operation of Waterford 3 which pertain to mechanical, electrical, fluid systems, reactor physics, chemistry and metallurgy evaluations.
2
r i .
EP-2-090 Emergency Plan Implementing Procedure Accident Assessment Revision 1 1
4.0 INITIATING CONDITIO*LS 4.1 Any of the following emergencies has been declared: Alert, Site Emergency, General Emergency or an event has occurred that has placed the reactor and/or its auxiliary systems in a degraded condition or in a situation with the potential for further degrada-tion. l 4.2 As determined by the TSC Supervisor or the Emergency Coordinator.
5.0 PROCEDURE 5.1 At the direction of the TSC Supervisor, the TSC Lead Engineer will supervise the technical and engineering response personnel and establish an operations / engineering assessment group in the TSC Technical Assessment Area. This assessment group should:
5.1.1 Determine overall plant status and the extent of the particular problems, including:
5.1.1.1 Primary Plant candition 5.1.1.2 Secondari Plant condition 5.1.1.3 Equipment operability 5.1.1.4 Instrumentation operability 5.1.1.5 operations staff diagnosis of off-normal conditions 5 1.~.6 Degradations in the interactions between components, systems and safety trains and/or functions 3
i .
Emergency Plan Implementing Procedure EP-2-090 l Accident Assessment Revision 1
!!OTE A Plant Status Checklist is provided as Attachment 7 1 to assist in the initial transfer of information between the Control )
Room and the Technical Support Center.
If not previously accomplished, request that the Control Room fill out this checklist and provide the information to the TSC via sound-powered phone.
5.1.2 Evaluate the condition of tha reactor, essential safety-related systems, and any significant problem areas identified in step 5.1.1 above, using, as necessary:
5.1.2.1 Piping and Instrumentation Diagrams, including piping system isometrics, general arrangement drawings and electrical schematics
~
5.1.2.2 Applicable plant operating and/or maintenance procedures 5.1.2.3 Parameters as given through the Safety Parameter Display System (SPDS), computer printouts or trend recorders 5.1.2.4 The W3 SES Final Safety Analysis Report 5.1.2.5 Applicable equipment technical manuals 4
i .
' Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 F
NOTE 1 Applicable drawings, manuals and procedures can be obtained from the Records Storage Area within the Technical Support Center.
NOTE 2 If additional information from the Control Room is required, access to the Control Room should '
be gained through a request to the TSC Supervisor anc performed in a'ccordance with f Control Room access provisions. General access to the Control Room is restricted at all times.
5 1.3 Assist the Control Room staff by relieving the reactor operators
. of peripheral duties such as:
5.1.3 1 Plotting cooldown curves, radiation levels or other key parameters to back up or assist in trend analysis 5.1.3 2 Verifying and logging instrument indications where continuous I
technical assessment and monitoring are required to provide notice when degradation is or may be occurring 5.1.3.3 Evaluating the perfunctory adequacy of natural circulation flow i or heat sink efficiency.
5.1.4 Design and coordinate the installation of short-term instrument and control modifications, including preparation of the respective installation or abnormal operating procedures necessary to support the evolution.
5
t .
Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 5.1.5 Inform the TSC Supervisor of engineering related areas where support from the Emergency Operations Facility's engineering staff is necessary, such as for:
5.1.5.1 Supplemental transient or accident analysis. which may include event tree analyses or computer calculations necessary to provide particular event possibilities that could occur and which should be preparatorily considered 5.1.5.2 Engineering development of system modifications necessary to ensure the immediate safe shutdown of the reactor and any system additions necessary to maintain long-term shutdown capabilities.
5.1.6 Inform the TSC Supervisor of equipment conditions that indicate the necessity to establish and dispatch an Emergency Repair / Operations Team from the Operational Support Center to ef-feet necessary damage control measures within the plant.
5 1.7 Provide recommendations or data to the TSC Supervisor as necessary to assure that the protection of station personnel and the public can be maintained.
5.2 Analyses of plant conditions should be performed to determine l reactor core status, including the estimated source term of a potential release of radioactive material from within containment.
Determination of the approximate source and damage estimate can be as follows:
5.2.1 Use the Containment Radiation Plots, Attachments 7 2 and 7 3, in the following manner:
5.2.1.1 Determine the time since the reactor shut down.
5.2.1.2 Determine the containment radiation monitoring reading.
5.2.1.3 Locate the radiation reading (from step 5.2.1.2 above) on the graph of the plots (Attachment 7 2) at the appropriate time coordinate (from step 5.2.1.1 above).
6
s Emergency Plan Implementing Procedure EP-2-090 Accident Assessment Revision 1 5.2.1.4 Take the ratio of the measured dose rate to the dose rate given on one of the curves for a known percent inventory (i.e.,
interpolate between curves).
5.2.1.5 Relate the % fuel inventory released to the " Approximate Source and Damage Estimates" as given in Attachment 7.3 (This value should be compared to the same case number as the curve used in step 5 2.1.4 above.)
5.2.2 Inform the TSC Leaa Engineer of the determined value for the approximate source and core damage estimate as derived from step
~
5.2.1, including any modifications to, or assumptions in, the general guidelines as given in Attachment 7.3.
6.0 FI?I AL C0!!DITIor!S 6.1 Abnormal plant conditions have been terminated or decreased below the " Alert" level emergency, and 6.2 Assessment of abnormal plant events or conditions has been completed or transferred to the Recovery Organization; or 6.3 The Technical Support Center is deactivated in accordance with EP-2-100.
70 ATTACHMENTS 7.1 Plant Status Checklist 7.2 Containment Radiation Plots 7.3 Containment Radiation Plots General Guidelines - Containment Radia-tion Plots Table 7
l O
PLANT STATUS CHECKLIST I
TIME ESFAS J,,2SI CONT. SPRAY H231 SIAS-YES/NO A-ON/0FF A-ON/0FF A-ON/0FF CIAS-YES/NO .B-ON/0FF B-ON/0FF B-ON/0FF MSIS-YES/NO AB-ON/0FF EFAS-YES/NO CSAS-YES/NO RAS-YES/NO SAFETY INJECTION TANKS DUMPED-YES/NO PRIMARY CONTAINMENT ACTIVITY RADIATION PARTICULATE CPM HI RANGE A R/HR INTEGRITY-YES/NO CPM HI RANGE B R/ HR
, PRESSURE PSIG IODINE HUMIDITY % GASEOUS CPM SUMP LVL IN.
REACTOR COOLANT SYSTEM NATURAL CIRCULATION-YES/NO SDM AVAIL.-YES/NO BORON CONC. PPM SHUTDOWN COOLING-YES/NO COOLDOWN-YES/NO-RATE F/HR CONTROL RODS SUBC00 LED MARGIN 'F MODE- 1 23456 ACTIVITY: IODINE ,4,Ci/ gm GROSS ___ -
ELECTRICAL TANK LEVELS A A 0FFSITE PWR AVAIL. YES/NO YES/NO RWSP D/G AVAIL. YES/NO YES/NO CST CSP D/G LOADED YES/NO YES/NO BAMT A B FWST A B D/G.F.0. A B SECONDARY PLANT DRY COOLING TOWERS MAIN CONDENSER AVAIL. YES/NO EAST-YES/NO WEST-YES/NO STEAM BYPASS AVAIL. YES/NO 7
I ATMOS. DUMPS AVAIL. YES/NO WET COOLING TOWERS SAFETIES LIFTED YES/NO EAST-YES/NO WEST-YES/NO MSIV'S OPEN/ CLOSED LVL IN. LVL IN.
EP-2-090 Revision 0 8 Attachment 7 1 ( / of 4L)
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CONTAINMENT RADIATION PLOTS y17-01 2 '-
l 10 5 e
8 -
4 - 10% ' CORE INVENTORY
! 1T41 3 * .
104 1% CORE INVENTO RY a-e.
4" k 2" k 0 1741 1g 3 100% G AP INVENTORY 5.- ,
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9 1 . t . . . . J . . . . I 1 2 4 s a lo 2g a a s[100 2 4 sjs1000 1 04Y 4 O AYs 30 DAYS 10 Attachment 7.2 (1 of 1)
EP-2-0 0 Revisioni .
,-- ,.m- . , , - , - ---a - - -w.--- -
CONTAINMENT RADIATION PLOTS GENERAL GUIDELINES Theoretical curves of gross gamma dose rate versus time are given for the range of potential source terms in Attachment 7 2.
The curves represent direct readings for the containment monitors located inside the containment.
The calculation of monitor response did not include any particulates or iodine since the noble gases are the most significant contributors to dose rate in the containment. At the worst, neglecting the particulates adds a slight amount of conservatism since the actual presence of particulates would result in a higher monitor reading.
NOTES
- 1. The curves account for the finite containment volume seen by the detector but do not account for any monitor physical or shielding characteristics or calibration uncertainties.
- 2. The curves assume that only airborne noble gases are significant. Sprays (if used) would make the iodine and any particulate contribution insignificant. However, particulate plateout on surfaces and direct shine doses from components may make the readings unreliable.
3 curve uncertainties are on the order of a factor of 2 to 5.
EP-2-090 Revision 0 11 Attachment 7.3 (/ofal)
CONTAINMENT RADIATION PLOTS CONTAINMENT RADIATION PLOTS TABLE Percent of Fuel Inventory Airborne in the Containment vs.
Approximate Source and Damage Estimate
% Fuel case Inventory
- E2A Released Acoroximate Source and Damnae Estimatg 1 100 1005: Regulatory Guide 1.4, 100% Fuel Damage, potential core melt 2 10 105: Regulatory Guide 1.4 (or 100% NRC Gap Activity, Regulatory Guide 1.25), total clad failures, core partially uncovered 3 1 1%: Regulatory Guide 1.4.(or 10% NRC Gap Activity), approximately 10% clad failure 4 - 100% coolant release
- 1005 Fuel Inventory = 100% Noble Gas EP-2-090 Revision 0 12 Attachment 7.' (.lofo6)
l WATERFORD 3 SES PLANT OPERATING MANUAL LOUISIANA P O W E R & L,1 G H T l
tmuTIEh SYSTEM EF-2-110 l POM VOLUME 18 REVISION 1 s.
b./
PCM SECTION ? APPROVAL DATE: -
~
EFFECTIVE DATE: Fuel Load Y#/II DIERGENCY PLAN IMPi.EMENTING PROCEDURE MAN-CAUSED EMERGENCIES LP&L W-3 RECORDS
.C:ON- RO:_LE D COPY NO. $b PORC Meeting No. f3 -0 2 A Reviewed: b CRC Chair an -
Approved: ?. %
Plant Manager-Nuclear 9
.a 9
I l
UATERFORD 3 SES I '
PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. SP H O Title Mad l'nte;h sm;/Geng2 i Effective Date / ult 4045 (if different frem approval date) l Cemelete 1. B. or C A. Change No. 1 B. Revision No. / ,
C. Deletion Nld REASON FOR CHAMGE. REVISION. OR DELETION 3e wid rN4* on rm w h / r/n a
- Hpe s.A Lej~j w AA A Eh nve bc/
QEOUTRED SIGNATURES Originator M < - Date Technical Review If4 Date N/A SAFETY EVALUATION ,
Does this change, revision, or deletion: YES NO
- 1. Change the facility as described in the FSAR7 2
- 2. Change the procedures as described in the FSAR7- a
- 3. Conduct tests / experiments not described in the FSAR7 M
- 4. Create a condition or conduct an operation which ex- d ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tacha10CFR50.59 Safety Safety Evaluation 4P [valuationchecklist.
N0c v Date @ll4S Group /Dep't. Head Review bbbOLb v
Data bl)43 -
l Temporary Approvale Date (NOS)
Temporary Approvala Date QC Review NA 4??I d- Date " - w -# '
PORC Review M k b Y d Date k-! b.V2 Meeting No. E -*>'8 PlantManag[-NuclearApphoval b db1D Date Ul? /d3 __
eTemporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6~ Attachment 6.9 (1 of 1) 9
___,____,,-m___., . , _ _ _ . _ , . ,,.-,,r ,_ __m__,_ _ _ _ . _ .,
e
- UATERFORD 3 SES
.' N PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. N'Od -
Titie - 4C-NmW ~
WC"NS Effective Date (if different from PM-N app} oval date)
Cbmniate 1. E. or C A. Change No. N/4 B. Revision No. /
C. Deletion h/4 DetRON TOR CM1? ICE. REVTSION. OR D EL ETTO*1 b h t hn M l b rA*) /l*///<-/n sb d- - h l:r-h>/!O }/ Y -~
i fkVMtl7 kn_ r */is 4 /Wlk, *.s / # k'<- $'-.<ssi14; -!+'s tfw - lN- -
' 'l 'l ~/ -/
REOUT9ED SIGNATURES Originator E b t @ btit ~ Date U- N'b" - ----
Technical Revieu -~ v hb & a - ' --
Date L1-l9-t % - -- -
SAFETY EVALUATION YES NO
, ,Does this change, revision, or deletion: -
L'
/1. Change the f acility as described in the FSAR?
Change the procedures as described in the FSART
- 2.
'u
- 3. Conduct tests / experiments not described in the FSAR?
V
- 4. Create a condition or conduct an operation which ex-ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
Safety Evaluation bb - -
Date blN ' --
N bl-IT- D v N h, Group /Dep't. Head Review - - Da te Temporary Approvala Da te - - -
- (NOS)
Temporary Approvaia - -- - -
- - - Date - -
QC Review W W v
~ ** - ----~--
Date - l-~/.3 & E-~--*
PORC Review N h b b k Date I-I i-U - -- Meeting No. ~#-02#--
PlantManagerkuclearAppr$ val YNbb- - Date -bbI83 - -
' Temporary approval must be followed by Plant Manager-Nuclear approval
, within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emsrgsncy Plan Impismsnting Procsdure EP-2-110
' Man-Caused Emergencies Revision 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
30 RESPONSIBILITIES
'4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5.1 Evaluation 5.2 Response Actions 6.0 FINAL CONDITIONS 70 ATTACHMENTS 7.1 Major Industrial Propertjes Within 10 Miles of Waterford 3 (1 page) 7.E St. Charles Parish Emergency Operations Center Emergency Hotline Report (1 page) 7.3 St. Charles Parish Emergency Preparedness / Industrial Hot Line System (12 pages) ,
LIST OF EFFECTIVE PAGES Title Revision 1 1-18 Revision 1 l
l l
l l
l .
$msrconey Plan Implementing Procedure EP-2-110
. Man-Caused Emergencies Revision 1 1.0 PURPOSE This procedure provides guidance in response to man-caused emergencies either from onsite or offsite sources which may affect the operation of the plant and/or the safety of station personnel.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 DOT-P-5800.2, Hazardous Materials Emergency hesponse Book 2.3 EP-1-001, Recognition and Classification of Emergency Conditions 2.4 EP-2-070, Protected Area Evacuation 2.5 EP-2-071, Site Evacuation 3.0 R ES POM SIBILITIES The Nuclear Operations Supervisor (NOS) or the Emergency Coordinator is responsible for ensuring that actions outlined in this procedure are carried out.
4.0 INITIATING CONDITIONS This procedure is to be initiated upon being notified of a man-caused emergency in any of the following ways:
4.1 A report from station personnel 4.2 Indication from plant instrumentation 4.3 A report from offsite agencies or individuals (e.g., Industrial Hotline) 5,0 PROCEDURE 5.1 EVALUATION 5.1.1 Evaluate the situation; request /obtain information in the following areas:
2 i
Emsrgoney Plan Implementing Proceduro EP-2-110
. Man-Caused Emargencies Revision 1 5.1.1.1 1.ocation 5.1.1.2 Nature of hazardous materials involved 5.1.1.3 Severity of the incident 5.1.1.4 Protective actions necessary 5.1.2 Obtain meteorological data and use Attachment 7 1 to assess the l impact of any airborne hazards.
5.1.3 Use Reference 2.2, DOT-P-5800.2, Hazardous Materials Emergency Response Book, to evaluate the nature of the hazard where appropriate.
'5.1.4 Classify the incident in accordance with Reference 2.3, EP-1-001, Recognition and Classification of Emergency Conditions, and carry out the immediate actions listed.
5.2 RESPONSE ACTIONS 5.2.1 Based on the results of the evaluation and in addition to the actions outlined in Reference 2.3, EP-1-001, Recognition and Classification of Emergency Conditions, carry out the following actions as appropriate:
5.2.1.1 Verify / initiate Control Room HVAC Protective Functions.
5.2.1.2 Initiate sheltering or evacuation of station personnel in ac-cordance with Reference 2.4, EP-2-070, Protected Area Evacua-tion, and Reference 2.5, EP-2-071, Site Evacuation.
5.2.1.3 If the incident is onsite, dispatch the appropriate response teams to the scene of the incident (ensure that appropriate respiratory and protective clothing are worn) to control the incident.
5.2.1.4 Request offsite assistance to aid onsite response personnel.
l l 5.2.1.5 For train derailments / mishaps onsite, notify the Missouri-Pacific Railroad.
l 3 i
l l
l
~
Emargency Plan Implementing Procedure EP-2-110 Man-Caused Emer6encies
~
Revision 1 1
5.2.1.6 For an aircraft crash onsite, notify the Federal Aviation Administration.
5.2.1.7 For trucking mishaps, notify the truokin5 firm (s) involved.
5.2.1.8 Maintain communicationn with offsite agencies. _
5.2.1.9 Continue to evaluate the' sit.uation and monitor meteorological information for chan61ng conditions until the situation is resolved.
6.0 FINAL CONDITIONS 6.1 Direct the restoration of equipment and systems to pre-activation conditions. -
6.2 Close out offsite communications.
6.3 Complete any.a.ctions which may have been init2ated under Reference 2.3, EP-1-001, Recognition and Classification of Emergency Conditions.
. 7.0 ATTACHMENTS 7.1 Major Industrial Properties Within 10 Miles of Waterford 3 7.2 St. Charles-Parish Emergency Operations Center Emergency Hotline Report .
7.3 St. Charleh Parish Emergency Preparedness / Industrial Hot Line System
-s 4
s
%- /
,. - , . - - , . , -- . - - . , , ,,.-- . w ,.4 , , c,,
MAJOR INDUF 11AL PROPERTIES -
~
, _WITHIN 10 MILEv OF WATERFORD 3 -
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Lake Pontchartesin O 0 /
\'N N, Mt Air
- eserve Garyville /
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LEGEND - l%JOR INDUSTRIES O
g IJilva QO q f
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q 7%
O ARGUSCllEMICALC0\.\
so ,,
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O BEKER INDUSTRIES \K O BIG TilREE INDUSTRIES (AIR
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O BONNET CARRE OIL & GAS FIELD 1 l Norc O CHEVRON OIL CO. I e Killor al :
O E.I. DUPONT de NEMOURS & CO. r- -
- n O GENERAL AMERICAN TRANSPORTATION l 'Q 00 11 ope CO. 1 N ,
O GOOD HOPE DIL & GAS FIELD. I g OG [
O GOOD ll0PE REFINERY l @ Uth O j *
@ llANVILLE OIL FIELD l @' a leWSat y
@ 1100KER CHEMICAL CO. ,/' ' . llal ) > ll' f
@ OCCIDENTAL CilEMICAL CO. I O ll ,
O INTERNATIONAL TANK TERMINAL , .
/
e I Destreinan i
i O KAISER ALUMINUM C0KE CALCINER @
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- Sillose ,/-
@ LUCY Oil & GAS FIELD (([ i
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l G MARATil0N OIL CO. T '
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,/ e I @ fl0NSANTO COMPANY 1 I i !
l Lull g 4
@ NORCO OIL & GAS FIELD
@ SEWELL PLASTICS CO.
'(Lac ~N Des Allemands I \ "'
l G SilELL CHEMICAL CO. l 'I
- G SilELL OIL CO. I ir Mhiib ik
- 6 SilELL OIL CO. CRAWFISH PLANT *p" l I 6 SOUTH LHCY OIL & GAS FIELD -
1 outte
@ TAFT GAS FIELD O
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- G TEXACO REFINERY '
- G UNION CARDIDE CD.
Paradle G USAMEX G WITCO CllEMICAL CO.
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, 9,9
ST. CHARLES PARISH EMERGENCY OPERATIONS CENTER
= EMERGENCY HOTLINE REPORT This is the St. Charles Parish Emergency Operations Center with an Industry Hotline Initial Notification Message.
Please obtain a copy of the Industrial Hotline Initial Notification Message Report and stand by to copy.
Due to the following circumstances, an incident has been reported by:
AGENCY / PLANT / Member Industry /NAME OF PERSON PROVIDING INFORMATION/ TELEPHONE This incident / emergency is a: (circle one)
CODE 1 - ALERT (Lowest Priority)
CODE 2 - SITE EMERGENCY (Higher Priority)
CODE 3 - GENERAL ALARM (Highest Priority)
NOTIFICATION TIME: hours DATE: ,
INCIDENT DETAILS: (circle one)
FIRE GAS RELEASE EXPLOSION LIQUID OTHER:
SUBSTANCE INVOLVED:
I.D. GUIDE GUIDE NUMBER _.
FLAMMABLE T0XIC OTHER METEOROLOGICAL CONDITIONS:
WIND SPEED WIND DIRECTION FROM RECOMMENDED PROTECTIVE ACTIONS:
ANTICIPATED DURATION OF INCIDENT:
ESTIMATED: ACTUAL -
AFFECTED PLANTS / INDUSTRIES / SECTORS:
EP-2-110 Revision 0 6 Attachment 7.2 (1 of 1)
~
i ST. CHARLES PARISH EMERGENCY PREPAREDNESS / INDUSTRIAL HOT LINE SYSTEM l
l OPERATING PROCEDURE MANUAL i
EP-2-110 Revision 1 7 Attachment 7.3 (1 of 12)
1 l e e l
l .
INDEX
- 1. PURPOS E - - - - - - - - - - - ----------- 1 II. SYSTEMS DESCRIPTION - - - - - - - - - - - - - - - - - 2 III. ADMINISTRATIVE - - - - - - - - - - - - - - - - - - - 3 IV. OPERATING PROCEDURE - - - - - - - - - - - - - - - - 4 V. SYSTEM REPATR SERVICE - - - - - - - - - - - - - - - - 8 ATTACHMENTS ATTACHMENT 1: REPATR SERVICE LISTINGS ATTACHMENT 11: SIMPLIFIED SYSTEM SCHEMATIC ATTACHMENT III: EMERGENCY COMMUNICATIONS CHECKLTST EP-2-110 Revision 1 8 Attachment 7.3 (2 of 12) 1
. . 1 B
i
'u ST. CHARLES PARISH EMERGENCY PREPARE 0 NESS / INDUSTRIAL HOT LINE SYSTEM
- 1. PURPOSE This system p.tovides a centtdi:ed communication network where emetgency information can be ccmmunicated betecen .the ECC and membet industties. The EOC witt coordinate al.i other civil agency assis.tance that may be necessaraj to resp md to an emergency. The Hot Line System is to be used in conjuction wi.th existing member indust.Paj cmergency p.tocedures.
The basic objective'is.to provide quick, effective and acewtate informa. tion to the Emergency Operation Centet (ECC) and member industtles of an impending or actual emera)ency.
/
EP-2-110 Revision 1 9 Attachment 7.3 (3 of 12)
- 11. SYSTEM DESCRIPTION A. This syMem is a p.tiva.te tie Line betceen t.he Emetgency Ope <tation Center Located at the. St. Charles Parish Courthouse in Hahnville .
and each member h dustry. It is a too-way automaic ringing ei,1 cult, ushg South Central Sett eqalpment Located in their Hahnville Exchange Building, and dedicated Bett System cable facilities becceen att Locations. The system can not be accessed by anyone other uan member industries and the ECC in Hahnville. It is activated by either de ECC or member hdustry Lifting de handset from delr HOT LINE telephone. Ringing voltage will be immedia,tely applied to de catted station and a tinghg tone wilt be heard by the calling station. When the catted station hea,ts his phone ringing he tifts the handse.t on his HOT LINE telephone.
Ringing will den be discontinued and a message or uformation can be exchanged at his point. The ECC has t.he capabillty to initia,te, answer or add any or att of'the separate HOT LINES an .azcanfstence type catt if requhe.d. A noticeable stansmission loss betceen member industties on this ' type catt should be expected.
B. The' system has a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> monitoring capability with consoles b 6e fallowing Locations:
- 1. Communications Room of EOC
- 2. ECC Secretary's Office
- 3. Sheriff's Offhe - Radio Qispatcher's Rocm C. The attached sketch iAttachment II1 shc% -the bad.c'. design.and
. touting of HOT LTHE circu.its betceen menbet industries and de EOC.
1 L
1 EP-2-110 Revision 1 10- Attachment 7.3 (4 of 12) l l
l
III. ADMINISTRATIVE PROCEDURE A. MEMBERSHIP:
- 1. Applientions are obtained from Oe. ECC Office
- 2. Applications approved by be Director of Emergency Preparedness are suinitted to South Centtal Bell Marketing Division for processing
- 3. Survey to be made by Marketing Division and cost of instnflatinn and monthly charge proposal submitted tu applicant
- 4. Member Industries will receive a copy of the St. Charles Emergency Preparedness /Industsial Hot Line Sys. tem Procedure Manual and are responsible.for their internal personnet Ltaining in de opera. tion of de system B. SYSTEM TEST
- 1. Each Thursday, beginning at 9:15hM, except holidays
- 2. ECC or Sheriff *s 0ffice willinitiate a catt 2.0 each member industry and each member industty will call back immediateig to provide a too-way system test
- 3. The syster conference capability will be tested weekly with random member industsies by ECC or Shexiff's Office
i i
EP-2-110 Revision 1 11 Attachment 7.3 (5 of 12) l - _
- t: . OPERATING PROCEDURE l
A. SYSTEM USE AUTHORIZATION :
The Hot Line System is to be use.d by auuori:ed personnet of member industties aniy and sclety for emetgency communication between said industty and de Err.etgency Operation Ce.nter. Member organizations shalt develop intennat p.tocedures designating Hot Line usage authorization and responsibltity.
N B. SYSTEM USAGE GUIDELINES
- 1. GENERAL lt is intended tha.t de Hot Line System be used for
- emergency situations in a member organi:ation's facilities which have or are anticipated to have visibility or impact beyond the affected facility's property Lines. These situations may include, bu.t are not Lic.ited to:
- 1. Unusual noises, odo.ts, abnormal and/or extended ftaring
- activity, etc. which 'may be perceived as atypical by the 9entral. pubiic.
- b. Internal emesgencies such as fLtes, explosions, gas or liquid releases, etc. which may be constalled by de af fected industty knd is unlikely to extend beyond neir fenceline, but may be visible to the public.
- c. Internal emergencies such as fLtes, expt.asions, gas or Liquid releases, etc. which may extend beyond de affected l
i IsldustrLJ's fGCliities.
- d. Extetnal emetgencies such as hazardous material transporta. tion accidents, pipeline Leaks /ruptu.tes, etc.
EP-2-110 Revision 1 12 Attachment 7.3 (6 of 12)
_ ~
C. SYSTEM CPERATING PROCEDURE
- 7. INDUSTRY-70-EOC Any siMtion cr emetgency meeting de guidelines described in B.1.a.b.c.d above should be promplig reported t.o EOC, and aduked if any assistance is needed. The authorized affected hdustty representative should clearly advise de ECC of de proper emergency code and apptopriate details, u.tilicing the Eme.tgency Cormnunication Checkiist (Attachment-III). As a requirement, when de EOC is notifLed af any incident, he affeeted udustty shati advise the EOC when de condition or emergency has cleared. En de event of a CODE 2 SITE EMERGENCY or CODE 3 GENERAL ALARM, the affected industty should conyeg to the EOC Director de necessa.1y infonmation, details, and recomendations to assure de proper and app.topsiate civit agency support is provided.
- 2. EOC-TO-INDUSTRY An industty or external emergency of a CODE 2 SITE EMERGENCY or CODE 3 GENERAL ALARM natute may necessita.te de EOC alerting a neighboring, downwind or otheswise potentialty affected industty of de nature. of de emergency so p. toper porteetive measures may be planned and/or initiated. The ECC should provide de necessang details sufficient t.o assure the proper protective measures can be taken.
- 3. INDUSTRY-TO-INDUSTRY The. Hot Line System is capable of providing industty-to-indust)uf cormnunications. When an energency or situation necessitates industry-to-industry correnanication, de EOC should be .tequested by the affected industttj t.o contact de requested oder industty on de Hot Line conference line. This made will enable ditect, tea (or more) way communication beboten indust'ies and the EOC.
EP-2-110 Revision 1 13 Attachment 7.3 (7 of 12)
.?. DJERGENCY COMMWIICATIONS C00ES The fattowing emergency communication code.s should be u.sec when a member industty deems it necessary to use the Hot Line System:
CODE 1 ALERT - Lowest level of priority. A minor emergency or problem such as a fhe, explosion, gas or Liquid release, unusual noise, unusual odor, abnormal and/or extended flaring activity or c u er internal event has occurred which may be visible or detectable by offsite people but for which no external action c.1 assistance is necessary. The emergency is under conttal or expec.ted to be brought under conttot in a short time.
CODE 2 SITE EMERGENCY - Higher level of pridrity - standby. A moderate emergency such as a fire, explosion, gas or Liquid retease, or cuer event has occurred which affects plant operation and for which protective action for offsite may be necessary. The emergency is not yet under control and may ex. tend or has extended beyond .the industty's conttot. Offsite emergency assistance would be placed in standby condition.
CODE 3 GENERAL ALARM - Highest Level of priority - emergency assis-tance needed. A severe emergency such as a maj6r l
fLte, explosion, gas or Liquid release, o.1 ouer event has occurted which seriously affects plant operation, jeopa.tdizes offsite areas and for which p.toteetive actions offsite will be necessa.ty.
E-tergency offsite assistance would be activated and de affected public and nearby industies would be notifLed.
EP-2-110 Revision 1 la Attachment 7.3 (8 of 12) 1 1
l
1 S. EMERGENCY CCMMUNICATIONS CHECKLIST Member industries are expected to complete de &nergency Cormunications Checklist iAttachment III) at us time of an incident to assure clear and accurate information is ttansmitted to the ECC. This information should be conveyed in .the sequence listed on de checklist. Member industries are encouraged to subsequently utilize this completed foran as may be needed by i>Lternal requiAements for documentatwn.
1 i
EP-2-110 Revision 1 15 Attachment 7.3 (9 of 12) wy
V. SYSTEM REPAIR SERVICE A. REPAIR SERVICE
- 1. System breakdowns or mechanical diffic"!!!es should be promptly reported to d e ECC. The EOC will coordinate repain wLth South Centrat Bell. Routine minor repaiu or emergency repair.s can also be coordinated by the affected member industry by calling de appropiate South Centut Bell Repa.ir Service number Listed in Attachment T.
B. SYSTEM MODIFICATION
- 2. Any modification to de. Hot Line System mas.t be cleated
- $1ough de Director of Stergency Prepa.tedness to assure system integrity and reliabilih] ate maintained. The ECC Director.will coordinate any requests for system changes becceen de member industty and de approp.~ late Soun Centtat T'~!L Marketing group.
r EP-2-110 Revision 1 16 Attach =e tt 7. 3 (10 of 2 2)
ATTACHMENT 1 ST. CHARLES PARISH E'fERGENCY PREPAREDNESS / INDUSTRY HOT LINE SYSTEM REPAIR SERVICE REPATR SERVICE NO.
CIRCUIT NO. MEMBER INDUSTRY 652-9011 60PL 8406 BUNGE CORPORATION 652-9011 60PL 8418 IKEY LUCAS (HOME) 652-9011 60PL 8420 GOOD HOPE REFINERIES 652-9011 6005 1131 GATX TERMINAL (443-2511) 652-9011 60PL 8401 SHELL CIL (NCRCO) 652-9011 60PL 3399 INTERNATIONAL MATEX 652-9011 60PL 3398 ST. CHARLES GRAIN 652-9011 60PL 3514 SHELL CHEMICAL (NORCO) 822-1435 60PL 8402 AMERICAN CVANAMID 822-1435 60PL 8473 FARMERS EXPORT COMPANY 870-1122 60PL 0423 TEXACO 870-1122 62PL 18012 MONSANTO 870-1122 62PL 18013 UNION CARBIDE 870-1122 62PL 18011 WITCO 870-1122 62PL 18010 BEKER 870-1122 62PL 18009 SHELL (TAFT) 870-1122 62PL 18008 H00KER 870-1122
\
62PL 18057 UNION CARBIDE STAR PLANT i 870-1122 62PL 18058 SHELL " CRAYFISH" 870-1122 62PL 12246 UNION CARSIDE LINCE 870-1122 62PL 1802% WATERFORD 111 652-9011 60PL $525 LITTLE GYPSV SHELL PIPELINE 652-9011 60PL 8625 EP-2-110 Revision 1 17 Attachment 7.3 (11 of 12)
ATTACHMENT 11 ST. CHARLES PARISH EMERGENCY PREPAREDNESS / INDUSTRIAL i
l HOT LINE SYSTEM l SIMPLIFIED SYSTEM SCHEMATIC UNION CARBIDE -
WITCO BEKER SHELL TAFT HOOKER STAR PLANT SHELL " CRAWFISH" LINDE WATERFORD lli h
U CONTROL EOC fl C
~y EXCHANGE HAHNVILLE TELEPHONE l]
NORCO TELEPHONE HAHNVILLE : E UI ENT EXCHANGE ON 4 a 1 f 1f __
GATX BOUTTE OIL SH TELEPHONE *^
EXCHANGE IKEY LUCAS 4 GOOD HOPE f BUNGE ST. CHARLES GRAIN MONSANTO SHELL CHEMICAL TEXACO LITTLE GYPSY FARMERS EXPORT BIG THREE SHELL PIPELINE AM. CYANAMID i EP-2-110 Revision 1 18 Attach::cnt 7.3 (12 of 12)
~
WATERFORD 3 SES PLANT OPERATING MANDAL l OUISIANA POWER & LIGHT EP-2-120 PCM70M PCM SECTION 18 2
REVISION APPROVAL DATF.!
1
' i '5W !
EFFECTIVE DATE: Fuel Lond 4/.a/&
G ERGENCY PLAN IMPLEMENTI C PROCEDURE GRE"s"lE6ibs CQNTROLLE3 COPY h .-
y'.*:.
eart PORC Meetir g No, f3 0;J ,
Reviewed: ,
P Cha r att j i
Approved:
Plant Manager-Nuclear
. . i l
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 50 120 Title Anruank im& M dolen:t _
Effective Date /4 41 ma (if different frem approval date)
Comniate A. B. e ra C A. Change No. 1 B. Revision No. i ,
C. Deletion NI4 RFASOM FOR CHANGE. REVTSTON. OR DELETTON ,
b es~ue,f di/s L Add AML c. A" C,<wA nD AJ) E % ecT-N e.' b n ,_
RKOUTRED STCMATURES Originator N Y Je Date 1 Technical Review N/ I ' Date N/$
SAFETY EVALUATION ,
'oes this change, revision, or deletion: YES NO
. Change the facility as described in the FSAR? /
Change the procedures as described in the FSAR7- -
2.
3 Conduct tests / experiments not described in the FSAR7 s
- 4. Create a condition or conduct an operation which ex- /
ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
Safety Evaluation #v b@l% Date hO-D Group /Dep't.HeadRevihw 4 bb11C Date Y -/ 2 -Q -
O I Temporary Approval' Date (NOS)
Temporary Approval
PlantManagehNuclearAppr$ val NbNd Date D17 /I3
' Temporary approval nst be folicwed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1)
, _ - _ . - . _ , _ - _ _ _ _ . , _ , , , . _ _ , . _ , _ _ _ , _ . - - - _ . . , . _ _ . - , . , _ - . . . . . ~ . . - - . - _ - _ , , , . - - , - . , , _ _ ,_ ..
WATERFORD 3 SES
~
PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. 'N -N - Title - M '7A'*7#f--~~-
Effective Date (if different from Pd-N approval date)
Camniete 1. B. o r- C A. Change No. N/4 B. Revision No. /
C. Deletion N/4 ,
MCASON COR CM MCE. RCVTSTON. OR DELETION b h-! h ra n l h kr' dei //< 4%nl d-b- kr'bd9r .RiddMs!! ' ~~
rkh'Jv4h /he.,i+1 $<v_s.r>:71.r./ /h!,,n!,; /kn r$zm N -
"I '/ "/ 'l REOUT9ED SIGNATURES
-Originator E OIMhi$8d --
- Date l l- I Db- - ----
-- Da te . If-l Q- t 2.--
Technical Review - bv Y I l
SAFETY EVALUATION Does this change, revision, or deletion: YES No y -
- s. .i t . Change the f acility as described in the FSAR? *
- 2. Change the procedures as described in the FSAR?
Conduct tests / experiments not described in the FSAR7
~-
3 4 Create a condition or conduct an operation which ex-ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safet- Evaluation checklist.
Safety Evaluation 9h Glh - - -- -
Date b'-b E - --
Group /Dep't. HeadReYiew kv N bd> j'-
--- Date -Il~/9 G '-
Temporary Approval 8 -
- - - Da te -
(NOS)
Temporary Approval * - - ~ ~ ~ ~~- Date - -
QC Revieu - A ' W ~ # -- * ----~~~
Date - H .3 & S ------
PORC Review Y b O d '
'Date I'l9-Y'2.-~ Meetin N o . Tb c 2 8 - -
PlantManagerkNuclearApphoval- MbNtN- Date - I'D -
i
- Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
f v l
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
Emergency Plan Implementing Procedure EP-2-120 Natural Emergencies Revision 1 TABLE OF CONTENTS 1.0 PURPOSE 2.0 REFEREN CES 3.0 RES PONSIBILITIES 4.0 INITIATING CONDITIONS ,
5.0 PROCEDURE 5.1 General 5.2 Tornado / Hurricane 5.3 Flooding 5.4 Earthquake 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 71 List of Structurally Safe Areas to Shelter Onsite Personnel (1 page) (LATER)
LIST OF EFFECTIVE PAGES Title Revision 1 1-5 Revision 1 l
1
(
Emergency Plan Implementing Frocedure EP-2-120 Natural Emergencies Revision 1 1.0 PURPOSE The purpose of this procedure is to provide site specific instructions for an emergency that supplement the Louisiana Power and Light Company Organization for Major Emergency plan.
2.0 REFERENCES
2.1 Louisiana Power and Light Company Organization for Major Emergency 2.2 Waterforo 3 SES FSAR, Chapter 16 2.3 Waterford 3 SES Emergency Plan
.2.4 EP-2-070, Protected Area Evacuation 2.5 EP-2-071, Site Evacuation 3.0 RES PON SIBILITIES The Emergency Coordinator is responsible for the implementation of this procedure.
4.0 ELLTIATING CONDITIONS This procedure shall be initiated whenever an Unusual Event, Alert, Site Emergency or General Emergency is declared due to natural events (e.g., hurricane, flooding or tornado).
5.0 PROCEDURE 5.1 GENERAL 5.1.1 The Emergency coordinator shall direct that the station alarm be sounded, at the end of which an announcement shall be made over the public address system which describes the nature of the emergency and gives a brief description of the hazard and any protective measures to be taken (e.g., site evacuation, sheltering, etc.)
5.1.1.1 Refer to Attachment 7 1 for a list of onsite shelter areas. .
2
_. ~ , .
Emergency Plan Implementing Procedure EP-2-120 Natural Emergencies Revision 1 5.1.1.2 Refer to EP-2-070, Protected Area Evacuation or EP-2-071, Site Evacuation, as appropriate.
5.1.2 The Emergency Coordinator shall direct that the station alarm be sounded at the end of the above announcement.
5.1.3 The Emergency Coordinator shall direct overnight accommodations to be prepared, as necessary.
5.2 TORNAD0/ HURRICANE 5.2.1 The Emergency Coordinator shall direct the Emergency Communicator to maintain regularly scheduled communications with St. Charles Parish Emergency Operations Center (EOC) in order to obtain the latest status of meteorological conditions as applicable.
5.2.2 When sufficient time and manpower are available, the Emergency Coordinator shall direct performance of protective actions for plant equipment and structures in accordance with Administrative Procedure (LATER).
~
5.2.3 Keep station personnel informed until tornado conditions have abated.
53 FLOODING 531 If sufficient time exists, the Emergency Coordinator shall direct Security to maintain a flood watch, as required, and:
5.3 1.1 Direct communications to be established between flood watch and Control Room.
5.3 1.2 Direct communications to be established and maintained with U.S.
Army Corps of Engineers, in order to obtain periodic status of river levee.
5.3.2 If flooding occurs, the Emergency Coordinator shall direct the following:
5.3 2.1 Verify storm and ficod doors, below flood level, in the Nuclear Plant Islant Strue;ure are closed.
i 3
EP-2-120 Emergency Plan Implementing Procedure Natural Emergencies Revision 1 S.3 2.2 Inspect below grade levels of the Nuclear Plant Islant Structure for leakage.
5.3 2 3 Direct Emergency Communicator to arrange transportation (rail, ~
boat, helicopter) for shift change, as necessary.
5.3.2.4 Coordinate procedure implementation with Emergency Operations Procedures (LATER).
5.4 EARTHQUAKE 5.4.1 The Emergency Coordinator shall direct that the seismic monitoring system be activated to record aftershocks.
5.4.2 The Emergency Coordinator shall direct visual inspection of the plant and site with particular attention paid to safety systems, yard tanks, transformers and intake structures.
6.0 FINAL CONDITIONS 6.1 Natural event declared over by the Emergency Coordinator 6.2 Recovery organization established 7.0 ATTACHMENTS 7.1 List of Structurally Safe Areas to Shelter Onsite Personnel (LATER) 4
Q O LIST 0? STRUCTUALLY SAFE AREAS TO SHELTER ONSITE PERSONNEL (LATER)
EP-2-120 Revision 1 5 Attachment 7 1 (I ofi )
\ \
l . .
s O ft LOUISIANA POWER S LIGHT CO. ,
2::pr::::f WATERFORD 3 E fr $ #sYl5 MISSING INFORMATION UST i- !
6 l
PROCEDURE No
~ /'OO PROCEDURE / d743/ &#Md/7dIJ k / J <
AFFECTED CLEARED ITEM pg gggggg DATE l lNITIAL I. A7} fill 64V4 JIV8 pf0(f /1/lX /1D , C?2l A NtdbrTilfin) 0$}7 lions Gef/fl//rf 71D.S 5. 3 2 / l l r! f#alwht t' 7. / \ l I I I I I I l l 1 I i i I .
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1 I I I I
- i I I l l l l
I I I I
I I I i l i I I I I I
I I 1 I l
i i I i l I i I I l l -
ALL MISSING NFCRMATiCN CN THIS UST HAS SEEN CLEARED I
1 ASStGNED auTHCR
_ _ - _ _ _ . . . . - - _ . . _ . . _ _ _ _ _ . _ . _ _ . _ . . . _ _ _ - _ . . _ _ . - . - _ _ . . . _ - . . _ _ . ..i
WATERFORD 3 SES PLANT OPERATING MANDAL LOUISIANA POW ER & t.lG HT NNN EP-2-130 PCM VOLUME 18 REVISION 1 ; . ;
PCM SECTION 2 APPROVAL DATE: -
0 EITECTIVE DATE: Fue1 Lead
. EMERGENCY PLAN DIPLEMENTING PROCEDURE EMERGENCY TEAM ASSIGN:ENTS L?alW-3 AECORDS
-CONTR _3: LE D COPY
,.,,i, NQ_ -
PORC Meeting No, f3.ca 8 Reviewed: kk ,
j (PCRC Chairman Approved:
a N) A>.L Plant Manager-Nuclear i
.am.-..mm
1
. WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. $P-2-l *30 Tit 1c Tw w a .
Effective Date Av44Lv4h (if different from approval date)
Camniate 1. B. er C A. Change No. /
B. Revision No/ h l ,
C. Deletion MA nrasos ;on b nevistos. on ortrTras s 3 m x, - _ a c d mt d1 hay -,0/ di, ic'N9(E. A %la f ni_t RKOUrWrD STC4dT ,
originato M Date _E -/[~~ M TechnicalRev[ew MQ v ' q Date 3M3 SAFETT EVALUATION Does this change, revision, or deletion: TES NO
- 1. Change the facility as described in the FSAR7 /
- 2. Change the procedures as described in the FSAR7 '
Conduct tests / experiments not described in the FSAR7 '
3
- 4. Create a condition or conduct an operation which ex- #
ceeds, or could result in exceeding, the Limits in Technical Specifiestions?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safet Evaluation checklist.
Safety Evaluation 4 O f GMV Date 3- h 3 Group /Dep't. HeadRev$ew v 4 N boh Date 2 Y7 v
i Temporary Approvala Date -
(NOS)
Temporary Approvale Date QC Review 4 '.4 , dr/ k /t Date a '
PORC Review N N NE a Date "- I 5-$ 1 Meeting No. 73-n-#
PlantManage/hNuclearApprval NeN A Date M'7 /d3 l eTemporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6 Attachment 6.9 (1 of 1) 2G
e WATERFORD 3 SES
.A PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. - O OO - Title /-%'w/I*/ - Ar' rod (if differ'ent from Y PM-N approval date)
Effective Date Chmolete 1. B. o r- C A. -Change No. N/A 4
B. Revision No. /
C. Deletion N/4
! 9eas0N rog cu1McE. Rev is toff. OR DELETTON
S-i/N/ev/ /w4w cAsX4- buz/J-Ar -b$ehu - & JAWS - --
! A m a n c. ,6782 kmA h%w-Sm%d* - - -- -
--( / 4 ~/
REQUTRED SIGNA *URQ Originator M ble>/NI - - -
Date I I~ I N1" ---
Technical Review -- M d &
Date 3 h NO - '- -
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, 3 SAFETY EVALUATION
,Does this change, revision,' or deletion: YES NO R
)1. Change the facility as described in the FSAR?
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- 2. Change the procedures as described in the FSAR?
Conduct tests / experiments not described in the FSAR?
3
- 4. Create a condition or conduct an operation which ex-ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-
! tach a 10 CFR 50.59 Safet- Evaluation checklist.
Safety Evaluation %O &- - --
-' Date- bb - --
Group /Dep't. HeadRevYew u6 ca k. - --- Date E-I9% ~-
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Da te - -
(NCS)
Temporary Approval *
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Temporary Approval *
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) QC Review A W N W - ~~ --~~~--
Date - h/ 3- /-B -- - - -
PORC Review Iftbb- Date ' I - l 9 -I3 - ~ ~ Meeting No. ft 0; # ---
PlantManageh-NuclearApprbval- DcO*%b-'- - Da te bIh /J3 -
' Temporary approval must be followed by Plant Managar-Nuclear approval y within 14 days.
UNT-1-003 Revision 2 32 Attachment 6.9 (1 of 1)
l
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's ,
. Emergency Plan Implementing Procedure EP-2-130
$mergency Team Assignments Revision 1 TABLE OF CONTENTS 1.0 PURPOSE 2.0 REFEREN CES 3.0 RESPONSIBILITIES 4.0 INITIt. TING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 71 Emergency Team Selection Sheet (1 page) 7.2 Task Implementation Sheet (5 pages) h.kh.
LIST OF EFFECTIVE PAGES Title Revision 1 1-91,6-1 Revision 1
% i ;&l J
b l 1
Emergency Plan Implementing' Procedure EP-2-130 Emergency Team Assignments _ y ' Revision 1
/
/, s i
1.0 PURPOSE ,
~
This-procedure provides guidance for the Emergency Coordinator in the formation of the Emergency Teams and tiheir "back-up" provisions. ,
s
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Pl'an ,
2.2 EF_-2-081, Search and Rescue
- s 23 EP-2-140, Reentry ,
s .
2.4 EP-2-010, Notifications'-and Communications \ '
u x..
EP-3-050, Emerger.cy Response Call Lisf. 'EQ N
2.5 s
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"' s - '
s 3.0 RESPONSIBILITIES t The Emergency Coordinator is responsible for Nthe implementation of this procedure.
4.0 INITIATING CONDITIQUfg s u i 4.1 This procedure shall be initiated uponx any of the following.'a s
conditions: \ -
4- 1
(, s., #O p, General 4.1.1 Declarationof]nususiEvent, Alert,' Site Einerge.r.ef , - l Emergency. -
0 4.1.2 Asdirected~QyNheEmergencyCoordinator. -
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A c' cs ,N N -
5.0 PRocEnuRE ,w KX -
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5.1 Upon declaration of an emerger,cy, the Emargency',Coorcipator 4
% shall assess what manpower and resources will be nec/ssary.
s ., M- *i- .
s 5.2 The Emergency' Coordinator shal{ refer to Attachment 7 1Cand select s
i the appropriate = response team to be utilized.
l I
5.2.1 Attachment 731, Emergency Team Selection Sheet, lists the availa-
- e. ,
ble emergency response-te-ams and ref erenpes Attachment'.7 2, whj.s .
ch, \ ,
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describes'the' correct asseme.ly ' ~ of that team.
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- Emergency Plan Implementing Procedure EP-2-130 Emergency Team Assignments Revision 1 5.3 Upon selecting the appropriate team, refer to the referenced page of the attachment.
5.3.1 The referenced page of the attachment will provide the necessary information for activating the teams. ,
6.0 FINAL CONDITIONS The necessary teams have been assessed and utilized.
70 ATTACHMENTS 7.1 Emergency Team Selection Sheet 71 Task Implementation Sheet ,
9 I
3 8
_. _ - _ ._. .-. .. __. =-.
EMERGENCY TEAM SELECTION SHEET 1
i TEAM ATTACHMENT Medical Emergency - First Aid Team 7.2, p.5 Maintenance - Emergency Repair / Operations Team 7.2, p.6 Search and Rescue Team 7.2, p.7 Fire Fighting - Fire Team 7.2, p.8 Field Monitoring Team 7.2, p.9 ll i
i .
EP-2-130 Revision 1 4 Attachment 7 1 (1 of 1) g m g - 4.-.4 -- - - - - - . . -
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TASK IMPLEMENTATION SHEET
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MEDICAL EMERGENCY Imelementine Procedures FP-2-200, First Aid and Medical Care EP-2-031, In-Plant Radiological Controls During Emergencies EP-2-032, Monitoring and Decontamination EP-3-010, Emergency Plan Training EP-3-040, Emergency Equipment Inventcry Avntinhia Me s ei t91 s Telechene Ochsner Clinic, Alton Ochsner Medical Foundation 818 2u60 1 gou tuv_mm11 West Jefferson General Hospital St. Charles Hospital 788 62n2 Ambulance Servie. j cAn3g 7PS- 6242 /I
'_22;;-
St. Charles Ambulance Service Wect Jefferson Air Care Helicopter 1 800 982 uno6 h;y; First Aid Team Assembiv .
During normal working hours, the First Aid Team will consist of various site personnel. Call for the team to be asse= bled over the public address system. After normal working hours, utilize on-shift Health Physics and/or Radiochemistry technicians; both have received "First Responder" first a4d training.
Locations of First Aid Kits are found in procedure EP-2-081, t
J J
k EP-2-130 Revision 1 5 Attachment 7.2 (I of5')
TASK IMPLEMENTATION SHEET EMERGENCY MAINTENANCE OF PLANT FACILITIES Imolementinz Procedures EP-2-031, In-Plant Radiological Controls During Emergencies EP-2-140, Reentry Reenir Ooerations Team Assembl y Direct Operational Support Center (OSC) Supervisor to establish an Emergency Repair / Operations Team in accordance with EP-2-140, Reentry.
The OSC Supervisor will draw from station Maintenance personnel that have mustered in the OSC in response to the emergency.
7 Mechanical 6 I&C 4 Electrical 6 Computer 12 H.P. (6-30 min.)
Additional Engineering staff may be available in the Technical Suport Center (TSC). If necessary, direct additional call-outs to be made. If a protected area evacuation has occurred (Site Emergency), personnel will be available at assembly areas (contact via Security).
EP-2-130 Revision 1 6 Attachment 7 2 (G of fIl 1
TASK IMPLEMENTATION SHEET SEARCH AND RESCUE ONSITE Imolementina Procedures EP-2-031, In-Plant Radiological Controls During Emergencies EP-2-081, Search and Rescue 4 Team Assembiv Direct the OSC Supervisor to establish an emergency Search and Rescue Team in accordance with EP-2-081.
Search and Rescue Teams should consist of volunteers from I
Operations, Maintenance, Radiological Controls, and/or Security.
Select members from personnel who have assembled in the OSC in response to the emergency.
7 Mechanical 6 I&C 4 Electrical 6 Computer 12 Health Physics (6, 30 min.)
Additional personnel available: Direct the TSC Supervisor to perform further call-outs. If a protected area evacuation has occurred, personnel will be available in a:sembly areas.
Contact the Shift Security Supervisor to request personnel from Security.
'l s
l l
l EP-2-130 Revision 1 7 Attachment 7.2 (3 of5I')
e 0 TASK IMPLEMENTATION SHEET FIRE FIGHTING Imelementine Procedures FP-1-010, Fire Emergency Procedure EP-2-110, Man-Caused Emergencies PS-11-103, Veh.icle Access Fire Decartments Telechene Offsite Fire Company -
(St. Charles Emergency Operations Center or 789-6266 Industrial Hotline)
Fire Team Assembiv Prior to the activation of the OSC, the NOS-SS will direct the Fire Team to assemble and perform fire-fighting tasks. After the activation of the OSC, the OSC Supervisor will direct Fire Team activities. The Fire Team consists of various on-shift personnel. Back-up to the Fire Team is offsite assistance.
ENSURE SECURITY IS NOTIFIED IF THE FIRE DEPARTMENT IS CALLED TO ENSURE EXPEDITIOUS ENTRY OF VEHICLES AND PERSONNEL.
Requests for the offsite fire company will be generated only throuEh the St. Charles Industrial Hotline.
EP-2-130 Revision 1 8 Attachment 7.2 ( Y of 5')
TASK IMPLEMENTATION SHEET i FIELD MONITORING Teniementine Procedures EP-2-060, Radiological Field Monitoring Emerrency Field Manitoring Team Assembiv The Emergency Coordinator or the Health Physics Coordinator may direct that EP-2-060 be implemented.
The assignment of personnel to Radiation Field Monitoring Teams shall be made by the Radiological Controls Coordinator (located in the OSC). He shall select at least two individuals, one of whom shall be qualified in the operation of the field monitoring equipment. If a vehicle is used, one of the individuals must be qualified to operate the vehicle.
Personnel Available 7 Mechanical 12 Health Physics (6, 30 min.)
4 Electrical 6 I&C 6 Computer Additional personnel: Direct the TSC Supervisor to perform further call-outs. If a Site Emergency has been declared, personnel will also be available from assembly areas. (Protected area evacuation is in process or has occurred.)
EP-2-130 Revision 1 9 Attachment 7.2 (f orf)
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EP-2-140 PCM VOLUMF. 18 REVISICN 1 M
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APPROVAL DATE:
PCM SECTION 2 r,m 1 T_n, A EFFECTIVE DATE:
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EMERGENCY PLAN IlfPLE fENTII;G PROCEDURE REENTRY LP&L W-3 RECORDS CONTROLLED COPY NO _ d PCRC Msecing No. f3 -cJ d ,
Reviewed: kb KC Chair an 4
Approved:
Planc Manager-Nuclear l
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WATERFORD 3 SES
. PLANT OPERATING MANUAL l
l CHANGE / REVISION / DELETION REQUEST Procedure No. 5l 3- N W-- Title kiiMRY Effective Date hist Acab (if different from approval date)
Camelete A. B. e ra C A. Change No. I B. Revision No. / ,
C. Deletion N/4 REASON FOR CHANCE. ROITSION. OR DELETION b (1 w o t dr h: & ,. -w t?) A i N'A S,A $ n u h d e $
M A EWmve ' %%
REOUTRED SIGN ATURES Originator d W f ./
- Date '
Technical Review N/4 Date 4/4 SAFETY EVALUATION ,
'oes this change, revision, or deletion: YES NO
.. Change the facility as described in the FSAR7 /
- 2. Change the procedures as described in the FSAR7-
- 3. Conduct tests / experiments not described in the FSAR7
- 4. Create a condition or conduct an operation which ex-ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
Safety Evaluation 4 NO3Gb Date N~l2- O Group /Dep't. Head ReviN k @ [C NAO' Date 4-O-33 i
Temporary Approvala Date (NOS) l Temporary Approval
- Date QC Review #A MM- Date #-/-*'
PORC Review N E N b Date hii-N 3 Meeting No. f3 -,r#
Plant Manage hNuclear Apprdval ( N M u D Date DOD
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
l UNT-1-003 Revision 6' Attachment 6.9 (1 of 1)
"- - - -- - - - - . . . , - . _ _ . , . ,m,_, , , _ , _ , , ,,
l l
l WATERFORD 3 SES
.R PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. -O -/ O Title - l'6# * " - - - - - - - - - - - -
Effective Date (if different from -t' PM-N approval date)
Camniete t. B. or C A. Change No. Wl.1 S. Revision No. /
C. Deletion a/4 .
DriSON FOR CHAMCE. REVT970N. OR DELETTO'l ffI# wJ cu, &i M dn&'4A,--Aidw enJa a,cd - - --
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REOUTRED sicNATURes Originator & bLOhMW'- ' -
Date lI-l i-f' - ---
Technical Review - ub (
Date -II-l9%S - -
i SAFETT EVALUATION
- Does this change, revision, or deletion: TES NO ts
- 1. Change the facility as described in the FSAR?
- 2. Change the procedures as described in the FSAR?
Conduct tests / experiments not described in the FSAR?
3.
u
- 4. Create a condition or conduct an operation which ex-ceeds, or could result in exceeding, the limits in Technical Specifications?
' If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
Safety Evaluation d - -- -
Date N'-ML - --
Group /Dep't. Head Review Ma fbA n
--- Date d'li-A -
Temporary Approva18 -- -- - -- Date - (NOS)
Temporary Approva1* - -- ~ ~ - Date -
/-/-3 .P3 - - - -
QC Revieu Y W Date -
PORC Reviek b b h N Date I - 3 9 - f l - ~ ~ Meeting No . f**C # ---
PlantManageh-NuclearApprhal- bbk'd- --'- Da te NL bV /
- Temporary approval must be fo11cwed by Plant Manager-Nuclear approval within 14 days.
v UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1)
l EP-2-140 Emergency Plan Implementing Procedure Reentry Revision 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 RES PONSIBILITIES P
4.0 INITIATING CONDITIONS 5.0 PROCEDURE 6.0 FINAL CONDITIONS 70 ATTACHMENTS
- LIST OF EFFECTIVE PAGES Title Revision 1 1-6 Revision 1 1
l Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 1.0 PURPOSE This procedurh provides both specific steps to be followed, and guidance to be considered, prior to and during the reentry of an evacuated area for the purposes of emergency repair to systems and equipment or investigative assessment of abnormal plant conditions.
NOTE The scope of this procedure does not include reentry into affected areas offsite. State and local agencies will coordinate any offsite recovery effort required following a Site or General Emer-gency in which evacuation was implemented as a protective action.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-030, Emergency Radiation Exposure Guidelines and Controls 2.3 EP-2-031, In-Plant Radiological Controls During Emergencies 2.4 EP-2-032, Monitoring and Decontamination 2.5 EP-2-033, Administration of Iodine Blocking Agents 2.6 EP-2-070, Protected Area Evacuation 2.7 EP-2-071, Site Evacuation 2.8 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation 2.9 EP-2-130, Emergency Team Assignments f
2.10 EP-2-170, Recovery 2
Emergency Plan implementing Procedure EP-2-140 Reentry Revision 1 3.0 RESPONSIBILITIES The Operational Support Center (OSC) Supervisor is responsible for implementing this procedure.
4.0 INITIATING CONDITIONS 4.1 This procedure is to be initiated upon any of the following conditions:
4.1.1 Conditions that require entry into an area classified as
" evacuated" according to EP-2-070, Protected Area Evacuation, or EP-2-071, Site Evacuation.
4.1.2 As directed by the Emergency Coordihator.
5.0 fROCEDURE 5.1 Assess the need for reentry and whether the benefits to be gained offset the potential hazards to the reentry personnel.
5.1.1 Utilize all available data including area and process monitor readings, survey data, and personnel observations to determine:
5.1.1.1 Which plant area (s) is (are) affected.
5.1.1.2 The conditions in the area, such as personnel hazards, temperature, toxic environment, and equipment condition.
5.1.1.3 Whether or not there are personnel in the area (s) who need assistance.
5.1.1.4 The time schedule, based on necessity, for reentry to commence.
5.1.2 Isolate and post areas determined to be unsafe or unnecessary to be reentered with appropriate warning signs and rope barriers (e.g., contaminated or high radiation areas).
3
Emergency Plan Implementing Procedure SP-2-140 Reentry Revision 1 5.2 Pre-plan reentry activities, including:
5.2.1 Protective clothing and survey equipment requirements.
5.2.2 Shielding and access control requirements.
5.2 3 Anticipated hazard protection and communications requirements.
5.3 Establish reentry teams from personnel available in the Operational Support Center, Control Room, or other assembly areas.
531 The OSC Supervisor should assign a team leader and communicator (as required).
5.3 2 The team members should be briefed on the plan of action and if radiological hazards are present, the Radiological Controls Coordinator shall conduct a briefing in accordance with EP-2-031, In-Plant Radiological Controls During Emergencies. Attachment 7.3 of EP-2-101 should be used to document the briefing.
5.3.3 The team members should complete an emergency exposure authoriza-tion form in accordance with EP-2-030, Emergency Radiation Ex-posure Guidelines and Controls, if high radiation levels are expected.
5.4 Ensure that personnel making the reentry are qualified for first aid, plant operations, health physics, and/or maintenance evaluations and corrective actions as necessary for the specific reentry evolution taking place.
5.5 For safety purposes, ensure that each reentry team is composed of at least two individuals.
4
Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 5.6 For radiologically affected areas, the guidelines of EP-2-031, In-Plant Radiological Controls During Emergencies, should be followed with specific emphasis on control of exposure, including:
5.6.1 Assigning an individual as a control point to time personnel entry and to maintain a record of all entries into the affected area using Attachment 7.3 of EP-2-101.
5.6.2 Ensuring that reentry personnel frequently check direct-reading dosimeters and withdraw to a safe area if assigned exposure limits are approached.
5.6.3 Directing reentry personnel to monitor radiation levels and take periodic air samples along the reentry route and subsequently post radiation and/or contaminated area signs.
5.6.4 Administering thyroid prophylaxis according to EP-2-033, Administration of Iodine Blocking Agents, if high levels of radioactive iodine are encountered.
5.7 For environmentally or structurally affected areas (i.e., steam leak, smoke, flooding, earthquake damage, toxic atmosphere, etc.),
ensure that appropriate measures are taken for personnel safety, including:
5 7.1 Reducing potential hazards to reentry personnel, if possible, by actions such as ventilation purge or the securing of systems.
5.7.2 Outfitting personnel with appropriate emergency equipment, such as self-contained breathing apparatus, steam suits, flashlights, tow lines, special tools and communications devices as required.
5.7.3 Testing the equipment for operability prior to reentry.
5.7 4 Directing reentry personnel to withdraw to a predetermined " Tre area" if severe unanticipated or unplanned conditions are encountered, pending further evaluation of the reentry effort.
l l
5 1
. e ,
Emergency Plan Implementing Procedure EP-2-140 Reentry Revision 1 5.8 Ensure that the OSC maintains a current status board on reentry team operations and that reentry personnel log out of the OSC prior to departing on assigned reentry activities.
5.9 Ensure that the reentry team leader maintains continuous com-munications with the OSC Supervisor, if possible, or otherwise at predetermined intervals to report progress of the reentry and observed conditions.
5.10 Coordinate the return of the reentry team to the control point.
5.10.1 Implement EP-2-032, Monitoring and Decontamination, if required.
5.10.2 Debrief team members at the OSC using Attachment 7.2 of '
EP-2-101. If radiological hazards were present, the Radiological Controls Coordinator should also. conduct a debriefing in ac-cordance with Attachment 7.3 of EP-2-101.
5.10.3 Report the results and findings of the reentry to the Emergency Coordinator.
5.11 Determine the need for additional reentries and, if required, for the initiation of recovery operations in accordance with EP-2-170, Recovery.
6.0 FINAL CONDITIONS 6.1 Reentry operations have been completed and all reentry team members have been accounted for.
6.2 Debriefing of reentry team members has been completed and documented.
70 ATTACHMENTS NONF I
6
i
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i l
- WATERFORD 3 SES PLANT OPERATING MANUAL p
I OUISIANA POWER & LIGHT S $t h EP-2-150 18 REVISICN 1 i q ; .3; aJ~ /
PCM VOLUME "" ' * - ' ' '
PCM SECTICH 4 APPROVAL DATE:
ETTECT M DATE: Fuel Load a//yf3 E2fERGENCY PLAN IMPLEMENTI m PRCCIDURE MERGENCY RECORDS' i.
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.vo._d3g PORC Meeting No. 13 -v 2 # .
Reviewed: kk %
P RC Chair =an i Approved: ht b Plant Manager-Nuclear m
u _. _ __ .
WATERFORD 3 SES PLANT OPERATING MANUAL CHANGE /RE7ISION/ DELETION REQUEST Procedure No. 8 h 2-sco Title lulMrev he #M -
Effective Date 4 ~t104A (if different from approval date) fd:.,pl e t e A. B. or C A. Change No. I B. Revision No. I ,
C .. Deletion
- N/4 RFAMON FOR CHANOE. MT/ISION. OR DFt_ETION A eM-1J d2lL $r . >. . mh/ duA,'.c /1f$ l $ b $ 4 w A s /
k 3 ed E Ne<Tiv e bT[
REOUTRED SIONATURFS. .
Originator / Y !s - Date I Technical Review dl*" Date N/4 SAFETY EVALUATION ,
Does this change, revision, or deletion: YES NO Change the facility as described in the FSAR7 /
- 2. Change the procedures as described in the FSAR7- /
Conduct tests / experiments not described in the FSAR7 '
3.
- 4. Create a condition or conduct an operation which ex- '
ceeds, or cculd result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Evaluation checklist.
Safety Evaluation 67 \MNd% Date Y~/1-Y3 Group /Dep't.HeadRevhw
- 4 OhNW Date b! l'8 D O
Temporary Approva18 Date (NOS)
Temporary Approval' Date QC Review 4 '4 'MM.- Date - - - '
PORC Review U fYt b N Date k-l Y -? 3 Meeting No. N ~cA PlantManageh-NuclearApproval UMk Date DDM1
- Temporary approval must be followed by Plant Manager-Nuclear approval ithin 14 days.
UNT-1-003 Revision 6' attachment 6.9 (1 of 1)
I4ATERFORD 3 SES em PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. -b/N -
Title -b/dNnV/- -1 1 r't ? f-------
Effective Date (if different from FM-N approval date)
Camniate 'A. B. or C A. Change .50. NN B. Revision No. /
C. Deletion n/>
RelSON: FOR CMANCE. REVTSTON. OR DetgTION Y/-f wyd lln % dl/b -'/a vbb b* db8h 4 r//M5pf ' * * - -~
dmhm 4&#k Maui, A%m w%du,. ----- - --
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recut 9ED SIGNATtIRes Originator k ' b 4v1N' - -
Date ' OW-- ---
Technical Review -- b a@ b@ >
-- Date ll-d O ' --
SAFETY EVALUATION YES NO fs Does this change, revision, or deletion: -
- 1. Change the f acility as described in the FSAR? 1.c_
v
- 2. Change the procedures as described in the FSAR? - "
- 3. Conduct tests / experiments not described in the FSAR?
'u 4 Create a condition or conduct an operation which ex-ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Saf ty Evaluation checklist.
Safety Evaluation b YI CA - -- -
Date I M '3 -- --
Group /Dep't. HeadRe$1ew Yb4 - - Date d 'I 9-0-- -
' i (NOS)
Temporary Approvala -- -- - -- Date -
Temporary Approval * --- Date -
QC Revteu - A ' W YNP - - ----*--
Date - '/~ / 3 -2: T - ~ ~ - ~
PORC Review M A b ~' Date i-li-IS --- Meeting No. fr-va 4 --
PlantManagerfNuclearApprhval SA MKEY--- Da te M N b - - -
- Temporary approval must be folicwed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 4 32 Attachment 6.9 (1 of -)
Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 1 TABLE OF CONTENTS 1.0 PURPOSE
2.0 REFERENCES
3.0 RESPONSIBILITIES 4.0 INITIATING CONDITIONS 5.0 PROCEDURE 5.1 Communications Logs 5.2 Emergency Response Facility Logs 5.3 Supporting Records 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS 71 Communications Log (1 page) 72 Facility Log Sheet (1 page)
LIST OF EFFECTIVE PAGES Title Revision 1 1-7 Revision 1 1
l Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 1.0 PURPOSE ,
This procedure outlines the logs / records to be maintained during an emergency and provides guidance on their final disposition.
2.0 REFERENCES
2.1 Waterford 3 SES Emergency Plan 2.2 UNT-4-006, Control of Plant Documents and Records 2.3 EP-2-100, Technical Support Center (TSC) Activation, Operation, and Deactivation 2.4 EP-2-101, Operational Support Center (OSC) Activation, Operation, and Deactivation 2.5 EP-2-102, Emergency Operations Facility (EOF) Activation, Operation, and Deactivation
~
3.0 RESPONSIBILITIES 3.1 The Emergency Coordinator and EOF Director are responsible for ensuring that the maintenance and updating of the facility logs and forms outlined in this procedure are carried out.
4.0 IRITIATING CONDITIONS 4.1 This procedure is to be initisted upon any of the following conditions:
i 4.1.1 At the direction of the Emergency Coordinator and/or EOF Director.
4.1.2 Declaration of any of the following emergency conditions:
l 4.1.2.1 Unusual Event
( 4.1.2.2 Alert I
4.1.2.3 Site Emergency l
2
Emergency Plan Implementing Procedure EF-2-150 Emergency Records Revision 1 4.1.2.4 General Emergency 5.0 PROCEDURE 5.1 COMMUNICATIONS LOGS 5.1.1 Log all information transmitted or received on the Communications Log sheets (Attachment 7.1) as indicated.
5.2 EMERGENCY RESPONSE FACILITY LOGS NOTE Each emergency response facility activated in response to an emergency must maintain an accounting of actions undertaken within the facility during its operation.
5.2.1 Initiate a log for the facility at the time of facility activation. The log shall consist of facility Log Sheets (see At-tachment 7.2).
5.2.2 Record information on Facility Log Sheets as it becomes available. Information shall include, as a minimum:
5.2.2.1 Time and date, shift, check block of facility, enter page numbers, person manning the position (Supervisor), Log Keeper (sign name).
5.2.2.2 Names of personnel assuming staff positions in the emergency response facility.
5.2.2.3 Plant status at the time of emergency declaration.
5.2.2.4 Major steps taken under the direction of the facility staff, including time and date these actions were initiated and the individual who directed the actions be taken.
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- Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 5.2.2.5 Important data received (e.g. , change in plant status, results of radiological surveys).
5.2.2.6 Summation of any formal meetings conducted in relation to the emergency.
5.2.2.7 Recommendations given to or received from non-LP&L personnel i providing support to the emergency facility.
5.2.2.8 Final emergency resolutions and summation of emergency facility actions in relation to the emergency facility's deac'ivation, including time and date of deactivation.
5.3 SUPPORTING RECORDS 5.3.1 Fcr documents that are ge.erated during the operation of the
! emergency facilities (e.g., Field Survey Results, Administration of Potassium Iodine Log), include the following information as a minimum:
i 5.3.1.1 Time, date and author.
5.3.1.2 Location in which document was generated (e.g., dose assessment area, technical assessment area).
, 6.0 FINAL CONDITIONS f 6.1 DISPOSITION OF LOGS AND RECORDS I
l 6.1.1 Collect all records and logs generated in the operation of the
emergency facility after each drill, exercise, or emergency l situation, etc.
6.1.2 Make copies of the collected records and forward the copies to the l
Emergency Planning Coordinator for review.
6.1.3 Handle all records and logs in accordance with UNT-4-006.
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Emergency Plan Implementing Procedure EP-2-150 Emergency Records Revision 1 i
7.0 ATTACHMENTS ,
71 Communications Log 72 Facility Log Sheet 9
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- =E Na, COMMUNICATIONS LOG TIME SENT TIME RECElvED CATE COMMUNICATION _.
CCCUf7 USED l MESSAGE FROM MESSAGE TO rEssace I
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AUTMCRIZED ST
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RECDVED BY CATE & TIME RECEVED
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...g TN!S COPY FCR COMMUNICATOR /ACT!CN EP-2-150 Revision 1 g nttachment 7.1 (1 of 1) g ,, , - _ - . --- --
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! FACILITY LOG SHEET ECC EOF 0 Page of DATE: '
TSC O supervisor:
TIE:
SHIFT: . OSC O tog Keeper:
Time Event Description I
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EP-2-150 Revision 1 7 Attachment 7.2 (1 cf 1-)
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WATERI:ORD 3 SES PLANT OPERATINh MANUAL ,
s g LOUISIANA -
POWER & LIGHT ,
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EP-3450 PCM VOLUME 18 REVISICN 1' g'l/'
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A? PROVAL DATE:
PCM SECTION 1 l EFFECTIVE DATE: r. . 1 7n,d 9 gjgg j i
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.DiERGENCY PLAN SUPPORTING PROCEDURE EliERGCICY COMMUNICATIONS GUIDELINES LP&L W-3 R! CORDS CON- RO:_ LED COPY l .w.430 PORC Meeting No. f3-DJo i Reviewed: k
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DRC Chair =an s Approved: *
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Plant Manager-l Nuclear
. . . WATERFORD 3 SES i
. FLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST
.rocedure Ns. 5f-3 '4!ra Title im u m!aey l'e mao u rwan Sa s sas sa.s Effective Date A</A MMA (if different from approval date) gemeleta 1. B. or C A. Change No. /
B. Revision No. / ,
f C. Deletion W I s
RFAMON FOR CHANOE. REVISION. OR DELETION Z) eMd e/tESeu & rhub MPC $r 8 kN A A '
!S M M EN oc.Tido D d-e #'
REOUT*tED STOMATURES.
Originator A - M Date Technical Review k/4 Date NM SAFETY EVALUATION ,,
Does this change, revision, or deletion: TES NO 1 Change the facility as described in the FSAR7 /
Change the procedures as described in the FSAR7- '
- 3. Conduct tests / experiments not described in the FSAR7 '
- 4. Create a condition or conduct an operation which ex- '
ceeds, or could result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safety Ev luation checklist.
Satety Evaluation bY GSlk Date 'I'll-%9 Group /Dep't. Head Review 6* 0 bb . Date N-MS
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Temporary Approvala Date (NOS)
Temporary Approval
- Date QC Review , # A -fh/ M - Date #-N **
PORC Reviab k b b b b -
Dat A /V-k3 Meeting No. fl ed PlantManageh-NuclearApprbval bau Date #!I7/83
' Temporary approval must be followed by Plant Manager-Nuclear approval within 14 days.
UNT-1-003 Revision 6' Attachment 6.9 (1 of 1)
- WATERFORD 3 SEE
/% PLANT OPERATING MANUAL CHANGE / REVISION / DELETION REQUEST Procedure No. ** 5~0N O ' '
Title < t//;'t? bmMitm>2S9 7 iUS rs.t (if diffe7ent from # PM-N approval date)
Effective Date Comnlete 1. B. o ra C A. Change No. NM .
B. Revision No. / f C. Deletion n/4 I, 4C MON' COR CHANCE. REVTSION. OR DELETION
' khfk ri3/ buib /b ill< l dim lb-bf "bbo !dhE!/b?! - - -~
dockr dws % min "AK r,w &nvL -V - -- -
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REQUIRED SIGNATURES Originator b b 4M 5th - -
Date I 'b N ' ---
Technical Review - S I ,-
N W -a - -
Da te - NO- '-
SAFETY EVALUATION f S oes D this change, revision, or deletion: YES NO
'1. Change tne facility as described in the FSAR?
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- 2. Change the procedures as described in the FSAR? h
~-
- 3. Conduct tests / experiments not described in the FSAR? I---
- 4. Create a condition or conduct an operation which ex- (- -
ceeds, or coulc result in exceeding, the limits in Technical Specifications?
If the answer to any of the above is yes, complete and at-tach a 10 CFR 50.59 Safe y Evaluation checklist.
Safety Evaluation kNI' ~ --
-~ Date 'b-8L - -
Cate'lI-lh T '
~
Group /Dep't. Head Re iew b' b" h . -- --
)
Temporary Approval * -- -- - -- Date -
- (NOS)
Temporary Approval * - - - Date * -'
QC Review - d d b h s - -- - -------
Date - & 'I"T79 ~~~-
PORC Review N b b d k Date ! ' l i -IA - - -' Me e tin g No . 13 "M f - -'
Plant Manager Nuclear Approkal - bb^M bdh- Date NAl-1D ----
' Temporary approval must be followed by Plant Manager-Nuclear approval 1
within 14 days. l 1
1 UNT-1-003 Revision 4 32 Attachment 6.9 (1 of 1) t
- Emergency Plan Supporting Procedure EP-3-060 Emergency Communications Guidelines Revision 1 TABLE OF CONTENTS 1.0 PURPOSE i
2.0 REFERENCES
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3.0 RESPONSIBILITIES i 4.0 INITIATING CONDITIONS
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5.0 PROCEDURE 5.1 Conduct of Communications 5.2 Operation of LP&L Emergency Phone Tree Network 6.0 FINAL CONDITIONS 7.0 ATTACHMENTS LIST OF EFFECTIVE PAGES Title Revision 1 1-4 Revision 1 4
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f Emergency Plan Supporting Procedure EP-3-060 Emergency Communications Guidelines Revision 1 1.0 PURPOSE To provide guidance on the proper techniques to be employed when conducting or transferring communications during an emergency. !
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2.0 REFERENCES
I, 2.1 Waterford 3 SES Emergency Plan 2.2 EP-2-010, Notifications and Communications 23 EP-2-150, Emergency Records 30 R ES PON SIBILITIES The Emergency Director, EOF Director and Emergency Coordinator are responsible for ensuring that the guidelines outlined in this procedure are employed at their respective emergency response facilities.
4.0 INITIATING CONDITIONS 4.1 This procedure is to be initiated upon activation of any of the following emergency response facilities:
4.1.1 Technical Support Center 4.1.2 Operational Support Center 4.1.3 Emergency Operations Facility 4.1.4 Corporate Command Center 5.0 PROCEDURE 5.1 CONDUCT OF COMMUNICATIONS 5.1.1 When calling another station or individual, always identify the station or individual you are calling followed by an identifica-tion of your station, e.g.:
" Operational Support Center, this is the Technical Support Center 2
O Emergency Plan Supporting Procedure EP-3-060 Emergency Communications Guidelines Revision 1 5.1.2 All communications related to the emergency response generated and received by.each of the emergency response facilities must be logged in accordance with EP-2-150, Emergency Records. [
t 5.1.3 All' messages being transmitted to non-LP&L agencies / organizations I from the emergency response facilities must be authorized by !
individual facility supervisors.
5.1.4 Upon receipt of information over any of the communications systems, or when giving direction / orders in a face-to-face dialogue, always repeat back the entire message to the sender.
'5.1.5 In sending information over any of the communications systems or when giving directions / orders in a face-to-face dialogue, keep the message short, concise and to the point.
5.1.6 Avoid the use of abbreviations when transmitting information, e.g.:
" Technical Support Center," not "TSC."
5.1 7 Always be alert for the use of terms which might be misunderstood "and avoid their use, e.g.:
" Increase / decrease" are easily misunderstood. Use " raise / lower."
5.1.8 To interrupt routine communications traffic to pass urgent information, interrupt the conversation with " Silence - Urgent Message." All parties on the line should stop their conversation and allow the information to be transmitted.
5.1.9 Always use accepted standard terminology in conducting com-munications, e.g.:
Not " Generator #2 is on-line" or " Diesel #2 is on-line"; instead use " Diesel Generator #2 is on-line."
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+ ' Emergency Plan Supporting Procedure EP-3-060 Emergency Communications Guidelines Revision 1 S.2 OPERATION OF LP&L EMERGENCY PHONE TREE NETWORK 5.2.1 Personnel responsible for no';ifying other LP&L individuals shall do so by using the LP&L Emergency Phone Tree Recall and Alerting (
System Booklet. f 6.0 FINAL CONDITIONS Use of this procedure is to be terminated when directed by Emergency Director, EOF Director, or Emergency Coordinator at their respective facilities.
70 ATTACHMENTS NONE 4
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