ML20236S785
| ML20236S785 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 06/26/1998 |
| From: | Cullen S AFFILIATION NOT ASSIGNED |
| To: | NRC OFFICE OF ADMINISTRATION (ADM) |
| Shared Package | |
| ML20236S767 | List: |
| References | |
| FOIA-98-260 NUDOCS 9807270224 | |
| Download: ML20236S785 (2) | |
Text
9 n .
i STANDING FOR TRUTH AnouT R ADI ATION MM 92-3L o m
,DutslWk 3 M*W I
June 26,1998 DE
' Certified Mail ^
Return-receipt reauested Freedom of information Act Officer U.S. Nuclear Regulatory Commission
' l Washington, D.C. 20555 '
-l Re: Freedom of Information Act Request !
l This is a request filed pursuant to the Freedom of Information Act.' ST R (Standing for Truth About Radiation) is a 501 (ch (3) not-for-profit that requestr !
any and all documents relating to and setting forth the following:
l
- 1) Any and all information pertaining to the 10 mile EPZ for the Millstone plant in Waterford Connecticut.' Specifically, STAR requests a copy of the EPZ plan for Millstone.
- 2) Any and all. information pertaining to the 50 mile ingestion pathway EPZ in place fo.r Millstone. Specifically, STAR' requests a copy of the 50 mile ingestion
, EPZ for Millstone.'
l STAR requests a waiver of all fees for this request. The STAR Foundation
, (Standing For Truth About Radiation) is a non-profit tax exempt organization (501 (c)(3)). STAR is a Long Island member organization established to g '$ promote safe and effective radioactive cleanup, containment, and management s . programs at all nuclear facilities.
S This request is in the public interest because it is extremely likely to contribute significantly to public understanding of the operations or activities of the '
o government and is not requested for any commercial purpose or intere'st. STAR bk ,
R og 5 U.S.C.$ 552. .
hau 10 CFR 9 50.47 (c) (2);
id.
66 NEWTOWN LANh SUITE 3 P.O. Box 4206 E AST H AMPTON, NY 11937 PHONE: 516-324-0655 fax: 516-324-2203 w w w. n o r a d ia t io n .o rg
a, ,
y members believe that the requested records will have great informative value and will contribute to our understanding of the NRC emergency planning for Millstone. Furthermore, the information sought will contribute to the understanding of the public at large and not one or a narrow segment of interested individuals.
Thank V. for your attention to this matter, if you have any question please do not hesitab to contact me.
Sincerely,
- k. '
Scott M. Cullen -
Counset l 1 1
d i
i I
Maat ikg. Ferry Ad %r 156) herf nd.UT orilas
- Mdl.ione Nerloer P,mv No..
m u.<>., rm ,,, c )
ro m,.in j Weserford, Cr Ot&5-0128 I (560) 441.t79l l Fan (860) 4414277-The Nrdwene Utahrw. Mr ices l Docket Nos. 50-245 l l 50-336 !
50423 j B17126
! Re: 10CFR50, Appendix E I l 10CFR50.47(b)(5) l -
10CFR50.54(q) i U.S. Nuclear Regulatory Commission i . Attention Document Control Desk M 24 E l l Washington, DC 20555 l Millstone Nuclear Power Station, Unit Nos.1,2, and 3 Emeroency Plan Revision 24 The purpose of this letter is to submit Change 1 to Revision 24 of the Millstone Nuclear Power Station Emergency Plan to 15.NRC Staff for review and approval in accordance j with 10CFR50.54(q).
This change provides updates it. F .rision 24 of the Emergency Plan as submitted to the NRC Staff for approval in a bter dated December 30, 1997.W A summary of changes from Revision 24 to Revision 24, Change 1, is contained in Attachment 1. A copy of the pages affected by Change 1 to Revision 24 ol the Millstone Station Emergency Plan is provided in Attachment 2.
l Northeast Nuclear Energy Company (NNECO) has reviewed this change in accordance with 10CFR50.54(q) and believes that the change does not decrease the effectiveness of the plan. The plan, as changed, continues to meet the standards of 10CFR50.47(b)
! and the requirements of Appendix E to 10CFR50.
l l
NRC inspectum Report 97-81,* which provided the results of the Emergency Planning and Exercise inspection conducted by the NRC Staff from August 20,1997 to m t. meter from David B. Arr.arine to U. S. Nuclear Regulatory Commission, "Misstone Nudoar Power Station, Unit Nos 1, 2, and 3, Emergency Plan Revision 24," dated !
December 30,1997
- Lemer from James T. Wiggins to 'i. S. Cams, " Emergency Preparedness inspecbon of the Mastone Station August 21,1997, NRC/ FEMA Graded Plume Exposure Exerdse,
_ and the Emergency Preparedness Program for Restart (50-245, -330, -423/97-81)."
- v v v i dated November 24,1997.
x9904020384-900324 7pp / * .
PDR. ADOCK OS000245 F FDR Vy
..u
U. S. Nucioar Regulatory Commission B171'!6/Page 2 August'29,19g7, and the subsequent Nouco of Violation dated December 30,1997,"
contained a violation concoming a decrease in effectiveness of Revision 22 of the Millstone Nuclear Power Stauon Emergency Plan. While NNECO believes that Revision 24 to the Millstone Nuclear Power Station Emergency Plan does not involve a decrease in plan effectiveness, it is being submitted for review and approval, along with Change 1 to Revision 24, in order to ensure that NNECO and the NRC Staff are in concurrence on the effectiveness of the plan.
In order to provide suf0cient training time for implementation of the revised plan, NNECO requests that Revision 24, including Change 1, to the Millstone Nuclear Power Station Emergency Plan become effective 60 days after NRC approval.
There are no regulatory commitments contained within this letter.
If you have any questions concerning this submittal, please contact Mr. Michael D.
Ehrodt at (860) 440-2142.
Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY yht&2 4d David B. Amerine Vice President, Human Services Attachments cc- H. J. Miller, Region 1 Administrator W. D. Travers, Ph.D., Director, Special Projects Office P. F. McKee, Deputy Director, Licensing and Oversight, Special Projects Office W. D. Lanning, Deputy Director, inspections, Special Projects Office i J. P. Durr, Branch Chief Inspections, Special Projects Office i J. T. Wiggins, Director, Division of Reactor Safety l M. C. Modes, Chief, Emergency Preparedness and Safeguards Branch j S. Dembok, NRC Project Manager, Millstone Unit 1 T. A. Eastick, Senior Resident inspector, Millstone Unit 1 D. G. Mcdonald, Jr., NRC Senior Project Manager, Millstone Unit 2 1 D. P. Beaulieu, Senior Resident inspector, Millstone Unit 2 l J. W. Andersen, NRC Project Manager, Millstone Unit 3
/ C. Corne, Senior Resident inspector, Millstone Unit 3
"' Letter from James T. Wiggins to B. D. Kenyon, ' Notice of Violation for NRC Emergency l Preparedness Program Inspection Report Nos. 50-245,336,423/97-81," dated December 30,1997.
)
__m__-_.- ._.____m -
i .
l Docket Nos. 50-245 50-336 50423 B17126 Attachment 1 Millstone Nuclect P:mer Station, Unit Nos.1,2, and 3 )
Summay of Station Emergency Plan Changes l
l March 1998 l o 25 F
U.S. Nuclear Reguletory Commission B17126/ Attachment 1/Page 1 Attachment 1 Summary of Station Emergency Plan Changes from Revision 24 to Revision 24, Change 1 The following table provides a listing of the plan changes by section and a description of each change.
Section l Description of Change Appendix D Procedure EPIP 4405 " Response to Personnel injuries' has been deleted from Appendix D ' Supporting Procedures List" and replaced by procedure C-OP 204 ' Response to Medical Emergencies". The station normally utilizes Common Operating Procedure C-OP 204 ' Response to Medical Emergencies", to address injury or illness to personnel onsite.
The transition to procedure EPIP 4405 was tested during an actual drill and resulted in confusion and delays in responding to the injured
=
personnel. A revision to C-OP 204 provides coordination of response during an activation of the station emergency plan.
Appendix J This change is being made in response to changes in the station normal organization. The change ensures that the Emergency Plan remains consistent with the Unit 1,2, and 3 Technical Specifications and the QA Topical Report.
Section 5, This change adds fcotnote (o) to the footnotes table and references to
, Table 5-1, footnote (o) to the Training Summary for the Shift Manager, the Station Pages 5-11, Duty Officer, the Unit Supervisor, Fire Brigade /EMT personnel, the Security Shift Su,misor, and Security personnel. This corrects an 15, and 16 omission which left the foutiv>te, and references to the footnote, off of {
Table 5-1.
Appendix 1, Millstone Unit 3 Emerg$ncy 1.; tion Level items PS2, PA2, PU2, EG1, l Figure 1-1, EU3, OG1, OS1, OA1, TA2, GA1, RCB4, and CNB4 have been !
l Pages I-8, 9, ctungad to accuratA reflect changes to EP!T 4400, " Event j and 10 A:d umnent, Classific dqc and Deportability".
I
- ~~ _ _ _ _
Docket No. 50-245 50-336 fiQd22 B17126 Attachment 2 Millstone Nudear Power Station, Unit Nos.1,2, and 3 Station Emergency Plan, Revision 24, Change 1 l
l l
l l
l l l
1 l
l March 1998
l SUPPORTING PROCggggg Emergency Plan Procedure Number Illit Section(s)
Emernency Plan imolementino Proc 6dortagflE)
EPIP 4400 Event Assessrnent, Classancet;cn and Deportability 62 EPIP Form 4400-1 Unit 1 EAL Table EPIP Form 4400-2 Unit 2 EAL Table EPIP Form 4400-3 Unit 3 EAL Tabe EPIP 4404 Notification and Communication 61 Emernency Plan Operatina Procedures (EPOP)
EPOP 4411 Director of Staten Emergency Operatons 52.1 NUC EPOP 4411 A Assistant Director Technical Support 522 NUC EPOP 4411 B Assistant Director, EOF 5 2.5 EPOP 4412 Evacuaton and Assembly 641 EPOP 4413 Potassium lodide Tablet Control and issce Agent 522, l
525 EPOP 4417 Manager of Centrol Room Operations (MCRO) 513 l
EPOP 4419 Manager of Operabonal Support Center (MOSC) 524 l EPOP 4422 Manager of Technical Support Center (MTSC) 523 l
NUC EPOP 4422A Thermal Hydraulic Evaluation Methods 5 2.3' EPOP 4424 Manager of Radiological Consequence 526 Assessment (MRCA)
EPOP 4425 Dosimetry issue and Personnel Rad'a' ion 64,65, Exposure Control During Nuclear Er.,ergencies Table 6-2 EPOP 4426 On-Site Emergency Radiological durveys 516 NUC EPOP 4428A Radiological Dose Assessment Team 526 NUC EPOP 4428D Meteorological Team 527,538 NUC EPOP 4428E Post-Accident Release Rates 52.7 l NUC EPOP 4428F Refined Dose Assessment 527 NUC EPOP 4428G Protective Action Recommendations 525 NUC EPOP 4428H Radenuclide Deposition and Dose Calculation 527 Millstone Emergency Plan Revision 24 D-2 December 1997 Change #1
SUPPOR g g ,p g Emergency Plan Procedure Number 1111g Sectionisi l NUC EPOP 44281 Directon of POSL Field Sampling 5 2.7 NUC EPOP 4428J Health Physes Network Communicat>ons 7 11 EPOP 4429 Radiaton Monitonng Team Deployment 5.2.7 and Control EPOP 4430 Off-Site Emergency Radclogical Surveys 5.2.7 EPOP 4432 On-Shift Dose Assessment 6.2.1 EPOP 4435 DrywelVContainment Curie Level Estimate 62 EPOP 4439 Unit 1 Core Damage Estimate 6.2 EPOP 4440 Unit 2 Core Damage Estimate 6.2 EPOP 4441 Unit 3 Core Damage Estimate 6.2 EPOP 4445 Unit 1 RX Coolant and Liquid Waste PASS 6.2.3 EPOP 4446 Unit 1 Stack and Drywe!! Air PASS 6.2.3 EPOP 4447 Unit 2 RX Ccolant and Liquid Waste PASS 6.2.3 EPOP 4448 Unit 2 Vent and Containment Air PASS 6 2.3 EPOP 4419 Unit 3 RX Coolant and Liquid Waste PASS 6.2.3 EPOP 4450 Unit 3 Vent and Containment Air PASS 6 2.3 NUC EPOP 4455 Manager of Public Information L34 NUC EPOP 4455A Nuclear News Manager 536 NUC EPOP 44558 Execuuve Spokesperson 535 t NUC EPOP 4455C Technical Assistant 537 t
NUC EPOP 4455D News Release 534,537 l
NUC EPOP 4455E News Conferences 536 NUC EPOP 4455F Rumor and inquiry Control 534 EPOP 4460 Manager of Communications (MOC) 528 NUC EPOP 4460A 1RG Representative 539 Millstone Emergency Plan Revision 24 D3 December 1997 Change #1
i SUPPORTING PROCEDUREg
]
Emergency Plan Procedure Number ' Ih[g Section(t)
Technicallnformation Coordinator (TIC) 5 3.15 EPOP 4465 Control Room Data Coordinator 53.1 EPOP 4470 EPOP 4475 Manager of Resources (MOR) 532 5.3 3 NUC EPOP 4475A External Resources Coorttinator 5.1.8, 5 3.16 EDOP 4480 Manager of Secunty (MOS)
Implementation of Recovery Operations 90 ,
NUC EPOP 4490 l
Eggmency Plan Administrative Procedures Management Program fo, Maintaning 80 EPAP 115 Emergency Preparedness Administrattye Control Procedures Fire Protection and Prevention Training implementing 81.3 NTM 7 205 Procedure Nuclear Trainina Procedures 8.1.1 NTM 7.212 Emergency Plan Training Program Implementing Procedure Radiation Protection A senes of procedures goveming the implementation Vanous RPM (various sections) of the radiation protec' ion and monitonng plan at Millstone Station.
Emernency Preparedness Department Procedures Emergency Planning Facility Manual 70 EPDP-06 Dntl and Exercise Manual 82 EPDP-07 Preparation and Controlof Emergency Program 8.3 EPDP 11 Changes l
Common Operatina Procedureg l
6.54,655 C-OP 204 Response to Medical Emergencies l' Millstone Emergency Plan Revision 24 D-4 Decemt>er 1997 Change #1 j
l
Millstone Station Normal OrEnnization PageIo(6 l
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Millstone Emergency Plan Revision 24 J7 December 1997 Change 81
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t W I 31998
, s@a' Qocket Nos. 60-245 50-336
.f.,r..! .m [50-423 B17254 jN Q'
$p' C p. i Re: 10CFR50, Appendix E l
3 ? 10CFR50.47(b)(5) [q[
- 10CFR50.54(q) gh,7
%p -
U.S. Nuclear Regulatory Commission E: Attention: Document Control Desk . g~;j' ', Washington, DC 20555
.e - ,t a.,
n .. Millstone Nuclear Power Station, Unit Nos.1,2, and 3 Chance 2 To Emerapn.py Plan Revision 24 h.TQ t Nuclear Energy Company (NNECO) 16,1998,m Northeas Station Emergency
- R.Uf in a letter dated April FR50.54(q).
$p lMr;f{i .t . submitted Change 2 to Revisionterial, 24notof th j
$. lan. The pages I
3 ~ ~; Material added to Revision 24 by Change h 2 caused /
..; affected by Change 2, to carry forward onto the next pa /
s' J containing the material which was moved forward as a jg' %2 submitted to the NRC Staff in the submittal the NRC staff has a complete, correctly paginated i f Revision ii of 24 of the April the Change 2 15,199 vers on gie - Emergency Plan, including Changesh1 and 2, NNEC Qq Plan sections in which material was carried forward. A
$cQi' are provided in Attachment 1.
ht x
'y i d ithin this letter.
. There are no regulatory commitments conta ne w Mr. Michael D.
If you have any questions concerning this submitta f[s Ehredt at (860) 440-2142..a v u* i 'Mi!! stone s Plan Revision ' t.etter from David B. Amerine to U. S.
- .m '
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f f.QWf" j J" U. 8. Nuclear Recutatory Commisalon [pg '" B17254/Page2 Very truly yours,
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P NORTHEAST NUCLEAR ENERGY COMPANY i'! , W.' lC s ..
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r, . _ Martin L. Bowling v/
* % Recovery Officer Technical Services M
SU. x h ~[l;- Attachments
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).tp - Pfe H. J. Miller, Region 1 Administrator cc:
wlN igh A' W. D. Travers, Ph.D., Director, Special Projects O W. D. Lanning, Deputy Director, inspections, Special Projects Of J. P. Durr, Branch Chief Inspections, Special Projects Office u./ J. T. Wiggins, Director, Division of Reactor Safety ec'. D. M. Barss, Emergency Preparedness and Safeguards Branch g S. Dembek, NRC Project Manager, Millstone Unit 1 4]'
%' T. A. Eastick, Senior Resident inspector, Mills 83: D. P. Beaulieu, Senior Resident inspector, Mittstone Unit 2 g&
f J. W. Andersen, NRC Project Manager, Mittstone Unit 3 A. C. Corne, Senior Resident inspector, Mi!! stone Unit 3 J.jg ' n:
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i.? 7 , ~ i Millstone Nuclear Power Station, Unit Nos.1,2, and 3 n q, Station Emergency Plan, Revision 24, Change 2 9,.1. . . i,.
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EMERGENCY PLAN
>f.Q MILLSTONE NUCLEAR POWER STATION ~w-pm.y W .
- .w TABLE OF CONTENTS
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-?a, vli f%.. f Ustof Appendices viii NI..N 4 Ust of Tables
' Ust of Figures ....... 1 1
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v 1. C oncept of Emergency O Zones................................ pe rations .............................
..............11 o( . - 1.1. Description of the Millstone Emergency Planning . .. ..... .. . 1 1 f_ 1.2. Interrelationships of State / Local / Licensee Emergency
. . .... . . . . . 1 2
. . . . . . . .. . . . 1 2 m3 Y- 1.3. Actions..................................................................
mt pT
^
1.4 As sist a nee . ... .. .. . . . . . . ... . .. ............13 . . . . . . . .. .
. . . . . . . . . .. . . 1 3 1.5. Public N notification .... ... ..........................21 ... . . . .. .. . .
M, - 1.6. Public inf ormation Program ............ ......... . ......... . ...... .. E.yd, , ,
- 2. Applicability and Supporting Plans ................................... ....................31
$.y, , . 3. o.' Sectlon Intentionally Blank (Reserved)................................. .................41 gg 4. Classification System . .. ........ ..........................
N7h .. . ....... 5-1 49' r ' 5. Eme rgency Res ponse O rg a nizat!on
' ................5-2....... .....
$. W. . . .. . . . . . . . 5-2
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6 5.1. On-Shift P ositions....... .. ... ........ ............ . . 5.1.1 Shitt M a n a g e r ... .. . . . .. . . ... .. .. .. . . . . . . .. . . .
, TI f.H3 ] .............53 i%.
?
0 5.1.2 Shift Technical Advisor ... ............ ....................... 5.1.3 Manager Of Control Room Operations ..................... . . . .. . . . . . . . . 5 3
%Wy% . ... . . .. .. . 5 3
. -mp.k h 5.1.4 Shift Technician ... . .. . ... . . ... ... . . . . ...
5.1. 5 On-Shift O pe rators . . ... . .. . .. . . .. . . .. . .. .. . . . .
. . . . . . . . . . . . 5-3
, gg.,i + 5.1.6 Health Physics Technicians....... . . ............ .......54 . ......... ..... . Q.m
@4, 5.1.7 Chemistry Technicians .... .............. ....... .......... .
..........5-4 f
sh 5.1.8 Security Shift Supervisor and Security Personnel. . . . . . . . . . . . . . 5-4
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Atj y,. 5.1.9 St ation Duty Office r .. . .. . . . . . . . . .. . . . . . . . . . l h.n: b -8 Mllstone Emergency Plan i w w Revision 24 I December 1997 I9%M
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X ,p.,.h y . - i }n *v.- t Q .. . . ... .... 5-4 sw , ' d' Ah d Nvs 5.1.10 Fire Brig ade i EMT ............... . . . . . . . .. .. . ....... .. . ...5-4 . ....... ... . .. (1 % 'g h ,[f *55.2.5.2.1 On-C att P ositions . . . . . .. . .. . .. .......... .. . 54 Director of Stallon Emergency Operations ...................... 55 Support..................................................................
- h. vM'., .^5.2.2 Assistant Director. Technical
, 5 5.2.3 Manager of Technical Support Center and 55 Acci 3
y . #. . g m, nter............................................................... 5.2.4 M anoger of Operational Support Ce 54 4, l Facility...............................................
- .; 5.2.5 Assistant Director Emergency Operations 56-f q. y s, .
5.2.6 Manager of Radiological Consequence Assessment.............. 56 p4} 5.2.7 Manager of Radiological Dose Assessment ................. 56
@d'3- 5.2.8 M anager of Communications . ............... ................... 56 h(
A 5.2.g Radiological M onitoring Te am ... ....... ...................... 57 N. . 5.2.10 EOF HP Techniel an . . . . . . .. . . ....... . 57 M 57 / d: q.y 5.2.1 1 EOF Shift Technici a n . .. ... . . ... ... . .. 5.2.12 OSC-Assistant Radiation Protection Supervisor 57 ...... W-t ' 5.2.13 M anager of Public information .. .............................. 57 t <i' 5.2.14 Executive S poke s pe rso n . . . . . . . . . . . .57... ... . . 5.2.15 Nucle ar News M an a ge r .. . . . . . . . . . .. . 57 . .. . . . .3 5.2.18 M an ag er of Re s ou rce s . .. . . . ....... . . 5-8 .. .. . .. , l a>- 5.3. Subject-to-C all P o sitio ns .. .. .. . .. . . . . . ... . ......58.. . .... lye 58
.m T. c; I 5.3.1 Control Room Data Coordinator ...........
50 5.3.2 External Resources Coordinator....58 58
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b, 5.3.3 Technical Assista nt. . . .. .. . . .. .. 58. .. .
@g 45.3.4 Mete orological Te a m .. .. . . ....................................
7
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sn .-. . 5.3.5 Technical Support Center- Shift Manager.......................... 58 p < ll'g3 5.3.6 C B ET S O pe r ator . .. ... . .. . . .. .. . . . . . 58 M.4.M. -' 5.3.7 Radiological Assessment Engineer . .. ........... .. 5-8 MD.. .. p /i s. ggh 4 5.3.8 Radiological Communicat ors . . . . . . ... .. . . ............. 58 q g'j
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3 9 Assistant Manager, Radiological Dose Assessme . . .. . . ..... 5 9
!e #.k.:e'.i. g 5-9 yej&n.gps @c.y. 5. .yE 5.3.10 Field Tea m Data Coordin
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&g% j 4, ga , .f rp,s .3.12 M anager of Se cu
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w, s.4. other OrpnkHons Prmeng Auktsnce .............. Mw* A.;N s.4.1 st.t. noe.i Aukt. nee ..... .... . . .. . . g+ i s s.4.2 Prtv ate Agency Assistance - e . .......... .......... .... ............................ &1 g' w.c. .
- s. em.rpney u...u rse ....... . ............
M; n 6.1, Notmcation and ActNdon of Emergency Owkdons........................... e 6.2. Auenment Actions .....................................................................................
,6:y% 63 gyy s
3 6.2.1 In&t Aueument ........................... . .. N .) 6.2.2 ProtectNe Action Recommendations ................................................. 6-6
# . 6.2.3 Dose As se s ement ..... .... ......... .... .. ............. ... .. . ..
W.( l 6.2.4 Rolease Rate and Dose Estimate Methodology 6-8 ......... he 6.2. 5 Secondary Dose Asse s sment................................ ... 6-8 ... y 6.3. CorrectNe Actions .. . .. ... .. ........ ..... .... .. ... ..69... . .. . . 97. c . i
- 6. 3.1 Fir e Fighting . . . . . . . . . .. . . . . . . . . . . . . . 6-9 . . . . .. . .
.,,.6-9
- e.
- 6.3.2 Damage Control. Repair and Decontamination ........
..6-9
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'.%1 6.4. ProtectNe Actions ..... ... .... . ... . . .. .6 12 try :
M- 1 6.4.1 On-site Protective Actions ...................... Supplies....................................................... 6-12
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6.4.2 On-site ProtectNe Equipment and g4, 6-12 l 6.4.3 Contamination Control Me asures ........ )
%an ' 6.4.4 Personnel Radiation Dose Determination .... ......... .. . . . .. . . . 6-13 I
T' * ........ 6 13
- 6. 6.5.1
- 5. Aid to Affect ed P ersonnel . .. .... ... .. .. . .
.f f
n Exposure Control Guidelines ..................... l ~.6-13.. . .....
,5, ,' .. 6.5.2 Emergency Exposure Control Guidelines.....for 6-14Off-S\
W i. ...... 6-14 1
- 6. 5.3 Decontamin ation ...... .... .. .... ... ..... ..
...... 6-14 l.
6.5.4FirstAid.................................................... l L_$<Q:
% E . 6.5.5 M edical Transportation ............................... .......... ....... 6 14
{ N@ N 6.5.6 M e dical Tre atme nt .. .. . ... ......~.7..1 .. ...
~ %e n 6.6. Pubtic inf ormation....... .............
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. . . . .. . . . . . . 7- 1 n
,k[ 7.1. C o ntr ol Ro o m . . .... . . .. . . ..................7-2 ..
gra.g 7.1.1. Normal Operations .... ...................... ...~. .~.. . . A 4.(N.,;, V 7.1.2. Alert and Notification ... ... ....................~ .. e . m Mittstone Emergency Plan '
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@ye. %@' l 7.1.3. Commun6 cations . . . .. . .. ... . .. ... . . . . . . . .... .. ... .. . . ... . . . .. . . .
._m 7.2. Emergerr" Operations Facmty..... ..... ..... ... ..................................... .................. .... ....
M, p. l M. w p. . 7.2.i.% tion............................................................................................... pg t 7. 2. 2. Location . .. .. . . . .. . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7.2.3. Structure and Habitabmty ........... ....... ................. .............................:.................. 7 3 8,9.3 .y / , c,. ., ,. 7.2.4 . L8y0Ut ............ .. . ......... ...... .. ... .. ...... . .... ... .... . ..... ..... . ... .. .. .. ..... . . . . . 4w
@.hhh; ga. k Communications ... .. .. ...... . . . .. . .. . . .. . . . .. . . . .... . ..... . .. .. . ........ . .. . .. . ... . . ..
7.2.5. g,ylW .hf 7.2.6. Power S upplles ........ .. ... ...... . ... . .... .. .. . .. .... . . .. ........ . .. ... . . . .... . . . .. . .. . . . 7.2.7. Technical Data and Data Systems ..................................................................... 7 3
. pg g 1 7-4
' 7.2.8. Records Availability and M anagement................................................................ } lysQ 7.3. Technical Support Center / Operational Support Center ................................................ j pg.l,- - W. ,, 7.3.1. F unction . . .. . . . . . . . . . . . . . . . . . . . . . . . .. . . . . .. . . . . . . . . . . u. 7.3.2. Location................................................................................................
'W- a 7.3.3. Structure and H abitabmty ......................................... . ........ ....... ..... .... ..... .. . ...
ix f( 7.3.4. Layout................................................................................................................ l h.n
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7.3. 5. Communications ... .. ... .. .. .. . . .. .. .. . . . ... . . . .. . . ... .. . . .. 5 7.3.6. P ower Supplie s ... .... ... . . . . .. . . . . . .. . . . .. . . ... . . ... ..... ... ..... . .. . . .. .... 7.3.7. Technical Data and Data Systems .................................................................. Q e 7.3.8. Records Av ailability . .. .... . .. . . . .. . . ... . . . .... . . . ... ........ .. .. . .... . ... . .... yy 7.4. Operational Support Center (OSC) and OSC Assembly Area ....................... M. ,h. 7.4.1. Function......................................................................................... t v?! .+ m. 7.4.2. t.ocation and S ize . . . . . . ... . . . .. . . . . . .. . . . . . . . . . . .. . . g%; 2%. 7.4.3. Structure and Habitability . ........ ...... ... ....... ...................... .... .... ..... .. .....
..y. 7.4.4. Communications . ..... ...... . . .. . . .. . . . . .... . . . . . .... . . .....
$. ~
7.4. 5. Em erge ncy Equipme nt ... ... . . . . . . . . .. . . . .. . .. . . . . ... ... . . . . . .... . ..
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qU._ SV p' e 7.5. Reserved..................................................................................... 94 7.6. Reserved.................................................................................... e 7.7. E merge ncy Equipment . .. .... . . . . . .. . . . . . ... .. . . .. .. . .. . .. .. . . .. .. . . l ,,. M 7.7.1. Emergency Response Data System ... ..... ................... ..... . ......... ... .
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% 7.8. Security Posts ........ .... .. .. ..... .. . . .. . . . . . . . . . . . . . .. . .. . . . . . . . .. ..
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$.A .,hR 7.9. J oint M edi a Ce nter . .. ... . . . .. ... .. . . . . . . .. . . . . .. . .
W& wm 7.10. Altemate 1.ocation .. ... .. ... ... .. ... . . . .. . . . . . . . . . . .
! 7.1 1. Communication S yste ms .. . . . . . . . . . . . .. . . . . . .. . .. .... . . . . . . .
%., 716
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=,}' 79 7.12. Assessment F acitales ... . ............. . .7 .9 . ... . .
.;f - WsQ o.. 7.13. First And and Medical F acilitie s79 ..........
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1 7.14. Damage Control Equipme nt81 .. . . . ~
.y - 8. Maintaining Emergency Preparedness ............................. 8-1 c Training...................................................................................
81
- q 8.1.
pd 8.1.1 SERO T r aining .. . . . . . . . . . . . .. . . . . . ... .8-3. . . . . . . . fn 6 8.1.2 Off-Site Emergency Response Training ........................ 83 M, 8.1.3 Additional Emergency Preparedness Training.............. 8-4 hi
% 8.2. Te sts, Drills, and Exe rcise s . . .. . . . . .. . . ... .. 8-4
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8.2.1 Testing of the Notification. Communication, and Alertin 8-5 T. ' ,
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8.2.2. Additional Tests. Drills, and Exercises..8-8 ............... I 1 m - - 8.3. Administration of Station Emergency Plan and..8-8 Procedu e%@sd.' [x ., 8.4. Public Inform ation Programs .................. . ................ 8-9 I y 8.G. Media I nforintion Program . . . . . . . .. ... .. ....... ....9-1. . .. . . . i 4~
.M- r, 9. Roc ov ery O ra ration s ......................... ............................ ....9-1 p ?
9.1 R econ ry P h as e . . . . . . . . . . . .. .. . . . . . . . .....9-1. ... .. . . p, .. 1t 91 9.2. Orgadzation for Recovery Operations ......................... g,el .j - 9.2 1 Director Recovery Operations ................................. 9-1 go t a 9.2.2 Manager of Technical Support.............. .................. .9-2 w
- l. J_ 9.2.3 M an age r of Plant Operations .. ................. .. 9 2 .. ... . ..
"if; N , ~}, .. 9.2.4 Manager of Radiation Control /Radwaste ................. 9-2 6#e 9.. as 9.2.5 M anager of Engineering Systems ....................9-3 ..........................
f,@.4 9.2.8 Advisory Support ...... . .... . . . . . ...... . .... . . . . ... . . ... ....... ...
. 9-3 1
N.. J'? 9.2.7 Manager of Pubtic information ..... ..... . ..... .. . . ..... . .. >
- a. 9.2.8 Regutatury Affairs and Compliance Department.. ......... . . .
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)qpi p e .. . APPENDlX A. DEFINITIONS, ABBREVIATIONS AND ACRONYMS ...................
h APPEN DlX B LETTE RS OF AGREEM ENT.................... ................................... L L w.. gg APPENDIX C -MAPS OF PLUME AND INGESTION EXPOSURE EPZ, LOCATIONS OF ON-SITE AND OFF SITE RADIOLOGICAL
' 83UhN.
,. 3, , 4..
MONITORING STATIONS, STATION EVACUATION ROUTES....................C-1 a&p,v - g
; . g. -
D1 LIST.............................................................
- hjffd{@ 'APPENDlX D - SUPPORTING PROCEDURES
,p . - .
m%up'[a APPENDIX E - MILLSTONE EMERGENCY
, EQUIPME
.............F 1
$'i APPENDIX F - DIAGRAMS OF EMERGENCY FACILITIES.....................................
ifE! -
@1RE. 1 ' ' APPENDIX G - CROSS REFERENCE TO NU
'M APPENDIX F 3 RADIOLOGICAL ASSESSMENT EQUlPMENT AND FACILIT 3 'i APPENDIX i - EMERG ENCY ACTION LEVEL SCHEME
.........................................................l-1
. p
. i CHARTS..............................................J-1 y:[ APPENDIX J - NORMAL STATION ORGANIZATION I
4 .o MG. APPENDlX K - EVACUATION TIME ESTIMATE: PLUME EXPOSURE P I
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?$MM APPENDIX L -INTENTIONALLY BLANK-RESERVED..................
Tf-$ & .....................M 1
$M, APPENDIX M. SERO PERSONNEL TRAINING
SUMMARY
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%,1 1 RE SERVED . ...... .. . ..
3 gyq;i-2 OFF-SITE HOST COMMUNITY AND R
...................22
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S @M,ks, .0 2-1 SUPPORTING PLANS AND q , 43 M [, y $c{:.s4-2 C a- ,a ALERT LIC EN SEE ACTIO N S .. . ......... 45 j r 5(4-3 SITE AREA EMERGENCY LICE
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5 -11 {ffff. ~ 5-1 STATION EMERGENCY RESPONSE ORGANI 6 18
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6-1 RESERVED........................................................
$r G':
gM.'.h AB
+ s-6 2 EMERGENCY EXPOSURE L H2
, ' 7-1 LOCATIONS OF EMERGENCY RH-1 HON-S 16 2'O . K3
$.n-H-2 OFF-SITE ASSESSMENT EQUIPMENT ...
1' n K-1 MILLSTONE EVACUATION TIME ESTIM by.:. - 9.c. a. M
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- L kt-m p;%o M O;w.111 EMERGENCY RESPONSE ORGANIZATIONS RESPONSIBILITIES..............................16 .
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.g.Y:-M 1-2 RESPONSIBILITIES OF STATE AND LOCAL AGENCIES FOR THE VARIOUS INCID h g CLASSI FICATI ON S .. . .. .. ... . .... . ..... .... ... .... .. . . . . .. . ... . . .. . . .. . .. .. .. . . .. . . . . . . . .....
.........................18 .,
. g4[.gg 1-3 LICENSEE EMERGENCY RESPONSE FACILITY RESPONSIBILITIES '
- F>
%p,%s.5 . . ~ y . P6-1 E R ORGANIZATION S ON N EL ... . . . . . . .... . . AND.. . . . . . LOCATION
. . . . .. . . . . . .. . . . OF . . . . .STAT 457-in NOTIFICATION OF EMERGENCY RESPONSE ORGANIZATIONS............................ 7-12 M.c 7 13
.....s......................................................
.$ @VM m 7-1b NRC EMERGENCY NOTIFICATION SYSTEM fif M 7-ic LINES OF COMMUNICATIONS BETWEEN EMERGENCY RESPONSE CENTERS
, N.b.$ MILLSTON E STATIO N .................... .... .... ... . . ... .... .. . . . . . . .... . . ... .. . .... ... .. .. .. . . .. . . . .. ..... .... .. .
Mbi ORGANIZATION FOR RECOVERY OPERATIONS......................................................... 94 . pw;.: . iW.4 C-1 MAP OF MILLSTONE EMERGENCY PLANNING ZONE, HOST COMMUNITIES AND EVAC UATI O N ROUTE S . .. . ... ..... .. ... .. .. ..... ...... ... . . ..... ..... . . .... . . . .. .. . . . . . . . . . . . . .. . . . . . ...
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".W, C-2 LOCATIONS OF ON-SITE AND OFF-SITE RADIOLOGICAL tw
- r. u A d MON ITORI N G STATI O N S ... ... .. . ... . . ......... .. ......... .... ... . .. . .. .. .... .. . .. . . .. .. . . . . .. .. . . . . ...
T2 ' C-3 MAP OF MILLSTONE 10 MILE EMERGENCY PLANNING ZONE ..................................C-4
- V
& C-4 MAP OF MILLSTONE 50 MILE EMERGENCY PLANNING ZONE ..................................C-5 A ROUTES..............................................C-6 -
Ms i C-5 MAP OF MILLSTONE STATION EVACUATION p n ,. , cM<:m"4 E-1 MILLSTONE EMERGENCY EQUIPMENT
+
SUMMARY
...............................F 2 4 F-1 DIAG RAM OF TSC / LAYOUT..........................................
~
h.cMOf f. . , OSC ,.
' ...........F-3
.mxw.$ F-2 DIAGRAM OF EMERGENCY OPERATIONS FACILITY.......................
............F-4
$8p' F-3 DIAGRAM OF OSC ASSEMBLY AREA LAYOUT ........... ....................... .. .........
l ' "g%W h. 1........................ . . . ........ ........... ........K6 - l ..< 9,% ,'A,}g$ . K-2 MILLSTONE *K-1EMERGENCY MILLSTONE EMERGENCY PLANNING ZONE 2..................
..... ......................... ........ K 7
. ........... ... ... ...... ........ K-8 PMNNIN M ' K-3 MILLSTONE EMERGENCY PLANNING ZONE 3.....................
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vW Mittstone Emergency Plan
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Revision 24 April 1998
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- y. }N '8, Emergency Response Organizatim y+
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This section describes the Station Emergency Response O F ' p '.( , SERO (Figure 5-1) replaces and prevails over the normal s normal station organization is outlined in Appendix J. ((4A ( Personnel are assigned to the SEROT by the yChief Nuc Ih job qualifications and other specialized training. Person i ing hMs 3pi% ,. plan training based on their specific emergency func
% .. Department ma n a n QW .it required training for each SERO function. m 7%,Y ii ' yM The SERO consists of on-shift staff, on-call staff, and subjec
- y. SERO staffing required to activate the ERFsithdconsists of the y 'W[- positions identified in Table 5-1. The specified ili dposit'ons toThe SERO are NUREG-0654, Planning Standard B, Table itions B-1.
j,;;cp ' ' subject-to-call staff are additional personnel beyond will be tion of the req Mt . - enhance the emergency response. The subject-to-call d l staff emerg U manned within 8 hours of SERO activation. The SERO hift ti as EMERGE is activ N@Ui an ALERT, SITE AREA EMERGENCY or GENERAL hp". SERO personnel are then supplemented by ffon-call y be and su indicated on Table S-1. Additional personnel resources, out N
!@g ' # activated, as needed.
f, ' sg The SERO is described in Table 5-1 and Figure j t sks, functional i e on-shift, 5-1. Table W Q[, '. . ~ l relationship between emergency t lies toand norma p: a hift staff may be on-call, or subject to-call staff. The normal on-shift staff comple N operating modes. During shu'.down i and refueling modes the on-
. reduced to the minimum sh% staff composition def nea e i[d' .' ' section of the unit tecindeal specifications.
i e listed in
!(( Procedures detailing responsibilities for the various SERO sta
[h j Appendix 0, as applicable. dhN b h 3
$#4b.r Also included in this section are brief descriptions of ths s T organizations that would provide assistance upon request.
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Appendix B contains copies of letters of hich agreement includes:
fro
- y. The on-shiMon-site positions are part of the normal statio
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? L..a 1
. Shift Manager l
2 y.., . e ShiftTechnical Advisor / .,
" e Shift Technician v &@r.
- Mdistone Emergency Plan Revision 24 f December 1997 3 51 Mj.: *
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i i% y. . g&nM./;?3o9 >8 Q N:'.Y<a,.. r- Y'. 4 h: yy uW;pdfff' N: eJ . Unit Supervisor
'5%.?ifi Control Operators MMJ r e -
gy 3,;3
- Plant Equipment Operators ff?
3.h;,Q GVp ~ , o Health Physics Technicians s e,w : _ '
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*; .' ChemistryTechnic!an
'hfhkME o Security Shift Supervisor and Security Personnel 1.Y 4 .
L t,g?g&gl'llC.^.c "o Station Duty Officer
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%C h; W Fire Drigade / EMT wh&Ggn.? m ..e- '
khk' & The on-call management positions include the following: b Director of Station Emergency Operations
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- Assistant Director, Emergency Operations Facility
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Assistant Director, Technical Support (Unit 1, 2, 3) R. *
- Manager of Technical Support Center (Unit 1,2,3)
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*' Manager of Radiological Consequence Assessment M;'I. .; ,
# t @$ f n* Manager of Radiological Dose Assessment iM+: . ,
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- Manager of Communications (Unit 1,2,3) +
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* ' Manager of Operational Support Center (Unit 1,2,3) 7:.{' l y.]
7 ' These positions are described below:
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' 5.1. ^ c" ' .i
. On-Shift Positions
- r. . .. .
S.1.1. Shift Manager (SM) m%w'.,;7 t
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The Shift Manager initia!!y assumes command of the SERO as the i l, ~ % M; 7 .. Control Room DSEO (CRDSEO) following Unusual Event or higher . I i;
' ' gf,;; O Cs);,.i;[$2' classification. In this position, the Shift Manager has the a l ;'
,.';;Q,{WC' responsibilities of the DSEO. Due to the numerous responsibilities k ' y
,Nf'. . J ' q ;. assigned the Shift Manager at the onset of an emergency, actions shall be prioritized as follows: (1) ensure safe operation of the plant, (2) f nsure y 'y y D' e
immediate notification requirements are met, (3) obtain operational and f it ' ' radiological assessment of the emergency, and (4) perform additional W .g(:d;; y. , emergency actions as directed by procedures as time and conditions
," 'Q.,. . . Mittstone Emergency Plan u ...: .
T JT76 &p @$ ^ Revision 24 Apol 1998 5-2 F 2 b^(d Change #2 d; *Gg, ,;,, Y, .
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. permit. The Unit Supervisor shall assume the responsibilities of the SM I
6 .. should the SM become incapacitated or otherwise unable to fuffill the
' V[iCC , ,/ ' ~ ' ._' ,the responsibilities of CRDSEO. If this is required, some.Jdelay in prioritized actions is expected. However, assistance is systfable from ig.D the Station Duty Officer and the unit STA. After being refleved by another j, l
. @ 0'c s., q. c quellfled DSEO, the Shift Manager becomes the Manager of Control "y ;
Room Operations (MCRO). The following CRDSEO responsibilities can [ 3 gg. %;;w . j , pnot be delegated: h/$ ;. .y , o Event classification. . e initiation of station emergency response. ,
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- Authorization of mitigation and repair activities. 1 j " P %
Command and control of station emergency response. yy gy'(cj f/ . . e e Approval of off site Protec/ve Act;on Recommendations.
, 7.(11[p.)]h ,
Approval of on-site evacuation. 44 "y
- Authorization of emergency exposures. ;
i gh: 7 ' e Authorization of off-site notifications. l Q h,if.- e
. ~ . .
c 5.1.2. ShiftTechnical Advisor (STA) j ( .> g , . The STA is responsible for the analysis of operational data. ' 5.1.3, Manager Of Control Room Operations (MCRO)
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The Manager of Control Room Operations responsibilities include control i
"W ' room operations, interface with ADTS conceming plant status and
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,q G changing conditions, classification changes and corrective actions and i *4 . interface with the MOSC to coordinate activities, as necessary.
~[F A 5.1.4. Shift Technician (ST)
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' ?(p: . The Shift Technician is responsible for conducting emergency notifications.
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- p. 5.1.5. On-shift Operators
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The on-shift Unit Supervisor (US), Control Operators (CO) and Plant l ^ - Equipment Operators (PEO) perform plant related functions in l J., accordance with unit and Station procedures, and as directed by the SM/MCRO The PEOs provide basic on-shift mechanical and electrical d..:, maintenance functions,in addition to radwaste operations. l [
.n M"'- 5.1.6. Health Physics Technicians (HP) '
$.E " The Health Physics Technicians provide initialin-plant and on-site
- S/ Q')#/
' radiological support actions as RMT #1.
- c. Mittstone Emergency Plan h.hfl ., Reision 24 6;; If 53 hmW W r,M.hh-[.y
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MMW i; av'.w ,, s h,y n..~n ., . .A 4f ?,1 I 4 W] 2,**' 5.1.7. Chemistry Technician E,m, 4 w.w ' The Chemistry Technician (affected unit) provides on-shift dose assessment, chemistry support and are avaltable to assist contro
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.h,hd Ejd~N, p ' ' la .ih!s personnetin other actions as directed. .
? p, 5.1.8. Security Shift Supervisor and Security Personnel Qx The Security Shift Suporvisor performs security related functions
}. > ". .v. .y ;' ~ ', accordance with unit and Station procedures, and as directed by th
.' M, 9 9 l ,
SM/MCRO. The Security Shift Supervisor is assisted by security g personnelin providing site access control and accountability, 1g& ,- 4 l k: 2. , 5.1.9. Station Duty Officer (SDO) D E. 9 ,s. m j. .] The Station Duty Officer or avaltable SRO notifies the NRC, as t , N . . '- ]., communications and evacuation or assembly of station personnel Q - f* ty, 5.1.10. Fire Brigade / EMT 4 3.a m-",.-, Li l A ,Y,c,9? , J
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The Fire Brigade provides immediate response to a fire on-site! YM EM , . M:- qualified personnel assigned to the Fire Brigade provide emerg
.j Sh g ,'$p:'f 1R - modical services for on-site personnelinjuries.
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4, *wl', - h.pjji % p 5.2. On-Call Positions
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5.2.1. Director of Station Emergency Operations (DSEO) 7 h ~,7 i..
- The EOF DSEO assumes overall command and con SERO and the licensee emergency response, after relieving the y# ~ ,
CRDSEO. The DSEO is responsible for notification and rele l jy.%;pg .r; ,,' '~ information to off site authorities and the public, recommending S. , -
' protective actions to the State of Connecticut and ap f appointed to fill SERO vacancies durin N[i A #D M[5' f y
u,- N r .r.* [db., J ' llhf effectively respond to the specific eme 9 be delegated: b y:. 3?:.> sgj.: ,
$$. : ., - Command and control of station emergency response, in
,.4,y.i'A.. coordination of response by off-site agencies.
w6(,A Approval of off site Protective Action Recommendations.
' 5N e e
Ordering station assembly, evacuation, or sheltering. Y. Authorization of emergency exposures.
. N-.. .
Mittstone Emergency Plan p . y A .% *,..' '^ Revision 24 December 1997 I( ' ;, '
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. Authon/atioit at of t site tu.tifu atnins l et httu al !>uppijrt (A[)[li)
S// Assistant I hn et hrs Ihe Al)l'.i is resporiseti te for providing the A()l3 reports to the ()St O l sessment comtisand and contro; of the SLHO technical. op and sepair staff T he A()I S poma<y tesponsib.hties includn a e Classification of the event e Ensuring actions are tat.en to mitigate degradation of systems d nt Approving accident management strategies and en management plan is implemented PPADs) Approval of on-site personal protective EDE actions for deos t Approving emergency exposure upg personnel Approval for the issue of Potassium lodide f the(Kl) to em personnel assigned to the ADTS. at the recommen MRCA 5, Manager of Technical Support Center (MTSC) and Ac Management Team (AMT) The MTSC analyzes operating data and The MTSC reports to the ADTS MOSC The provides techoscat support to the ADTS, TSC and provides and MCRO, 6 affected and unaffected unit TSC staff reports to the M mechanical accident assessment functions The MTSC is assisted b l Hydraubc 4 engineer electncal engineer and a Generation Test Acadent Management Team (AMT 524 Manages of Operational Support Center (MOSC) The MOSC assembles boefs, equips The MOSC reports to the ADTS Repair and Operational deploys and coordinates Emergency Assessment. i Search / Rescue PersonnelTeams assigned ' The to assist MOSC ass in perf Support Cente r functions report to the MOSC cali staff call OSC assistants maintenance speaaksts and othe 19%'
- 1314 mb dated Jo', - h #I.4
Millsh)fie' k f f et*I(jef H y NRC inspection Report '20 2138.f? uh .ina tw Resv>nse N t'v 'stt 8f l .' *
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T ' l l l 525 Assistant Director, Emerc 'ncy Operations Facility (ADEOF) 1 f The ADEOF reports to the DSEO in the EOF. The ADEOF is responsible l for providing command and control of the event radiological assessment and radiological support activities. The MRDA, MRCA, MOC and MPI report to the ADEOF. The ADEOF is also responsible for:
. Approval for the issuance of Potassium lodide (KI) to emergency personnel assigned to the ADEOF, at the recommendation of the MRCA.
. On-site radiation protection.
. Off site radiological dose assessment.
. Personnel providing logistics support for external response agencies.
. Managing the collection and communication of event data and news releases.
. Assumes responsibilities of DSEO,in the event the DSEO becomes incapacitated er otherwise unable to perform the assigned duties.
5.2.6. Manager of Radiological Consequence Assessment (MRCA) The MRCA reports to the ADEOF. The MRCA coordinates health physics activities including on-site radiological assessment, personnel exposure control and radiation piotection programs. Personnel assigned to assist in on stte radiological assessment functions report to the MRCA. 5.2.7. Manager of Radiological Dose Assessment (MRDA) The MRDA reports to the ADEOF. The MRDA coordinates off-site radiological monitoring and dose assessment. The personnel assigned to assist in performing these functions are the Assistant Managers of Radiological Dose Assessment (AMRDAs), Radiological Assessment Engineer (RAE), Field Team Data Coordina',or (FTDC), and the Meteorological Team raembers (MET). 5.2.8. Manager of Communications (MOC) The MOC reports to the ADEOF. The MOC provides information conceming the operation and status of the plant and radiological conditions to the NRC Headquarters Emergency Operations Center, Bethesda, MD and the NRC Region 1 Emergency Response Center as requested. ( 5.2.9. Radiological Monitoring Team (RMT #2) j HP Technicians serve as RMT # 2 and provide radiological surveys. HP ) coverage and dosimetry issue for emergency teams, search and rescue and fire-fighting activities The RMT reports to the MRCA Millstone Emergency Plan Revision 24 5-6 December 1997
+ __
l 1 5 2.10. EOF HP Technician P i The EOF HP Technicien prov6 des HP . Technician reports to the MRCA. 5 211. EOF Shift Technician The EOF Shift Technician performs notifications of license I state and local officials. { S.2.12.OSC-Assistant Radiation Protection Supervisor (OSC The OSC-ARPS reports to the MOSC and the MRCA. Th provides radiological controls within the TSC/OSC/OSC The ARPS also provides radiological support for emergency dispatched by the OSC. S.2.13. Manager of Public Information (MPI) The MPI reports to the ADEOF. The MPl gathers eme il information and transmits it to the Nuc for rumor control activities at the site. S.2.14. Executive Spokesperson (ES) t The ES reports to the DSEO and acts as the company s the State EOC and Joint Media Center, providing t ws f ace-to-f communications with state officials and representing the conferences. The ES may also provide background infor conceming licensee PARS provided to the State DEP. S.2.15. Nuclear News Manager (NNM) The NNM reports to the ES and supervises fanall public inf bl activities. The position of NNM is activa information reteases. 5.2.16. Manager of Resources (MOR) The MOR reports to the DSEO. The MOR f d fills SE provides 24 hour / day planning for manpower, tran quarters, equipment and supplies at the site. I Millstone Emergency Plan Revision 24 Apal1998 3./ Change #2
53 Su)1ettdpf3Rqshpnj 5 31. Control Room Data Coordinator (CRDC) dt The CRDC assists the MOC and TIC in obtaining pla S32 Extemal Resources Coordinator (ERC) l g The ERC reports to the MOR. The ERC assists the M for personnel, equipment and supplies at the site. 5.3.3. Technical Assistant (TA) tion The TA reports to the ES and provides the ES with t as required. 5.3.4. Meteorological Tearr i The Meteorological Team provides meteorological rt dose d calculations and long term meteorologicalinformation, to assessment activities. S.3.5. Technical Support Center- Shift Manager (TSC-SM The SRO assigned to the Technical Support l pertise in Cente communications with the control room and provides t accident assessment activities. 5.3 6. CBETS Operator i The CBETS Operator provides computer based e 1 information. 5.3.7. Radiological Assessment Engineer (RAE)f ance of i The RAE assists the radiological assessment team dose calculations. l 5.3.8. Radiological Communicators (two positions)site The Radiological Communicators provide commu l radiological activities. MRDA) {two Assistant Manager, Radiological Dose Assessment 5.3 9 positions} l onitonng The AMRDAs assist the MRDA in performance o and dose assessment. Matstone Emergency Plan Revision 24 December 1997 58 '~ _
r l l 5 310 Feld Team Data Coordinator (FTDC) The FTDC provides communications and information from The FTDC also boefs and deploys field monitonng teams. it w E O F 5 311. TechnicalInformation Coordinator (TIC) The TIC reports to the MOC and is responsibio for collect information and key plant parameter dat EOF, TSC and the State EOC. 5.312. Manager of Secunty (MOS) The Manager of Secunty reports to the DSEO and is resp maintaining site secunty. 5.4. _ther O Oro1nizations Providina Assistance 5.4.1, State / Local Assistance During , mergency, assistance from state or local agencies m d local required. The State RERP defines responsibilities L tt s of of the agencies. Detatis of prnv;ded assistance are contained These Agreement (Appendix 8) with the agen assistance and to verify appropriate communications cha 5 4.2. Pnvate Agency Assistance id nt Assistance of private agencies may also be required du ) Details of the type of services expectedt are containe affirm agreement. The letters are updated annually or as ne agreed-upon assistance and to venfy appropriate c channels. Appendix B contains a hsting of operational letter agreement. 5.4.3. Federal Assistance Request for o. -site federal assistan Y j te mnse times The licensee does not anticipate need for additiona / responding to an accident C at the The licensee maintains work centers fo l Station EOF %)tstone Emergenc.y liian Revson 24 April 1'f>8 S9 Change #2
TSC Dedicated federal telephone communications and access licensee communicator s equipment are provided in this area J I i l Mittstone Emergency Plan Revision 24 December 1997 5-10
ir w l
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STATION EMERGENCY RE On-Emergency Location Shrft Emergency Positon/Tette ,_ Normat Positiorvirtle Maroe f asks 1dj Mager Functional Affected Unet Control Area Manager of Cent of SNf1 Menepet (SM) Room Respons&e for safe Room Operations UnA Operations and - 1/ site operaten of the unet essess of anduding the Station Outy Offcer operatonal aspects. Station Outy Offecer
- i nd) implementation of assessment of od- vmai & emergency SNft Techncal Advisor normal opera +,onal SNft Technical Advisor operating procedures aspecs (STA)
- idj Unet Supervisor (US). US
- 2dj Control Oper stu (CO). CO
- 2dj Plant Equipment PEO Operator (PEO) fd Affeced Unit Control Director of Station Room Operat>on Managers. Emergency Operatons 1 _ Assume command and SNft Managers Ernergency control of Station EOF Orection and Emergency Operstior.6
. Controi . Support of Dstecors Irwtist>an of information
' Operatonal to hcensee, federa..
Acadent state and local Assessment State EOC/ Joint Media authontees NU Esecutsve Center harson VP Nudear Spokesperson NU Recovery Officer f Communications to the State EOC
! Nucsear Direcor 1 Coordinates station emergency response adons with that of the State EOC/Joent Media State Technical Assestant Center Nuclear Licenseng Provides information to Engineers / Training Staff the NU Esecutrve State EOCIJoint Mede Spokesperson Nuclear News Manager Manager. Nudear Center Supervise public Pubine information informaton. Nudear s,formatson actrvrtees n informaton Staff
%seminate informatior recetved from Manage o
of Put*c informaton t nt { appropnate govemme ) officaals media. and l
, generat pubiac __
l l Mmstone Emer gency Plan Revision 24 Apol 1998 5-11 Change #2 _,,n-,vy- N
- - em -.
e i NSE ORGANIZATION Red H esp Preferred
- Ts eerwng Stamng ' W to- Surnmery Worker Quet Quahticeteons Coe Staff *
(Rekt to ( A(.f+.4s M) l YES Shm Manager 1,4*' 6.9.14 YES f YES YES SRO 1.4 i YES STA ! 1,4 YES YES YES SRO 1, 4"', 6. 9.14 YES YES CO 1 YES YES PEO 1 Sensor Nudeer 1,4.6,9,14 Management i l sae I 1 1,9,14 Senior Nudeer Management ANSTFn
.c CA?.a i
E tb 1,2.9 Nuc6 ear Technecal Staff Nudear Statl anwa wgU
- 1. 4. g th
TO ST ATION EMERGENCY r i 1 On j Emergency Position / Title i meegency I ocat'W' Shrft Maror T ask s Normal Position / Title Mayor Functonal Area EOF Detector, Manager Assistant Director Reeceogsuit Assume command and Emergency Operations control chadioeogecal Chahrwis and F acility Event assessment and Commurwcations management of the ewmt Ensures oft one radoeogical assessments are prov*ded to the State DEP Recommends PARS to the DSEO Assump command and control of mtemet and extemet Commuriscatuorts EOF EOF Provide HP controls for HP Tech Decontammation HP Tech the EOF. supervise cnd Ra$ation D, con Facirty Co &d Shift Technsoan Unit Control Room / EOF ic Notify hcensee, federal. Sfuft Techncarv SRO/ Not4 cation and Staton Duty Officer '" Communications
- tate and local ofhoals TSC Shrft Manager TSC Communicate with CR SRO Manager of EOF Operations Training NotAcouon and Coorenate technical Communications data communscaton Staff Commurwe, tens between EOF, CR, (Technical)
T SC, and govemment agenoes Provide nformaton to MPI EOF Unit Personnel Technical information OtKam piant data for Technscal Coordinator Informaton Emergency Response Commurwcatens Fachties and Technical Assistant at State EOC as reovered EOF Manager of Pubuc Provide mformation to Nuclear information PutAsc information Team Lead information the PI staff at State EOC/Joent Media Nuclear informaron Center Provsde Staff Rumor Control Affected unit Control Operations Traeneng Control Room Data Ensure needs for plant Coordinator Room Technical Data Staff Communscatons data and enforma' ion are rnet EOF Manager of Radiological Direct On site RMTs. R.sdiatson Pro 1 on Or>Sao Radio 6ogical Supvs , A$st R.s1 ation Consequence l samphng program and Assessment Acodont Protect >< i Supvs f raduaton protecten Assessment Health Physiost. program Perform dose ALARA Coordinator assessment Hea"h Physics Mgrs calculations Millstone Emergency Pian Revissori 24 I April 1998 5 12 Change #2
I l l ll NSE ORGANIZATION -- - r Hesp Prefetved b f toineng Red Sutged to- Quel Ouahfcatione l WRStalling Summwy Workm CasStoff* (Refer to 4.+aden M) 60 Nudoer Owedor.
- 1. e. 7,9.14 Managet t
l I I l YES HP Staff 1 YES 1 YES Qualifed Shift 1,3.9 YES Technecian 1'* 1b 1.4*.6.9.14 YES Und Spectfsc. Sh'fl Manager or SRO g 1.2,4.9 Und Specrfic, SRO i nsed. pasi m APERTURE id present SRO or Cert l l l l Atmo 4% on i Und Specrfic. SRO ib 1,2.4,9 hcensed, licensed operator trainer, SRO or Cert i Nudear Staff 1,4,9 th l _. Una Specific, hcens ed 1,2.4,9 YES operator training.
~
Idb SRO/ Certified _ HP Supervision 1.4.9 1 i
,lo 20 70 - . _ _ _
- __ _. . _ _ _ ~
- - - - ~~
f -- TADL
~
i ST ATION EMERGENCY RE! l l Ork l _ Ernergency Locaten Shrft Emergency Pos# tion /Tsue l Nonnel Poution/T rue f Mafor Tesss id Mapor Fund wr.* Aftected Unit Control Aree RMT#1 Room HP coretage and HP Techncan Radotogcal staten surveys for
$urveys repaw, corrective actions. Seerth and Rescue. and nee-fvptng l'ersonnel i enennorrig. and ) icf CR/OSC/OSC Chemstry Technoans Assembly Area
_80.S'M'880* Cromstrf Technoans Radoecgral Arco *+'ry ; Assesvna. <s , dua. Protecton Dose Ar.sef.stners NAP / SAP RMT#2 HP Techneven AO:rsss mirol EOF Manager of R3deological Ern. .est ./Soentists Dose Assessment Off-s% Roo<AogscM Ce.edenote efivi- O,smestry _ j Does Assesurore sampfeng pregres.,, dosa. h 9C;ervisor/ Staff ' ast,ec,emer'.! arid col 1 E ">F Qauge assrssment Radiological /(ssessment _ m.,. Engmeers/Soentists Engenver _ __, _ Ocse Cd:utatens E ('F Asntant Menagst r,f
. , .._ __ Chemstry Radnologcas Dose Oow A.sessc*snt, Supervssor/ Staff Hawgist Assessmert ._
Carrw ans OSC [Enginees s/Soentists O'C ARF Unet Personr'el Radcegical contro', Het orts to the MOSO aM MRCA Proedes ' , wf:hin the OSC resological contrc9s I f wfthin the TSC/OSC/OSC assembly areas are provides radiological supportfor emergercy leams dispalmed by i tOF Fee *! I ear < Deta OSC. i N4 = L .p tment . { _ _ __ Dep6oy RMTs. co41ect Corsdenatre . RadnotogT.at Radio I Staff , f vt data i W/As.segned Pervrenel RbfT C46 Co.w.anscations Off-site Surveys P~NI b Me: corn 6vaican Tee. { ' 'y St wp S<aertiststmnginew s a Provide meteorologcol ' 6%mtw.s i Meteorolog. cal data mterpretation. ! Services calcutateons,long term meteorological Midd'iste Statan mformation Iw-Prod .9.on Operot ons l ingestion Pathway Sevece t,. xsstory ~~ Erwironmental Samphng (POSL,' ersimnef ~ ~ ~ ~ ~ ^ Sonnces Meteorological Tower ~~ - Repaar Support ra!! stone Emerp( m.y Piar. Revision 24 r(pot 1998 5 13 c eri,o v'
O ySE ORGANIZATION Hesp Preferfed Red Itanng Quel Quahfutms w Seemng** Subred to- Summary Nor Can Stae * (Meiet to W' M)~ l I J m
)
HP staff I YCS 1 [ YES YES Quakfed Chem Shrft 1 1,15 YES Tech l i YES Quahfed HP Tech 1 YES -_ RAB, HP, or 1,4.5,7,9. Chemtstry Staff 1 11,12,13,14 RAB staff Ib 1,4,5.9.11, 12.13 RAB or State 1,4,5,7,9. Chemistry Staff 2e 11,12,13.14 Engineers HP staff YES 1b 1, 4 YES APERTURE
> CARD Also AvaRable a AP*rhn Card
} HP staff, Staten sta ff 1, 4, 5, 9 _ Ib s YES Quakfied HP Tech 1 YES j J l 4 NU Envvonrnental l 1,4,10 Department staff 4 1b
~
J POSL personn el l 2k j J L ,
IAD m% ST ATION EMERGENCY R I l l i Or> imergency Location Shsfi Ernergency Position /fitte Normal Po iton/irtle Mapor Fu w.el Maror f asts 7SC Ar.a Assistant Director. f Operations Mgro Techneat Support Assume wr. mand and Engineer Mgra AOC8 dent control of the station Senior Staft Engineers Assosamort operating, fechocal I M. W . iland assessment and ropeer Depadment Heads Cw z ?- icr. staff Classrfy events Manager of Technical TSC Miegemon Responsible for Unit Ernneer Support Center UrWt System anatysis of operations Engeneenng data, development of procedures. _l r econvrsod repart, and l TSC cmecirve .ct.ons TSC Support Staft Mechancal Engerwer Assest Manager of T echncal Support f TSC / TSC Support Staff Electncal Engineer TSC Generston Test Service Generation Test Speoalist Engineer TSC Acodent Management
' Manager. Supervisors.
Asasst Manager of Team Leader Plant System Engineers en Safety Techocal Suppor'. Anatysis Branch Enyneer Reper Provide acodent TSC and Comsctrve AMT Mechanical ACtBOn anahsis Mechanical Engineer Engineer (Core Thermal Hydravlecs) TSC _ Engineer (T-H) Manager of Operational OSC Maintenance Support Center Es atuation, rep.aw, and Reper and Management corrective actions Correctrve Actions OSC/ OSC Asserey Ares Mechanic Mechanic osoosc Asserey Aree Electroan , Elecincian
- 1&C T echnician _
I&C T echncan OSC OSC Assrstant Unit Maintenance Coordinate on site Operational Suppo rt actrvtties and personnet Supervisor OSC OSC Assistant l&C Supervisor EOF Manager of Resources Station Staff Cout Jinates requests Resource for assistance. Acquestaan & organges Station Personnel personnel for rehef shift Dispatching work, account SERO Matistone Emergency Plan
; personnel _
Revision 24 Apnt 1998 5-14 Change #2
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TADLd ST ATION EMERGENCY REf 0 On-Emergency Location Shrft Emergency Position /Tette .-- Mayor Tasks Normal Position /T etle Mager Fwn .d EOF Ara Estarnet Resources Coordinate acquis# tion Station Staff Coordinator of personnet and equipment from _ corporate or outsade sources Wethersfield None Maertam usT.puter IRG/IT Personnet hlormston Per avestee.0;4 As Required Resources Fue Ungede / EMT T S (a) Fro Bngade i EMT FWeaghang Frengteng/ Em Fcy Mw Per As Required Services Secunty Personnel / Sec. Securny Portonnel / Searth and rescue Statio.) Personnet Plan Seartit and Rescue Station Personnel, as operations G;--ee required EOF None Regulatory Affairs / Proveds logistics Estomet Response bcensing Staff support for extemal Logleecs response personnet Useson with NRC Site 1 Response team CAS/SAS Securny Person Seconty Personnel Communeestions with SERO Notecatens ADTS/DSEO. Aarvate SERO j Nou6 cation System EOF HP Department Staff RAD Communicator __ HP Cui ...unscaucas EOF Co.,J ,w 4 CBETS Operator HP Department Staff EOF Exposure Monttonng Manager of Secunty
. _ .E v_=ne Control Secunty Personnel Estatesh EOF securny See access Orocts Secunty corsol & personnel Personnel en support of acomuntet>1rty emergency operations (6renghtng commurm atons, i
personnet accountatntity) assrst en personnel Per omtatxtery Securny Personnet Sec Secunty Personnel Ptaa Estatesh staton I see access controt secunty Support and personnet emergency operations _
-- ,_w r e i and pedvira personne l I
accountatwtity Secunty Shift Superveso r Secur,ty Shift Supervise on-sne _ See access control Supervisor f <.e: secunty operations
&p w&*ty Totals 19 Millstone Emergency Plan Revision 24 December 1997 5 15 Change a t s
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I ZZ IADL STATION EMERGENCY RE Table 61 Notsp; O May be provided by shift persortnel assigned other function b Subrect-to-Can Staff resource 9, are personnel beyond minimum required SERO C Statx)n positK)n (Counted as affected unit resource). l d Per Unit. O Assigned, affected unit resources, additional SERO staff will respond from non affected units. (accounts for additional personnel from the unaffected units). f Overan station resource. g Chemistry Tecincians are specific for each unit. h Carries out independent responses at time of incident notification i Previously counted in totals. j Only one senx)r reactor operator, reactor operator and non-licensed operator is re k car-in specialized resource- (Non-SERO personnel) l Total does not include Secunty staff or Fire Brigade personnel on-shift f l m On-Shift total reflects Shift Manager / Affected Unit Control Room DSEO as one position. f n SERO position provides personnel from each unit to respond. o Enhanced training requirement as identified during emergenc p Statx)n Duty Officer provides notification and communications as 30-minut notificatx)n and communications responsibilities, q On-Can Shift Technician reports to the EOF. A 30 to 60-minute goal has been established for the identified individuals. with the remainder arriving at various times during the next 30-minute interval.
* !ndicated Staff response times are from the time of notification to report to emerge
- Subject-to-Call Staff positions will be manned within 8 hours of SERO activation.
I l l l Millstone Energency Plan Revision 24 April 1998 5-16 f'fe se .. #'
f ( NSE ORGANtZATtON l l l Jent response. . l I i conditions (shutdown and refueling). i l E cY& s. 4 on-shift l h& i 4Ngg& s will report within about 30 minutes, CAg Ron
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6, Emergency Measures Emergency measures begin with the identification and c2 Ossification of an emergency and the activation of the appropnate emergency organizations. Emergency measures mclude assessment actions, corrective actions, and recommendation of protective a actions. The Emergency Action Levels (EALs) have predetermined values or conditions which, when met or exceeded, require declaration of an emergency classification, notification of the licensee emergency response organization, state and local officials, and corrective and/or protective actions A general uuttine is presented as follows 6.1. Notification and Activat on of Emergency Organizations The authonty and responsibility for initially classifying and declaring emergencies, initiating notification to emergency organization personnel, state and local officials, the NRC and initiating immediate actions necessary to limit the consequences of the emergency reside with the Shift Manager (SM), who is on site 24 hours a day. The SM initially assumes command and control of the SERO as the Control Room Director of Station Emergency Operations (CROSEO). The SM will function as CRDSEO until relieved by the on-call DSEO, a shift relief occurs, or the event is terminated. After a relief by the on-call DSEO, the SM assumes responsibility as Manager Control Room Operations (MCRO). The CRDSEO I DSEO is responsible for ensuring that timely and appropriate notifications are made. SERO responsibilities may be transferred dunng a normal shift rotntion when a qualified relief reports on site and is fully briefed on current and past conditions. For emergencies that are not untt-specific, the Unit 1 Shift Manager assumes the position of DSEO until relieved, or the event is terminated. The SERO is activated by a combination of public address system The announcement, Station emergency alarm actuation and pager message. PA announcement can include the incident location, emergency classification and personnelinformation. Initially, the emergency or ganization consists of normal on-shift personnel. Notification of the emergency organization and state and local officials is by the Emergency Notification and Response System (ENP.S) and SERO Notification System, which are initiated by Control Room personnel. Notifications will be made using commercial telephone lines, should a failure of either system occur. The Connecticut State Police will assist with backup notifications to state and local officials, as necessary. Following the declaration of a " State of Emergency" by the Governor, OEM may l direct the DSEO to discontinue use of the ENRS for further state and local notifications and directly communicate with the State EOC for classification changes or event updates The State OEM will then assume responsibilities for f Mdh, tone Emergency Plan Revision 24 61 Apol 1998 Change #2 I \
notification of the local communities. The State EOC will coordinate activation of l the Public Alerting System sireno with the local governments, as needed. The ENRS consists of computer based systems. When activated, a pager tone alert and a mossage are transmitted to the pagers. The ENRS system is used for notification of emergency events and decreases the time necessary to notify off-site officials. The radiopager message satisfies the 15-minute' notification requirement for state and local officials. The state and local officials call a dedicated telephone number which records their response time and provides more detailed incident information. A goal of 15 minutes has been established for completion of the SERO initial notification sequence. K Radiopager messages include the following information:
. Station identification
( . Event classification (including State Posture Code) The follow-up messages are received by off-site officials calling the dedicated telephone numbers provided to each responder. The information above is repeated and additionalinformation is provided as follows: {
. Name and Title of communicator k . Affected Unit
. Verbal summary of incident details
. Release information
. Meteorological conditions (if applicable)
. Additional services requested
. Expected update messages Details concerning release type, quantities and actual or projected dose rates will be developed, as appropriate, and provided to responsible officials, when requested.
I The ENRS system provides initial event notification to the emergency organizations. When emergency facilities are activated, various communications i systems are employed. These systems allow transmission of detailed technical.I I information of the event in progress as well as direct voice communications between facilities and decision makers. Detailed radiological information will be f relayed to the DEP at the State EOC for analysis and decision making. l A representative from State DEP responds to the EOF and provides a liaison with the EOF and State EOC staff. The NU Executive Spokesperson, Technical Assistant and the Nuclear News Manager respond to the State EOC. Work space and communications for federal agencies and the Town of Waterford are located in the EOF. The TSC provides a work area and limited communications for the NRC Millstone Emergency Plan Revision 24 62 December 1997
The State of Connecticut EOC in Hartford employs vanous communication systems to provide information to the OEM Area Coordinators and the local commun.ty EOCs This system is usM to transmit technical, radiological, administrative and resource data between the local community EOCs and the State EOC. This system utiltzes radio, telephone and FAX devices to provide l continuous contact with the affected areas The State EOC coordinates the Public Akrting System siren actrvation to immediately precede Emergency Alert System (EAS) broadcast messages. The pr. mary notification (radiopager and dedicated telephone lines) contacts and the continuing lines of communication between on-site emergency response facitrties and off-site emergency response centers are indicated in Figures 7-1a through 71c. 6.2. Assessrrent Actions 6.2.1. Initial Assessment Event class 1ication is based on EALs. The EAL tables provide an incident classification based on instrument read (ngs available in the control room or other observations. The NRC incident classification and corresponding state postute codes are transmitted io state and local ofGcials via the ENRS. On-Shift dose calculations are conducted, when appropriate, and used to verify or challenge the incident classification and the associated PAR. Ancident specific PARS, beyond those associated with the event c! Ossification and posture code, are developed using dose assessment or plant conditions in accordance with *NUREG-0654, Supptement 3' guidance for severe reactor accidents. Accident specific PARS,if indicated, will be transmitted directly to the State DEP Duty Officer. The Shift Technical Advisor provides independent assessment of emergency actions. The TSC, when activated assumes n more expanded role and responsibility beyond that of the STA. Additional technical services and support are obtained as necessary from a combination of station personnel, corporate personnel, and off-site assistance companies / agencies. The State DEP does an independent assessment of plant conditions and off-site dose assessment. 6 2 2. Protective Action Recommendations (PARS) Tbc State RERP includes procedures for use by state and local community officials for pubhc protectsve actions in the plume exposure pathway. Public PARS requinng evacuation are to be initiated only for GENERAL EMERGENCY events Mittstone Emergency Plan Revision 24 63 December 1597
i l The licensee will provide a PAR to state and local authorities The provided PAR will be revised thould changing conditions warrant ! The protective actions, when authonzed, are implemented by state and local officials using the Public Alerting System sirens in conjunction with the EAS. The Govemor of Connecticut is responsible for public protective action decisions after a state of emergency is declared. Poor to a state of emergency dociaration, local chief executives'are authonzed to take the public protective actions associated with the GENERAL EMERGENCY posture codes. l When emergency response facilities are activated the State DEP will collect and process information to independently venfy and recommend changes,if necessary, to the licensee provided protective action recommendations. 6.2.3. Dose Assessmsnt Radiological assessments by the SERO include determination of radiation exposure rates by both analytic and direct measurement methods. Direct measurements are performed by RMTs deployed to field monitoring locations. The analytic methods use computerized dose calculation models or hand calculations. Projected dose estimates are calculated for different downwind sectors and distances. The results may require reclassification of the emergency. Further assessments are performed as required and updates are provided to off-site authorities. On-site radiation protection activities are coordinated by the MRCA. Off-site RMT activities are coordinated by the FTDC under the direction ; y of the MRDA. Field data and projected dose information is transmitted to j the State DEP, as necessary, ) The emergency plan procedures contain methods for relating the various measured parameters to dose rates for the key isotopes. Dose assessment is performed by licensee personnel assigned to the control room or EOF to <>erform calculations. Information from dispatched field monitonng teams and plant conditions are then used to verify incident classification,
- a. Use of Sta* ion Monitors The station has an extensive system for monitoring radioactive f materials released to the environment. As a general requirement, the various process monitors are capable of initiating appropriate ..
alarms and/or actuating contml equipment to provide containment of radioactive materials if pre-established limits are reached. High range containment monitors have been notalled in the Unit 1 drywell and Unit 2 and Unit 3 containment to be used to determine containment atmosphere curie inventory. Procedures have been Millstone Emergency Plan Revision 24 l 6-4 December 1997
f 6stablished for converting these monitor readings into potential dose assessment data I bgh-range radiation monitors have been installed at the potential effluent points to determine effluent release rates should the normal range existing stack monitors go off scale or become inoperative during an emergency These hgh-rang'e monitu s cover the entire postulated range of releases and exceed the valuas specifed for a GENERAL EMERGENCY. These systems allow for monitonng releases during emergency conditions. Procedures have been established for converting these monitor I readings into relean rates. On-site RMT surveys are taken to venfy release rates. 1 The site has a permanent meteorological installation that records { wind speed, direction, and temperature differences continuously in { the Control Room and at 15-minute intervals via a computer system.
- b. Use of Emeroency Action levels (EAls) ,
J The EALs contain effluent monitor radiation levels which correspond to predetermined dose assessments and appropriate emergency classification levels.
- c. Dose Estimates for Radioactive Releases Upon determination of an emergency or potential emergency condition that is anticipated to have off-site consequences, off site doses are estimated. The critical exposure pathways for short-term emergency actions are the extemal dose due to noble gases and the intemal thyroid dose due to inhalation of radioactive iodine. In these cases, estimated release rates are combined with meteorological dispersion estimates in order to l
predict off-site doses. Station emergency plan procedures include a method to calculate the distances at which the Environmental Protection Agency protective action guide (PAG) limits may occur. i When the station EOF is activated and radiological dose assessment personnel have arrived, estimates of off-site doses based on more sophisticated techniques and by analysis of actual RMT data can be provided. I J Mittstone Emergency Plan Revision 24 December 1997 ) 6-5 i. _ _ , ,_ ,y [ w
624 Release Rate and Dose Estimate Methodolo',i l l a ht2 gt Gas Release Rate E@matej The stack monitor readings for each unit are obtained and converted to release rates by multiplying the readings by an appropnate f actor. If the stack monitors are off scale, the hgh-range radiation monitors are used to determine stack release rates. The high-range radiation monrtor readings are converted to a stack release rate using a predetermined factor. Grab sample 3' results, if available, may be more accurate than gross monitor readings. Release rates based on actual samples,if available, will be used in heu of monitor based calculations. l if no release estimates based on fixed monitors are available, the release rate will be estimated using field monitoring results.
- b. ,R_rdioactive lodine Release Rate Estimates if radioactive iodine grab sample results are available, they may be used to calculate the totaliodine release rate. If grab samples are not avaCable, the total noble gas release rate is multiplied by a predetermined io6ne-to-noble gas ratio (depending on the plant condrtions) to chtsin the iodine release rate.
- c. Post-Accident Samotina System Each unit features a Post Accident Sampling System (PASS) that provides the capability for obtaining samples of liquid and gases, under accident conditions in general accordance with the Reg.
Guide 1.97, NUREG-0578 and NUREG-0737. After samples are obtained, radiological and chemical analyses will be performed. Results of radiological and chemical samples will be used to establish plant status and to provide information supporting projected dose assessments.
- d. Meteorological Data Input to the meteorological section of the procedures includes effective release height, temperature differential, wind speed, and wind direction based on actual or projected readings.
Meteorological data, acquisition and flow are desenbed in Section 70 Millstone Emergency Plan Revisson 24 6-6 December 1997 \ --
e 191WE!.tcAtR91t12 Vin!sD1 The calculated TEDE contnbutions willinclude plume extemal exposure, ground extemal exposure and inhalation exposure. TEDE doses are calculated for vanous sectors and distances using both computenzed and manual methods.
- f. Committed Dose Equivalent (CDE) Thyroid The radioactive iodine release rate and meteorological data are used in computenzed and manual methods to obtain the prefected maximum off site CDE thyroid dose at various distances and sectors
- g. yenfication When appropnate, dose rates are venfied by on-stte and off-site RMTs which have been deployed with portable emergency radiologicalinstrumentation and communication equipment.
- h. RMT Mobilization and Monitorina
- 1. Notification / Coordination Methods - When notified by radiopager and/or the station evacuation alarm, the RMT members report to the EOF, Control Room, North Access Point (NAP), South Access Point (SAP), or areas as assigned. The teams are then dispatched by the appropriate SERO managers.
- 2. Composition - Each of the off-site RMTs consists of two persons, at least one is a health physics technician. The on-site RMTs are health physics technicians.
- 3. Transportation - Three dedicated company vehicles are used for transporting off-site RMTs.
- 4. Monitonng and Equipment - A generallist of radiological monitoring kit equipment is included in Appendix E.
Complete inventories are provided in station procedures. The kits are provided with appropriate radiological monitoring equipment to measure radioiodine concentrations in air as low as 10'7 pCi/cc. Mittstone Emergency Plan Revision 24 67 December 1997 l l
Environmental Thermoluminescent Dosimeters (TLDs) and - air particulate samples, air sample cartndges, goat milk, cow milk, soll, vegetation, and water are collected by the Northeast Utilrties Production Operation Services Laboratory (POSL) personnel
- 5. Deployment Time The off site RMTs can be deployed in approximately one hour. The on-site RMTs can be ,
deployed immediately after equipment checks. { j
- 6. RMT Communication- The off site RM T reports information via radio communications or telephone.
Off-site Monitorina by DEP
)
- i. l The State DEP dispatches off-site mon:toring teams of state i personnel.
- j. Plume Monitorina Over Water Millstone Environmental Lab vessels may be used to provide transportation for plume monitoring over water. RMT personnel will be assigned to perform over water monitoring as necessary.
6.2.5. Secondary Dose Assessment Long-term off-site radiological dose assessment (secondary assessment) is provided by the State DEP. The State DEP is assisted as necessary, by NU and other agencies. After the assessment has been completed, the State DEP recommends protective actions to the Govemor for approval. I 6.3. Corrective Actions Corrective actions are implemented by the use of detailed station procedures. I These procedures prioritize actions to prevent or mitigate the consequences of an accident. The instrumentation, control systems monitors, and radiation monit -ing systems , l provide indications of the safe and orderiy operation of the unit. These systems l provide the operator with the information and controls r.eeded to start up, operate at power, and shut down the plant. They further provide the means to cope with an abnormal operating condition should it occur. Control of plant systems and information displays are centralized in the control room. This instrumentattun provides the basis for initiation of corrective actions. i The following additional corrective actions are implemented during emergency situations as necessary. Mitistor.e Emergency Plan Revision 24 68 December 1997
-- c_ _.
( L______ _ ______ _ _
4 1 1 631 Fire Fighting Procedures for responding to fire emergency situations are in place. Firefighting strategies for plant areas are available for ne by responding personnel. The Shtft Fire Bngade Captain, with assistance from the operations Fire Brigade Technical Advisor,is in charge of extinguishing the fire Applicable health physics, secunty, and safeguards procedures apply. If outside assistance is needed, the Waterford Fire Department is called. 6.3.2. Damage Control. Repair and Decontamination Station persor..iel normally provide decontamination, repair and damage contro: services. For ALERT, SITE AREA EMERGENCY and GENERAL EMERGENCY operations, the support of specialized outside contractors is obtained, as required. Decontamination of personnel and equipment is conducted in accordance with approved procedures. 6.4. Protective Actions 6.4.1. On-site Protective Actions Persons in the owner-controlled area of the site, but outside the protected area, are considered members of the general public. Persons within the protected area are either station personnel, contractor personnel, or visitors. If the protected area has been evacuated, Security willinspect locations outside the protected area to ensure all personnel have evacuated. The radiological protec; e a .'. ions specified in this section and in Emergency Plan Procedu.es are augmented by the normal health I physics procedures and are used during an emergency unless different actions are identified and authorized by the DSEO. The MRCA assumes responsibilities as the Health Physics Manager and establishes radiological control areas (RCAs) in response to the incident. Access to the RCA is controlled by the emergency team briefing process unless immediate access is authorized by the ADTS to facilitate emergency repairs.
- a. Action Criteria Protective actions are taken when an incident has occurred, or may occur, that could result in concentrations of airborne radioactivity or radiation levels that exceed normal limits for a i
specific area or areas and cannot be readily controlled or personnel safety from other causes is threatened Station procedures provide guidance for protective actions, such as evacuation, assembly or sheltenng Millstone Emergency Plan Revision 24 l 69 December 1997 l l
b NotificeMa The actuation of radiation monitonng alarms, station emergency alarm, fire alarms, and public address announcements alert personnel to hazardous conditions and response actions Secunty and Srte Access Contr.g_f )
- c. \
if station access has been restricted, traffic is diverted through a secunty checkpoint in the EOF parking lot. Site access roads will , be manned and barricaded as necessary. 3tation access controls will be supported by the Waterford Police department and the Connecticut State Police, as necessary. Personnel accessing the protected area must bs authorized by the ADTS. Station secunty procedures provide detailed guidance for responding to an emergency.
- d. Evacuation Evacuatica is a station-wide event and may occur upon classification of an ALERT SITE AREA EMERGENCY, or GENERAL EMERGENCY event. An emergency atarm actuator is l
located in each unit control room. This actuator activates the l evacuation alarms in all three unit areas. The protected area is l defined as the area inside the security fence, through which access is controlled by the Secunty Department. When ordered to evacuate, personnel take the following action:
. SERO personnel respond according to station procedures.
- Other station personnel respond as directed by plant page or station secunty.
I Station j Personnel can be evacuated in about 30 minutes , secunty will conduct a sweep of owner controlled areas outside the fence to ensure personnel have evacuated. l If evacuation from an assembly area to off-site is directed, personnel willleave the site on foot, by company or private vehicles, or by private buses per letter of agreement. The station
)
will coordinate site evacuation with the Town of Waterford. Station evacuees leaving the site will follow instructions for general population evacuees as directed by the Town of Waterford RERP Mitistone Emergency Plan Revisen 24 i 6 10 December 1997
e Eggonnel Agiountability When the SERO is activated, shift and on-duty SERO personnel I will report to assigned ERFs Personnel reporting to the Control Room and TSC/OSC will use installed card readers to provide accountability information. Each Unit SM/MCRO will provide the names and/or keycard number of all personnel under his direction to the MOS. The MOS coordinates with secunty to ensure personnel have exited the protected area or logged into a specific location using their keycard. Secunty Officers will conduct an inspection of the station and protected areas to ensure compliance. When evacuation has been venhed, an accountability program will be run on the security computer system. The MOS and SM/MCRO coordinate to determine the names of i personnel not accounted for. Personnel not accounted for are paged via the station public address. Personnel not responding after five minutes are considered missing. At this time, initial 4 accountability is completed and search and rescue actions are initiated. Station procedures provide detailed guidance to meet the established goal of 45 minutes to complete accountabihty. SERO Managers are responsible for accountability / of personnel under their direction. The MOS maintains a log of personnel entering and leavir.g the protected area Personnel reporting to the site respond to the EOF prior to entry, if access to the site has been restricted,
- f. Personnel Monitorina All personnel within the Protected Area are monitored for radioactive contamination prior to leaving the Owner-Controlled Area. Portal monitors and RMTs will be used for monitonng personnel. An off site monitoring location will be established if radiological conditions on site prohibit adequate monitonng.
Each ERF has a radiological control point, personnel friskers, area radiation alarms, and air monitors. The MRCA will establish decontamination areas as necessary Decontamination facilities are available at the EOF and other areas within the station. The Haddam Neck Plant EOF may be used for monitoring and decontamination if conditions pronibit on-site monitonng. Transportation to an off-site facihty will be provided, as necessary. Monitoring and decontamination l Mitistone Emergency Plan Revision 24 6 11 December 1997
procedures are detailed in the Radiation Protection Manual (RPM) Documentatic") of personnel contamination surveys will be maintained. Any person suspected or known to have ingested radioactive matenal w1!1 receive broassay examinations as specified by the RPM. 642 tJse of On-stte Frotective Equipment and Supplies Protective equipment and supplies are used to minimize external and internal radiological exposure and contamination of personnel entenng the station. Detailed procedures on the use of protective equipment and supplies are referenced in Appendix D. 6 4.3. Contamination Control Measures
- a. Detailed guidance for controlling radioactive contamination of personnel s'id equipment is provided in the RPM.
- b. During accident conditions, the MRCA may approve conditional release of items from the RCA. in excess of RPM release limits.
Special controls for release of this equipment will be instituted.
- c. Personnel are advised not to consume on-site drinking water and food supp;ics during an accident, untit sampling and analysis are completed.
- d. For areas outside the station protected area, RMTs will be used to identify radiation control areas and security will be used to control access. Public access areas of the site will be controlled to off-site radiological cnteria.
- e. Radiological waste material will be controlled, stored and shipped in accordance with the RPM.
' Off site surface contamination and other radiological control criteria are detailed in the state and local RERP.
6 4.4. Personnel Radiation Dose Determination Health Physics (HP) coverage is provided 24 hours per day to support normal Station operations. During accident conditions, HP technicians may accompany emergency workers, as needed, during RCA entnes Emergency dosimetry, i.e. self-reading Pocket ton Chamber dosimeters (PICS), alarming dnsimeters, and permanent recording dositneters ' (TLDs) are used by the initial SERO responders, as necessary
%Ilstone Emergency Plan Revision 24 f December 19'37 6 12 I
Additional dusivitetr y is distributed t>y Itl' gwasunnel and a swued to individuals. including ofi. site endsviduals atreveng at the LOI-TLDs are available from and analyzed by the NUSCO Dosimetry Laboratory The indevedualintegrated dose records are maintained by the HP Cepartment Exposure information is recorded from self reading dosimeters and provides personnel exposure tracking untif TLD results become available The TLD results will be used as a permanent exposure record Permanent dosimetry will usually be read when et is determined that .he emergency workers have received an exposure near their administrative hmet or if an overexposure is suspected. All other dosimetry is read on a schedule estabhshed by the MRCA. 6.5. And to Affected Personnel f Provisions are made, .o assist personnel who are injured and/or have received htgh radiation exposures. EMT qualified personnel, assigned to the Fire Bngade provide on site emergency medical services. First aid and decontamination facilities are available on-sste and off site. The following subsections desenbe measures to be used to provide necessary assistance - G.5.1. Exposure ControlGuidehnes in the event of an ALERT, SITE AREA EMERGENCY or GENERAL EMERGENCY. emergency worker exposure limits are automatically increased in accordance with EPA 400. This limit remains in effect until mission-specific limit upgrejes are required and authonzed by the appropnate emergency manager (refer to Table 6-2). The use of radioprotective Potassium lodide will be evaluated for administration to on site emergency workers in r :ordance with SERO procedures. Exposures are commensurate. wh the significance of the objective and are held to the lowest levels that the emergency permits. In ai! situations, every reasoncble effort is made to minimize exposure to emergency . personnel.- Planned actions are carefully vamined by weigning the nsks and consequences of potential exposure and injury agair.st the ;"obabihty of success and the benefits to be gained frorn these actions 652 Emergency Exposure Control Guidelines for Off Site Personnel if off site eroergency persont'el aie required during a nuclear inc: dent to support combating fires. provide emergency first aid, or transporting injured and/or contaminated injured to off-site medical treatment facilities. exposure hmits as speufied in Table 6-2 are apphed Appropnate dosimetry will be issued to all off site responders in accordance with the RPM Minstono Enegency l'ian , l(tavi%:Of t 2 I f n 13 Apti 1%8 Cliathje x.#
- , - _ , - - - - - - _.---U.... - - - -_ _ _ - , . - - - . ._ -- ----------.,--------.u.- - - - - - - - - - - - - - - - - - - - - - - - - - - - ~ - - - - - - - - - - - - - - - - -
Off site medical f acihty staff personnel performing medical treatment on l injured and/or contaminated injured persons shall control exposure in accordance with f acility emergency procedures Medical staff shall be issued appropnate dosimetry (i e . TLD and pocket dostmevi f All cosimetry will be evaluated to determine and document the actual exposure received responding to the emergency 653 Decontamination ? - Radiological decontamination of personnel, supphes and equipment and waste disposal are conducted in accordance the RPM, under direction of 1 HP personnel 4 <1 I Each unit normal decontamination facilities could be used to decontaminate emergency response personnel The EOF is the pnncipal decontamination facility dunng emergencies. A shower with holding tank and supphes for personnel decontamination are provided. If on-stte areas are not usable because of inclement weather or continuing releases, the Haddam Neck Plant EOF with similar facilities may be used. 654 First Aid EMT quahfied personnel are available to assist ill or injured personnel on-site 24 hours per day. If necessary, a physician may be requested to provide medical assistar.ce on-site. 6.5.5 Medical Transportation injured or radioactively contaminated injured personnel requiring hospitahzation are transported using local community ambulance services The ambulance may be requested via dedicated or commercial telephone The ambulance crews are trained to respond to radiological incidents. Personnel qualified in radiation protection are directed to report to the receiving hospital or accompany the injured and contaminated patients to the hospital. If necessary, the receiving hospital will be provided details of patients being transported. Station procedures provide detailed instructions for personnel responding to personnel injunes or contamination 6 5 6. Medical Treatment Arrangements for the pnmary care of injured, or radioactively contaminated injured personnel are made with the Lawrence and I Memorial Hospitalin New London and Middlesex Hospital in Middletown Millstone Emergency Plan I Revision 24 6 14 December 1997
The hospital Communications will be by commercial telephone lines stof' is trained annually and the facility is equipped tod treat contam enfured patients Contaminated wounds are treated and decon , as necessary by the hospetal staff 66 Pubite Information The pubic information emergency response personnel consists of of Public Informaten (MPI), the Nuclear News Manager (NNM) the Ex Spokesper1 son and supporting staff. The MP the State EOC. The NNM reports to the Executive Spokesperson an pubic information acuvrties at the EOF and offcials i i I l l l Mmstone Emergency Plan Revision 24 December 1997 6 15 y -
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Ituk W . (RESERVED) I l l Mittstone Emergency Plan Revision 24 6 16 December 1997 m .
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TABLE 6 2 EMERGENCY EXPOSURE LIMITS : Ifag Gatenon 5.0 Rem"3 Annual Part 20 10.0 Rem Mission to protect valuable property 25.0 Rem'D Mission to save a life or prevent / mitigate a severe accident 25 0 Rem"3 Mission of Off stte RMTs
>25.0 Rem")
Voluntary mission to save a life or prevent /mrtigate a severe accident NOTES: Automatic exposure up to 5 Rem is allowed. When authorized by the ADTS or ADEOF, (1) members of the SERO responding to on site emergency response facilities are designated emergency workers subject to NRC 10CFR50.47(b).11 radiation exposure controls which are the EPA guidelines for on-site emergency workers in accordance with EPA 400, emergency workers are allowed an exposure up to 10 Rem (2) TEDE for operatiens necessary to protect valuable property. (3) Depending on station radiological conditions, authorized emergency workers may rece exposures up to a job / mission-specific designated limit, not to exceed 25 Rem TEDE The MRDA has the authonty to upgrade off-site RMT exposure limits to 25 Rem TEDE (4) when necessary to perform critical off-site dose assessments. When authorized by the DSEO, exposures above 25 Rem may be received for life saving (5) activities on a volunteer basis and with full awareness of the risk involved. NOTE: it is recognized by NRC and EPA that an accident involving significant .adiation exposure is a low probability occurrence. An exposure level below 25 Rem is not considered to be life-threatening and will occur once in a hfetime. ALARA princiofes will be applied when possible. Dose received during an emergency is included as par worker occupational exposure record and subtracted from the planned special exposure available. All exposures in excess of 10CFR20 will be tracked and recorded as once in a hfeti exposures. Total Effective Dose Equivalent is defined as part of the station h l program Millstone Emergency Plan Revision 24 6 17 December 1997 f;
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- 7. Emergency Fac6tities and Equipment 1ri., section edentifies, describes. and gives the localuns of emergeracy operation centers, support centers, communication systems, and first aid and trydecal facshties Diagrams of the station emergency response facihtees (ERFs) are provided in Appe F. Locations of the on-site emergency response facihties (ERFs) are indicated in Tablo 71. The vanous facihties and equipment are controlled and surverfied, using l Emergency Preparedness Department Instru: tion EPDI 06 ' Emergency Planning Facihty Manual" Th#s document provides detailed hsts of equipment and schedu conduct of f acshty/ equipment surveillance Equtpment inspection ano inventones, are conducted quarterly, or after known or suspected use of equipment occurs, en
-ks of emergency equipment are accordance with this procedure. Operational c' in of the emergency response completed at specified intervals and dunng acts organization.
7.1. Control Room The Control Room is the pnmary f acihty where conditions of the plant are monitored, controlled and corrective actions are taken to mitigate any abnormal conditions. The Control Room provides the main communications hnk between the Station and the other ERFs concerning system problems as well as long-term and short-term corrective actions. The Control Room is the primary operations ' center during events classified as UNUSUAL EVENT, and prior to the activatio , of the other ERFs for ALERT, SITE AREA EMERGENCY, and GENERAL f EMERGENCY classifications. The SM/CROSEO can initiate and c I appropriate procedures from the Control Room until additional assistance available. Emergency hghting, power, ventilation systems, and shielding enable operat to remain in the Control Room to ensure the station can be m condition. In addition, the operators are able to evaluate station conditions an relay pertinent information and data to appropriate emergency facilities, 1 personnel, and agencies during all emergenc;es. To ensure that opera and other personnel can remain self-sufficient, portable radiation monitors, respiratory equipment, portable lighting, and alternate communication syste are maintained in the Control Room. The three control rooms use the Off-site Facilities information System (OFlS)( in addition, the control rooms the primary data communications link to the ERFs have Safety Parameter Display System (SPDS) terminals 711 Normal Operations 1 The Control Room for each plant is the on-site location from which the it contains the instrumentation, controls, nuclear power plant is operated and displays for
%Ilstone Emugency Plan RevNort ?.1
/1 April 1%H CtiarH}e #?
? ,, l , ---- -- L =______
e Reactor coolant and Auxiliary systems
- Balance of Plant and Nuclear Steam Supply systemc i
- Electncal systems e Safety systems (including engineered safety features). ond
. Accident monttonng systems 7.1.2. Alert and Notification Each Control Room is equipped with an ENRS from which personnel transmit radinpager messages. State and local emergency response personnel ca!!in and receive a summary report desenbing the nature of the incident and the plant status.
7.1.3. Communications in addition to regular direct-dial telephone lines and on-site extensions. each controt room is equipped with reliable emergency communication systems (dedicated telephone knes and radios) necessary to alert PNtion and other essential licensee, state, and local community persont.el and maintain communications with the station ERFs throughout an emergency. Each control room, thw TSC and EOF has a dedicated telephone system to communicate with the NRC. 7.2. Emeroency Operations Facility 7.2.1. Function The EOF serves as a near-site support facihty for the management of the overall site emergency response, the coordination of radiological and environmental assessments, and determination of recommended public protective actions. It is the crimary on-site communication center and contains appropriate communication links to on-site data sources and off-site organi at,ons. Also located at the EOF are emergency radiological monitonng and decontaminate. ion equipment and supphes, protective clothing, respiratory protective devices. The EOF also contains a facility for limited analyses of radiological data. The EOF is activated during events classified as ALERT, SITE AREA [ EMERGENCY, or GENERAL EMERGENCY and is the pnmary interface between the SERO and off-site agencies. Minstone Emergency Plan Revision 24 72 Decemt>er 1997
I i 722 Location The EOF is located approximately one (1) mile north of the station protected area on the west side of the access road, approximately 600 $ feet inside the site boundary (refer to Appendix F Figure F 2) 7 2 3. Structure and Habitability I The EOF is designed for continuous operation dunng an emergency it is a rectangular, one-level above ground, strwture having 2 foot thick, steel reinforced concrete walls and ceiling It provides approximately 7,000 ft' j l of working space and has a protection factor greater than 500 from a semi-infinite noble gas cloud airborne source and a protection factor of l I 133 for lodine 131. J The heating, ventilation, and air conditioning (HVAC) system is rated at 2,000 CFM and is located insid9 the EOF. Operating in the filtered recirculation mode, the system provides a habitable environment for the l designed occupancy of 250 people. l The EOF has manually activated airtight doors, decontamination facilities and a dedicated emergency diesel to provide backup AC power. l i 7.2.4. Layout The EOF functional areas are indicated in Appendix F, Figure F-2. 7.2.5 Communications l The EOF is the pnmary communications center at the station during an emergency. The EOF is provided with communications to the controf rooms, TSC/OSC, State EOC, Joint Media Center, and NRC. An ENRS terminalis available as well as radios, dedicated telephrer 3 normal telephones and facsimile machines. 7.2.6. Power Supplies Normal power is provided to the EOF from the station power gna Emergency power is provided automatically by an emergency diesel generator, capable of meeting all EOF power requirements. 7.2.7. Technical Data and Data Systems The EOF receives plant operational data via the OFiS and direct voice f communications with the other ERFs. Facsimile machines provide j l i l hardcopy communications tietween ERFs. l Millstone Emergency Plan Revision 24 7-3 December 1997 ( l l A---__-___-__
1
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128 Records Availability and Management An administratively controlled libeary of atstion and plant specr0c drswings and procedures is maintained in the EOF This information is stored at the EOF in hard copy or ektctronic form 73 lechnectlSyppgrt Cen'er/Operth9DAljiupp91CfDit! 731 Function The TSC provides technical support to plant operations permannelin the Control Room. OSC (co-located wrth the TSC) and EOF dunng an emergency. The TSC is activated with. 60 minutes of notification of an ALERT or higher event. TdC personnel are under the direction of the ADTS The MTSC will use communication networks, data system networks, and available documents to analyze the plant behavior throughout the incident. TSC personnel will also research, collect, and interpret plant parameter data, perform detailed calculations, trend data, determine probable consequences of proposed plant corrective actions and provide engineonng recommendations to mitigate plant system degradation. The MTSC communicates with the MCRO to evaluate plant conditions, and recommends corrective action via the ADTS. The ADTS, located in the TSC, provides guidance and direction to the control room operating personnel. The MTSC coordinates with the MOSC to brief emergency repair teams. The NRC dispatches representatives to the TSC to monitor plant r.onditions and station emergency technical support activities, and to maintain communications with the NRC Director of Site Operations. 7.3 2. Location i The TSC is located inside the protected area, adjacent to the west side of the Unit 3 control building. 1 7.3 3. Structure and Habitabihty The TSC/OSC is a 2000-ft2 below-ground facility with one-foot thick (minimum) exterior walls and ceiling. It was designed and built in accordance with the Connecticut State Building Code. It is able to withstand the most adverse conditions reasonably expected during the l i design hfe of the station. A dose consequence study for the TSC/OSC revoaled that the calculated f 30-day integrated doses to personnel in the TSC/OSC following a design basis accident at any of the three units are within 10CFRSO Appendix A. Millstone Emergency Plan Revision 24 74 December 1997 i
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General Design Cntena 19 guidetenes and the NRC Standard Review Plan for Controf Room Habitability LlH111 Thyrood 30 Rem Whole body gamma 5 Rem Beta skin dose 30 Rem The HVAC system is rated for 2,000 CFM and located in the TSC/OSC penthouse, which is above ground level. The facility recerves an isolation s@nal initiating HVAC operation, from the Unit 3 control building isolation (CBI) segnal. This system is designed to maintain habrtabilttffor facility occupants. 7 3 4.1.ayout Work centers exist to enable OSC and TSC personnel to monitor plant ) data on the OFIS, SPDS terminals, and provide technical assistance. The entical safety functions may be continuously monitored on provided SPDS displays. The NRC woA area provides a space for the NRC to establish local area network communicat;ons ar'd monitor OSC and TSC activities. NRC dedicated telephone system connections are provided, in addrtion to site telephone access. 7.3.5. Communications The OSC and TSC are provided wnh reliable communications to the control rooms and EOF. A facsimile machine is provided for hard copy data transmission.
)
7.3.6. Power Supplies The TSC/OSC is powered from the Unit 3 normal power bus. The Secunty system emergency diesel generator provides reliable backup J power to meet all TSC requirements. l l 7.3.7. Technical Data and Data Systems 1 The TSC willinitially receive plant operational data for each unit via the unit SPDS and/or OFIS system and telepnone communications between the TSC and the control room. OFIS automatically records plant system J variables and provides history, data trending and graphic print capability to the ERFs. Millstone Emergency Plan Revision 24 7-5 December 1997 I w____-__-_____-___ __ _ _ _ _
l 738 Records Availatxtity An administratively controlled libr_fy of station and plant spectfic drawings and procedures is maintained in the TSC This information is stored in hard copy or electronic form 74 Qoerational Su229.rLQnnitLLQSC) and OSC Anembly Area 74.1. Function The OSC is a protected area f acility, co-located within the same structure as the TSC Emergency response personnelw:. assemble in the OSC
] dunng an emergency, to provide support to the affected control room The OSC provides a staging area for emergency teams being dispatched i j
dunng accdont conditions. The OSC Assembly Area provides space for additional SERO personnel outside the TSC/OSC. 7 4.2. Location and Size The OSC is located within the TSC/OSC f acility adjaccat to the west side of the Unit 3 control building The OSC is approximately 23 feet by 26 feet. The OSC Assembly Area accommodate support personnel not located in the TSC/OSC f acility. The OSC Assembly Area is located in the William Ellis Technical Support Center (B475), Conference Room C-102, which is approximately 50 yards west of the TSC/OSC (see Figure F-3). 7.4.3. Structure and Habitability f The 03C has the same habitability as the TSC. The OSC Assembly Area has no specific habitability criteria. 7.4.4. Communications The MOSC wiil maintain communications with the EOF and the affected control room using normal or dedicated telephones in the OSC. The MOSC will directly communicate with personnel within the TSC. l Mdistone Emergency Plan j Revision 24 . 7-6 December 1997
T45 Emergency Equip ment In order to support the OSC function, the following emergency equipment ts located in OSC storage locations e Radmt:on Monitonng Team Kit e Po'(aale Radios e Protective Clothing
- Respiratory Protection Access to additional HP and maintenance equipment is readily available to obtain specific materials required to perform OSC functions.
7.5. Reserved 7.6. Reserved 7.7. Emergency Eouioment Emergency equipment is stored at various on-site locations, including the control rooms,- TSC/OSC, access points and the EOF. l I For a representative list of emergency equipment, see Appendix E. Emergency equipment is maintained in accordance with station procedures. l 7.7.1. Emergency Response Data System (ERDS) The ERDS, established in accordance with regulatory guidance, is provided via electronic data transfer. An ERDS link is initiated within an hour of an ALERT or higher emergency notification. 7.8. Security Posts The security posts that are established and used during an emergency are addressed in general terms to avoid disclosing safeguards information. More specific information is contained in the proprietary Security Plan and procedures. The Station Security Department primary objectives during an emergency are to maintain adequate station security, facilitate the evacuation of the protected area and outlying areas, and to assist with 3mergency communications, as necessary. Either the Central or Secondary Alarm Station will become the Secunty Command Console if an emergency occurs and will function as an on-site emergency communications dunng the first 60 minutes while the SERO is being Millstone Emergency Plan Revision 24 7-7 December 1997 I. I L___-__-______
activated Security computer card readers units are used to perform the accountability for the protected area 7g Joint Media Centat The Joint Media Center is located within the State EOC in Hartford, Connecticut. The Joint Media Center is activated by the State OEM as the pnnetpal media contact point for the utihty, the state and local communities during a SITE AREA EMERGENCY, GENERAL EMERGENCY, or other incidents that may generate high media interest. State and licensee plans do not include use of the Station EOF for a media center, however limited space is available for media briefings or conferences at the facility. 7.10. Afternate Location An alternate location is designated for off-site officials who are unable to reach the EOF due to radiological or environmental conditions near the EOF. The Attemate Location is physically located at the headquarters of Northeast Utilities at 107 Seiden Street, Berlin, Connecticut. The Afternate Location has communications capability with the site emergency response facilities (i.e., EOF. TSC, control room, etc.). There is enough space to accommodate off-stte officials requiring access to site emergency managers. ( 7.11. Communication Systems l The communication links between emergency response centers and off-site J agencies are shown in Figures 7 ia through 7-1c. The tie 4ine telephone communications to licensee Corporate Headquarters are based on land-line and l microwave systems. These systems provide reliable communications l and consist of a combination of the station PA system, emergency alarm, intraplant telephones, computer terminals, dedicated hotlines, commercial and utility (tie 4ine) telephones, facsimile machines, and two-way radios including utility, State Police, Waterford Police, and CONVEX (Connecticut Valley Exchange) radio communications. In addition, the Station has NRC dedicated telephone system lines installed in the control rooms, EOF and TSC, Two-way radio communications are used f.o maintain communication betwee.) the EOF and RMTs. Police and utility radio communication are used by the Control Room in the event of the failure of the telephone system for off site communications. Backup power is maintained for selected communication links in the protected area and the EOF. Ambulances are equipped with radios and can communicate with the hospital. Normal communication between the station and off-site medical facilities w over commercial telephone. There are also, hotline telephones between the ' units 1 and 3 Control Rooms Central Alarm Station and EOF to the State Police, Waterford Police / Waterford Emergency Communications Center Mdistone Emergency Plan Revision 24 I ! 78 December 1997 l I i ( - - - - - --------
j I The states of New York and Rhode Island are within the 60 tmfe ingestion pathway EPZ and are contacted through the Connecticut OEM and State Police as desenbed in the State RERP. Fishers Island and Plum Island, New York, are within the plume exposure EPZ and are notified of emergency events via ENRS radiopager. 7.12 Amnsment Fagigg Appropriate on site and off site monitonng instruments and laboratory fac,9t'es needed to analyze an accident are available 24 hours per day and are listed *n Appendix H. Tables H-1 and H-2. The MRDA and MRCA will coordinate the collection of sample media by the Radiological Monitoring Teams (RMTs). The RMTs will return samples to the EOF for analysis when directed. Appendix 8 provides letters of agreement with pnvate laboratory facilities specified in Table H 2. Post accident environmental sampfes are collected by responsit..e state agencies and analyzed by the State Health Department laboratory. The licensee l will assist the State of Connecticut in the collection of environmental samples under direction and control of the Department of Environmental Protection, as f requested. l 7.13. First Aid and Medical Facilities 24-hour per day first aid services are provided by EMT qualified personnel. First Aid supplies and equipment are stored in various locations throughout the j station. The Site Medical Facility is also available during selected hours, which may provide equipment and personnel to assist in medical emergencies. 7.14. Damaoe Cnntrol Eouipment Damage control equipment consisting of fire hydran's, fire hose stations, fire extinguishers, and portable lanterns are providec' uroughout the station for fire fighting. Self-contained breathing apparatus is located strategically throughout the station for fire fighting, entry into airborne radioactivity or toxic gas areas. Selected equipment spare parts are stored in the warehouse for emergency repairs. Tools and equipment required for equipment maintenance are available in the maintenance shops. 7.15 Meteorotocical Data Acquisition
.The Millstone site has a primary meteorologicalinstallation consisting of a 450-foot instrumented tower, a chmate-controlled shelter, and a computenzed data acquisition system. Wind speed ar i direction are measured at four different levels: 33,142,374, and 447 feet. Vertical temperature difference is measured at 142,374, and 447 foot levels. the verticalintervalin all three cases is measured from a baseline height of 33 feet. The critical parameters of wind speed, wind direction, and a measure of atmospheric stabdny are continuou available in the control rooms and at the base of the mensological tower. Other non-critical meteorological parameters are a!so measured.
Mdistone Emergency Plan Revision 24 l 79 Apol1998 Change st2 l - - _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ - ___ __
7 The site has a backup meteorological monitonng system, located at tha l southwest comer of the training facility The system consists of a 10 meter instrumented mast, a climate-controlled shelter, and a backup computerized data ,l acquisition system. Additionalinformation may be obtained frorn a weather service organization, listed in Appendix B. The primary source of meteorological data used by the meteorological team is the EDAN system, an electronic data acquisition network. If EDAN is inoperative, the entical data may be obtained over the telephone from operators reading Unit 3 Plant Process Computer data. Should the primary meteorological tower instruments not be operating properly, the backup meteorological installation located near the training building may be used. If both on-site systems are inoperative, arrangements have been made to obtain information from the assisting weather service organization. Millstone Emergency Plan f Revision 24 l 7-10 December 1997 I
TABLE 7-1 LOCATIONS OF EMERGENCY RESPONSE ' 'lTERS On site Location i Control Room Unit 1,2. and 3 Control Room
- 2. Assembly Areas (as necessary) Buildings and parking lots adjacent to the North and South Access Points
- 3. Technical Support Center / Adjacent to and below Unit 3 Control Operational Support Center Bldg. OSC Assembly Area Bldg. 475.
- 4. Emergency Operations Facility Just off the Site Access Road Off site Location Attemate Location Corporate Headquarters (Berlin) 1.
Connecticut State Armory (Hartford) /
- 2. Joint Media Center State Emergency Operations Center Connecticut State Armory (Hartford) 3.
Local Community Emergency Refer to the Local Community 4. Operations Centers Radiological Emergency Response Procedures I 1 1 l l
%Ilstone Emergency P:an Revision 24 7 11 December 1997
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