ML19350B709

Amend 41 to PSAR

ML19350B709
Person / Time
Site:	05000471
Issue date:	03/16/1981
From:	BOSTON EDISON CO.
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ML19350B708	List: ML19350B707 ML19350B709
References
NUDOCS 8103230461
Download: ML19350B709 (100)

Text

E O Amendment 41 March 16,-1981 l

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O Pilgrim Station Unit 2 Preliminary Safety Analysis Reporr O

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, BOSTON EOlsON COMPANY B00 BovLaTcN STREET BosTcN, MASSACHUSETTS C2199  !

i,".*^,",,"**" Marchlp,1981 aw.

Director of Nuclear Reactor Regulation Attention: Mr. F. Miraglia, Chief Licensing Branch No. 3 U. S. Nuclear Regulatory Commission -

Washington, D. C. 20555

, PSAR Amendment No. 41 to License Application Filed 12/21/73 (Docket No. 50-471)

Reference:

(a) NRC letter dated March 3, 1981 from R. L. Tedesco to R. M. Butler

Dear Mr. Miraglia:

Pursuant to the Atomic Energy Act of 1954, as amended, and the Comission's Rules ~ and Regulations issued thereunder, Boston Edison Cogany hereby L supplements and amends the License Application filed December 21, 1973 by supplying the attached PSAR Anendrrent No. 41.

This Amendment incorporates into the PSAR revisions to Section 13 which provides the responses to the NRC questions on Amendment No. 40, Emergency Planning, which were forwarde'd by reference (a).

This transmittal consists of three (3) signed originals and sixty (60) copies of Attachment #1 (PSAR Ameedment No. 41).

i Very truly yours, v/

Commonwealth of Massachusetts) l County of Suffolk' )

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-p Then per< inally appeared before me J. Edward Howard, who being duly sworn, did state that he is Vice President-Nuclear of Boston Edison Cogany, an V Applicant herein, that he is duly authorized to execute and file the within Amendment in the name and on behalf of Boston Edf son comany and the other '

Applicants herein and that the statenents in said letter are true to the best of his knolwedge and belief.

bhBh Notary Putlic m2)

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My Connission Expires: [u// 4, / f/M

BOSTON EDISON COMPANY PSAR DISTRIBUTION LIST:

George H. Lewald, Esq. Les W. Cooley (3 copies)

\ Thomas G. Dignan, Esq. EDS Nuclear d Ropes & Gray 220 tiontgomery Street 225 Franklin Street San Francisco, CA 94104 Boston,11A 02110 L. G. Cummings, Vice President The Board of Selectmen Marsh & McLennan, Inc.

s Town of Plymouth 1221 Avenue of the Americas

11 Lincoln Street New York, New York 10020 1 Plymouth,liA 02360

.

W. R. Bisson, Vice President Robert H. Culp Montaup Electric Company Lowenstein, Newman, Reis, P. O. Box 391 Axelrad & Toll Fall River, MA 02722 1025 Connecticut Ave., NW Suite 1214 G. D. Gowdy, Project Engineer Washington, D.C. 20036 Stone & Webster Engineering Corp.

P. O. Box 2325 Charles Brinknan, Manager Boston, MA 02107 Combustion Engineering Inc.

Nuclear Licensing Office Combustion Engineering, Inc.

Triangle Towers 1000 Prospect Hill Road Suite A-1 Windsor, CT 06095 4853 Cordell Ave. Attn: Mr. E. P. Mailman (16 copies)

Bethesda,itD 20014 Robert Wanczyk Charles Bardes Yankee Atomic Electric Company NELIA Seabrook Nuclear Station The Exchange 20 Turnpike Road i Farmington Avenue liestboro, MA 01581 4

Farmington. CT 06032 Thomas C. Stewart J. E. Booker it&fi Protection Consultants Gulf State Utilities Co. 200 Clarendon Street Post Office Box 2951 Boston, MA 02116 O Beaumont, Texas 77704 John J. Carney Bruce W. McKinnon, Manager Community Power Development Dept.

Nuclear Energy Property Mass. Municipal Wholesale Electric Co.

Insurance Association Stony Brook Energy Center 85 Woodland Street P. O. Box 426 Hartford, CT 06102 Ludlow, MA 01056

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Dr. Charles Cole John L. McLean Holdsworth Hall - Natural Teledyne Engineering Services Resources Center 303 Bear Hill Road p 'Amherst, MA 01002 llaltham, MA 02154 V

l COSTON EDISON COMPANY '

I PSAR Distribution 2.

Loren K. Stanley Anthony D. Cortese, Comissioner Nuclear Services Corp. Dept. of Environmental 477 Division Street Quality Engineering Campbell, CA 95008 100 Cambridge Street Boston, PA 02108

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Hilliam H. Dormer Mass. Dept. of Public Safety Paul Goman  !

1010 Comonwealth Ave. C. T. Pain, Inc.

Boston, MA 02215 101 Huntington Ave. - 8th Floor O Directorate of Licensing Boston, MA 02199 i

U.S. Nuclear Regulatory Commission John D. Fassett, President  !

Phillips Building The United Illuminating Co.

7920 Norfolk Avenue 80 Tenple Street ,

Bethesda, MD 20034 New Haven, CT 06506 Attention: Dino Scaletti (63 copies)

Phillip C. Otness, General Mgr.

Gerald S. Parker Mass. Municipal Wholesale Electric Co.

Director, Radiation Control Programs Stony Brook Energy Center i Mass. Dept. of Public Health P. O. Box 426  ;

Room 835 - 80 Boylston Street Ludlow, MA 01506 Boston, itA 02116 O Bechtel Power Corporation (32 copies)

Dean P. Amidon Mass. Dept. of Public Works Division of Waterways

Post Office Box 3965 c/o Central Receiving 100 Nashua Street, Room 529 San Francisco, CA 94119 Boston, MA 02114 l Attention: Mr. B. N. Pusheck

Gerald E. Anderson, President l

New Bedford Gas & Edison Light Co.

P. O. Box 190 i

Canbridge, PA 02139 Ralph M. Wood, Esq.

! m Public Service Conpany of N.H.

1000 Elm Street i

Manchester, NH- 03105

! Neil Todreas l Nuclear Engineering Dept.

(~- Room 24-109 l Mass. ' Institute of Technology

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77 Passachusetts Ave.

l Cambridge, MA 02139 l Joel Watson i Environmental Retaarch & Technology

696 Virginia Road l

-Concord,t% 01742

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COBTON EDISON COMPANY  !

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- v SERVICE LIST f

Andrew C. Goodhope, Esq. William S. Abbott, Esq.

• Chairman, Atomic Safety 50 Congress Street, S925 O and 1.4 censing Board U.S. Nuclear Regulatory Comission Boston, MA 02109 Edward L. Selgrade. Esq.

Washington, D.C. 20555 Patrick J. Kenny, Esq.

Mr. A. Dixon Callihan Mass. Office of Energy Resources Union Carbide Corporation 73 Tremont Street i O Post Office Box Y Oak Ridge, TN 37830 Boston, MA 02108 Office of the Secretary l

Dr. Richard F. Cole Docketing and Service Section Atomic Safety & Licensing Board U.S. Nuclear Regulatory Comission U.S. Nuclear Regulatory Comission Washington, D.C. 20555 Washington, D.C. 20555 Chief Librarian Stephan M. Leonard, Esq. Plymouth Public Library JoAnn Shotwell, Esq. florth Street Francis S. Wright, Esq. Plymouth, MA 02360 Assistant Attorney General l Commonwealth of Massachusetts Environnental Protection Div.

One Ashburton Place Boston, MA 02108 Atomic Safety & Licensing Board U.S. Nuclear Regulatory Conmission Washington, D.C. 20555 -

Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Richard J. Goddard, Esq.

Office of the Executive Legal Director U.S. Nuclear Regulatory Comission -  ;

O- Washington, D.C. 20555 Henry Herman, Esq.

. 50 Congress Street Boston, f% 02109 Mr. & Mrs. Alan R. Cleeton 22 Macintosh Street Franklin, MA 02038 O

l sonroN EoisDN COMPANY ,

INTERflAL PSAR DIST. LIST J. R. Stevens A. F. Corry 9 J. M. Lydon J. E. Howard R. J. DeLoach

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A. V. Morisi  ;

l W. F. Hickey i l R. M. Butler l G. M. McHugh ,

D. A. Bryant i

11. F. Brannan C. H. Minott J. W. Ashkar i S. Maloney ,

I P. P. O'Brien l l

R. D. Nachon l

! P. M. Ilolzaan J. Pawlak j H. R. Balfour BECo Librarian V. J. Zukauskas W. J. Merritt J. Vorees G. J. Davis l F. J. Wiedenmann .

W. S. Stowe (For Service List Dist.) (

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PS PSAR l.

I PILGRIM STATION UNIT 2

PRELIMINARY SAFETY ANALYSIS REPORT Amendment 41, March 16, 1981 The change pages included in this Amendment comprise pages changed in response to NRC comments.

All pages supplied with this Amendment are identified by the Amend-l ment number and date in the upper outside corner of each page. The type of correction on each changed page is identified as follows:

Question response pages are indicated by a vertical change bar in the outside margin of the page opposite the changed text area. The Amendment number and NRC question number (where applicable) are i shown to the side of the change bar for ready cross reference between the corresponding NRC question and the affected text. Where no specific NRC question is involved in a text change (as for instance

! in general update changes), only the vertical change bar and Amend-ment number are used to identify changed text areas. If complete i new paragraphs are inserted, the change bar and queution number are 4

placed opposite the paragraph heading only. Succeeding pages of the new material do not contain the change bar.

All-insert material is collated in the order in which it will be inserted in its respective chapter.

4 The following Change Page Instructions sheet should be used as a

guide for the removal of old pages and insertion of change pages for l this Amendment. 7. separate instruction sheet is provided for each chapter. These instructions will serve as a permanent record of the affected pages of this Amendment and should be placed at the end of L

the respective chapter following the yellow NRC Question tab page.

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^ The new title page supplied should replace the old title page in

Volume I. This general instruction page should also be placed

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following the new title page, after the instruction pages for the l

previous amendment.

!O num )

l Instructions-1

1 AMENDMEi.T 41 PS PSAR March 16, 1981

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CIIANGE PAGE INSTRUCTIONS I VOLUME IX l CHAPTER 13 i Remove Insert i

13.3-1/13.3-2 13.3-1/13.3-2 j

() 13.3-11/13.3-12 13.3-11/13.3-12 f 13.3-17/13.3-18 and 13.3-17/ Blank thru 13.3-19/13.3-20 13.3-19/13.3-20 j 13.3-33/13.3-34 13.3-33/13.3-34

! 13.3-39/13.3-40 thru 13.3-39/13.3-40 thru l 13.3-57/13.3-58 13.3-58A/ Blank  ;

13.3-61/13.3-62 thru 13.3-61/13.3-62 thru 13.3-65/13.3-66 13.3-65/13.3-66 Figures 13.3-4 thru 13.3-6 Figures 13.3-4 thru 13.3-6

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13A-i/ Blank thru 13-i/ Blank thru 13A-1/13A-2 13A-1/13A-2 13A-9/13A-10 13A-9/13A-10  ;

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'13A-10A/ Blank and '

i 13A-10B/ Blank l

13A-ll/13-12 and 13A-ll/13A-12 and '

13A-13/13A-14 13A-13/13A-14 13A-31/13A-32 thru 13A-31/13A-32 thru

() 13A-37/13A-38 13A-37/13A-38 13A-63/13A-64 i 13A-63/13A-64

____ 13A-99/13A-100 thru 13A-105/ Blank -

a O AM29.13-9/ Blank AM29.13-9/AM41.13-10 4

thru AM41.13-19/ Blank AM41.13-i/ Blank

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I PS PSAR AMENDMENT 29 February 24, 1977 O TABLE OF CONTENTS 1 '

f CHAPTER 13 - VOLUME XI ,.

CONDUCT OF OPERATIONS Section Title Page 13.1 ORGANIZATIONAL STRUCTURE 13.1-1

() 13.1.1 CORPORATE ORGANIZATION 13.1-1 13.1.1.1 Corporare Functions, Responsibilities 13.1-1 and Authorities 13.1.1.2 Applicant's In-House Organization 13.1-3 l 13.1.2 NORMAL STATION SHIFT CREW COMPOSITION 13.1-13 t

- 13.1.3 QUALIFICATION REQUIREMENTS FOR STATION 13.1-14 PERSONNEL 13.1.4 INTERRELATIONSHIPS WITH CONTRACTORS 13.1-14

() 13.1.5 AND SUPPLIERS APPLICANT'S TECHNICAL STAFF 13.1-14 13.2 TRAINING PROGRAM 13.2-1

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13.2.1 PROGRAM DESCRIPTION 13.2-1 13.2.1.1 Basic Mathematics 13.2-1 13.2.1.2 Basic Nuclear Technology 13.2-1 13.2.1.3 Power Plant Observation 13.2-1 i

() 13.2.1.4 13.2.1.5 Design Lecture Series Simulator Training Program

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13.2-2 13.2-2 13.2.1.6 On-Site Training 13.2-3

() 13.2.1.7 Nuclear Engineering Work Experience Radiochemistry Training 13.2-3 13.2-3 13.2.1.8 13.2.1.9 Instrumentation and Control Training 13.2-4 7

.13.2.1.10 Radiation Safety Training 13.2-4 Volume XI i 13-1 i

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AMENOMENT 41 PS PSAR Maren vi, 1981 )

Section Title Page 13.2.2 RECORDS 13.2-4 13.3 DISCUSSION OF PRELIMINARY PLANS 13.3-1 FOR COPING WITH EMERGENCIES 13.

3.1 INTRODUCTION

13.3-1 13.3.1.1 Purpose 13.3-1 13.3.1.2 Scope and Aoplicability 13.3-2 13.3.1.3 Concept of Ocerations 13.3-6 13.3.1.4 General Information 13.3-8 13.3.2 ORGANIZATION, FACILITIES, AND SUPPORT 13.3-10 SERVICES 13.3.2.1 Participants in the Emergency Procram 13.3-10 13.3.2.2 Boston Edison Emercency Response 13.3-17A Organization 13.3.2.3 Emergency Facilities and Equipment 13.3-26 13.3.3 EMERGENCY CONDITIONS 13.3-32 13.3.3.1 Classification System 13.3-32 13.3.3.2 Personnel Emergency 13.3-33 13.3.3.3 Unusual Event 13.3-34

. 3.3.4 Alert 13.3-34 13.3.3.5 Site Emergency 13.3-35 13.3.3.6 General Emeroency 13.3-35 13.3.4 NOTIFICATION AND COMMUNICATION 13.3-37 13.3.4.1 BECo Actions 13.3-37 13.3.4.2 Coordination with Participating Agencies 13.3-38 13.3.4.3 Content of Messages 13.3-40A 13.3.4.4 Communications Equipment 13.3-41 Volume XI 9

13-ii l

PS PSAR AMENDMENT 41 March 16, 1981 Title Page Section Testing 13.3-41 13.3.4.5 RESPONSE TO ACCIDENT CONDITIONS 13.3-42 13.3.5 13.3.5.1 Accident Assessment 13.3-42 13.3.5.2 Emergency Monitoring 13.3-46 13.'3.5.3 Protective Action Guides 13.3-46 13.3.5.4 Protective Response 13.3-47 13.3.5.5 Radiological Exposure Control 13.3-52 13.3.5.6 Recordkeeping 13.3-56 13.3.5.7 Recovery and Reentry 13.3-56 13.3.6 PUBLIC INFORMATION 13.3-57 13.3.6.1 Preparatory Public Education Program 13.3-57 13.3.6.2 BECo Public Information Programs for 13.3-58 l O Emergencies MAINTAINING EMERGENCY PREPAREDNESS 13.3-59 13.3.7 13.3.7.1 Drills and Exercises 13.3-59 i

13.3.7.2 Emergency Response Training 13.3-61 f

13.3.7.3 Planning Effort Development 13.3-65 i

13.3.8 LETTERS OF AGREEMENT 13.3-66 t

13. REVIEW AND AUDIT 13.4-1

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13.5. STATION PROCEDURES 13.5-1 13.6 PLANT RECORDS 13.6-1  ;

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13.6.1 PIANT HISTORY 13.6-1 .

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() .13.6.2 OPERATING P' CORDS ' -13.6-1 13.6-1

13.6.3 EVENT RECC RDS -

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', 13.7' INDUSTRIAL SECURITY' O

' Volume XI i

13-111-

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AMENDMENT 41 PS PSAR March 16, 1981 Section Tith Page 13.7._ PERSONNEL AND FACILITY DESIGN 13,7-1 13.7.2 SECURITY PLAN 13.7-2 Appendices 13A EVACUA'1.0N CLEAR TIMES ESTIMATES 13A-1 l

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O Volume XI 13-iv

PS PSAR AMENDMENT 41 March 16, 1981 13.3 DISCUSSION OF PRELIMINARY PLANS FOR COPING WITH EMERGENCIES 40 l

4 13.

3.1 INTRODUCTION

( 13.3.1.1 Purpose Section 13.3 of tne PSAR is intended to generally descrioe tne emergency plans being developed for Pilgrim 2. Tnis section is not

' intended to be a detalleo fin't ~mergency plan for Pilgrim 2.

Tne Emergency Program for Pilgrim 2 will consist of a plant

Emergency Plan anc af f-site emergency plans (tnat will include tne Massacnusetts Comprenensive Emergency Response Plan, witn appendices for all towns in tne plume exposure EPZ, tn e Rn ode Islano Nuclear 41 Facility Incident Evacuation Plan, and agreements to respono Oy other groups) to provide for protection of plant personnel and tne general public in tne event of an incident. Specifically, tn e purpose of the Pilgrim 2 Emergency Plan, th e Commonwealtn of Massacnusetts Comprenensive Emergency Response Plan and tne Rnode Island Nuclear Facility Incident Evacuation Plan will be to assure 41 tnat the following emergency planning goals are acnieveo

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1) Timely and accurate assessment of an emergency condition and proper notifiestion of responsible autnorities.

2) E f fective coordination of emergency activities s'e.ung all l

organizations naving a response role.

3) Continued assessment of actual or potential consequences botn on-site and oft-site.

4) E f fective implementation of emergency measures in tne environs.

5)' Continued maintenance of an adequate state of emergency preparedness.

13.3-1

AMENDME NT 40 PS PSAR Octooer 10, 1960 An integral part of planning for protective action will oe tn e role played oy agencies of tne Commonwealtn o f Massacn usetts, tn e Town o f Plymoutn , anc otner towns in tne plume exposure emergency planning zone. Under State law, eacn of tnese towns is a required participant in tn e State plan. Letters of agreement from town and state officials are containea in Section 13.3.6. Letters from nospitals, federal agencies, anc otn er response organizat ons are also included in Section 13.3.8. Tne Plume Exposure Emergency Planning Zone is snown in Figure 13.3-1. Tn e Ingestion Patn way EPZ is snown in Figure 13.3-2.

13.3.1.2 Scope and Applicability Section 13.3 cescrioes tne plans tnat will exist for coping witn emergencies tn at may arise at oilgrim 2. Tn e following discussion is intended to satisfy tne requirements cf 10 CFR 50.34(a)(6) and 10 CFR 50 Appena1x E.

As provided in 10 CFR 50 Appencix E, tn e PSAR must contain

" sufficient information to ensure tne compatioility of proposed emergency plans for botn on-site areas and tn e E PZ s , w i tn facility design features, site layout and site location witn respect to suen considerations as access routes, surrouncing population distrioutions, lana use ana local jurisdictional counaarles for tne EPZs". Fu r tn e rmo re , tn e PSAR must provice suf ficient information to sn o w "tn e means oy wn icn tn e standarcs o f 10 CFR Part 50.47(o) will be met". Finally, tne PSAR is also expected to provide aescriptions o f items A tn rougn H in Section 11 of Appenaix E to 10 CFR 50. Tn e following discussion identifies wnere in Section 13.3 tnis information is providen.

An integral part of tne development of tne proposea emergency plans for on-site areas ano EPZs nas oeen assuring tnat tne proposed plans are compatiole witn facility design features, site layout ano site location. Specific 9

13.3-2

l I PS PSAR AMENDMENT 41 March 16, 1981  ;

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() 4) Mobilization of the Boston Edison Company Emergency Response Organization '

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5) Continuing data collection, duse projection, and  !

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assessment actions; and  ;

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6) Recovery and re-entry.

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() Tne BECo Emergency Response Organization is oescribed in detail in Section 13.3.2.2.

13.3.2.1.2 Massacnusetts State Aaencies 41 i Ine functions -of state agencies during emergency conditions are descrioed in tne Massacnusetts Comprenensive Emergency  ;

! Respons2LPlan. Tne responsibilities of principal agencies are.

i defined tn erein. ' Figure 13.3-3 illustrates use Commonwealtn of (I Massacnusetts Emergency Response Organization.

13.3.2.1.2.1 Department of Public Healtn

-The Department of Puolic Healtn (DPH) is tne state agency witn tecnnical expertise in matters of radiation protection. Tn e .

.DPH will De. tne lead .tecnnical agency for any- emergency response tnat. involves state ano local. agencies. Inis emergency response will be conducted in accordance ~ witn tne Commonwealtn of L

() Massacnusetts Radioloaical Emeraency Response Plan for -Fixeo Site Nuclear Facilities, prepared by. tne Massacnusetts Civil Defense JAgency.

Tne MDPH in cooperation Lwitn tne Massacnusetts State Police,

() y nas _ organized a~ Nuclear Incident Advisory Team (NIAT) consisting

'of MDPH staff, advisors and consultants drawn from private, state, and federal institutions wno are expert in tne various aspects of emergencies involving raoloactive materials. In ble event. o f .a

() raolation emergency, alerted by eitner tne MDPH or f tne State

? Police, teams will be dispatened i

13.3-11 .

AMENDMENT 40 PS PSAR l October 10, 1980 to the plant site to assist in the monitoring and assessment j activities. At the site they will be based at the Emergency Operations Facility. MDPH's responsibilities include:

1) Activate and coordinate the Nuclear Incident Advisory Team (NIAT);

2) Assist in determining the extent and magnitude of the emergency; and

3) Recommend protective actions to control and limit public exposure.

13.3.2.1.2.2 Commonwealth of Massachusetts Civil Defense Agency Tne Massachusetts Civil Defense Agency (MCDA) will have the principal authority and expertise to coordinate the resources of

'; tate government during an emergency. Th ese responsibilities include:

1) Assist Of fices of Emergency Preparedness in Plymouth and surrounding towns in implementing protective actions recommended by MDPH (by law, each town is considered a participant in the State plan, and town plan documents are included in tne State plan documents);

2) Coordinate evacuation activities connected with reception towns; and

3) Develop and update the state government plan for dealing with radiation emergencies.

O 13.3-12

i PS PSAR AMENDMENT 41 March 16, 1981 13.3.2.1.6.? Jordan Hospital, Plymoutn 0 Hospital fac111 tics and medical personnel wi1+ oe available at Jordan Scspital in Plymoutn . Section 13.3.8 cor tains tne agreement witn tne nospital staf f to receive and treat cases of O' radiation exposure or contamination.

13.3.2.1.6.3 Sn riners Hosplia.} for Crippled Cnildren Burns Institute - Bostbn Unit Tne Burns Inst 3 tute will provide emergency medical services in accordance witn tne agreement in Section 13.3.8. Inis facility is eauipped to deal witn radiation related injuries on a long-term basis.

13.3.2.1.6.4 Tn e Cniloren's Hospital Medical Center Clinical Genetics Division O Tne Cnildren's Hospital will provide consultation in genetics. Tecnnical support from tne cytogenetics laboratory will also oe made availaole. Section 13.3.8 contains die letter of agreement.

13.3.2.1.7 State of Rnode Islano i .

l Portions of the State of Rnode Is1 ;1d lie witnin tne Ingestion Path way EPZ. Tne State of Rnoce Islano Defense Civil

() Preparedness Agency has prepared tne Rnode Island Nuclear Facility Incident Evacuation Plan. In tne event of an emergency at Pilgrim Station, the Rnode Island Defense Civil Prepareoness Agency will be 41

~~ notified by eitner Boston Edison Company (Emergency Director) or

, (_,/ tne Massacnusetts Civil Defense 4gency, depending on tne level of Emergency. Emergency Response in tne State of Rnode Island will be carried out in accordance witn tne above plan. Tn e Rn ode Island Plan provides for tne coordinated ef forts of all cities and

) towns and several state agencies, including tne following:

! 13.3-17 i

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-,-r, . ~ - - .- . , , , _ , , _ , , _ , , , _ _ , , . , . . , , . ,_ - _ , _ _ _ , , , _ , , , , , _ _ , ,- _ _ _ , _ , ,

PS PSAR AMENDMENT 41 March 16, 1981

1) Defense Civil Prepareoness Agency

() 2) 3)

Department of Healtn Department of Transportation

4) State Police 73 5) National Guard

) 6) Civil Air Patrol Tne Rnoce Islano plan is comparaD1e to tne Massacnusetts plan in tn e following respects: 41 (v)

1) Tne Defense Civil Preparedness Agency will carry out a coordination and communication function.

2) Tne Department of Public He altn will supply principal expertise in matters of radiation protection and need to tax e protective action.

3) Tne Governor will taxe cnarge of tne entire ef fort of state government as soon as ne is availaole to ao so.

13.3.2.2 Boston Edison Emergency Response Organization Tne BECo Emergency Response Organ 17ation will consist of tne On-site Emergency Organization and a Hecovery Organization (o f f-site) . BECo on-snif t responsio111 ties for emergency response will be unambiguously defined. Adecuate staffing to provioe initial facility accident response in key functional areas will oe maintained at all times. Timely augmentation of response

[}'- '

Interfaces among various on-site capabilities will be available.

response activities and off-site support ano response activities will be specified.

13.3.2.2.1 On-site Emergency Organization An emergency operating organization composed of plant personnel s

j will be designated ano trained to augment tne snif t operating personnel. Tne anticipated Pilgrim 2 Emergency ' Organization is 13.3-17A

AMENDMENT 41 PS PSAR March 16, 1981 provided in Figure 13.3-4. Provisions will be made for rapid assignment of otner plant personnel to tne emergency operating organization as required. In all emergencies, tn e on-duty Waten Engineer or any of his supervisors, if present, will classify an emergency and initiate the Pilgrim 2 Emergency Plan. Tne normal snif t operating group will be trained to be self-reliant so tnat otner plant personnel assigned to tne emergency operating organization will nave suf ficient time to assemble and to integrate smootnly into tne emergency operations.

Tne minimum staf fing requirements of Taole B-1 of NUREG-0654 cill be satisfied. Tn e station work force is capable of readily achieving tne minimum levels during normal working nours. During otn er periods , including nign ts and week ends, tn e minimum on-sn i f staff will be augmented from tne following groups:

41

1) Of f-snif t Pilgrim 2 sta f f,

2) O f f-sn if t Pilgrim 1 sta f f, and

3) Boston Edison Company neadouarters staf f.

Call lists will be developed, witn provisions for alternates, to augment tne station staf f in accordance witn tn e time ano functional requirements specified in Taole 8-1.

Tne positions in the on-site emergency response organization are as follows.

13.3.2.2.1.1 Emergency Director Tne Waten Engineer on duty at tne time tne emergency condition crises will become tne Emergency Director and will be in command of the on-site emergency organization until relieved oy a designated member of the Plant Operations Review Committee (normally to be tne Manager of Nuclear Operations). If tne Waten Engineer oecomes incapacitated for any reason, tne Operating Supervisor will assume the responsibilities of tne Emergency Director until relieved by tne Manager of Nuclear Operations or nis designated alternate. In tne case of a nigner level emergency, tne Manager of Nuclear Operations may assume tne position of Emergency Director.

• 13.3-18

I PS PSAR AMENDMENT 40 October 10, 1980 Tne Emergency Director will be responsible for assessment of emergency situations, especially where tne emergency presents a real q or potential nazard to of f-site persons or property. It will De nis i responsibility to classify an emer- gency. Tne Emergency Director will make tne decision to notify and provide recommendations to authorities responsible for i

of f-site measures; tnis autnority will not be delegated. Regardless 1

of existing plans, tne judgment of tne Emergency Director will be

extremely important in assessing a:ergency situations and in taking appropriate protective and corrective actions. As sucn , h e will

implement the Pilgrim 2 Emergency Plan tn rougn tne use of Emergency Plan Implementing Procedures, and activate necessary and reaufeed portions of tne Emergency Organization.

Tne Emergency Director will be autnorizeo by Boston Edison Company to take all necessary actions witnin tne scope of

responsiollity of Boston Edison as defined oy tne Emergency Plan.

Alternates to assume tnis position will De identified in station procedures.

f

) 13.3.2.2.1.2 Shif t Tecnnical Advisor A Sn i f t Technical Advisor will be assigned to cover eacn operating snif t. He will nave specific training in plant responses to of f-normal events and transients. He will be trained in accident analysis of tne plant. Tn e Snif t Tecnnical Advisor will advise tne Waten Engineer on plant operating actions tnat can mitigate tne effects of an accioent.

13.3.2.2.1.3 Emergency Communications Coordinator Tne Emergency Communications Coordinator will report to tne Emergency Director. He will function as a ' liaison oetween tne Emergency Director, the BECo Emergency Coordinator, of f-site organizations and agencies, and tne on-site Emergency Organization (i.e. , -Tecnnical Support Center Supervisor, Operational Support Center Supervisor, ano tne Control Room).

13.3-19

AMENDMENT 40 PS PSAR October 10, 1980 j As required, tne Communications Coordinator will provide, using available equipment, reliaDie ano accurate communications. He will also maintain records of outgoing ano incoming communications.

13.3.2.2.1.4 Jynnical Support Center Supervisor Th e Tecn nica t Support Center Supervisor and nis staf f will report to the TSC in accordance witn station proccoures or as directed by tne Emergency Director. Tne tecnnical support personnel will analyze current ano projected plant status and, tn rougi dedicated communications witn the Emergency Director (at tne EOF) and tne Waten Engineer (in tne control room), provioe tecnnical support and recommendations regarding emergency actions.

13.3.2.2.1.5 TSC Staff Tne following personnel will be assemoled in tne TSC wnen required by procedure or wnen directed to do so by tne Emergency Director:

1) TSC Supervisor

2) Reactor Engineer

3) Healtn Physics Engineer

4) Technical Engineer / Communicator

5) Operating Engineer

6) Cn emical Engineer

7) Maintenance Engineer Tne Station Organization will designate individualc for tne above assignments.

13.3-20  ;

I

J PS PSAR AMENDMENT 41 March 16, 1981

() 3) Judgment of Emergency Director. Tne Emergency Director will declare an emergency of a given classification any time tnat, ir, nis juogment, th e l

plant status warrants sucn a decitration.

In an actual emergency, if tne above tnrer considerations indicate that more tnan one emergency class is applicable, blis will trigger declaration of an emergency of tne class wnicn is O tne most severe inoicated; 1.e., i f a.- E Al. indicates tn e occurrence of an Unusual Event, wnile tne Emergency Director's judgment indicates the existence of an Alert, tn en an Alert will be declared.

Eacn of ble emergency classes will be enaracterized by Emergency Action Levels (EALs). Except for tne Personnel Emergency class, tne EALs wili consist of specific sets of plant and environmental parameters (i.e., instrument indications, system status, etc.) wnien will be used to O. initiate. emergency class declaration, notification, and

-mobilization of emergency organizations. Tnese EALs will oe useo specifically to ootain early readiness status on tne part of emergency response personnel and emergency organizations.

Tne Emergency Director will nave tne_ ultimate responsibility to classify emergency conditions cased on tne EALs. He will also nave authority to oeclare an emergency condition based on _any event tnat may af fect tne safe operation of tne plant.

L13.3.3.2 Personnel Emergency Tnis class of emergency will include accidents or N occurrences wnicn ' involve. on-site treatment of injureo personnel:or off-site treatment of uncontaminated people. Tn is - 41 classificat.f.on will incluoe tnose situations wnich have no poentialLfor escalation to more severe erergency conditions.

O 13.3-33

AMENDMENT 41 PS PSAR March 16, 1981 13.3.3.3 Unusual Event Tne least severe of tne emergency classes tnat mignt reauire off-site notification is an Unusual Event. It will be classified as a conoition wnere a degracation of eitner nuclear fuel, reactor coolant system, or containment building nas occurred or may occur, resulting in a plant unit being placed in a made of operation as reouired by tne Tecnnical Specifica-tions. Tn e incident will oe classified as an Unusual Event only if tne event is a minor one at:0 no releases of raoioactive material requiring off-site response or monitoring are expecteo unless furtner degradation of safety systems occurs.

Some instances of personnel injuries will be included in tn e catetory. In cases wnere a contaminated individual must be 41 treated of f-site, tne situation will be classified as an unusual event.

BECo will take action as warranted by the event and as delineated by Emergency Plan Implementing Procedures.

Notification of agencies will be conducted for information purposes.

13.3.3.4 Alert An Alert will be classified as a conoition tnat is in process or nas occurred wnicn involves an actual or potential substantial degradation of tne level of safety of tne plant. Th is classification includes tnose events tnat could oe associated witn limited releases of racloactive material.

Tne Alert class will include emergency situations tnat are expected to be minor in nature, out wnere it nas been deemed prudent to notify some of f-site emergency participants and mobilize a portion of tne Emergency Organization. Because o f tn e nature of tne Alert class (possiole limited releases of racioactive material), assessment actions will be initiated.

O 13.3-34

AMENDMENT 40 PS PSAR October 10, 1980 13.3.4.2.1 Massachusetts State Police i

Upon decoaration of an emergency the Mas 2achusetts State Police will be notified by radio telephone from the Pilgrim 2 O Control Room and requested to notify the Massachusetts Department of Public Health, Massachusetts Civil Defense Agency. The message will be received at the Middleboro State Police Barracks. As part of the detailed planning process, the l content of initial and followup messages will be established.

After notification of MCDA and MDPH has been made, the State Police in Middleboro will notify town Police Departments and stand by in readiness to assist them in traffic control and evacuation as needed.

13.3.4.2.2 Massacnusetts Department of Public Health In the event of a radiological emergency, a member of the Bureau of Radiation Control of the Massachusetts Department of

() Public Health will be notified by the State Police.

The NI AT team will be alerted by either the MDPH or the State Police. NIAT groups will be dispatched to the plant site to assist i in the monitoring and assessment activities.

13.3.4.2.3 Massachusetts Civil Defense Agency l

l The MCDA will be notified by the State Police, except in the case of an Unusual Event, when BECo will notify them for informational purposes. MCDA will notify and mobilize its Regional Office. MCDA has communication capability with town agencies via the National Attack Warning System (NAWAS) and " fan out" notification procedures.

13.3.4.2.4 Local Agencies The Town of Plymouth Police Department- will be notified by the ud Pilgrim 2 Control Room. The Plymouth Of fice of Emergency 13.3-39

I AMENDMENT 40 October 10, 1980 PS PSAR Preparedness (POEP) will be notified by the Town of Plymoutn Police. POEP will be advised by MDPH (througn MCDA) of any protec-tive actions to be taken within areas defined by HDPH. Th e POEP Director will implement an emergency plan developed for the Town.

l The police departments of surrounding towns will be notified by tne State Police (ordinarily via the Law Enforcement Administrative l

l Police Radio). Directors of local Of fices of Emergency Preparedness l

l 1

l l

O l

l l

I l

O O

O 13.3-40

_- _ _ - _ _ . - - _ _ _ _ - _ - _ _ _ . - . =. . - -- --

AMENDMENT 41 1 PS PSAR March 16, 1981 will be notified by local police. Local directors of Of fices of s Emergency Preparedness will be advised by MDPH (tnrougn MCDA) of any protective actions to be taken. Local directors of Emergency Preparedness will implement emergency plans developeo for tnelt towns.

13.3.4.2.5 U.S. Coast Guard The U.S. Coast Guard will be notified by tne Pilgrim 2 Control O Room in tne case of a Site or General Emergency.

13.3.4.2.6 United States Department of Energy Radiological Assistance Program BECo or MDPH may request assistance from tne United States Department of Energy - Radiological Assistance Program (DDE-RAP) oy telepn one .

13.3.4.2.7 State of Rnode Island Tne State of R1 ode Island would normally be notified by tne BECo Recovery Manager or Emergency Coordinator ouring tne Second ,

Line notification process depicteo in Figure 13.3-6. Tnis would be accomplisned by telepnone communication to tne Scituate State Police 41 Headquarters. Tne MCDA can also contact tne Rnode Island State l Police by the NAWAS system. Tne MCDA can contact tne RIDCPA (Newport) via NAWAS or tne Civil Defense National Voice System (CDNVS), Civil Defense National Teletype System (CONATS), Civil

! Defense National Radio System (CDNARS) and by telepnone, l

i

/9 t

Q 13.3.4.3 Content of Messages The content of all initial and followup messages between BECo I

and agencies will be incluoed in emergency plans ano procedures.

Any message wnicn may foreseeably be used witn tne public (e.g. , via 13.3-40A l

PS PSAR AMENOMENT 40 October 10, 1980

~

electronic media) will be developed and incorporated into BECo plans

(]

's and procedures or agency plans and procedures, as appropriate.

13.3.4.4 Communications Equipment Is

Provisions will exist for prompt communications among principal response organizations to emergency personnel and to the public.

BECo will provide for suf ficient eauipment to assure primary and backup means of communication for the BECO Emergency Response

('^)

\/ Organization and for communication with the state, local and federal emergency response agencies. This will involve, as a minimum, combinations of the following communication systems: NRC Hot Line, other dedicated phone lines, radio telephone, conventional t ele ph one , voice powered telepnone, walkie-talkies, microwava communications, page boy beeper systems, station public address system, plant safety parameter communication and display, and other systems. State and local agencies will have at their disposal fs several systems for communication with each other and with oth ers

\

\ -) such as BECo and NRC. As a minimum, these systems will include combinations of the following: conventional telephones, radio telephones, walkie talkies, State Police Radio Network , Civil De fense Radio Network , National Attack Warning System (NAWAS, a dedicated land line telephone system), Law Enforcement Administrative Police System (LEAPS), and Radio Amateurs for Civil Emergencies System.

Communication with the public by state and local agencies will

,s be in accordanca with the Commonwealth of Massachusetts i )

( ,j Comprehensive Emergency Response Plan.

1 l

13.3.4.5 Testing l

,/-

(_,/ BECo will incorporate provisions for periodic testing of the communications eauipment into tne P1' grim 2 Operating Procedures.

For example, emergency call lists will be checked regularly. Also, i /x major drills and exercises will provide an opportunity for testing i t i N/ of eauipment and procedures for notification with organizations and between organizations.

13.3-41

AMENDMENT 41 PS PSAR March 16, 1981 13.3.5 Response to Accident Conoitions 13.3.5.1 Accident Assessment 0

Adeauate methods, systems and equioment for assessing ano monitoring actual or potential of f-site consecuences of a raciological emergency conoition will be in use.

Plant instrumentation will provide tne initial indication of tne occurrence of an accident. Tnese initial reaoings (sucre as containment pressure, containment raoloactivity, emergency core cooling status, etc.) will provide a basis for classifying accioents into one of the following categories:

e Unusual Event e Alert e Site Emergency e General Emergency Analyses will be performed to establisn tn e values of tn e K ey param-etors wnicn can be used for placing an accident situation into one of tn e four classifications. Pilgrim 2 Emergency Procedures will incluoe tne relationships between instrument readings and emergency class to enaole the Emergency Director to appropriately classify a spectrum of accidents. The Emerger.cy Action Levels wnicn will be used to classify events will be developeo in accordance with Crite-rion I.1 and Appendix 1 to NUREG-0654. Tn e metn odology ano proce- 41 Tes to be developed will use tne most easic indicators suitable for l .icssification purposes. Tne metnodology for site and general emarcency classification will not reauire calculations, analyses or otner personnel actions wnicn cannot be completed witnin 15 minutes during of f-normal working nours, including nign ts and week enos.

Pilgrim 2 will nave systems and instrumentation to provide initial vr.41ues and continuing indication of important radiation parameters througnout the course of tne accident. Tne capability and rosources will incluoe post-accident sampling capability, radiatico and effluent monitors, in-plant iodine instrumentation and cont ainment radiation monitoring in accordance witn NUREG 0578.

13.3-42

PS PSAR AMENDMENT 41 March 16, 1981 l At tne EOF, adeouate metnods, systems and equipment for l assese.'.ng ano monitoring actual or potential of f-site consecuences of l a raciation emerge 6:=, 111 De in use.

A system will also De provicea wnicn uses radiation ano effluent monitors, wey process monitors, meteorological instruments ana  :

computer naraware ano sof tware to enaole estimation of tne source of radioactivity availaole for release, cuantity and rate of releasea radioactivity, atmospieric dispersion of released racioactivity and i

nistorical and projected radiation ooses resulting from tne radioactive release.

Tne monitors aescribea in Regulatory Guice 1.97 Revision 2 for Type E variables will be used for making real-time dose projections.

Tne various raalation monitors laentifiea in Regulatory Guiae 1.97 (i.e., Containment Radiation, Area Radiation, Airborne Racioactive

'4aterials Releasea from Plant) will oe usea to provide tne oest 41 ouantitative estimte of released racioactivity. Tne meteorology variaoles iaentifiea in Regulatory Guide 1.97 will oe usea for cnaracterizing' atmospneric transport. Tne environs raalation and radioactivity ana acciaent sampling capability varisoles will also oe used to assess tne relet.s9s of radioactivity. Tne . projected ooses will oe 'aeterminea using tne variables laentifieo acove coupled. witn appropriate assumptions. Prior projections will oe updateo curing l tne course of tne event.

Tn e algoritn m wn icn will oe .useo for tne calculation of radiation dose is:

2 Dose = 1 Q i x %Q x DCFi wn e re Q is tne cuantity of raaloactivity releasea to tne a tmo spn e re ,

X/Q is tne atmospneric dispersion factor, l

DCF - is tne cose conversion f actor, and i

I b a

p 1 denotes values'applicaole to'racioisotope, 1.

i i

l' 13.3-43.

_,-_.._,,_,_..._.._s... . ,.. _ ,_..,,.... m _, _ . _ _ __ . , , . . _ , _ , , , - , _ , . , - , , _

AMENDMENT 41 PS PSAR March 16, 1981 Tne considerations for estimating eacn of tn e elements o f tn e algoritnm are discussed oelow 13.3.5.1.1 Radioactive Release Ine determination of racioactivity released to tn e environment aill De based on tne best availaole indicator. For example, tn e reading of tne plant vent monitor w111 De corre11ated witn raa10 activity release rate so tnat tne output from tnis monitor Can ce used to alrectly estimate tnis parameter. On tn e otn er n and, if a direct measure of radioactivity release rate is not available, tn e best availaole data will oe used to calculate tnis quantity. An example is radioactawity release rate from tne containment. Tn e containment raoiatio.- nonitor will initially oe used to estimate tne radioactivity inventory in tne containment. Tnis initial information elli De supplementeo by containment atmospn ere sampling. A containment 19a< rate will be estimateo cased on containment pressure. Tn ese will De used to estJmate tne radioactivity release rato.

13.3.5.1.2 Atmospn eric Dispersion Tne meteorological measurement system ano atmospneric dispersion element of the overall cose calculation and projection system will De implementeo according to the guicelines in Appendix 2 to NUREG-0654 R0 vision 1. Tne measurement system will oe in general accordance witn proposed Revision 1 to Regulatory Guioe 1.23. A primary and backup system will De provideo for tne parameters wnicn are required for use in tne estimation of alspersion. Items wn icn reaulre furtner evaluation are tne availability specifications and tne need for 41 rodundant computer systems. An analog backup for meteorological parameter recording will be proviaed.

A Class A moael, as descrioeo in Appendix 2 to NUREG-0654 will De coveloped. Tn e model will employ 15-minute average meteorological acta from tne meteorological measurement system to calculate atmospleric transport witnin tne plume exposure emergency planning zone. Tne moael will incorporate consloeration of site-specific 13.3-44

. . . - . . =- . - _ . . -

PS PSAR AMENDMENT 41 March 16, 1981 I features including terrain and tne lano-water interface. Tn e source cnaracteristics, including release locations ana influence of ouildings, will also be reflectea in tne model. Tne model output 41 will incluoe plume dimensions and position ana location, magnitude p

d ano arrival time of peak concentration and tne concentrations at

selected locations. Tn e bases for tn e model will be documentea.

i 13.3.5.1.3 Dose Conversion Factors Dose conversion factors will be developea. Factors will be calculatea for isotopes wnicn are nazardous from an innalation standpoint (e.g.,'I-131) ano tn ose wn icn cause external exposure (e.g., Kr-88). A library of tnese dose conversion factors will be incorporatea into tne computer sof tware package usea for tn e cose l calculation.

13.3.5.1.4 Computer System A computer system will be used to acquire key cata and perform tne calculations. Calculations will be made on a pericaic oasis, and spatial and temporal dose distribution will be maintained tn rougnout tne period of release of radioactivity. A oefault library or capability for manual entry of cata will also be included in tne sof tware package to provide values if instrumentation is inoperable or off .: ale. The oef ault values will be selected to provice conservative (i.e. , n ign ) estimates o f dose. Anotner feature of tne Tecn niques to h)%

overall system will be a dose pro,jection capability.

be considerea in developing tne projection metnodology will oe manual ,

entry of best estimates of future conaltions, trend analysis ana persistence.

Tne ' computer system output will be' available in tne Control Room, Tecnnical Support Center, Emergency Operations Facility ano otner locations, if.reauirea.

I 13.3-45

AMENDMENT 40 PS PSAR October 10, 1980 13.3.5.2 Emergency Monitoring Monitoring t.cm.5 will be oispatcned to specified downwind locations baseo on prevailing and anticipated meteorologica2 conditions. Tne prime objective of tne emergency of f-site monitoring groups will be to rapidly survey areas downwind of the plant site to datermine the extent and magnitude of any uncontrolled release of radioactive material following an incioent.

E acn monitoring team will collect samples and survey data anu elli transmit information to and/or receive instructions f rom tn e Emergency Operations Facility. Meteorological cata, area topographical maps and actual radiation survey data collected oy off-site survey teams will be used to rapidly define affected areas and assess the extent and significance of tne release. Information will be reauired with as little delay as possible. Tn e r e f o r e , th e survey will consist of simple methods and approximate results witn a minimum loss of sensitivity. Hign sensitivity iodine monitors w11J De available for use by the field monitoring teams. Concentrations of iodine as low as 5 x 10-8 uC1 /cc will be capable of being measured.

13.3.5.3 Protective Action Guides Protective Action Guides for whole Body and Thyroio txpusuies to Airborne Radioactive Material and Protective Actions Guides for Exposure to the Public Via tne Food Pathway will be based on EPA auldelines. Protective actions will be planned for on-site personnel. Recommended protective actions will also be planned for tn e of f-site population-at-risk .

On the basis of present planning for Pilgrim 2, tn e following correlation will be used for establishing a specific relationship between the Protective Action Guides (PAGs) and tn e Alert , Site Emergency and General Emergency classifications.

O 13.3-46

PJ PSAR AMENOMENT 40 Octooer av, 19LO

, 1) General Emergency - the radiological criteria will be the numerical values for tne projected dose to the general public (i.e. ,1 Rem wnole body and 5 Rem tnyroid) recommended as tne lower limits by EPA-520/1-75-001 and also stated as an EAL by NUREG-0654.

2) Site Emergency - the radiological criteria will be one-nulf (1/2) of tne numerical values for tne projecteo doses to the general puolic recommended as tne lower limits by EPA-520/1-75-001. A Site Emergency will be declared if projections indicate dose rates of 50

. mrem / hour wnole body at 30 minutes or 500 mrem /nour wnole body at 2 minutes (thyroid dose limits = 5 times whole body limits).

3) Alert - the radiological criteria (i.e. , 100 mrem whole body ano 500 mrem thyroid) will be projected doses to tne l general public that will be one-tentn (1/10) o f tn e E AL

' lower limits for a uene ni dmergency. An Alert will oe declared in the event of a sustained release greater than ten times- Technical Specification effluent limits (tnyroio dose limits = 5 times wnole body limits).

13.3.5.4 Protective Response A range of protective actions will be available for the plume i exposure patnway EPZ for emergency workers and the public.

l Guidelines for the enoice of protective actions during an emergency, consistent witn Federal- guidance, will be developed and in place.

Protective action for. the ingestion pathway EPZ appropriate to tne locale will be' developed. Boston Edison Company would recomment to E ' civil authorities 'those protective actions as described in EPA-520/1-75-001 (Rev. 6/79).

1O 13.3-47

AMENDMENT 40 PS PSAR October 10, 1980 13.3.5.4.1 Criteria for Requesting Outside Assistance Any incident th at causes or tn reatens to cause an individual located at the site boundary to receive a total radiation dose in excess of the Protective Action Guidelines will require tne Emergency Director to notify and request assistance from various outside agencies.

Requests for assistance from outside agencies for non-radiological incidents sucn as fires or natural emergencies will be made by the Waten Engineer or tne Nuclear Operations Manager wnen it becomes apparent that plant personnel are not or may not be capable of coping with the situation witnout assistance.

13.3.>.4.4 Protective Cover, Evacuation, Personnel Accountability During an emergency, die relocation of persons may be requireo in order to prevent or minimize exposure to radiation and radioactive materials. Th e following subsections discuss the policies wnich will apply to sucn situations.

13.3.5.4.2.1 Plant Site

! Evacuation of all non-shif t personnel, subcontractor personnel and visitors from the station will be initiated immediately upon recognition by the Waten Engineer tnat a Site or General Emergency enists. The Station Evacuation Alarm will be sounced. Operating personnel will be directed to the Control Room. Emergency Organization members will be directed to tne Emergency Operations Facility, tn e Tech nical Support Center, and tne Operational Suppor t Center. All other personnel will be directed to the parking lot.

These instructions will be given over the station's public address system.

Visicurs vu tne plant or site will be provided information on what to do if an emergency exists while they are un site.

13.3-48

_ _, _ ___ _~ .__ _ . _ _ _ . . _ .._ __ . . -._ . . ._ _

i PS PSAR AMENDMENT 41 i

i March 16, 1981 A metnod will be developea to account for all on-site i ss/ personnel. Tn e metn oaology will assure tn e determination o f tn e 41

. location of tnese people witnin 30 minutes of tne time a site 3 evacuation nas been oraerea.

i 13.3.5.4.2.2 Of f-Site Areas l,

l

i. Government agencies nave primary respons10111ty for taking

, protective actions _ outside tne site boundary. BECo will provide s

- recommendations for protective actions for consideration by of f-site autn o rities . Suen recommendations are expected to oe of part'.cular value early during tne course of an acciaent situation before +

of f-site autnorities nave mobilizea. Bases for recommended j protective actions will be developea ana will incluae tne following considerations:

i i i i 1) Emergency Action Levels w111 be definea *1icn will result in categorization of accidents into one of tne four

O designateo classes. Tne E ALs will correspona to plant i conoitions suen as indications of core damage, status of 41-!

containment integrity and release rate of radioactivity to tn e . environment.

l

2) An estimate will be made of current oose rates -(if a

- release is' occurring) as well as project.ea doses at  !

off-site. locations.. Tnese cose rates will oe referencea to EPA's recommended Protective Action Guides to alo in

()

determining tne appropriate protective response.

3) , Tn e time int'erval over wnicn a particular dose is je-- projected to occur will be -compared witn estimates of As ,/) _ evacuation time to assist in. determining tne appropriate response.

f s 4)- Consideration of sneltering in nomes, salools ano otner f ' \- . buildings will De basea on tne protection factor. af forded

[ ~

- by tn e structure. - Tn e Massaalusetts Compren ensive -

l 13.3-49

.- - _ - . . . _ __._r,_ . , . - , . . _ _ . _ , . . . . . , - _ , , , _ _ . . _ . _ _ _ _ _. _ . - - _ . . _ _ _ _ _-- -

AMENDMENT 41 PS PSAR March 16, 1981 Emergency Response Plan includes dose reduction factors for representative structures. BEco will acopt tnese values in consideration of protective action recommenations.

5) Recommendations for protective actions will aaaress special populations witn consiaeration of tne factors aiscussed above. Tne time to evacuate a medical care facility, for example, would be considereo in combination witn tn e estimated exposure at tne location witn aose reauction accountea for ana tne time interval over wnicn exposure is predicted.

Ine proceaural aspects of tne protective action recommenaations will 41 De developed as part of tne final emergency plan. However, an example a111 indicate tne bases on wnicn procedural gulaance will De developed. BECo woula recommeno sneltering as an appropriate protective measure if tne following situation prevallea:

e A release of radioactive material was occurring from tne station.

The integrated wnc e body dose was projected to be

~

e suostantially below 1 rem and tnyroia dose less tnan 5 rem (tne lower EPA PAG values).

i e Tne interval over wnicn release of racioactive material is l expectea to continue is less tnan tne est 2 mated evacuation time in tn e a f fected o f f-site areas.

Tne Massacnusetts Comprehensive Emergency Response Plan incorporates NRC guidance on Emergency Action Levels. Tnis approach relies on information proviaed by tne site for determination of minimum initial off-site response.

A memoer of tne Massacnosetts Department of Public Healtn will be at tne EOF and will be kept continuolly informed of tne results of eccident essessments and environs monitoring. A representative of ble 41 13.3-50

~

l l

1 PS PSAR AMENDMENT 41 March 16, 1981 State of Rnode Islana will also De a f fordea an opportunity to operate in tn e EOF. MCDA will provice information to Rnoce Island of ficials if tneir representative cannot be present in tne EOF. If necessary, 41 BECo will provide information to Rnoce Island agencies. In a General O

y Emergency, NIAT members will be dispatenea to tne EOF to provice aaditional monitoring capaoility. Tn e MUPH will determine wn at off-site actions, including evacuation, snoulo ce recommenaea to tne Governor of Massachusetts wno, tn rougn tne Secretary of Puolic Safety ano tne Civil Defense, will direct tne appropriate response. Tn e Governor of Rnode Island, witn tne support of nis state agencies, 41 will make similar determinations.

For releases wnicn coula require an evacuation, tne Governor may declare a state of emergency, and tne town Boards of Selectmen can also declare an emergency for 01eir local jurisdiction. Notification of tne public would be accomplinneo by tne local ano state agencies using all means readily avallaole. It is assumea tn at, if an evacuation were reauirPJ, it woula De accomplisnea primarily via motor venicle.

For releases af fecting of f-site areas out not of tn e magnituae requir...J evacuation, including tn e 50-mile raalus ingestion patn way EPZ, otner public protection measures may be taken at tn e discretion of tne appropriate State agencies. Tnese measures may incluae radio broadcasts warning people to avoio designatea areas, to remain indoors, close windows, avoid consuming uncovered food or aring, to take cows of f pasture, etc. Tnese measures are discussea in more detail in tne Commonwealtn of Massacnusetts Comprenensive Emergency Response Plan and tne Rnoae Island Nuclear Facility Incicent - 41 Evacuation Plan. Matters sucn as notification of agricultural agencies are discussed tn e r ein .

Analyses nave been performed to -estimate times for evacuation of population groups within tne plume exposure EPZ. Tne analysis considereo evacuations during tnree possible situations:

1) Peak population, good weath er (e.g. , during summer- resort season).

I 13.3-51

AMENDMENT 40 PS PSAR October 10, 1980

2) Normal population, adversa waatn er (e.o. , during a winter storm).

3) Normal population, gooo weatn er (e.g. , during f all, winter or spring wnen weatner is good and roads are clear).

Time estimates were oeveloped for a numoer of geograpnic sub-arens of tne plume exposure EPZ, including tne 2-mile radius area, and several modified 5 and 10-mile radius 90-degree sectors. No major impeciments to evacuation were identified. Tne results are contained in Table 13.3-4. Tne full report of tne evacuation time estimate s tudy is included as Appendix 13A.

13.3.5.5 Radiological Exposure Control Means for controlling radiological c gosures, in an emergency, elll be establisn ed for emergency wor,< ers. The means for controlling radiological exposures snall include exposure guidelines consistent ei th EPA Emergency Workers and Lifesaving Activity Protective action Guides (Manual of Protective Action Guides and Protective Actions for Nuclear Incidents).

13.3.5.5.1 PNPS Emergency Personnel Exposure Criteria An emergency situation transcends tne normal reauirements 01

limiting exposure. Higner maximum exposure levels will be consioereo acceptable during an emergency. However, every reasonable effort will be made to minimize exposure, even in emergencies.

For conditions in wnich it may be possiole to save a life, tn e Emergency Dir ector will determine tne amount of exposure tnat will De permitted in order to perform the emergency mission. However, in no cases will the exposure incurred during life saving activities ce permitted to exceed 75 Rem. In situations wnere tne accident victims are in areas inaccessible because of extremely nign radiation fields, it will be determineo oefvre rescue is initiated tnat the victims nave not or will not have received a lethal oose (approxiinomy 600 Rem) before rescue is completed.

13.3-52

r PS PSAR AMENDMENT 40 October 10, 1980 When emergency on-site action is necessary to reduce a hazaro potential to acceptable levels or to prevent substantial loss of property, an exposure up to 12 Rem may De received by participating

volunteers. However, volunteers, under special circumstances, r.a y receive up to 25 Rem exposure.

i 13.3.5.5.2 Use of Protective Eauipment and Supplies

In order to minimize tne inhalation dose to members of tne emergency urganization, respiratory equipment will be locateo E.t strategic points througnout tne planc secluding the Emergeity Operations Facility. A self-contained breathing apparatus vill- ce 4

used in any situation involving exposure to hign level gaseuus activity or oxygen deficient atmospneres, or wnere air auality is in s

doubt.

Protective apparel available will be snoe covers, head covers, gloves and coveralls or lab coats. Additional items of speciali2ed apparel sucn as plastic or ruocer suits and face snields will be I available for operations involving nign-level contamination.

Health physics- personnel will evaluate tne radioloaical

cnditions and specify the required items of pro ective clotning to l be worn.

In the event of a release of a gaseous plume of radioactive materials in M11cn any on-site individual is projected to receive a dose from radiciodine concentrations in tne air, administration of stable iodine will be cnnsidered for use as a thyroid clocking agent. A single dose af potassium iodide (KI) in tablet form will De administereo as tne 6nyroid blocking agent to tne af fected individuals as soon as possible, preferably witnin two nours of exposure.

13.3.5.5.3 Contamination Control Measures Control of in-plant contamination will be performed in accordance with Plant Radiation Protection Procedures using n-plant equipment.and supplies. Tne Emergency Operations Facility will 13.3-53

AMENDMENT 41 PS PSA3 March 16, 1981 contain radiation survey instrumentation for monitoring on-site personnel ana equipment. Exclusion area access will ne contro11ea at barricaces on Rocky Hill Roaa and at tn e intersection of Rocky Mill Road ana Route 3A. Tnere are expected to De no commercial agricultural proaucts or public water supplies witnin tne exclusion area. Area access control curing a Site or General Emergency will oe consistent witn EPA recommencea Protective Actions Gulaelines ano enforced oy tne Emergency Director.

Wnenever grouna or surf ace contamination activity levels for Unrestricted Areas are exceedea in a particular area witnin tne exclusion area out outsloe tne protectea security area, it will De isolated ano treated as a Restrictea Area. It will nave appropriate radiological protection ano access control as will oe descrioed in plant r8Jiation sa fety procedures usea in Controllea Areas witnin tne protected security area. In tn e event contamination levels r e a cn tn e levels for Restricted Areas, decontamination or otner protective actions as necessary will be consiaered. Tn e af fected area will oe permittec to return to normal use wnen contamination levels nave oeen reduced to tne Unrestricted Area station levels.

13.3.5.5.4 Decontamination ana First-Aid Tn e station's Healtn Pnysics personnel will De experiencea in tne control of racioactive contamination ano in decontamination worx, ana oill nave training in first-ala. In aooitic7, permanent station personnel will nave training in control of raaicactive contamination, and in first-aia. At tne direction of tne Emergency Director, tn e Decontamination ana First-Aid Emergency Team may oe assemolea.

Decontamination ana first-aid facilities will oe provicea at ol e station. Tnese facilities will oe usea wnen possiole. In tn e event tnese facilities are not avallaole, an area witnin tne Emergency Operations Facility will be used to admini;ter first-aia, and an adjacent location will be designated for decontamination activities.

Tne specific location at tne station ana tne layout for first aid and decontamination facilities w)ll be oevelopea in tne course of tne 41 detailed design and informatior will oe providea in tne FSAR.

13.3-54

PS PSAR AMENDMENT 41 l March 16, 1981 Similarly, the specific location and layout of tne first aid ano i

decontamination facilities at tne Emergency Operations Facility will 41 be incorporated into tne detailed design of tnis facility.

1 O

t 13.3.5.5.5 Meoical Services

! Arrangements will be maoe for meoica2 services for contaminateo injured individuals.

O 13.3.5.5.5.1 Meoical Transpurtation 4 Agreement nas been reacheo witn a local amoulance service in tne Town of Plymoutn to provide prompt amoulance service for transporting persons witn injuries involving radioactive contamination from tne statiSn to designated nospitals. Sucn service will be available on a 24-h our per day oasis. Agreement nas also been reacned witn tn e Cn ie f o f tn e Town o f Plymoutn Police Department to provide amoulance service. Radiation monitoring-services will be provided by BECo wnenever it becomes necessary to use tne amoulance service for tne transportation of radiaticn act ident patients.

13.3.5.5.5.2 Medical Treatment Tne BECo Medical Department plan for tne management of accioents and radiation exposures will include

(1) First-aio treatment j

on-site by. the Healtn- Pnysicist and/or personnel trained in first-aid for minor cases; (2) transportation to Jordan Hospital for more i

~ seriously injured cases requiring Emergency Room care, laboratory work, X-rays or life-saving' procedures; and, (3) wnen directed by tne l BECo Medical Department, transportation to Boston for aomission to l facilities' equipped for long-term or intensive care of raalation

[]

V injuries.-

~

( In all cases, a bECo employee trained in healtn pnysics will be I in. attendance as necessary, supervising decontamination and assays,

'O first-aid, and assisting in medical management.

l l'

13.3-55

AMENDMENT 40 PS PSAR October 10, 1980 All cases referred to outside facilities, nospitals, doctors, ,

etc. may be oecontaminateo on tne site. First consideration w111 oe given to treatment o f th e injury. Decontamination in th e n ospital cill oe directed oy tne accompanying BECo employee trained in n eaitn pn y sic s . Personnel of tn e Jordan Hospital Emergency Ward have oeen trained to receive and give emergency care to contaminated or overexposed individuals. The hospital nas preparea an emergency plan for radiation casualties.

13.3.5.6 Record <eeping E ach Emergency Center Supervisor or Director and eacn Emergency Team Leader will be responsible for tne recordkeeping activities associated with their group's emergency duties. Typical of tne records to be maintained are the radiation records (i.e., surveys, projected dose calculations, personnel / population-at-risk evacuations, etc.) and security /accountaollity records (i.e., wno is presently on each team or at eacn center, and any security tn reats) .

Tnere will be forms in tne Emergency Plan Implementing Procedures to be used for determining projected radiation doses, and for accounting for evacuees. Tne responsibilities of eacn recorox seper aill include maintaining tne forms mentiones above ano recoI ding tn e times, places, and personnel involved in all essential and pertinent occurrences / events that tak e place during th e emergency.

13.3.5.7 Recovery and Reentry General plans for recovery unu rcentry will be developed. Once tne hazard potential has passed, steps will be taken to recover from the incident. All actioris snould be preplanned in order to limit exposures. Access to the area will be controlled and exposures of personnel documented.

The Emergency Director and the BECo Recovery Manager have tne joint responsibility for determining and declaring when an emergency situation is stable and has ente?;ed tne recovery pnase. Th ey will evaluate tne status of tne emergency by observing monitoring 13.3-56

. . . - - _ =- - - - . _ . ..- -- . .

AMENDMENT 40 October 10, 1980 1

instrumentation and reviewing all current i and pertinent data available from emergency response and/or

monitoring teams. They shall consider the emergency under

control and in the recovery phase only when the following l general guidelines are met:

1) Radiation levels in all in-plant areas are stable or i are decreasing with time.  !

O 2) Releases of radioactive materials to the environment t

from the plant are under control or have ceased.

3) Any fire, flooding, or similar emergency conditions are controlled or have ceased.

l At the time of declaring that an emergency has entered the

! recovery phase, the Emergency Director shall be responsible for notifying all applicable agencies (e.g., Federal State, and local agencies).

Once the recovery phase beginc, the On-site Emergency

Organization will merge with and become a part of the Recovery Organization, led by the Recovery Manager.

Recovery actions that plan for or may result in radioactive releases will be evaluated by the Recovery Manager and his staff as far in advance of the event as possible. Such events and data pertaining to the release will be reported to the appropriate off-site emergency response organizations and l

agencies.

r i O .

l

13;3-56A

_ _ - _ . . _ . - . , _ . . . . . - _ _ . . . . _ . . . . _ . _ . _ . . . _ _ _ _ _ . _ . . . _ . _ _ _ . . _ . _ . _ _ _ , ~ . . _ _ .

PS A 'MENDMENT 41 March 16, 1981 13.3.6 Puolic Information 13.3.6.1 Preparatory i)ublic Information Program Information will ]e maoe avallaole, on a pericolc oasis, to tne public on now tn ey would be notified and wnat tneir initial actions snoula be in an emergency. Tn e principal points of contact witn tn e news media for dissemination of information during an emergency will be establisned in advance. Proceoures for dissemination of information to tne public will be estaolisnea and will be coorainated witn tn e responsible agencies.

At least annually, information will be disseminat co tn e puolic in tne plume exposure EPZ regarding now tney will be notifico and woat tneir actions snould be in an emergency. Tne public eaucation and information program will be a coorainated ef fort of BECo ano tne

) Commonwealtn o f Massacnusett.s. Tnis will De accomplisned in tn e form of pampnlets delivered to eacn nousenold in tne EPZ. Quantities of h

V pampolets will also be provioeo to towns for use in eoucating tne public. The pampnlets will include information regaroing:

a) Educational information on radiation. 41

, b) Contact for additional information.

A c) Protective measures, e.g., evacuation routes and relocation centers, sh eltering, . respiratory protection and radioprotective drugs.

d) Special needs of tne nancicapped.

. y#

O) Ef forts will be .made to provice information to tne transient population via tne same pampnlets as well as otner notices and publications. Town governments will be active in providing j

information to transients.

Tne program will be' accomplisnea oy yearly review, revision, ano f

dissemination of basic emergency planning information wnicn will 13.3-57 L _ _

A: *:DMENT 40 PS PSAR October 10, 1980 include a description of tne warning systems for tne occupants of tn e plume exposure pa tn aay EPZ. Dissemination will be acnleveu oy general malling ano nand distribution and will incluae metnods to reacn tn e transient population on a town by town oasis. Tn e BE Co l Puolic Information Department will conauct seminars to acouaint tn e neas media witn tn e- emergency plans, backgrouno information on raclation, anc points of contact for release of puolic information.

13.3.6.2 BECo Puolic Information Program for Emergencies 13.3.6.2.1 Public Information Department Puolic information releases will oe issued, in cooroination witn tne BECo Emergency Director, tn rougn tne BECo ruolic Information Department. Tn e Puolic Information Department will senc Puolic Information representatives directly to Information Central in Pl y mou tn . Tn ese representatives will oe responsiole for tn e issuance of accident status reports to tne news mecia. Tn e Puolic In formation Department will also send a representative to tne Emergency Operations Facility to inter f ace between tne Emergency Director at tn e site and Information Central in Plymoutn. Tn e Public Information Department will provice 24-nour per ore coverage anc will nave procedures for tne dissemination of i...ormation to tn e news mecia in tne event of an accident at Pilgrim 2.

13.3.6.2.2 Information Central A Press Center will oe locateo in Plymoutn , ano it will be l l

referred to as Information Central. A BECo Public Information representative will be tnere to interface witn tn e local, state ano federal government public information officers in order to oevelop and provide public news releases coordinated wi tn all emergency organizations concerning current plant status, occurreo events, and expected future emergency anc recovery operations-Also, a Pilgrim 2 Site P.epresentative will De present at Information Central to aid tn e interpretation o f site-related 13.3-58

I I

i M1ENDf1ENT 4 0 !

PS PSAR October 10, 1980 l 1

l I

terminology. Frequent communications witn tne dOF will n elp ensure up-to-date information is made available to tne news media, j Space and tables will be availaole for tn e press. Site maps ano l telepnanes will be provideo. Tnis f acility will centain occument l reproduction equipment, telecopying eaulpment, ano television (

electrical connections for use by tne news meola. [

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13. 3-58 A l ,

PS PSAR AMENDMENT 41 Match 16, 1981 13.3.7.1.2.3 Fire Emergency Drill O At least every tn ree mor.tn s, fire drills will ce conducteo to test tne station's reaoiness to. extinguisn ano control a fire witnin tn e station. Tne arills will also evaluate and document tn e response I

of station personnel ano participating of fsite agencies to varying l fire situations. Off-site agencies will oe offered involvement in tne

annual' drill as mucn as possiole, out at a minimum tne communication lines ano notification procedures will be tested. A post-drill

,l

O .

criticue will oe neld af ter eacn

~

fire drill is completeo to icentify e

t l possible areas for improvement in equipment and/or procedures.

J 13.3.7.1.2.4 Communications Drills Communications between tne station anc otner groups will oe testeo according to the following seneoule:

i Organization Testing Frequency

% Monitoring teams Montn ly 41 Emergency centers (TSC, EOF, DSC) Montn ly State and local governments witnin ,

i plume exposure EPZ Montn ly i State organizations wiblin ingestor  ;

, patnway EPZ Quartecly ,

, Federal emergency response organizations Annually

i e 13.3.7.2 . Emergency Response Training I 4

i

!- Radiological Emergency response training will be provicea to

() tnose wno may be called upon to assist in an1 emergency.

Tne primary cojectives of_ ble Pilgrim 2 Emergency Plan training

' program will be as follows: 41

() 1) Ensure b1at appropriate incivioual's nave a biorougn knowledge of tne Emergency Plan and related implementing ,

. procedures;

, () ~2) Instruct inciviaua'Is in tneir specific -roles to ensure

' effective and expeditious action during an emergency;  ;

13.3-61 L

j .-

AMENDMENT 41 PS PSAR March 16, 1981

3) Periodically present significant enanges in tne scope or contents of tne Emergency Plan;

4) Provide refresner training to ensure tnat personnel nave an up-to-date and tn o rougn K nowleoge o f tn eir outies and 41 responsibilities; and

5) Provioe th e various emergency organization groups witn tn e required training tnat will ensure an integrateo and prompt response to an emergency situtation.

The Senior Nuclear Training Specialist will nave overall responsibility for tne implementation of all reauired training. E a cn group leaoer will be directly responsible for conoucting Group Employee Training witnin nis group under tne cognizance of tne Senior Nuclear Training Specialist.

Cnanges in training requirements will be incorporateo into tne Training Manual by tne Senior Nuclear Training Specialist. Any deficiencies will be reported to tne Manager of Nuclear Operations.

Follow-up corrective action will be tak en by tn e Senior Nuclear Training Specialist.

13.3.7.2.1 General Orientation Training progra.ns will De estaolisneo for all classes of personnel working at tne plant site. Tne programs will include initial instruction ano subsequent retraining. Station personnel tnat are identified as memoers of tne Emergency Organization will receive retraining once a year.

Tne General Employee Training Program will instruct all employees in tne general proceoures utilized to assure nuclear plant safety and personnel safety.

E acn employee will receive additional formal training and retraining in procedures and tecnniques required by nis position.

Tnis will include training in nis individual responsibilities curing an emergency as required by tne Emergency Procedures.

13.3-62

r PS PSAR AMENDMENT 40 October 10, 1980 13.3.7.2.2 Specializeo On-Site Trainina Personnel assigned to tne Pilgrim 2 Emergency Organization witn

specific Emergency Plan duties ano responsio111 ties will receive specialized training. Emergency Plan training sessions will be conoucted at least annually for plant personnel to ensure tnat tney nave a tnorougn knowledge of tneir specific duties and responsibilities. Tne following personnel will be involveo:

i

/ 1) Emergency Director

2) 011ef Operating Engineer

3) 911f t Tecnnical Advisor

4) Radiation Emergency Team Coordinator

5) Emergency Team Leaders

6) Emergency Teams

7) Tecnnical Support Center Supervisor and Staff

6) Operational Support Center Suprevisor and Staff

9) Emergency Communications Cooointtor

!(- 10) Fire Brigade

11) Emergency Security Coordinator l 12) Decontamination and First-Aid Team

13) Emergency Repair ano Damage Control Team t

14) Site Representative 13.3.7.2.3 Spenialized Offsite Training

(

> Eacn of trie of f-site emergency groups will eitner De requireo s,

(i.e., BECo employees), contracted, or invited, at least every twelve montns, to' participate in a training prcgram at Pilgrim 2. Tnis training requirement will be exclusive of ine drill requirements in

'. tn at credit for training cannot ce acauired as a result of

- s-) drill / exercise activities.

Eacn of tne following emergency groups or positons will receive tne general orientation program on tne Emergency Plan and tne l

~

Emergency Plan Implementing Procedures. ,

13.3-63

AMENDMENT 41 PS PSAR March 16, 1981

1) BECo Recovery Mana,3r

2) BECo Emergency Coordinator

3) BECo Informatiun Central Representative

4) BECo Recovery Organization

5) Federal, State, and Local Support Services

6) Nuclear Steam Supply System (NSSS) venoor, Aren i t e c t-Enginee r (A/E), and otn er emergency support groups.

Pilgrim Station will provice site-specific emergency response training for tnose of f-site emergency organizations nien may oe calleo upon to provice assistance in ble event of an emergency.

Training for nospital personnel, amoulance service personnel, police and fire cepartments slail incluce procecures for notification, casic raciation protection, and tne expected roles of tnese inolviduals during emergencies. For ulose local services support organizations wno will enter tne site, training will include site access procecures and tne identity (Oy position and title) of U1e indivioual in U1e on-site Emergency Organization wno will control tne organizations' support activities. 41 E acn off-site response organization will participate in and receive training. If mutual aio agreements exist oetween local agencies sucn as fire, police and amoulance, tne training snall also be of fereo to tne otner departments w1o are memoers of Die mutual aio district.

Training is likely to involve state ano local officials, out cill oe offered to federal officials as well. State officials woulo include State Police, MDCA, MDPH, Department of Environmental Quality Engineering, Department of Transportation, Department of Agriculture, and any otn er agency wnicn see<s training. Local support agencies from tne following towns will oe invited for training: Plymou tn ,

Corver, Kingston, Ouxoury, and Marsn fielo.

Tn e lengtn nf training sessions will average onesialf oay to a full cay. Tn e total amount of training received by any incividual s could depend on the numoer of training sessions recuireo for nis 13.3-64

AMENDMENT 41 PS PSAR March 16, 1981 particular neeos. A person required to receive training in tn ree 41 subjects may spend approximately two days in training.

13.3.7.3 Planning E f fort Development Tne responsibilities for plan development and review and distribution of emergency plans will be estaolisned, and planners will be properly trained.

13.3.7.3.1 Procedures Tne Emergency Plan ano Implementing Procedures will be reviewed annually and updated as necessary to incorporate results of training and drills and to account for cnanges on-site or in tne environs.

Audits of these areas will be performed once every two years to verify compliance witn tne Pilgrim 2 Operational Ruality Assu.~ance Plan, tn e Fire Protection Program Plan, internal rules and procedures, federal regulations, and Operating License provisions. In addition, th e Emergency Planning Coordinator will, by virtue of nis involvement witn k

tne Pilgrim 2 Emergency Planning Program, provide an ongoing _ review, and coordinate tne periodic reviews and audits.

Tne Emergency Planning Coordinator will, tn rougn letters, meetings, seminars, or otner means availaole, ensure tnat all elements of the total emergency organization (e.g. , BECo, state, feoeral, local, etc.) are informed of the Pilgrim 2 Emergency Plan and amendments, and tne Implementing Procedures and revisions.

/- Results of eacn annual review and update will De reported to tne

\~- Vice President-Nuclear.

13.3.7.3.2 Document Distribution ano Control.

Tne Emergency Planning Coordinator will De responsible for tne Pilgrim 2 Emergency Plan distribution ano control.

O 13.3-65

AMENDMENT 40 October 10, 1980 PS PSAR 13.3.7.3.3 Emergency Planning Coordinator O

A BECo staf f memoer will De designated as tne Emergency Planning Coordinator. His general responsibilities will oe related to maintaining tn e Emergency Plan by k eeping it consistent witn regulations, by conducting exercises and drills tnat test tn e Plan, coordinating to e ensuing criticues, and Dy distributing tn e Plan to all participants. Tne Emergency Planning Coordinator will also nave i cn arge o f tn e maintenance and inventory of emergency eauipment and supplies.

I

( 13.3.8 Letters of Agreement Several organizations coulo or would oe involved in tn e event o f l an emergency at Pilgrim 2. Tne attacned letters inoicate a 1

aillingness to provide emergency services on tne part o f tn e following organizations.

1) Commonwealtn o f Massacn usetts State Police, t

2) U.S. Government l Department of Energy l Coast Guard.

National Weatner Service

3) Town of Plymoutn Of fice of Emergency Prepareoness Police Department Fire Department

4) Medical Organizations Medical Services of Cape Coo Jordan Hospital Sn riners Hospital Cn 11dren 's Hospital 13.3-66

PS PSAR AMENDMENT 41 March 16, 1981 EMERCENCY Federal, State 41 D'a'cTo* . --___ - and Local Response Agencies EVERGENCY TECHNICAL OPE R ATIONS SUPPORT CONTROL DOM OPE R A TION AL F ACILITY CENTER SUPPORT l l CFNTER l

COMMUNIC A T IONS TSC CHIEF OPE R ATING OSC COOR DIN A TOR SUPE R VISOR SUPE RVISOR ENCINEER

' 1 l

TECHNICAL SHIFT STAFF ENGINEER / ---

TECHNICAL COMMUNIC ATOR N 1 EER ADVISOR WATCH

, ENCINEER l - OR OPER ATINC TECHNICAL REACTOR OPE R ATING SUPERVISOR ENGINEER ENGINEER SUPE RVISOR w

I 1

RADIATION HEALTH NUCLEAR l NUCLEAR EMERC TEAM -

PHYSICS PLANT -

AUXILI ARY COORDIN ATOR ENCINEER OPE R AT ORS OPE R ATORS E NVIRONMENT A L i -

MONITORINC -

PLANT ENGINEER CHEul5T TEAMS w

l ~

OPE R ATING -

MAINTENANCE IEC ENGINEER ENCINEER TECHNICI AN 4

~ PUB LIC -

CHEMICAL ELECTRICAL INFORMATION ENCINEER -

MAINTENANCE OUALITY ME CH ANICAL ASSUANCE MAINTEN ANCE i

i

- ADMINISTR ATION HEALTH i

CROUP PHYSICS TECHNICI ANS f

I t t SUPPLEMENTAL STAFF -

SECURITY

% EkERCENCY TEAMS PE RSONNEL

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FROM UNAFFECTED f f UNIT SUPPLEMENTAL STAFF AOMINISTR ATION ASSISTANT l _ -COMPUTER t ENCINEER i

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i FIGURE 13.3-4 i

ANTICIPATED PILGRIM 2 ON-SITE EMERGENCY ORGANIZATION i

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SAR AMENDMENT 41 March 16, 1981

\ First-line Second-line obtification tbtification i I I I I I I I I I l

"m l l 1 l

1 I I I l BECo l BECo Emergency Coordinator i Recovery Manager ' k BECo Recovery Organization ~

Boston i I DOE-RAP l l Outside Assistance i I (i.e. Bechtel, CE,

,  ! ItPO, sister utility, l BECo i etc.)

l ('s Emergency i

I l State of Rhode Island 41 Director l  :

1 I i

1 I I

Plymouth l Plymouth Office of

! Police ' k Emergency Preparednes:

Dept. I l

I I I I I I I I I I State Police k Mass. Dept. of Public l 1 F Health l l Mass. Civil Defense 1  : Agency I

l Surrounding Town Police 1

l Reception Area Town l Police

I I I I I l

I I

,~ 1 FIGURE 13.3-6 NOTIFICATION DIAGRAM

PS PSAR AMENDMENT 41 March 16, 1981 O

O O APPENDIX 13 A EVACUATION CLEAR TIMES ESTIMATES l

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O 13A-i

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il PS PSAR AMENDMENT 41 l March 16, 1981 i ,

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] I i i i i EVACUATION TIMES ESTIMATES .

l j- FOR AREAS NEAR l I, PILGRIM STATION  !

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!. I' j HMM Document No.79-048 {

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Reviseo Septemb(r-18, 1980

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Prepared.for:  ;

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l BOSTON EDISON COMPANY  !

800 Boylston Street  ;

Boston' Massacnusetts 02199

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-Prepared by:

HMM - ASSOCIATES, INC. [

~ 255-Bear. Hill Road .

Waltn am , Massach usetts 02154- l O .

. 13A-il

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, AMENDMENT 41 PS PSAR March 16, 1981 l

TABLE OF CONTENTS Page  !

I. INTRODUCTI0t.  ;

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2. POPULATION aNO AUTOM0cILE DAT A USEO FOR CLd,,k IIvi 3 ,

, d S TIMA TE S f

3. TnE EVACUATION 1. In0RK s i

4. EV ACUATION MOD

.L CASES 15 i 1 5. ESTIMATES OF dVACUATIOn TIMES 2e  !

6. Af4CILLARY EVACUATION DATA 32 i ANid X A THE EVAC MODEL 26 i

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ant.Ex e POPULATION AND AUTOMOsILE DATA 3e i ANfdX C MuudL CASd suTOM0eILE ASSIGNMit.TS 09  !

AnidX 0 ASSUMPTIONS MAbi IN M0vdL RUNS yo ANtd X i Thi EVACU4TICf4 rdTn0xs LISTIt4GS 99 *1  !

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4 13A-111

PS PSAR AMENDMENT 40 October 10, 1980

1. INTRODUCTION 4

In a letter dateo July 2, 1980, the Emergency Preparecness Task q Group of the Nuclear Regulatory Commission (NRC) issued a request for information regarding estimates of evacuation times for vaiious areas arouno nuclear power reactors.

The request related primarily to tne actual evacuation time for botn " normal" and " adverse" weatner cor.ditions. In adultion, nowever, NRC nas requested each operator to provide ancillary information'on four related topics. First, NRC has asked for estimates of tne total time to evacuate special facilities , sucn as hospitals. Second, NRC has uArecceo the operators to provide i estimates of tne time required to notify tne population at risx.

Tnird, tne time required for confirmation of evacuation has been requested. Fourtn , and last, NRC nas asked eacn operator tc icentify the alternative protective actions, such as sneltering, whicn raay be implemented wnere "special evacuation problems" are identified.

As a response to this request, Boston Edison Company has sponsored tne calculation of evacuation time = associated with several t

evacuation scenarios. These calculations were undertaxen by HMM Associates, Inc. , of Waltham, Massacnusetts, using available population data, ano EVAC, a computer-based traffic simulation model.* Tne ancillary evacuation data were obtainea during interviews with the persdhnel of the Massachusetts Civil Defense Agency (MCDA). MCDA is the State agency witn primary l responsibilities for emergency preparedness.

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• See Appendix A for a description of tne EVAC model.

13A-1

AMENDMENT 41 PS PSAR March 16, 1981 Ine evacuation stuales were oiscussec witn oo tn tn e Massacn uset ts Civil Defense Agency and witn tne Civil Defense agencies for towns witnin tne Plume Exposure EPZ at several points. Pre 11m nary results o f analyses were presented to a joint meeting of state and local officials at a presentation Dy HMM at tn e State Police carrac4 in Middleboro, Massacnusetts. Later results of studies gare also presented at a meeting of state ana local of ficials nela at tn e Plymoutn Carver Intermediate Scnool in Plymoutn . In adoition, representatives o f HMM and tne Massac1usetts Civil Defense Agency met witn tne towns on an individual basis to discuss tne evacuation studies and tne town emergency plans. Inalvidual meetin3 s were nela witn Civil Defense, police and fire of ficials in tneir of fices in 41 Pl y mou tn , Duxbury, Kingston, Carver and Marsnfielo. During tn ese meetings, tne evacuation study program and results were oiscussec.

Evacuation routes ano evacuation assumptions useo in ble study were outlined. As necessary, tne assumptions and data were revised to re flect suggestions by tn e local of ficials.

Tne Massacnusetts Civil Defense Agency is continuing to work wi tn tne local of ficials to improve local emergency response plans. In is work is proceeding using tne output of tne evacuation stuales sponsored by BEco. Refinement of evacuation plans is casea on cnanges in NUREG-0654 Rev. I requirements as well as on data generated auring tn e evacuation studies. Tne State Plan revision forwarcea to NRC on January 2, 1981 re flects improvements in town plans mace a f t t reviewing the evacuation modeling. Tne amenced town plans nave been sent to the selectmen in eacn town for signature ano approval.

Tnis appenoix nas been compiled to document tne responses to tne l/

NRC request. In subsequent sections, tne report describes:

a Population ano Automobile Data Used for Clear Time Estimates (Section 2.0);

e Tn e Evacuation Network (Section 3.0);

e Evacuation Model Cases (Section 4.0);

e Estimates of Evacuation Times (Section 5.0); and e Ancillary Evacuation Data (Section 6.0).

13A-2

PS PSAR AMENDMENT 41

3. EVACUATION NETWORK

1 3.1 Study Area M

l Ine stuoy area useo for evacuation time estimates is snown on 3 Figure 3-1. Inis study area is baseo on tne NRC suggested plume exposure emergency planning zone (EPZ) witnin a racius of 3

i approximately 10-miles from a nuclear facility. Tn e corder o f tne 10-mile radius is modified to reflect political and geograpnical boundaries wnicn accurately depict an evacuation. Tne study area incluaes tne towns of Kingston, Duxoury, ano most of Plymouth , as well as tne portion of Carver east of Route 58, ano tne portion of l

Marsn field soutn of Careswell Street, but not incluoing tne Brant Rock area. It also includes the small portions of Plympcon, Bourne, and Warenam witnin tne 10-mile radius.*

Figure 3-1 A is a detailerj map of tne Plume Exposure EPZ for j

s Pilgrim Station. Th is sn o w s tn e c ou nd a rie s f o r tn e E PZ wn icn a r e s nearly identical in tne evacuation study area, ano tne 10-mile radius from tne site center. In adoition, tne locations of radiolcgical 4

sampling and monitoring stations, major evacuation routes, evacuation 41 areas and special facilities are indicateo on tne map.

Figure 3-18 is a detailed map of tne Ingestion Exposure EPZ.

,_ Tne map indicates tne locations of reception centers, major produce I farms, major dairy-farms, and water supplies. Tn e 10, 20, 30, 40, and 50 mile raoli are indicateo on tne map.

( 3.2 Network Definition l

In order to estimate evacuation clear-times, an evaluation of

, made'ol tn e tra f fic ~ network lixely to De used by departing automobiles. Key roadways witnin tne study area were examinea.

l Inree sources of information were used in compiling descriptions of L

,.~

• Current emergency plans do not suggest evacuation of tne small, f ( sparsely populated sections of Plympton, Bourne, and Warenam -

witnin 10 miles.

't 13A-9

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! PS PSAR AME NDMd N T 40 Octuoer 10, 1960 tn e evacuation network : 1) tne evacuation networ< descrioea in tne Massacnusetts Emergency Hesponse Plan of December, 1979. 2) existing

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5-mile roaoway network information preparea in 1975; ano 3) data gatnered oy HMM during fielo studies in 1979 and 1980. Tn e mo s t O recent survey resulted in tne generation of data suitable for

calculating evacuation times using a computer mooel for simulation of j various evacuation scenarios witnin tne study area.

i Tne transportation ietwor< elements considerea in tne evacuation modeling consist of major streets and intersections witnin tne EPZ.

, Tne major streets incluce roadways of tne following classifications.

1) Expressways as enaracterizea oy nign Gesign standaros, limited access, grade separation, and primarily tn rougn traffic. Route 3 between Duxbury, a t tn e nor tn , and Bourne, on tn e soutn , is tn e only expressway in tn e study j area.

l 2)~ Arterial Streets as c*iaracterizec oy continuity of travel; connecting ousiness, population, or major recreation areas, ana traf fic controls ano geometric aesigns wnicn ennance traf fic flow and safety.

3) Connector Streets as cn aracterized by ling s oetween resi-dential areas (served by local roads) and arterial streets.

Tne smaller local resloential roadways are' not specifically evaluated as part of. th e mooel simulation.

In accition to tne roadways, tne evacuation network includes tn e intersections of major streets. Tne intersections are particularly important, since tne aallity of intersections to nanale traf fic is tne major capacity constraint during an evacuation.

Tne total traf fic networx consicered in tne evacuation estimates is .snown in Figure 3-2. For tne purposes of. calculating evacuation times, tnis network nas been cocea into a system of " lings" and

" nodes". Tne nodes are tne network intersections on Figure 3-2; tn e link s are tne individual roadway segments oetween tne noaes.

2 i

-t- 13A-11

AMENDMENT 40 PS PSAR October 10, 1980

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FIGURE 3 2 - TOT AL. TRAFFIC NETTORK P00R ORlGINAL 13A-12

PS PSAR AMENDMENT 41 March 16, 1981

,/~'N

() Annex E is a computer printout tnat lists tne cnaracteristics of

• the ling s in tn e evacuation network . It corresponos to Figure 3-3.

Tne listing outlines tne cata describing tne number of lanes, traf fic 41 capacity and tne possiole turning movements for eacn lin< in tn e

(' evacuation network.

3.3 Internal Links ana Nooes (q_/I A total of 221 links, representing actual roao segments, are includea in th e networx . A total of 130 internal nodes, representing actual intersections and assignea venicle entry points witnin tne model nave been incluaed in tne network. Figure 3-3 snows tn e model networx used in tne evacuation time estimatus.

Tne noces serve a dual purpose in tne evacuation model. First, tney act as intersections. Traf fic entering eacn node may nave turning alternatives wnico represent tne enoice availaole in tne

- s, actual roaaway natwor< . In acoltion, capacity constraints associatea

( s

(_,/ witn intersections are modeled at eacn noce. Secondly, naaes in tne EVAC model serve as tne entry points for evacuating tra f fic. Cars are simulated to enter tne model network at noces (i.e., noces serve as surrogates for all tne parxing lots, ariveways, etc. , f rom wn ien i

evacuating automoolles originate). Cars are allocatea to noces cased on population density ano node locations. Appenaix C presents i cetailed information on tne allocaticna of cars to nodes. Certain l noces do not actually represent an intersection, out are locatea on a f 7_s lengtny road segment to serve as a point for local population to tne

/ \

( ,)

[

enter tne evacuation network in tn e computer model.

3.4 Exit Nodes

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(_)S Exit nodes are tne mecnanism tn rougn wn icn evacuating automoolles leave tn e model networx . Tnese nodes are located arouna tn e peripn ery o f tn e networ< . Exit noaes, snown on Figure 3-3, ere l fs all numbered in tne 800's.

( )

Q) 13A-13

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/IcuaE 3 3 . h00E5 AND L1hK5

- P00R ORl8 NM

i i

1

i 1 PS PSAR AMENDMENT 41 l

( March 16, 1981 l

O double counting, since many of tne transients countea at oeacnes, i

! recreational areas, ana nistoric sites are seasonal or permanent i

residents. It is also assumed tn at all stop signs, tra f fic lig its ano

'l l

tra f fic control measures are oceyea, and tnat local officials ao l notning to expedite traf fic movement. Tnese assumptions aad i

i significant increments to estimated clear times. Annex D aescrioes in f detail tnese and otner assumptions made curing tne course of tne

()

clear-time moceling procedure.

It snoulo be notea tnat tne evacuation time estimates assume tnat j no puolic transportation facilities will oe required to accomplisn tn e '

l evacuation. Tn e estimate implicitly presumes tn at tnose persons witnout automobiles will De evacuatea in tne automoolies of frienas,

! neignoors, or relatives.

Tne Civil Defense Agency is currently developing proceaures for 41 l

l. tnose wno will require public transportation. Assembly locations will -

!, be designated ano people requiring transportation will be aavisea to I

() proceed to tne most convenient location. Buses ano truck s will oe alspatenea to tnese assemoly points and people will be transported out

o f tn e EPZ.

i

j. .

f k

O

( 13A-3)

Ec_... _. _ _ _ - . . , _ . _ , . - . - . _ _ . _ . _ . _ . _ . . . . . . . _ _ . _ _ _ _ _ . _ _ . _ _ . . _ _ . . . - . _ _ .-

AMENUMENT 40 PS PSAH October 10, 1980

6. ANCILLARY EV ACUATION UAT A*

O In response to the NRC reauest, several ancillary evacuation topics nave been discussea witn tn e Massacn uset ts Civil De f ense Agency (MCDA). Tn e following subsections document tn e conclusions o f th ose oiscussions.

6.1 Special Facilities Tn ere are f our f acilities wnlen Qualify as "special facilities" for evacuation purposes. Tnese are tne Jordan Hospital (n 3-1/2 miles) in Plymoutn , tn e Plymoutn County Jail (n 3-3/4 miles), tn e Massacnusetts Correctional Institute (SSn 7-3/4 miles) ano tne Town o f Plymoutn Jail (WNW 4-3/4 miles). all prisoners will oe removed from tne incarceration facilities by bus or oy police cruiser. A projected peax tota' of 242 prisoners reouire evacuation. Inis number of prisoners can be moved using a total of five to seven buses. Tn ree to four ouses woulo be reauired to evacuate tne County Jail; one or two for tne Massacnusetts .arrectional Institute; and a single small bus woulo De required for tn e Town Jail. At present, tnere are no firm arrangements for provioing ouses to tne correctional facilities. However, local of f1Cials are currently developing plans for provioing tne needed facilities. Plans may incorporate tne use of buses from nearoy National Guard units. In any event, tne seven buses on tne roaa network ouring an evacuation would not appreciaoly affect evacuation times.**

Tne Jordan Hospital evacuation may prescnt more tecnnical problems. Tn e peax inpatient population is estimatea to De 135 persons. Many of tnase reouire special medical attention. Tn e

• Per personal communication witn Bernie Nolan, MCOA, January 18, 1980.

• • Seven cuses nave no measurable ef fects on tne evacuation time estimates. To be corservative, nowever, tn e HMM

- estimates assume tnat all transients will leave tne area oy passenger ca:.. Accordingly, tne models assume tnat 64 automooiles are aodeo to tTe network to evacuate prisoners.

13A-32

_ -- - . . .= - - -

l PS PSAR AMENDMENT 41 March 16, 1981 special attention may make total evacuation impractical. It is possible tnat movement of some patients presents a greater nealtn nazard tnan any potential for radiological exposure. For otn er patients, evacuation may reauire amoulances witn life supporting

, eaulpment.

At tnis time, Jordan Hospital nas not orafteo an emergency response plan. Development of a plan is being uncertaken now.

Inerefore, evacuation details for tnis facility nave not been fully aefined. For calculating clear times, nowever, it was assumed tnat all hospital patients would be removeo using privately ownea v en ic l e s . It was assumea tnat eacn venicle coulo transport U1ree patients.

Sneltering is tne single alternative protective action program being consioered f or tne four special f acilities. Tn e Massacnusetts i

1 Civil Defense Agency nas initiateo a field engineering analysis to determine protection factors at tne auilaings in eacn location.

Plans nave Deen developeo for consolioating prisoners at tn e correctional facilities in buildings at eacn location witn th e nignest protection factors. Decision on wn etn er to sn elter tn e pr.isoners or to bus tnem to Bridgewater State Hospital will De made oy tne State Department of Public Healtn. Since tne prisoners can be movea during tne general evacuation, it is unlikely tn at sn eltering 41 I will be recommenoeo.

Jordan Hospital is actively working on its protective action plans at this time. Present concepts call for nospital of ficials to make decisions on sneltering versus evacuation cnoices. Tn e nospital O of ficials will be in communication witn tne Department of Public Healtn during an emergency. Tn e Department will aavise the of ficials of tne significance of potential reoiation doses as tney mage tnese decisions. In any event, surgury will continue anc patients for whom

(]

D movement presents a significant nazard will be snelterea ratner tnan evacuated. To the extent possible, patients will be noused in nospital locations witn oest protection factors.

13A-33

l 1

AMdNDMENT 40 PS PSAR Octooer 10, 1980 6.2 Notification Times At present, MCDA estimates tnat tnere is a set of four public notification times tn at may be applied to tn e Pilgrim EPZ. Based on discussions witn tn e Town o f Plymoutn , MCDA estimates a minimum notification time of 45 minutes for tne town. During adverse weatn er, tne notification is estimateo to taxe 60 minutes.* For otn er towns witn in tn e EPZ, a minimum notification time of 35 minutes is estimated curing normal weatner. During aaverse weatn er, tn e non-Plymou tn notifications are estimated to oe 45 minutes. Tne longer notification times in Plymoutn reflect the larger resloent population and tn e larger geograpnical area.

Some portion of eacn notification time estimate snould procaoly be added to tne clear time estimates to conservatively oetermine total evacuation times. It appears, nowever, tn a t incremental increases may oe limited. Tnis conclusion was reacneo as e result of a orief, audiitative review of tne printouts from tne EVAC Computer model runs. Tne printout oata indicate tn t Key intersections oecome loaaeo auickly under simultaneous notificat; , cases. Cars oegin waiting in leng tn y queues almost immediately. E staggering notification times, queue length s auring tn e early portion. f an evacuation may oe reduced, witn ou t reaucing tn e rate at wn , automobiles leave tne evacuation area. In sn art , autos wait in t iveways and parxing lots rath er tn an in aueues. In is could , in some ,ases reduce total evacuation times from tne simultaneous notifit tion cases. A reasonaole estimate rtould be tnat 0 to 30 minu: ' could De addeo to tne clear times outlined in Taole 5-1 to estimats total evacuation time.**

Tn e Plymoutn Of ficer of Emergency Preparedness feels tnat a longer notification time may oe required. A minimum figure of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> nas oeen Citea during informal discussions.

• • No special instructions to tn e public (e.g. , tying a nandxerenief to th e door, or leaving tne door open) nave oeen craf teo to date. MCOA feels tnat public acceptance of special instructions is particularly important. Concerns relate to advertising tne vacancy of dwellings to ourglars or looters.

13A-34

PS PSAR AMENDMENT 41 March 16, 1981 m 6.3 Confirmation Times

'V Confirmation c' evacuation will be uncertaxen by tne same teams wn ico are currently planneo to oe useo to provice public notification. Tn e confirmation will De provideo Dy brie t visual

{')

\- inspections ** for indicat. ions of continued numan activity in an evacuated area. MCDA suggests tnat confirmation times for tnis process will be tne same as tn e notification times estimateo witnout

(~~T tne presence of an early warning system.

V 6.4 Special Evacuation Proolems MCDA feels tn at tne Pilgrim EPZ nas no "special evacuation problems", sucn as unusually nign population censity areas, wnicn preclude evacuation as tne primary protective action to reouce radiological exposures in tne event of an emergency. Tne population at risk can ce removed in a timely and cruerly f asnion. In ere are,

(~T nowever, several alternative actions tnat can be taken to protect 4 4 k/ citizens in tne event of an accident involving potentially dangerous radiation releases. Many of tnem are outlineo, in general terms, in tne MCDA Emergency Response Plan. Tne application of a particular action would depend on a number of factors sucn as time availaole to implement tne action, its risks, ano availaole resources. For example, in a situation in wnicn a plume is expected to pass over an area before it can De evacuateo, tne recommanced protective action would lik ely involve taxing snelter, as opcosed to evacuation. Otn er measures incluoed in tne MCDA plan include controlling access to 7-~3

( -)

affected areas, control of foodstuffs, ano administration of radioprotective drugs.

(~~~} 6.5 Otn er Considerations 5-)

Tne evacuation time estimates incluoes no venicle volumes associateo witn " spontaneous evacuation" of Cape Coo. Tnis

/~Ti assumption is based on tne relative ease witn wn ien spontaneous 41-s

\> evacuation can be prevented. State Police can control tne flow of traf fic exitirg tne Cape by posting details at tn e two bridges.

13A-35

AMENDMENT 41 PS PSAR March 16, 1981 Inese details can allow oroerly flows of f-Cape at tnose times wn en they will not inter fere witn tn e evacuation o f tn e EPZ. no en tn e ,

1 i i spontaneous evacuation oegins to impede tne flow o f ven icles leaving l tn e EPZ , o f f-Cape tra f fic can be n alted, ano if necessary, reverse routed away f rom tne bridges. Similarly, evacuating traffic at tn e Sagamore bri.1ge traffic circle (notes 800 ano 801) woulo be airected 41 down Route 6A Dy State Police. No modeling o f tn is aspect o f tn e evacuation was performed.

h Route 3 was moceled in tne evacuation time estimate study. Tn e

) noces on Houte 3 are coded witn 200 series numbers (see F\gure 3-3).

Since tne major tra f fic flow is toward tn e nortn , tn e ne t a o rx was j expanded to cover many lin< s outside tne EPZ tn at lead to '(oute 3 nortn o f tn e 10-mile radius. Inis precaution was taxen to ensure tnat maximum loacings on Route 3 were investigated.

r t

t l

i OI ,

s I

l l

13A-35 A  ;

~. -- . - - . . - . - - - . - . _ _ _ - - . . - - . . . ._-.

AMENDMENT 41 PS PSAR March 16, 1981 ,

l O'

O l O

ANNEX A THE EVAC MODEL -

i h

I O

p 9

O 9

13A-36 l

l AMENDMENT 41 PS PSAR March 16, 1981 4 THE EVAC MODEL a

Tnis Annex describes tne general structure of tne model ano tnree  ;

I of its major features: tne dynamic route selection, tne priority i treatment of flow at unsignalized intersections, and tne capacity calculations. i l

I l General Structure i; O EVAC is organized in four basic units (proceoures): tn e main

program, the data procedure, tne preprocessor, ano tne simulator.

Inis section, briefly explains tne functions of eacn of tn ese units.

Tne main program controls tne entire execution. It starts oy calling on the data procedure, wnicn reaos in tne cata and' tne execution  ;

instructions, tnen calls in tne preprocessor wnicn performs some preliminary capacity calculations. Next, tne main program controls

- the simuistion itself and tne reporting of tne network conditions at specifieo intervals including tne plotting. Tnis program also

]

controls tne rest of tne reports and tne lengtn of tne simulation oy 1

terminating tne program once tne networx l's empty (or after a specified time).

, Tn e data procedure reads in tn e network , t1e parameters and tne options to be used in tne run. Inis subroutine ~ uses a special list

. processing tecnnique to store tne network ; tn e linx list is stored with botn forwaro and backwaro pointers. In otner words, all tne r

l links pointing into and out of any given noce can ce easily identified at any moment during tne simulation. Tnis list processing tecnniaue

, is one of tne keys to tne mooel's computational efficiency.

$ On reauest, tne cata procedure performs a set of cnecks on tne

) . network to ensure connectivity and validity. It also performs a set of enecks on tne input' date to identify coding . errors'. It is expected-tnat these enecks would oe performed only once for eacn site studied.

r i If errors are found, tne routine keeps scanning tne network until it l .nas been completely cnecked ano tne run is tnen terminated. Tn e . da ta procedure also produces ~a set of warnings if unlixely (but possible) 4

-situations are encountered.

13 A- 37 I - . . _ -

AMENDMENT 41 PS PSAR March 16, 1981 Ine preprocessor procedure converts tne pnysical oescription of eacn link into measures of capacity, speed ano censity. For eacn specified type of ling , tne preprocessor computes two types of capacity:

o section capacity - wnien is tn e capacity along tne ling regaroless of downstream intersection restrictions; ano o approacn capacity - wnicn is tn e capacity of tn e ling to nandle venicles approacning tne cownstream intersection.

Section capacities are associateo witn nignway sections wnereas tn e tra f fic flow tn rougn intesections is controlled oy tne approacn capacity. EVAC computes octn capacities since tney serve olf ferent purposes. The section capacity serves as an upper bound on tne flow tnat can move along a linx , restricting tne numoer of venicles tnat will reacn tne intersection during a simulation interval ano tne number,of venicles tnat can be loacea onto a lang from tn e intersection. Tn e approacn capacity, on tn e otn er nand, limits tne number of cars that can actually move tn rougn th e intersection.

Venicles tnat reacn tne intersection but cannot move tnrougn it are assigned to a cueue.

Tne EVAC simulator includes two separate procecures, tne ling pass and tne node pass. Tn e linx pass nanoles tne flow on tne links wnile tne node pass nandles tne transfer of flow from ling to 11ng.

Dynamic Route Selection EVAC does not use a pre-specified set of turning movements at eacn intersection; insteao, tne turning movements are determined at eacn simulation interval as a function of tne enanging traf fic conditions and directionality of tne lings. Drivers approacning an intersection are assumed to make a enolce of outbouno (away from tne intersection) link s caseo on now fast tnis outbound ling can get tnem to safety. Tn is, in turn, is a function of tne direction of tne 13A 37A

PS PSM AMENDMENT 41 March 16, 1981 outoound link s (away from tne nuclear plant or nazard areo) and tn e tra f fic cono1tions on tne outbound link s.

Tne route selection proceoure used in EVAC reflects tne two above-mentioned cnoice criteria tn rougn a user-supplied " preference O. factor" wnien is specifleo for eacn linx ano tne speeds on eacn o f tn e  ;

outbound linxs. In order to facilitate tne explanation of tne route  ;

cnoice mecn anism, let PF j denote tne preference factor for tne J-tn outbound linx at some intersection. In otn er words, tne relative 'a  ;

priori' pre ference o f linx j is PF j g PF g wnere tn e sum goes over all tne linx s emanating out of tne node under consioeration (including j). Tne enoice procaoility, or tne snare of orivers encosing an outbound link j out of a given intersection at (simulateo) time t, P j(t), is determined as a function of tne preference factors and the speeds on all tn e outbouno ling s as:

P j(t) = j j ,

PF x U (t) wnere Uj (t) is tne speed on linx j at time t. It sn oulo oe noted tnat oriver benavior during an evacuation is assumeo to be myopic in that only information regarding tne immediate  ;

outbound -link s at eacn intersection is assum:0 to influence

route choice decisions. Also note tnat tne P (t)'s are computed for eacn incoming linx separately due to turning pronibitions from some lin6ts into some otner 11% s (a reference to tn e incoming link was omittea from the notation of tne '

cnoice probability for clarity of exposition).

Tn e Priority Treatment O

U Even under evacuation conditions, it can be expecteo tnat i

traf.fic approacning an unsignalized intersection from certain

, links would nave tne rignt of way over incoming traf fic from lower priority approacnes. Since it is not clear tnat sucn

' priority would correspono to tne existing intersection l

i 13 A-37B

AMENDMENT 41 PS PSAR March 16, 1981 controls, tn e input to EVAC includes a user-specifieo lin< priority parameter. Inis is a oinary parameter inuicating primar y or secondary priority of a linx .

Tne volume of venicles being processec (at every intersection ano at eacn simulation interval) and transferrea from inbound to outoound 11n< s is subject to several constraints wnicn determine tn e e f fective capacity of tn e intersection. During tn e simulation, traffic coming in from all primary priority links is assigned t o tn e intersection first, subject only to tne intersection capacity constraints. ' ower priority tra f fic, on tn e otn er nand, is restricted oy botn tne capacity of tne intersection ana tr.e effect of tn e n ign er priority tra f fic.

Inc capacity of tne seconaary priority approacnes is a function o f tn e gap acceptance oenavior of tne minor approacn arivers ano tne neadway aistrioution in tne primary approacnes' flow. In oroer to modei the capacity of secondary priority approacnes, a capacity allocation proolem proceaure is utilized. Tn e seconaary priority approacn es emit traf fic only under one of tne following conditions:

first, if tnere is reslaual intersection capacity from tne primary priority traffic, flow can be emitted into tne intersection from tne secondary priority roaa subject to tn e reslaual capacity constraint.

Second, if tne residual capacity is zero, EVAC provices some small capacity for tne lower priority approacn es to allow for "sneax-in" e f fects.

Note tnat tne priority treatment applies only to unsignalizea intersections ano tn at ootn types of approacnes (primary and secondary priority) are treateo ioentically in tne moael in all respects e.0ept for tne adoea constraint on tne flow from secondary ll priority approacn es.

Capacity Calculations O

Ine capacity of a transportation f acility is tne maximum flow tn at can go tn rougn tn e f acility . EVAC determines capacity in two stages: first, tne preprocessor assigns a section capacity and an approacn capacity to eacn ling in tn e network . Second, approa cn 13A 37C

AMENDMENT 41 PS PSAR March 16, 1981 capacities are upoated continuously, tn rougnout tn e simulation as enanging turning movements a f fect tn e maximum tn rougnput of eacn 11ng into its downstream intersection.

Ine capacity calculations are baseo on tne Hignway Researcn O4 Boaro's Hign way Capacity Manual (HCM) . Following tnis reference, tn e section capacity is calculateo in tne preprocessor for links witn and witnout pnysical separation between opposing oirections wnile tne approacn capacity is calculateo as a function of tne pnysical conditions (width, parking, turning pock ets, etc. ), environmental conditions (area type, pead nour and loao factors), tra f fic cnaracteristics (traf fic mix and percentage of turning movements), and approacn type. Derivations of tnese calculations are outlined in the users manual fcr tne mooel.

As mentioned before, tne approacn capacities calculateo in the preprocessor are not tne actual counos on tne flow. EVAC adjusts tne approacn capacity continuously in order to reflect tne enanging venicular turning movements resulting from tne dynamic route selection.

Tn e capacity o f tn e 1-tn approacn coming into ak intersection at j simulation interval t, C i (t) is given by:

1 -

I C 1 (t) = C 1

x AL(t) x AR(t) i L

wn e re C is tne stanoard capacity of ling i calculateo oy tne i

i preprocessor ano AL(t) and AR(t) are tne correction factors for t

le f t and rign t turning movements, respectively. Tn ese correction factors are a function' of tne percent of tur'ning tra f fic, th e approacn widtn , and parking allowance, as suggested by the HCM. These factors do not apply wnen tne turning traf fic is using special turning lanes or turning

O pocxets.

i 13A-37D/38

t i AMENDMENT 41 PS PSAR  !

March 16, 1981 l

O! l-e; l

l e

l ANNEX B POPULATION AND AUTOMOBILE DATA USED FOR

(

I CLEAR-TIME ESTIMTES l.

O O

G O

13A-38 ,

I i

PS PSAR AMENDMENT 41 March 16, 1981 j

, l' Figure B-4, tne 10-m11e rose for seasonal population, was

} oeriveo in tne same manner as Figure B-3. Tn e 0-5 mile seasonal i

j population were taken oirectly from Figure B-2. Tne aggregate 2-10 i

i mile seasonal numoers from Taole b-z were assigneu to 1-m11e l increments using tne allowation percentages from Figure 8-7.

Tn e 1960 peak transient estimates of Figure b-5 were ceriveo 01rectly from Taoles B-3 tnrougn b-10. Inese cata were simply transformeo to population rose form. Tn e 19o0 transient population j in Figure B-o were aso ceriveu from tne taoles, in tne manner

previously oescrioeo.

l l B.3 Deriveo Auto Estimates In oroer to estimate evacuation times, tn e four s. of

} population oata were convertea to tne numoers or automoulles. It was i

i assumea tnat permanent resloents woulc evacuate witn 2.5 people per dutomoolle.

The 1970 census oata Inoicutea tnat Plymou tn County nac 3.01 persons per nousenola. Tne preliminary Ayeu census cota inu1 cates f

tnere are 2.66 persons per nousenolo in Plymoutn Ctunty. HMM 41 Associates assumes (nat eacn nousenolo will evacuate in une car. Tn e 2.68 to 3.01 figure, nowever, was rounueo oown to 2.2 for mooeling purposes. Inis~ numoer falls witnin tne range of 2 to 3 persons per venicle citeo in NUREG-0634 Rev. 1, Appenuix 4.

AutomoD11e occupancy factors of 3.0 ano 4.0 were useo for tne transient ano seasonal population, respectively. Tn e 3. 0 figure was

-assumeo oy HMM Daseo on informal surveys conoucteo at New Engleno oeacnes in tne past. Tn e survey work consistea of counting tne numoer of persons per car arriving at several oeacn parxing lots 41

-s ouring peax summer montns. Tn e 4. 0 rigure was assumeu Oy. HMM Daseo s ,,/- on a orief review of availaole literature. Tn e U.S. Depar tment or Interior,* ano tne Massacnusetts Department of Environmental Outocor Recreation, U.S. Department of Interior Bureau of Outocar 41 Recreation, Decemoer 1973.

13A-63:

1

I i

- I 1

AMENDMENT 41 PS PSAR March 16, 1981 4 Management

• ootn use 4 persons / site as tne stanoar(7 r.umoer or I occupants for a seasonal camping site. HMH dssurc u tn e t an equal 41 f censity applies to tne summer cottoges in tne EPl. Tn e resultant roses oisplaying tne numoers or automuolles to De evacuatec from tne EPZ are snown in f gures e-o, 6-9, 8-10, ano u-11 for tn e permanent ,

seasonal, pee.< transient, ono winter transient cases, respectively.

l O

l s

l l

l' 4

O O

• Massacnusetts Outocors, Statewloe Comprenensive Outocar Recreation 41

~

O Plan, Massacnusetts uepartment of Environmental Management, Septemoer, 1976, 13A-63A'

AMENDMENT 40 PS PSAR October 10, 1980 NNW NNE 60%

40%

NW NE 40%

30%

10 %

5%

30%

20%

ENE 30%

I I I W to mi S mi s mi 7mi s mi s mi 4 mi ami 2" 1 ='

E 40% 30%l 20%J I 5% 5%

15 10%

10 %

ESE WSW '* 20%

20 %

20% 20% 30%

0%

20% to%

20% #

10%

20% 20%

l SW s%

20%

SE 20%

20% 40%

SSW "*

i SSE

=

G FIGURE B PERCENT OF PERMANENT AND SEASONAL AUTOS ASSIGNED TO ONE-MILE INCREMENTS (from 5 to 10 Mile Total)  :

13A-64 1

l AMENDMENT 41 i March 16, 1981 1 O

. O l

O ANNEX E

l THE EVACUATION NETWORK LISTINGS 1O l

l O

O

/

O 13A-99

AMENDMENT 41 March 16, 1981 LEGEND FOR COMPUTER LISTINGS OF NETWORK CHARACTERISTICS LINK = L ink identification number.

FROM = Upstream node number (A-node) for associated link.

TO = Downstream node number (8-node) for associated 1 ink.

LEN = Link length in feet (A-node to B-node).

AW = Width of intersection approach.

LW = Link lane width.

SW = Lateral clearance = Distance from edge of travel-way to obstructions along link midblock.

L = Number of lanes in direction of travel.

PR = Priority of movement along link, in reference to movement along intersecting links.

Dominant or major link approaches are classified as Priority 1, Secondary (i.e.

those link approaches controlled by stop signs, yield signs, etc. ) approaches are generally classified as Priority 2.

LT = Lane type, classified as follows:

1 - One-way, no parking 2 - One-way, parking on one side 3 - One-way, parking on two sides 4 - Two-way, no parking 5 - Two-way, with parking 6 - Rural divided highway, no parking 7 - Rural undivided highway, no parking 8 - Freeways and expressways.

O O

13A-100

'j AMENDMENT 41 March 16, 1981 i AT = Area type, classified as follows:

1 - Central business district 2 - Fringe 3 - Outer business district 4 - Residential.

t PK = T 5)arking along link permitted F - Parking along link prohibited.

SPD = Free flow speed over link.

JAM = Jam Density = relative measure of links

() PRF =

carrying capacity.

User preference or movement along each

' outbound link. Preferences are initially assigned based upon free-flow conditions.

Actual route assignments are calculated by the program, considering the assigned preferences as well as speed, censity and capacity relationships.

FCAP = Link capacity.

STR, CAP = Identifies destination of movement from downstream node, and associated intersection

~

capacity.

l l RGH,-CAP = Identifies destination of right-turn movement I from downstream node, and associated special turning lane capacity, if applicable.

LFT, CAP = Identifies destination of lef t-tbrn movement from downstream node, and associates special turn lane capacity, if applicable.

DIAG, CAP = Identifies destination of designated movement from downstret, node, and associated capacity.

FLOW = Used in special cases for designating network L

(j)

( flows.

O a

7

(,

13A-101

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2 J 13A-102

AMENDMENT 41 March 16, 1981

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'                                            PS PSAR                                     AMENDMENT 29         i February 24, 1977 O

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l AMENDMENT 41 March 16, 1981 RESPONSES TO NRC REVIEW COMMENTS ON PILGRIM STATION UNIT 2 PSAR SECTION 13.3, AMENDMENT 40 PSAR SECTION COMMENT 13.3.2.2.1 Discuss how sufficient onsite emergency personnel and augmentation capability will be provided in accordance with the reouirements of NUREG-0654, Table B-1. RESPONSE: See added inf orma t ion in Section 13.3.2.2.1. PSAR SECTION COMMENT Figure Show the interface with Federal, State and local 13.3-4 response agencies. RESPONSE: The interface with Federal, State and local response agencies occurs at two levels during an emergency. Initially, the Emergency Director is responsible for liaison and communications with of f-site agencies. (See revised Figure 13.3.4. ) When the BECo Recovery Organization has been mobilized, the Emergency Coordinator will assume responsibility for interf acing with offsite response agencies. (See revised Figure 13.3-5.) The responsibilities of these two individuals will be described in the Unit 2 Emergency Plan Implementing Procedures. During normal operations, the Emergency Planning Coordinator will interf ace with Federal, State and lccal response agencies as discussed in Section 13.3.7. PSAR SECTION COMMENT 13.3.2 The principal Rhode Island State of fice or agency with responsibility for ingestion pathway protective actions must be identified and an agreenent providing for notification criteria, protective action criteria and establishment of notification system provided. O AM41.13-10 t

AMENDMENT 41 March 16, 1981 RESPONSE: The principal Rhode Island State office or agency with resporaibility for ingestion pathway (N") protective actions is the Rhod 0 Island Defense and Civil Preparedness Agency. This agency has developed the "Rhode Island Nuclear Facility Incident Evacuation Plan." This plan is (~') intended to provide for emergency preparedness

   'x_ ,/              in the State of Rhode Island in the event of emergency at Millstone Station and Connecticut Yankee in Connecticut or Pilgrim Station in Massachusetts. This plan emphasizes the emergency notification process. Along with the Massachusetts Comprehensive Emergency Response
   @                   Plan, the Rhode Island Nuclear Facility Incident Evacuat ion plan will form an integral part of the Erergency Program for Pilgrim 2. This is mentiuned in Sec t ion 13.3.1.1. The role of the State of Rhode Island is also discussed in Sec t ions 13.3.2.1.7, 13.3.4.2.7 and 13.3.5.4.2.2.

Letters of agreement with the State of Rhode Island will be obtained and provided in the FSAR. These will contain an agreement providing for notification criteria, protective action criteria and establishment of and notification system. p_ ( ) i/ PSAR SECTION COMMENT 13.3.3.2 Reclassify events involving offsite treatment or transportation of contaminated injured persons as unusual events. RESPONSE: See revised Sections 13.3.3.2 and 13.3.3.3. PSAR SECTION COMMENT 7-x, 13.3.5.4.2; Letters of agreement or State and local plans

         ) 13.3.4.2;   that provide for " prompt" (15 minute) protective 13.3.2.1.1  action decision-making on a 24-hour basis by offsite agencies must be provided. This must include a description of the decision-making chain, t imes required, and provisions for rs                  24-hour availability of decision-makers and
        )              communications. Backup communications not vulnerable to loss of normal power or overload by public use must also be provided to each individual in the decision-making process (see NUREG-0654, Appendix 3).

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U AM41.13-ll

AMENDMENT 41 March 16, 1981 Describe in general the system proposed to alert and provide an information mecsage to the plume EPZ public within 15 minutes in accordance with NUREG-0654, Appendix 3. Provisions f or special instructions to special populations (e.g. schools) should be m iscussed along with provisions for summer beac'. and boat populations. RESPONSE: As discussed in Sections 13.3.4.1.2 and 13.3.4.1.3 of fsite notification of agencies will occur within 15 minutes of determination of an emergency. The Emergency Director will notify and be prepared to recommend protective actions to the MDPH. If necessary the Emergency Director can also make protective action recommendations within 15 minutes to the local Chief Executive. This action would be carried out through the Plymouth 'olice who are on duty 24 hours per day. Where time permits, the following system would be used for c etermining protective actions. The MDPH Radiation Control Officer (on call 24 hours per day) would be alerted by State Police. He would review accident inf o rma t ion from Pilgrim Station. He would make independent cecisions based on source term, meteorological and demographic data. He may use field measurements to evaluate the hazards of the accident in terms of protective action guides. Based upon this assessment, he will make appropriate protective action recommendations to MCDA and, where appropriate, to local author ities. The Massachusetts Plan also calls for automatic triggering of certain protective actions upon the occurrence of designated classes of emergency. For example, in the case of a General Emergency, sheltering is ordered for all persons within two miles of the plant and all persons within five miles of the plant in a downwind direction. These automatic protective action declarations f acilitate decision making within the required 15 minute time period. Where time does not permit an independent assessment by MDPH, the recommendations of the BECo Emergency Director may be used as a basis of decisions regarding protective actions. These recommendations will ordinarily be communicated to MDPH. However, if necessary, the Emergency Director can also make protective action recommendations to the local Chief Executive, who is legally empowered to order protect ive actions. AM41.13-12

   .    - _ - .  ..    .=                          . _ . -             - - - _ . - . _ -                - - -   . .

AMENDMENT 41 March 16, 1981 The capability for prompt (15 minute) protective O action decision making on a 24-hour basis exists at state and local levels. Both decision makers and communications will be available on a 24-hour basis. Each ind ividua l in the uecision making process will be provided with backup communications not vulnerable to loss of normal O power or overload by public use. are discussed in state plans. These matters In accordance with Appendix 3 of NUREG-0654, there will be a system to alert and provide an information message to the plume EPZ within 15 ( minutes. This system is under design at this time.. A public information package will be distributed to households in the area. Efforts will be made to reach thL transient population with this information. Schools will be notified as part of public notification. Special instructions, if any, will be communicated by school officials -pursuant to town and school , evacuation plans. Alerting of beach populations will be provided for by the outdoor alert system. Boat populations will be provided for as follows. The Coast Guard will use marine band radlo to alert much of the boat population. Coast Guard boats will also be used-to alert and notify boats without radios of the need to take protective action. PSAR SECTION COMMENT 13.3.5.l' Commit to develop EALs in accordance with NUREG-0654, Criterion I.1 and Appendix 1. 'The EAL recognition methodology for site and general emergencies must . .,ot include performance of- any calculations, persennel actions, etc., that O cannot be completed in 15 minutes during the backshift. RESPONSE: See revised Section:13.3.5.1. PSAR < O SECTION COMMENT-

     '13.3.5.4'     Describe the methodology used to determine the 13.3.5.4.1    protective = action ~ recommended offsite to include:

'b3 AM41.13-13

AMENDMENT 41 March 16, 1981

1. Development of EALs corresponding to plant conditions (core, containment, ESF),

2. Use of evacuation time estimates for conditions at the time of the accident and for special populations.

3. Use of the protection factors for homes, schools, etc.,

4. Consideration of special populations and facilities, and

5. Consideration of EPA, PAGs.

The State and local protective action decision makers must agree in priciple to rely on information provided by the site for determination of minimum initial of fsite response. Provide the protection assumed to be provided by local homes, schools, places of work, etc. in accordance with NUREG-0654, Criterion J.10. m. RESPONSE: See revised Section 13.3.5.4.2.2. PSAR SECTION COMMENT 13.3.5.4.2.1 Commit to develop a method to account for site personnel within 30 minutes. RESPONSE: See revised Section 13.3.5.4.2.1. PSAR SECTION COMMENT 13.3.5.5.2 Describe the provisions for the development of specific criteria (action levels) to be used to implement onsite protective measures. Discuss the need and provisions for onsite corrective actions under accident conditions. RESPONSE: Onsite protective measures will be implemented on the basis of oction levels to be developed and incorporated into station procedures. Onsite protective response will be initiated based on emergency classification (i.e. site evacuation would be ordered for general emergencies), ef fluent monitor readings and contamination levels. Similarly, onsite corrective actions will be f.escribed in procedures. AM41.13-14

9 AMENDMENT 41 March 16, 1981 PSAR l O SECTION COMMENT 13.3.7.2 Describe the provisions to have each onsite individual who may S;L reautred to perform a task crucial to impler ntatt3n of the emergency plan demostrate annua' ly thef.r ability to perform 1 O these tasks. RESPONSE: Maintenance of emergency preparedness for Pilgrim 2 will be accomplished through training, drills, and exercise. ( ') As discussed in Section 13.3.7.2.1, training will include General Employee training, which includes general emergency training and specialized training. All station employees will receive General Employee Training. Each employee will receive additional formal training and retraining in procedures and techniques reautred by his position. To the extent that the individual is expected to have responsibilities during an emergency, his formal training would include this subject matter. As discussed in Section 13.3.7.2.2, personnel assigned to the Pilgrim 2 Emergency Ortenization O will receive retraining at least annually. Orills of many types will be conducted. Frequency of drills will depend on the type of drill involved. Drills will be an opportunity

for simultaneous training of skills and demonstration of skills. Deficiencies demonstrated in these drills will be corrected.

This is discussed in Section 13.3.7.1. Exercises will also be conducted. A major exercise wil' be conducted annually. Onsite individuals ill demonstrate their ability to f-~ iI perform tasks crucial to implementation of the

  \ '#                                Emergency Plan.

PSAR-SECTION COMMENT 13.3.6.1 Describe. the provisions to provide protective i action information-to the public in accordance with NUREG-0654, Criterion G.I. Describe how information will be provided to transient populations such as boaters and s_f beachgoers. (See NUREG-0654, Criterion G.2.) I RESPONSE: See revised Section 13.3.6.1. AM41.13-15

                                                        ,       , _ , ,        . _ _ . ~ -

AMENDMENT 41 March 16, 1981 PSAR SECTION COMMENT 13.3.7.3 Provide the location and preliminary information on the emergency response f acilities and data systems in enough detail to demonstrate that they will provide an adequate basis for identifying the seriousness and potential scope of emergency situations, for assessment of information, and recommendations for protective actions and disseminating information to tha public. Relate your response to the guidance provided in NUREG-0696. RESPONSE: NUREG-0696 describes the f acilities and systems to be provided by licenses for use during emergency situations. The facilities include:

                . Technical Support Center (TSC)
                . Onsite Operational Support Center (OSC)
                . Nearsite Emergency Operations Facility (EOF)
                . Safety Parameter Display System
                . Nuclear Data Link The TSC, OSC, and EOF are discussed in 13.3.2.3. Alternative locations for the facilities are being evaluated. BECo will develop these five Emergency Response Facilities in accordance with guidance provided in NUREG-0696 Final Report dated February 1981.

PSAR SECTION COMMENT 13.3.7.1.2.4 Communications with the State organizations within the ingestion EPZ must be tested quarterly and monthly communications drills must be conducted wi;h the monitoring teams and emergency centers. RESPONSE: See revised Sect ion 13.3.7.1.2.4. PSAR SECTION COMMENT 13.3.5.1 Revise the general description of the dose projections methodology to conform to NUREG-0654, Appendix 2. This description should include the concepts of the Class A model, incorporating site specific conditions "ia a meteorological measurement system as described in proposed Revision 1 to Reg. Guide 1.23. RESPONSE: See revised Section 13.3.5.1.2. AM41.13-16

AMENDMENT 41 March 16, 1981 PSAR O SECTION COMMENT Figurr 13.3-i; Provide a map showing the plume EPZ in sufficient Appendix 13. A, detail to define the boundaries of the zone, hospitals, relocation centers and special populations in accordance with NUREG-0654, O Appendix 4. RESPONSE: See revised Section 3.1 and Figures 3.lA and

3.1B in Appendix 13.A.

PSAR

      ) SECTION                            COMMENT Appendix 13. A, Describe in more detail the process used to ob'.ain the comments from local town officials and the current status of this effort. Letters should be included from the towns contacted summarizing their comments.

RESPONSE: See revised Section 1. PSAR SECTION COMMENT

  /')

k/ Appendix 13A, Section 6.1 Discuss the use of alternative protective actions at special f acilities. This should include the shelter factors assumed, evacuation times for those f acilities and a discussion of how the protective measure to be recommended for those facilities will be determined (see comment on Section 13.3.5.4). Nursing homes, schools and camps should be considered as special facilities.

RESPONSE

See additional information in Section 6.1.

1 PSAR () SECTION COMMENT Appendix 13.A, Include consideration of. the ef fects of Section 6.4 " spontaneous" evacuation of people from Cape Cod when calculating the " Case 6" evacuation times.

   <-                   Two evacuation routes terminate (Nodes 800 and
  -(                   801) in the area of the Sagamore Bridge Circle and the evacuation study should be expanded to determine the time required to evacuate those people down Route 6A.

{7 3_J' Discuss how access to Route 3 was modeled (no Nodes are shown). RESPONSE: See new Section 6.5 in Appendix 13.A. AM41.13-17 L

AMENDMENT 41 March 16, 1981 PSAR SECTION COMMENT Appendix 13.A Provide the basis fo r the automobile occupancy B.3 factors. RESPONSE: See revised Sect ion B.3. PSAR SECTION COMMENT Appendix 13.A, Provide the Roadway characteristics as described Section 3.2 in NUREG-0654, Appendix 4-III B (page 4-6). RESPONSE: Information provided in Appendix 13.A Annex E. PSAR SECTION COMMENT Appendix 13.A, Provide a further dcscription of the algorithm A . . '> x A used in the Model. Describe how highway capacity was determined and how the dynamic route loading is conducted. RESPONSE: See revised Annex A. PSAR SECTION COMMENT Appendix 13. A, Discuss estimated evacuation time for the public Section 5 that must use public transportation in accordance with NUREG-0654, pag e 4-9. RESPONSE: See revised Section 5. PSAR SECTION COMMENT 13.3.5.5.4 Provide the proposed location (show relation to emergency centers) and physical layout of the first aid and personnel decontamination facilities. RESPONSE: See revised Section 13.3.5.5.4. O 9 AM41.13-18

 - - .                       .- -_                         -... .                         - - - - - - . - .        _   . - . .         - . . _ = . . - . _ . . .

I j AMENDMENT 41 i March 16, 1981 e t E i j PSAR SECTION COMMENT i l 13.3.6.2.3 Provide a more detailed list of the State and i local support agencies to be invited to onsite i j t ra in ing . Provide for training of these

personnel on the functions they may be required to perform or condition they may encounter i V

! onsite that are not part of their normal  ; ! (offsite) duties /tra'.ning. Describe the , ! proposed length of this training and type. ,

r

!' - RESPONSE: See revised Section 13.3.7.2.3.

i i i l l e i f [ 0  ;

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I I O I i l 0 e AM41.13-19

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