Text

Forwards Maine Yankee Defueled Emergency Plan. Change to Maine Yankee Emergency Plan Has Been Made in Accordance with 10CFR50.54(q)
	ML20154L482
Person / Time
Site:	Maine Yankee
Issue date:	10/15/1998
From:	Zinke G; Maine Yankee
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	GAZ-98-53, MN-98-63, NUDOCS 9810190318
	Download: ML20154L482 (22)
	v • d • e

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l MaineVankee P.O. BOX 408

WISCASSET, MAINE 04578 + (207) 882-6321 L

October 15,1998 MN 98-63 GAZ 98-53 UNITED STATES NUCLEAR REGULATORY COMMISSION Attention: Document Control Desk Washington D.C. 20555 j

References:

(a)

License No. DPR-36 (Docket No. 50-309)

(b)

Maine Yankee Emergency Plan, dated December 30,1993 (c)

Maine Yankee Letter to NRC (MN 97-89) dated August 7,1997 (d)

Maine Yankee Letter to NRC (MN 97-119) dated November 6,1997 (e)

Maine Yankee Letter to NRC (MN-47) dated June 29,1998 (f)

Maine Yankee Defueled Emergency Plan, dated August 1998 (g)

NRC Letter to Maine Yankee, dated September 3,1998, granting Exemptions from 10 CFR 50.47 and Appendix E

SUBJECT:

Submittal of Maine Yankee Defueled Emergency Plan i

Gentlemen:

Pursuant to 10CFR50.4, please find enclosed an informational copy of the Maine Yankee Defueled Emergency Plan. This change to the Maine ' Yankee Emergency Plan has been made in accordance with 10 CFR 50.54(q).

j The Defueled Emergency Plan was implemented on September 18,1998, and replaces the Emergency Plan of record (Reference b). The Defueled Emergency Plan implements the applicable portions of 10 CFR 50.47 (b) and Appendix E of Part 50 as specified by the NRC in its letter (Reference g) granting exemption from certain requirements of 10 CFR 50.54(q) 10 CFR 50.47(b) and (c), and Appendix E to 10 CFR Part 50 at Maine Yankee Atomic Power Station.

This change, described more completely in Attachment A, has been reviewed by the Nuclear Safety and Regulatory Affairs Subcommittee and the Independent Review Audit Committee. It has been determined that this change to the Maine Yankee Emergency Plan:

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(1) _does not decrease the effectiveness of the Plan resulting in a loss of reasonable

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assurance that adequate protection can and will be taken in the event of a radiological i

emergency as reqmred by 10 CFR50.47(a),

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(2) does not result in the loss of ability to meet any of the applicable standards described m 10CFR50.47(b) or any NRC approved attematives to these requirements, (3) does not delete or contradict any regulatory requirement for a defueled nuclear plant.

-We have discussed relevant aspects of this change with representatives of the Maine Emergency Management Agency (MEMA) who concur with the changes contained herein.

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9810190318 981015ADOCK 05000309.'

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PDR

l' MaineYankee L

UNITED STATES NUCLEAR REGULATORY COMMISSION MN-98-63 Attention: Document Control Desk Page Two

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l We trust this infonnation is satisfactory. Should you have any questions regarding this information, l

please contact me.

. Very truly yours,

~

i George A. Zinke. Direc or Nuclear Safety & Regulatory Affairs Attachment c:

Mr. Hubert Miller (2 copies)

Mr. Mike.Webb Mr. M. Roberts Mr. P. J. Dostie, SNSI

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Mr. Uldis Vanags, SPO Mr. John Libby, Director, Maine Emergency Management Agency m:\\jmt\\nrc-dep98.wpd

ATTACilMENT A MAINE YANKEE DEFUELED EMERGENCY PLAN IMPLEMENTATION JUSTIFICATION

1.0 INTRODUCTION

The implementation of the Maine Yankee Defueled Emergency Plan (DEP) subsumes the Emergency Plan that was developed for the facility while it was an operating power plant. The DEP has been written, consistent with the revised accident bases, to reflect the reduced scope of emergencies that can occur at Maine Yankee and the significantly reduced risk associated with those events. In developing the DEP, specific exemptions to 10CFR 50.47(b) and Appendix E to 10CFR50 were requested in References 1 and 2.

These exemptions reflect the appropriate level of emergency planning for the facility in its present configuration and represent a realistic approach to the overall emergency preparedness program for the facility as it enters the decommissioning and dismantlement process.

2.0 DESCRIPTION

OF CIIANGE This change effectively replaces, in total, the Maine Yankee Emergency Plan developed for the facility when it was an operating nuclear power station. Coincident with the implementation of the DEP, a complete set of Defueled Emergency Plan Implementing Procedures (EPIPs) will replace the existing EPIPs. The new EPIPs have been developed to implement the reduced scope of onsite emergency preparedness and response commensurate with the significant reductions of postulated accidents and beyond design basis events during decommissioning.

Details of the DEP and how it continues to meet the applicable sections of 10CFR50.47(b) and Appendix E to 10CFR50 are identified in the following table. The portions of the requirements for which an exemption has been granted by the USNRC (Reference 3) are indicated with a strikccut.

10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan 50.47 Emergency plans An Emergency Plan has been developed to comply with the applicable standards as (b) The onsitc and, cxccpt as provided in paragraph (d) of this identified in Reference 3.

scction, offsite emergency response plans for nuclear power reactors must meet the following standards:

(1) Primary responsibilities for emergency response by the Responsibilities for emergency response nuclear facility licensee and by State and local organizations are identified in Section 8 of the DEP, within the Oncrgency Planning Zones have been assigned, the

" Organizational Control of Emergencies".

emergency responsibilities of the various supporting This sectic, identifies each position in the organizations have been specifically established, and each Emergency Response Organization (both principal response organization has staff to respond and to on-shift and augmented) and specifies i

augment its initial response on a continuous basis.

primary responsibilities for each position.

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1 10CFR50.47(b) or Appendix E Standard.

Maine Yankee Defueled Emergency Plan (2) On-shift facility licensee responsibilities for emergency The responsibilities and interfacing response are unambiguously defined, adequate staffing to relationships of the on-shift ERO are 1

provide initial facility accident response in key functional defined in Section 8.1.1. of the DEP.

areas is maintained at all times, timely augmentation of Included in this section are the non-response capabilities is available and the interfaces among delegable duties of the Emergency various onsite response activities and offsite support and Director.

response activities are specifiedt (3) Arrangements for requesting and effectively using Offsite Assistance is discussed in assistance resources have been made, an ngemcats to Section 11 "Offsite Assistance". Letters accommoda:c State and local staff at the liccascc's acar-site of Agreement (Appendix I) have been m..n..e..y y.

dons "acility have been made, and other secured with various service organizations organizations capable of augmenting the planned response (Wiscasset Fire Dept., Wiscasset have been identified.

Ambulance Service, Bath Fire Dept.,

Duke Engineering and Services, etc.) that may be called upon to assist in mitigating an emergency at the facility. Periodic drills and orientation sessions are offered to these organizations to ensure their understanding of the expected response, I-should they be summoned to assist.

(4) A standard emergency classification and action level Section 4 " Classification of Accidents" scheme, the bases of which include facility system and effluent identifies the various categories of events parameters, is in use by the nuclear facility licensee, and Staic that are included in the defueled and local ic;pon.:c plans call for reliance on infomiation emergency action level classification provided by ft.uity liccascca for de:ca.mations of mirdmum methodology. The Defueled Emergency ini !a offsite respenac measurcs.

Classification scheme is based on the NEl (formerly NUMARC-007) methodology, adjusted to focus on the Spent Fuel integrity vs. RCS/ Fuel / Containment g

barrier integrity. For each initiating i

condition, a corresponding basis has been developed to ensure the basic intent of the event class has been satisfied.

(5) Procedures have been established for notification, by the The process for notification of State and licensee, of State and local response organizations and for local organizations is described in Section notification of emergency personnel by all organizations; the 6.1.2 "Offsite Organizations".

a content ofinitial and followup messages to response Information to be communicated is 1

organizations and :he public has been established; and means described in Section 6.1.3. The actual to providc carly notification and cicar instruction :s the process is contained in the Defueled j.

populac-c within the plume exposurc pathway "mcrgency Implementing Procedures written to Planning Zonc have beca catabli;hed.

support the DEP.

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10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan (6) Provisions exist for prompt communications among The various means of cor.imunications are principal response organizations to emergency personnel and detailed in Sections 7.5.. and 7.5.2, to the public.

"Onsite Communications Systems" and "Offsite Communications Systems".

These systems include dedicated telephone lines, radios and commercial telephones.

(7)-Information is made availab!c te the public on a pcriedie Section 8.1.2.8 delineates the basis on how thcy.vi!! Se notificd and what thciHnitial actions responsibility for interfacing with the should behs cmcrgency (c.g., listcning 1c a !ccal broadcas:

news media to the Public Affairs antion and rcmaming indcors), the principal points of contact Coordinator. Appropriate procedures for with the news media for dissemination ofinformation during dissemination ofinformation, under an emergency (including the physical Iccation cr !ccations) are emergency conditions, are contained in an established in advance, and procedures for coordinated implementing procedure.

dissemination ofinformation to the public are established.

(8) Adequate emergency facilities and equipment to support Descriptions of the available facilities are the emergency response are provided and maintained.

contained in Section 7.0 " Facilities and Equipment". The facilities are maintained in accordance with departmental surveillance procedures.

j (9) Adequate methods, systems, and equipment for assessing The primary source of any potential and monitoring actual or potentialeffske consequences of a radiological release has shifted from the radiological emergency condition are in use.

Reactor Coolant System to the Spent Fuel Pool (SFP). In preparation for long-term storage of the spent nuclear fuel, new monitoring systems (both process and general area radiation) have been installed for the Spent Fuel Pool Island and are operational at Maine Yankee.

Meteorological data is available via the Programmable Logic Controller (PLC) from the installed met tower. Procedures have been developed to correlate instrument indications to projected doses at the site boundary, consistent with the Defueled Safety Analysis Report (DSAR) revised Design Basis Accident (DBA).

These systems are briefly described in Section 5," Detection of Accidents". In addition to monitoring for a radiological emergency, systems for monitoring SFP temperature, level and cooling water flow.

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10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan

(-10) A range ofpro:cetive ac: ions havc bcca developcd for the Not required per Reference 3.

plumc cxposurc pathway EPZ for cmcigency workers and the public. Guidelincs for thc choice of pro cc ive actions during mmncigcacy, consis: cat with Pcdcral guidance, arc developed and in placc, and pro:cctive acticas for thc ingestion cxposurc pathway EPZ appropriate :c hc localc have been devcioped.

(11) Means for controlling radiological exposures, in an Onsite Protective Actions, including emergency, are established for emergency workers. The means applicable radiation exposure limits are for controlling radiological exposures shall include exposure discussed in Section 6.3 " Protective guidelines consistent with EPA Emergency Worker and Actions". Additionally, the facilities in Lifesaving Activity Protective Action Guides, use were designed to shield against direct radiation from the operational DBA. The anticipated direct radiation from the defueled DBA is considerably less than that value. The design of the facilities is included in Section 7.0 " Facilities and Equipment".

(12) Arrangements are made for medical services for Agreements have been secured with the contaminated injured individuals.

Wiscasset Ambulance Service, Mid-Coast Hospital (Brunswick) and the Maine Medical Center (Portland). These agreements are contained in Appendix I to the DEP.

(13) General plans for recovery and reentry are developed.

Recovery is discussed in Section 10,

" Recovery".

(14) Periodic exercises are (will be) conducted to evaluate Drills and exercises will be conducted in major portions of emergency response capabilities. periodic accordance with Section 9.3," Drills and drills are (will be) conducted to develop and maintain key Exercises". Section 9.3.3 identifies skills, and deficiencies identified as a result of exercises or followup activities pertaining to drills are (will be) corrected.

documentation of observations, initiation of corrective actions and tracking to closure via existing departmental processes.

(15) Radiological emergency response training is provided to Section 9.1 addresses training to be those who may be called on to assist in an emergency.

conducted for the ERO and for those who may be called in to assist in the response effort.

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10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan (16) Responsibilities for plan development and teview and for Section 9.0 assigns responsibility for plan distribution of emergency plans are established, and planners development and maintenance to the are properly trained.

Manager, EHS/ Emergency Preparedness.

Additionally, Section 9.2 details the process for periodic review and updating of the DEP and Implementing Procedures.

(c)(2) Ccacm!!y, the plume caposure pathway EPZ for Not required per Reference 3.

nuc! car powcr plants sha!! consis of an area abou: 10 miles (15 km) in radius and the ingestion pathway EPZ shall consist of an arca abou: 50 miles (S0 km) in maius. The caact size and conngura: ion of the EPZs surrounding a panicular nucl car powcr reactor sha!! bc det.....incd in rciation to local cmc. cacy responsc accds and capabilitics as they arc affected by such conditions as demog. phy,:opography, land charac cristics, acccas rou;cs, and jurisdictional boundaries.

The size of the EPZa also may be det.....ined on a case-by-cesc basis for gas-cooled nacicar reac: ors and for reactors with an authorized power icvc! Icss than 250 MW

he..ual. The plans for the ini, cation pathway shall focus on such actions as arc app.opria:c to pro:cc: :h food ingestion pa:h way.

Appendix E to Part 50 The DEP is referenced in the DSAR, Section 6.5.1. The DEP is docketed as a III. The Final Safety Analysis Report separate document supporting the DSAR.

l The Final Safety Analysis Report shall contain the plans for -

coping with emergencies. The plans shall be an expression of the overall concept of operation; they shall describe the essential elements of advance planning that have been considered and the provisions that have been made to cope with emergency situations. The plans shall incorporate information about the emergency response roles of supporting organizations and offsite agencies. That information shall be -

sufficient to provide assurance of coordination among the supporting groups and with the licensee.

The plans submitted must include a description of the elements set out in Section IV for the Emcrgency Planning Zonca o1 (EP2+) to an extent sufficient to demonstrate that the plans provide reasonable assurance that adequate protective measures can and will be taken in the event of an emergency.

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10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan i-IV. Content of Emergency Plans '

Based on the DSAR, there are no credible accidents that could result in exceeding The applicant's emergency plans shall contain, but not the EPA PAGs beyond the site boundary, j-necessarily be limited to, information needed to demonstrate therefore, evacuation time estimates and j

i compliance with the elements set forth below, i.e.,

other protective actions beyond the site i

l organization for coping with radiation emergencies, boundary are exempt for the Maine L

assessment action, activation of emergency organization, Yankee plan.

l notification procedures, emergency facilities and equipment, -

l training, maintaining emergency preparedness, and recovery.

In addition, the emergency response plans submitted by an applicant for a nuclear power reactor operating license shall contain information needed to demonstrate compliance with the standards described in {50.47(b), and they will be.

evaluated against those ' tandards. The nucicar power reactor s

epcra bg license applican; shall ala; p.evide an analysis of the time required :o cvacas:c and for tsking c:hcr pro:cc;;ve I

actions fcr various scc ors and distancca within thd plume capesure pathway FI'Z for :. is'ent and pm..;;ncn; pphik%.

A. Organization Section 8 identifies the Emergency l-Response Organization (ERO) for dealing The organization for coping with radiological emergencies with emergencies. Duties, responsibilities shall be described, including definition of authorities, and authorities are defined for each responsibilities, and duties ofindividuals assigned to the position of the ERO.

licensee's emergency organization and the means for notification of such individuals in the event of an emergency.

1. Section 8.1.1 identifies the normal "on-Specifically, the following shall be included:

shift" staff and their emergency -

1. A description of the normal plant operating organization.

responsibilities (relative the DEP). The L

means for notification of the ERO (both the on-shift staff and augment staff) are described in 6.1," Notification and Activation"

2. A' description of the onsite emergency response organization 2.a Section 8.1 describes the E

with a detailed discussion of:

organizational control of emergencies.

More detailed descriptions of the various

a. Authorities, responsibilities, and duties of the individual (s)

ERO positions and responsibilities are who will take charge during an emergency; contained in the position descriptions found in Section 8.

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10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan

b. Plant staff emergency assignments, Plant Staff assignments are maintained by the Emergency Preparedness staff. The assignments are made based on satisfactory completion of required training (and continuing training). The ERO staffing is the responsibility of Station Management as prescribed in Section 9," Maintaining Emergency Preparedness".

c. Authorities, responsibilities, and duties on { sic} an onsite The Emergency Director (ED)is emergency coordinator who shall be in charge of the exchange responsible for these functions. Details of ofinformation with offsite authorities responsible for the ED's responsibilities are contained in coordinating and implementing offsite emergency measures.

Sections 8.1.1.1, Shift Manager / Emergency Director and 8.1.2.1, Emergency Director.

3. A dcscrip ;ca, by positica and ihnction to bc performcd, of Not applicable, all Maine Yankee Staff thc liccnscc's hcadquartcrs personnc! who will bc sent :0 the are located at the site.

plant site :c augment :hc casitc cmcigcncy crganieetten-

4. Identification, by position and function to be performed, of Dose Projections will be performed persons within the licensee organization who will be initially by the on-shift ERO. When the responsible for making effette dose projections, and a TSC is operational, this function will be description of how these projections will be made and the performed by the Radiological results transmitted to State and local authorities, NRC, and Assessment Coordinator or designated other appropriate governmental entities.

staff. Sections 8.1.1.1 and 8.1.2.4," Shift Manager / Emergency Director" and

" Radiological Assessment Coordinator" define these responsibilities.

5. Identincatica, by positica and function c bc performcd, of Not applicable in the defueled condition.

cther cmpicycca of the liccascc with spccial qualincaticas for The anti:ipated range ofincidents has coping with cmcrgcacy conditicas that may arisc. Othcr been deflned and contingencies put in pctscas with spccial qualincatwns, such as consultants, who place (i.e industrial-type events, fire arc not cmpicyccs of thc licenscc and who may be ca!!cd upon medical, etc.). Section 11,"Offsite for assistancc for cmcrgcncica shall also bc identincd. The Assistance" and Appendix I," Assistance spccial qualinca icns of thcsc persons shali bc describcd.

Agreemems" identify supporting organizations that have agreed to support Maine Yanl.ee as necessary.

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10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan

6. A description of the local offsite services to be provided in Section 11,"Offsite Assistance" identifies support of the licensee's emergency organization.

the local offsite services (i.e fire, police and ambulance) that might be called upon to respond to an emergency at Maine Yankee, as well as the medical facilities that may receive workers from the site.

7. Identification of, and assistance expected from, appropriate Section 6.1.2, "Offsite Organizations" State, local, and Federal agencies with responsibilities for identifies the notification sequence for coping with emergencies.

offsite organizations. Section 6.4

" Coordination with Offsite Agencies" describes the type of response that might be implemented by those organizations and Section 11,"Offsite Assistance" identifies offsite organizations that may be either called upon to assist (fire, police, ambulance) or to monitor the local environment (Dept. of Health Engineering).

B-Jdcatification of the Sta c and/or local officials scaponsibic Not required per Reference 3.

forplanning for, ordcring, and contro!!ing appropria c pretctive actions, including evacuations when acces;ary.

B. Assessment Actions Section 5.0 " Detection of Accidents" identifies the means of detecting and The means to be used for determining the magnitude of and monitoring accidents processes. Section for continually assessing the impact of the release of 6.2," Radiological Assessment" describes radioactive materials shall be described, including emergency the general methodology for assessing an action levels that are to be used as criteria for determining the event. Specific assessment actions are need for notification and participation oflocal and State contained in the Defueled Emergency agencies, the Commission, and other Federal agencies, and the Plan Implementing Procedures (EPIPs),

emergency action levels that are to be used for determining when and what type of protective measures should be Section 4, " Classification of Accidents" considered within and outside the site boundary to protect provides an overview of the accident health and safety. The emergency action levels shall be based classification process. Emergency Action on in-plant conditions and instrumentation in addition to onsite Levels (EALs) have been developed that and offsite monitoring. These emergency action levels shall be reflect the facility's defueled condition.

discussed and agreed on by the applicant and State and local These EALs have been reviewed and governmental authorities and approved by NRC. They shall found to be acceptable to the State and also be reviewed with the State and local governmental local governmental authorities.

authorities on an annual basis.

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10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan C. Activation of Emergency Organization Section 3, " Types of Accidents" describes the postulated spectrum of accidents that o

The entire spectrum of emergency conditions that involve the could occur at the facility. These alerting or activating of progressively larger segments of the descriptions are based on the events as total emergency organization shall be described. The analyzed in Section 5 of the DSAR.

communication steps to be taken to alert or activate emergency personnel under each class of emergency shall be described.

The notification and alerting process is Emergency action levels (based not only on onsite and offshe described in the DEP, Section 6, radiation monitoring information but also on readings from a

" Emergency Response"(for the onsite number of sensors that indicate a potential emergency, steelnes and offsite organizations that interface the picssur; in containmsu..... u.

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with MY). Notification message content Cor; Cooling Sys:cm) for notification of offsite agencies shall and verification process is also included i

be described. The existence, but not the details, of a message in this section.

authentication scheme shall be noted for such agencies. The l

emergency classes defined shall include: (1) notification of Emergency Action Levels have been unusual events, (2) alert, m.u

.um3,us,, omm m developed for the defueled condition, a

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gcacral cmcrgency. These classes are further discussed in description of the event categories is NUREG - 0654; FEMA - REP - 1.

included in Section 4, " Classification of Accidents".

In the defueled condition, the limited hazards posed by the facility also limits the severity of the event classification scheme to an Alert.

D. Notification Procedures The process for notifying these officials is described in Section 6.1.2,"Offsite

1. Administrative and physical means for notifying local, Organizations". The means of j

State, and Federal officials and agencies and agreements notification (i.e. physical hardware to be reached with these officials and agencies for he promp used) is described in Section 7.5.1 and ac;ifica:ica of the public and for public cvacustica or other 7.5.2, "Onsite Communication Systems" y.

.m m., mm..m.,

o m m, ummm, um...,, shall be and "Offsite Communications Systems",

described. This description shall include identification of the appropriate officials, by title and agency, of the State and local govemment agencies w;;hin thc EPZs (1)

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10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan

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1 10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan

3. A licensee shall have the capability to notify responsible Maine Yankee has committed to notifying State and local governmental agencies within_@-15 minutes responsible State and local officials afler declaring an emergency. The licenscc sha!! demcastra:c within 60 minutes based on the reduced that the Sistc/ local ofScials havc the capabili'y c makc a hazard associated with the facility and the public notifica ica accisica promp !y cn bcing fnformcd by thc significantly reduced scope of anticipated Eccnscc of an cmcrgciicy conditica. "y Fchruary 1,1982, cach response by non-licensee staff. This nuc! car pcwcr reac'er licenscc shall dcincastra'c that capability is maintained 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months / day - 7 administrativc and physicalIiicalis havc bccn catablishcd for days / week.

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f__ __ ! _ _ I f.. a _._ _ a f f' _.. a ! _ _ _ f a f. - _..L 1I _ I..f a L I 1 f _ !.. a _.

aavana assuaswusta6w aavuaawuuvaa va buw y6ausaw (sv aunas a s sasusLabwa c[ )ic tisiiC }ia State aiid !cC.l! G[EC!a!s aiC iiG 5bCd !!iaI a situation exists rcquiritig urgent action) c the more likcly cycn:s whcrc thcic is substantial ;imc availab!- fcr thc Statc and local gevcmmciital cfricials to makc ajudgmcn whc;hcr cr not to activa:c the public notincation system. 'vVhcrc thcrc is a dccisicn :c ac'iva:c the iisiincaticii sys:cm, thc Staic and 1 - _. 1 Pf* _ ! _1_

... I l l 3_a___!__..L 4L__a-

.. a !.. a a l _ _ _ a ! _

aVw ua U4aawausa TV a an uwkwa sa usaw VV aawbaawa Lv uw ba V ubw La a.s waabaa w notincatica sys:cm simultancsus y cr in a gradus:cd or stagcd

_ _ _ _ TL _ _ _ _ _ _ _ I t.

1 :6.. f_ _ _ _ a... a ! _,... _ t.. _.. t_1 _

a nus u awa, a saw a wayvaaastlauty ava uv u v uuug auwas u yLaUnaw nctincation sys:cm shall rcmain with the appropria:c govcmmcntal authoritics.

E. Emergency Facilities and Equipment Section 6.3.3, " Personnel Monitoring" describes the various methods available Adequate provisions shall be made and described for for monitoring staff for radiation emergency facilities and equipment, including:

exposure. These methods include personnel dosimetry, portal monitors and

1. Equipment at the site for personnel monitoring; whole body counting.

I i

i 11 i

I i

~..

10CFR50.47(b) or Appendix E Standard.

Maine Yankee Defueled Emergency Plan

2. Equipment for determining the magnitude of and for Section 5.1," Area and Process Monitors",

continuously assessing the impact of the release of radioactive describes the systems used to detect and materials to the environment; initially assess releases of radioactive materials.

Section 6.2," Radiological Assessment",

details the methods to assess the overall impact of a radioactive release.

3. Facilities and supplies at the site for decontamination of Decontamination of onsite individuals is onsite individuals; covered in Section 6.3.4,

" Decontamination". Kits are located in the Staff Building and can be transported to any of the specified assembly areas as needed.

4. Facilities and medical supplies at the site for appropriate Section 6.3.2,"First Aid / Medical emergency first aid treatment; Response" addresses this standard.

5. ' Arrangements for the services of physicians and other Letters of Agreement (LOA) exist with medical personnel qualified to handle radiation emergen;ies the Mid-Coast Hospital (Brunswick, ME) on-site; and Maine Medical Center (Portland, ME) for treating personnelinvolved in radiological medical emergencies, over exposures or radiologically contaminated injuries. In addition, a Memorandum of Understanding (MOU) has been entered with the above facilities relative to the protocols to be followed in managing such incidents. These facilities maintain liaison with specialists in treating radiation induced injuries. These documents are referenced in Appendix I,

" Assistance Agreements".

6. Arrangements for transportation of contaminated injured An LOA exists with the Wiscasset individuals from the site to specifically identified treatment Ambulance Service to provide facilities ~outside the site boundary; transportation ofinjured personnel l

(including those exhibiting radiological contamination) to one of the facilities that have agreed to provide definitive care for such injuries. This LOA is referenced in Appendix I," Assistance Agreements".

12

10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan

7. Arrangements for treatment cfindividuals injured in support See items 5 and 6 above.

oflicensed activities on the site at treatment facilities outside the site boundary

8. A licensee onsite technical support center and c liccascc A Technical Support Center (TSC) has near-site ca.crgency opere:iens facility from which effective been designated on the first floor of the direction can be given and effective control can be exercised Staff Building, it is described in Section during an emergency; 7.2," Technical Support Center". This facility has sufficient space and

)

equipment for the ERO to manage the anticipated spectrum of accidents.

9. At least one onsite and one offsite communications system; The communications systems, including each system shall have a backup power source.

backup power sources are described in Sections 7.5.1 and 7.5.2,"Onsite.

Communications Systems" and "Offsite Communications Systems". Provisions have been made for loss of normal power somces to each primary system. In addition, alternative communications

- )

systems are available for use by the ERO.

I All communication plans shall have arrangements for Section 7.5.2, "Offsite Communications emergencies, including titles and alternates for those in charge Systems" describes the methods and at both ends of the communication links and the primary and primary point of contact for offsite backup means of communication. Where consistent with the notification.

function of the governmental agency, these arrangements will i

include:

Section 9.2.4.2,"Offsite Systems" commits that these systems will be tested

a. Provision for communications with contiguous State / local on a quarterly basis.

governments within the plume exposurc pc:hway EPZ. Such communications shall be tested monthly quarteriv.

b. Provision for communications with Federal emergency Section 7.5.2, "Offsite Communications

~

response organizations. Such communications systems shall be Systems" describes the methods and tested annually.

primary point ofcontact for offsite notification.

I Section 9.2.4.2,"Offsite Systems" commits that these systems will be tested on a quarterly basis.

13

... ~,

,.--1

10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan

c. Provision for communications among the nuclear power Section 7.5.1, Onsite Communications reactor control room, the onsite technical support center, and Systems" describes the means for thc acar-si;; cmcrgcncy opcreticas facility; and among the communication between the Control nucicar facility, the principal S atc and Iccal emergcncy Room and the TSC.

opcrations centers, and the ficid asscasment : cams. Such communications systems shall be tested annually.

Section 9.2.4.1, "Onsite Systems",

describes the communications systems checks for onsite facilities.

d. Provisions for communications by the licensee with NRC The NRC Emergency Notification System Headquarters and the appropriate NRC Regional Office (ENS) has been retained in the Control Operations Center from the nuclear power reactor control Room. It is described in Section 7.5.2.4, room,-the casitc ;cchnical supper; cca:ct, and the acar-site "NRC Emergency Notification System sumeum.7 wmiens facility. Such communications shall be (ENS).

tested quarterly monthly.

Section 9.2.4.2 specifies the commitment for a quarterly surveillance of this system.

F. Training.

ERO training provisions are described in Section 9.1," Training". An.'imergency

1. The program to provide for: (a) The training of employees Plan Training Program has been and exercising, by periodic drills, of radiation emergency plans developed that specifies the required to ensure that employees of the licensee are familiar with their elements for inclusion in the it itial specific emergency response duties, and (b) The participation training for ERO qualification md in the training and drills by other persons whose assistance continuing training to maintain may be needed in the event of a radiation emergency shall be qualification. Each ERO position has described. This shall include a description of specialized initial been reviewed to determine the training and periodic retraining programs to be provided to appropriate lessons to be administered to each of the following categories of emergency personnel:

ensure the ERO member has the

i. Directors and/or coordinators of the plant emergency rudimentaryjob knowledge to perform organization; their respective tasks.

ii. Personnel responsible for accident assessment, including control room shift personnel; All Maine Yankee staff are located at the iii Radiological monitoring teams; site, as such there are no " headquarters iv. Fire control teams (fire brigades);

support personnel".

v. Repair and damage control teams; vi. First aid and rescue teams; vii. Medical support personnel; vni. Licenscc's headquar:crs supper; pcracnnc!;

ix. Security personnel, t

i i

1 14

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

10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan i

In addition, a radiological orientation training program shall be Section 9.1.3,"Offsite Assistance made available to local services personnel; e.g., local Training" commits to offering training to emergency services / Civil Defense, local law enforcement those organizations that might be called personnel, local news media pcssons.

upon to assist in an emergency. This l

training will be offered annually and l

covers general facility layout /walkdowns, industrial and radiological safety, access, communications and specific responsibilities consistent with the j

organization's function.

L

2. The plan shall describe provisions for the conduct of Drill and Exercise commitments are found emergency preparedness exercises as follows: Exercises shall in Section 9.3," Drills and Exercises".

l test the adequacy of timing and content ofimplementing l

procedures and methods, test emergency equipment and communications networks, cst the pubi;c no:if, cation sys:cm, and ensure that emergency organization personnel are familiar with their duties.

b. Each licensee at each site shall conduct an exercise ofits In Section 9.3.2, " Exercise", Maine onsite emergency plan every 2 years. The excalsc may bc Yankee commits to conducting an f.ncluded in the full panidpation bic. Ja! cxcrdsc required by exercise of the emergency plan annually.

j parag. yh 2.c. of this acc;ica. In addition, the licensee shall The scenario will be developed to test as take actions necessary to ensure that adequate emergency much of the major elements of the plan as j

response capabilities are maintained during the interval is practicable (based on the scope of the between biennial exercises by conducting drills, including at exercise). The sequence of events is least one drill involving a combination of some of the intended to mimic the credible spectrum principal functional areas of the licensee's onsite emergency of accidents expected in the defueled response capabilities. The principal functional areas of condition.

emergency response include activities such as management and coordination of emergency response, accident assessment, The exercise and evaluation process shall protective action decision making, and plant system repa'r and serve as the primary means of validating 1

corrective actions. During these drills, activation of all of the the overall effectiveness of the emergency licensee's emergency response facilities (Techmical Supper preparedness program. Section 9.3.3, Ccatcr (TSC), Opcm: ions Suppen Cen:ct (OSC), and the

" Drill and Exercise Evaluation" outlines Emergency Opera; ions facility (EOF)) would not be the process for evaluating drills and necessary, licensees would have the opportunity to consider exercises, including follow-up actions for l-accident management strategies, supervised instruction would program enhancements based on be permitted, operating staff would have the opportunity to evaluator observations and player resolve problems (success paths) rather than have controllers

feedback, intervene, and the drills could focus on onsite training objectives.

i 1

15

10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan

c. Offsite plans for cach sitc shall b; cxcrcised bicanially veith Not required per Reference 3.

full panicipation by cach offsite authority having a roic undcr the plan. 'A"icic the offsitc authority has a reic undcs a radiological responsc plan for merc than onc sitc, ;; shall fully participa:c in onc cxcrcisc cycry tvec ycars and shall, at leas:,

pania!!y participa c(5) in c hcr offai:c plan cxcrciscs in this PeM

d. A Sta:c should fully panicipa:c in the ingest;ca pathway Not required per Reference 3.

portion of cxcrciscs a: icast oncc cycrj six years. In Sta:cs wi h merc than onc sitc, the Staic shculd retaic this panicipation from site to sitc.

e. Licensees shall enable any State or local Government Section 9.3.2, " Exercise" commits to support servicc locatcd within the plume cxposure pathway inviting State and local offsite response EPZ to participate in the licensee's drills when requested by organizations (i.e. local fire, police or such State or local Government sunport service.

ambulance service) to participate in the annual exercise of the DEP.

)

f. Remedial exercises will be required if the emergency plan is State and local organizations (local fire, not satisfactorily tested during the biennial exercise, such that police or ambulance service) will be j

NRC,-in consultation with FEMA, cannot find reasonable invited to participate in drills and exercise assurance that adequate protective measures can be taken in (Section 9.3.2). Remedial exercises will the event of a radiological emergency. The cxicn of Statc and be conducted as necessary based on the local panicipation in remcdial cxciciscs must bc sufficicat ic results of the exercise evaluation process.

show that appropria:c corrcctivc mcasurcs havc bcca taken regarding thc cicmcnts of the plan not propcily cs:cd in the picvious cxcrciscs.

g. All training, including exercises, shall provide for fonnal Section 9.3.3 provides for evaluation of critiques in order to identify weak or deficient areas that need exercises. Maine Yankee training correction. Any weaknesses or deficiencies that are identified procedures specify criteria for evaluating shall be corrected.

the effectiveness of training evolutions and the requirements for follow-up and corrective actions, as necessary.

h. The participation of State and local governments in an Section 9.3.2, " Exercise" commits to emergency exercise is not required to the extent that the inviting offsite response organizations applicant has identified those governments as refusing to (i.e. State and local fire, police or participate further in emergency planning activities, pursuant ambulance service) to panicipate in the to 10 CFR 50.47(c)(1). In such cases, an exercise shall be held annual exercise of the DEP.

with the applicant or licensee and such governmental entities as elect to participate in the emergency planning process.

16

1 10CFR50.47(b) or Appendix E Standard Maine Yankee Defueled Emergency Plan G. Maintaining Emergency Preparedness Section 9.0 outlines the general processes for maintaining the emergency Provisions to be employed to ensure that the emergency plan, preparedness program, its implementing procedures, and emergency equipment and supplies are maintained up to date shall be described.

Section 9.2, " Review and Updating of the Defueled Emergency Plan and Implementing Procedures" describes the processes for reviewing the plan, procedures and conducting readiness surveillances for facilities and equipment.

i H. Recovery Recovery is addressed in Section 10,

" Recovery".

Criteria to be used to determine when, following an accident, reentry of the facility would be appropriate or when operation could be resumed shall be described.

V. Implementing Procedures A set ofImplementing Procedures has been developed in concert with the No less than 180 days prior to the scheduled issuance of an Defueled Emergency Plan. The list of operating license for a nuclear power reactor or a license to procedures is found in Table 1-1, possess nuclear material the applicant's detailed implementing "Defueled Emergency Plan Implementing procedures for its emergency plan shall be submitted to the Procedures". The procedures were Commission as specified in @50.4. Licensees who are developed and validated during several authorized to operate a nuclear power facility shall submit any table top drills with the proposed ERO.

changes to the emergency plan or procedures to the Each functional position was reviewed to Commission, as specified in Q50.4, within 30 days of such determine the appropriate content of the changes procedure set to ensure the commitments of the plan were adequately addressed and an effective, coordinated response could be mobilized.

t l

l 17

1 3.0 JUSTIFICATION FOR CilANGE 3.1 Design Basis Accident Reduced Maine Yankee submitted a Certificate of Pemianent Cessation of Operations and a Certification of Permanent Removal of Fuel to the NRC in a letter dated August 7,1997. As a result, the Maine Yankee

]

10CFR50 license no longer allows operation of the reactor or replacement of fuel in the reactor vessel pursuant to 10CFR50.82.

The Maine Yankee Emergency Plan (MYEP) was developed in accordance with 10CFR50.47 and 10CFR50 Appendix E, to provide reasonable assurance that public health and safety would be protected in the event of a nuclear accident. As a result of the decision to permanently shut down the reactor and l

discontinue operation, the range of accidents that could occur have been substantially reduced in scope, j

l number and severity.

l The Defueled Safety Analysis Report (DSAR) in Section 5.0, discusses the radiological consequence analysis for the range of credible accidents for Maine Yankee. The general classification of accidents for the permanently defueled condition are limited to:

l 1.

Inadvertent criticality of the stored spent fuel, 2.

Fuel assembly handling accident, 3.

Spent fuel shipping cask drop in the spent fuel, i

4.

Loss of spent fuel decay heat removal capability, 5.

Loss of spent fuel poolinventory, 6.

Radioactive release from a subsystem or component, or 7.

Low level waste storage accident.

Each of these accidents was evaluated using conservative initial conditions and analytical methodologies as detailed in Section 5.0 of the DS AR. In the defueled condition, the potential to have a radioactive release that impacts the area beyond the site boundary is significantly reduced. Analyses that have been submitted in support of this Defueled Emergency Plan and Defueled Technical Specifications indicate that any release will not result in doses beyond the site boundary that will exceed the EPA Protective Action Guidelines l

(Reference 4).

The bounding radiological event has been determined to be a Low Level Waste Storage Building Accident.

This accident involves the dropping of a highly loaded spent resin liner within the building, resulting in liner failure, spillage of the spent resin, and the release of a fraction of the radioisotopic contents as a cloud to the environment. The contents of this cloud for the basis for determining the radiological source term at the site boundary. Based on the analysis performed for this event, the site boundary TEDE dose consequence equates to 110 millirem which is well below the EPA PAG lower limit of 1,000 millirem.

l In addition to the postulated accidents associated with the permanently defueled Maine Yankee plant, Maine Yankee analyzed the potential consequences of a beyond design basis accident associated with the complete loss of the spent fuel pool water (Zirconium fire scenario). The analysis demonstrated that after January 16,1998 the natural circulation of air was sufficient to keep the fuel cladding temperature below zirconium oxidation temperature criterion (565 *C) and thus Maine Yankee is not susceptible to this 18 I

l

.. -. -. - - - -. - - - -. -.. ~ - -

incredible event (Reference 5).

3.2 Reenlatory Reautrements still mit

. Part 50.54(q) to 10CFR50 requires in part that a licensee authorized to possess and operate a nuclear power reactor maintain in effect emergency plans which meet the planning standards of 10CFR50.47 (b) and the requirements of 10CFR50 Appendix E. Maine Yankee is no longer authorized to operate its nuclear power reactor pursuant to 10CFR50.82. 10CFR50.54 (q) states, in part, "The nuclear power reactor licensee may

. make changes to (their emergency plan) without Commission approval only if the change does not decrease -

the effectiveness of the plans and the plans, as changed, continue to meet the standards of 50.47 (b) and the requirements of Appendix E of this part".

Maine Yankee has submitted specific exemptions from 10CFR50.47(b) and Appendix E consistent with the exemptions approved for facilities in similar circumstances. These exemptions ensure that the Defueled Emergency Plan addresses the appropriate standards that pertain to a defueled facility and provide reasonable assurance that credible events are dealt with in a manner consistent with the reduced risk to the

. general public and facility staff. The NRC granted relief from certain emergency planning requirements (Reference 3). As presented in the foregoing analysis, the plan meets the remaining standards and conditions identified in the regulations.

4.0 CONCLUSION

The purpose of an Emergency Plan is to provide reasonable assurance that the public will be adequately protected in the event of a nuclear accident. In determining whether a proposed change to an Emergency Plan decreases the effectiveness of the plan, one must evaluate whether the degree of assurance that the public would be adequately protected in the event of a nuclear accident has been adversely impacted by the contemplated change.

These changes to the response to an emergency in the defueled condition, do NOT decrease the effectiveness of the Emergency Plan, for the reasons stated above and summarized below:

1.'

The risk.s associated with the facility in its defueled condition have been analyzed and documented to be significantly less than the risks posed by an operating plant; 2.

An organization has been designed and put in place to respond to the credible range of events associated with the facility in the defueled condition; 3.

Equipment and facilities have been designated for use during emergency conditions and are maintained in a constant state of readiness to assure availability to the response organization, 4.

Means for assessing the radiological status of the facility (including spent fuel in the SFP) have been modified to specifically address the revised source term in the defueled condition.

For these reasons, this change to the MYEP does not decrease the effectiveness of the Plan to meet any of the applicable planning standards of 10CFR50.47(b), nor any requirements of Appendix E to 10CFR Part 4

50 (as committed to in Reference 1). These changes have been reviewed by the Nuclear Safety Regulatory 19 i

d Affairs Subcommittee. It has been determined that these changes:

(1)

. Do not decrease the effectiveness of the Plan, under defueled/non-operating conditions, resulting in

~ he loss of reasonable assurance that adequate protection can and will be taken in the event of a t

radiological emergency as required by 10CFR50.47 (a);

(2)

Do not result in the loss of ability to meet any of the standards described in 10CFR50.47(b) and Appendix E, or any NRC approved attematives to these requirements; (3)

Do not delete or contradict any applicable regulatory requirement.

5.0 REFERENCES

1.

Letter: M. J. Meisner to USNRC. Defueled Emergency Plan and 10CFR50.54(q)- Exemption Request, (MN-97-119) dated November 8,1997.

2.

Letter: G. A. Zinke to USNRC. AdditionalInformation Regarding Request for Exemptions from 10CFR50 Requirements, (MN-98-47) dated June 29,1998.

3.

Letter: USNRC to M. J. Meisner. Exemption From Certain Requirements of 10 CFR 50.54 (q),

10 CFR 50.47 (b) and (c), and Appendix E to 10 CFR 50 at Maine Yankee Atomic Power Station (TAC No MA00059) dated September 3,1998.

4.

EPA-400, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (October,1991).

5.

Letter: G. A. Zinke to USNRC. Supporting Information for the Defiteled Emergency Plan and Financial Protection Exemption Requests, (MN-98-40) dated May 15,1998.

2 I

20

4 DEFUELED EMERGENCY PLAN MAINE YANKEE ATOMIC POWER COMPANY WISCASSET, MAINE l

4 August 1998 Y

l TABLE OF CONTENTS Section Eage TABLE OF CONTENTS 11 APPENDICES iv LIST OF TABLES v

LIST OF FIGURES vi DEFINITIONS vii

1.0 INTRODUCTION

1.1 l

2.0 FACILITY DESCRIPTION 2.1 Maine Yankee Site 2.1 2.2 General Area 2.1 2.3 Spent Fuel PoolIsland 2.1 3.0 TYPES OF ACCIDENTS 3.1 Radiological Accidents 3.1 3.2 Non-radiological Events 3.2 4.0 CLASSIFICATION OF ACCIDENTS 1

4.1 Definitions 4.1 4.2 Categories of Events 4.1 5.0 DETECTION OF ACCIDENTS 5.1 Area and Process Monitors 5.1 5.2 System Status Monitors 5.1 6.0 EMERGENCY RESPONSE 6.1 Notification and Activation 6.1 6.1.1 Maine Yankee Staff 6.1 6.1.2 Offsite Organizations 6.2 6.1.3 Information to be Communicated 6.2 6.2 Radiological Assessment 6.2 6.3 Protective Actions 6.3 6.4 Coordination with Offsite Agencies 6.5 6.5 Public Information 6.5 7.0 FACILITIES AND EQUIPMENT 7.1 Control Room 7.1 7.2 Technical Support Center 7.1 7.3 Radiation Controls Checkpoint 7.1 7.4 Assembly Areas 7.2 7.5 Equipment 7.2 l

l ii August 1998 i

_.. _ ~ _

TABLE OF CONTENTS (continued)

Section Easa 8.0 RESPONSIBILITIES 8.1 Organizational Control of Emergencies 8.1 8.1.1 On-shift Organization 8.1 8.1.2 Augmented Organization 8.2 9.0 MAINTAINING EMERGENCY PREPAREDNESS 9.1 Training 9.1 9.2 Review and Updating of the Defueled Emergency Plan and Implementing Procedures 9.2 9.3 Drills and Exercises 9.3 9.4 Independent Program Review 9.4 10.0 RECOVERY 10.1 11.0 OFFSITE ASSISTANCE 11.1

12.0 REFERENCES

12.1 s

i lii August 1998

APPENDICES APPENDlX l-Assistance Agreements 1-1 APPENDIX ll - Supporting Plans and Documents ll-1 q.

iv August 1998

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

LIST OF TABLES

- Number Ijtig Eag.e 1-1

. Defueled Emergency Plan Implementing Procedures 1.2 4-1 Emergency Classification System Events' 4.2 6-1 Guidance on Dose Limits for Emergency Workers (EPA-400-R-92-001) 6.4 1

4 v

August 1998

LIST OF FIGURES Number Title Page 2 Maine Yankee Site - General Area 2.3 2-2 Maine Yankee Site - Facility Layout 2.4 6-1 Maine Yankee Site Initial Notification and Activation Process 6.7 7-1 Technical Support Center 7.5 7-2 Assembly Areas 7.6 7-3 Communications Systems 7.7 8-1.

Maine Yankee On-Shift Organization 8.6 8-2 Maine Yankee Emergency Response Organization 8.7 l

vi August 1998

DEFINITIONS 4

a ALERT -The highest event classification recognized in the defueled condition. Events are in process or have occurred which involve an a@l or potential degradation of the level of safety of the plant. Any releases are expected to be limited to a small fraction of the EPA Protective Action Guide (PAG) Exposure Levels.

ASSEMBLY AREAS - Designated locations where personnel may be directed to

~

congregate in the event of the need to evacuate all or portions of the facility.

CONTROLLED ACCESS AREA (CAA) -The area that encompasses the Fuel Building and the Spent Fuel Pool.

EMERGENCY ACTION LEVEL (EAL)- Conditions that, if met or exceeded, warrant classification and declaration of an emergency.

EMERGENCY DIRECTOR (ED)- The senior management representative assigned to the Emergency Response Organization (ERO). The ED is responsible for the overall l

coordination and direction of the company response to an emergency condition.

EMERGENCY RESPONSE ORGANIZATION - A group of trained staff designated to respond to a declared emergency.

1 INDUSTRIAL AREA - The owner controlled area outside of the Controlled Access Area (CAA) lNITIATING CONDITION - Plant parameters, equipment status and/or personal observations that comprise the individuai EALs.

LOCAL ORGANIZATIONS - Those organizations that provide specific services under emergency conditions (i.e. police, ambulance and fire department).

PROGRAMMABLE LOGIC CONTROLLER (PLC)- Computer based system that allows remote control and indication of Spent Fuel Pool Systems and auxiliaries. PLC terminals are located in the Control Room and Technical Support Center (TSC).

4 I

SHIFT MANAGER (SM) - The senior management representative on-shift. The SM assumes the position of Emergency Director until relieved of ED functions by another l

ED qualified individual. The SM normally works in the Control Room.

SITE BOUNDARY (0.5 mile)- The owner controlled area established at 0.5 mile from the plant, where EAL limits have been defined in accordance with the ODCM and EPA guidance.

SPENT FUEL POOL ISLAND (SFPI) -The portion of the facility that contains systems and equipment necessary for monitoring and maintenance of the spent nuclear fuel stored on the Maine Yankee site. It has been designed to be independent from the remainder of the facility such that dismantlement operations can proceed without impacting the safe storage of the spent fuel.

vii August 1998

DEFINITIONS (continued)

TECHNICAL SUPPORT CENTER (TSC) - An onsite facility, located on the first floor of the Staff Building, where actions are taken and coordinated in response to an emergency condition.

UNPLANNED RADIOLOGICAL RELEASE - An unnlanned release of radioactive material, in gaseous and/or liquid state, that causes a valid alarm on radiation monitoring effluent instrumentation and is directly attributable to the event or is a result of intentional venting, to the environment, of structures, systems or components (e.g.

Spent Fuel Pool) containing radioactive material from the event.

UNUSUAL EVENT - The least severe event classification recognized in the defueled condition. Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant. No release of radioactive material requiring offsite response or monitoring are expected.

l l

viii August 1998

~. -

PAGE LIST l

EAGE CURRENT REVISION TOC (ii)

August 1998 TOC (iii)~

August 1998 APPENDICES (iv)

August 1996 LIST OF TABLES (v)

August 1998 LIST OF FIGURES (vi)

August 1998 DEFINITIONS (vii)

August 1998

- DEFINITIONS (viii)

August 1998 PL-1 August 1998 PL-2 August 1998 1.1 August 1998 1.2 August 1998 2.1 August 1998 2.2 August 1998 2.3 August 1998 2.4 August 1998 3.1 '

August 1998 3.2 August 1998 3.3 August 1998 4.1 August 1998 4.2 August 1998 5.1 August 1998 6.1 August 1998 6.2 August 1998 6.3 August 1998 6.4 August 1998 6.5 August 1998 6.6 August 1998 6.7 August 1998 7.1 August 1998 7.2 August 1998 7.3 August 1998 7.4 August 1998 7.5 August 1998 7.6 August 1998 7.7 August 1998 8.1 August 1998 8.2 August 1998 8.3 August 1998 8.4 August 1998 8.5 August 1998 l

8.6 August 1998 l

8.7 August 1998 l

9.1 August 1998 9.2 August 1998 PL-1 AUGUST 1998

.. - ~......

PAGE LIST PAGE CURRENT REVISION 9.3 August 1998 9.4 August 1998 10.1 August 1998 11.1 August 1998 12.1 August 1998 APPENDlX l-1 August 1998

= APPENDIX 11-1 August 1998 4

4

(

l PL-2 AUGUST 1998

1.0 INTRODUCTION

This document describes the Maine Yankee Atomic Power Company's plan for responding to emergencies that may arise at the Maine Yankee site while in a permanently shutdown and defueled condition. In this configuration, no reactor operations can take place. The fuel is stored in the Spent Fuel Pool and the plant is prohibited from moving the fuelinto the reactor vessel. An analysis of the possible design basis events and consequences is presented in the Defueled Safety Analysis Report (DSAR).

The analyses of the potential radiological impact of an accident at Maine Yankee in the permanently defueled condition indicates that any releases beyond the exclusion area boundary are expected to be less than the U.S. Environmental Protection Agency (EPA) protective action guide (PAG) exposure levels, as detailed in EPA-400-R-92-001," Manual of Protective Action Guides and Protective Actions for Nuclear incidents" (Ref.1). Exposure levels which may warrant pre-planned

)

response measures are generally limited to the Site Boundary. For this reason, l

radiological emergency planning is focused on the Site Boundary.

The plan acknowledges the substantially reduced risk of any potential accidents in the plant's permanently shutdown and defueled configuration and the associated reduced consequences. This plan reflects the fact that Maine Yankee has been

]

permanently shutdown and defueled and therefore poses a significantly reduced potential risk to the public's health and safety. The overall purpose of the plan is to delineate the actions necessary to safeguard plant personnel and minimize damage to site property in the event of an incident at the plant.

A set of Emergency Plan Implementing Procedures (EPIPs) has been developed in support of this plan. These procedures contain the necessary information for the Emergency Response Organization (ERO) to ensure the committments of this plan are met in the event of an emergency at Maine Yankee. A complete listing of the EPlPs is found in Table 1-1, Defueled Emerency Plan Imolementina Procedurgt i

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l 1.1 August 1998

TABLE 1-1. DEFUELED EMERGENCY PLAN IMPLEMENTING PROCEDURES Number Title 2-50-0 EMERGENCY CLASSIFICATION, NOTIFICATION AND ERO ACTIVATION 2-50-1 EMERGENCY DIRECTOR ACTIVITIES 2-50-2 TSC ACTIVATION AND OPERATION 2-50-3 TECHNICAL RESPONSE COORDINATOR ACTIONS 2-50-4 DAMAGE CONTROL COORDINATOR ACTIONS 2-50-5 RADIOLOGICAL ASSESSMENT COORDINATOR ACTIONS and DOSE PROJECTIONS -

.2-50-6 RADIOLOGICAL ASSESSMENT and MONITORING 2-50-7 EMERGENCY SECURITY ACTIONS 2-50-8 MEDICAL EMERGENCY RESPONSE 2-50-9 PUBLIC AFFAIRS COORDINATOR ACTIONS

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l 1.2 August 1998

2.0 FACILITY DESCRIPTION 2.1 Maine Yankee Site 2.1.1 Overview The Maine Yankee site is located in the town of Wiscasset, Lincoln County, Maine. Site coordinates are approximately 43 degrees 57 minutes 5 seconds north latitude and 69 degrees 41 minutes 45 seconds west longitude. The site, of approximately 820 acres, is bounded by the Back River on the east, mainland on the north and Birch Point Road on the west. In addition, Maine Yankee owns Foxbird Island and Little Oak Island. The plant is located on a peninsula known as Bailey Point which extends south to Montsweag Bay (Figure 2-1).

The site (Figure 2-2) consists of an Industrial Area, the Controlled Access Area (which encompasses the Spent Fuel Pool Island), support systems and several office / administration buildings. Deconstruction and dismantling operations will take place within the Industrial Area, with the various systems, components and buildings / structures being systematically removed in accordance with the general decommissioning plan.

Spent nuclear fuel will be placed in long term storage within the specified secure fuel storage area and will be monitored by both an operating crew and the security force.

2.2 General Area Within 5 miles ofibo site, land use is largely rural residential, small businesses, summer houses, idle farmland and forest. Housing is scattered along principal roads and is cor centrated only in the center of Wiscasset.

The waters of the Back River, Montsweeg Bay and associated tributaries are tidal and open to boating, both commercial and recreational. Regulation of this boating is the responsibility of the U.S. Coast Guard and the State of Maine.

These waters are reported to be relatively low in the production of fish and shellfish. The primary type of boating in the Montsweag Bay - Back River is shallow draft pleasure boats. With no commercial traffic in the area, there is essentially no hazard to the site from potential accidents with commercial barges or boats carrying hazardous, toxic or explosive materials.

Industrial activity within the gerteral area of the plant is minimal. The largest industrial facility is the Bath iron Works, a shipbuilding facility located on the Kennebec River approximately 10 miles southwest in the city of Bath.

The Wiscasset Municipal Airport is the nearest airport to the site and is located over a mile northwest of the site. It consists of one runway (approximately 3,400 feet long by 75 feet wide). This runway is aligned such that takeoffs and landings are on headings of either 070 or 250 (the predominant heading is 250).

The majority of aircraft that are serviced by this facility are privately owned and are similar to the Piper Colt, Cherokee, Cessna 150 and 172 type craft. The largest aircraft that typically use the facility are similar to the Lear 25, Citation 11 and Rockwell Commander type craft.

2.3 Spent Fuel PoolIsland The Spent Fuel Pool Island (SFPI) houses the Spent Fuel Pool (SFP) and 2.1 August 1998

associated systems for monitoring and cooling the spent nuclear fusl. The SFP Is constructed of reinforced concrete on bedrock. It has a reinforced concrete floor,6 foot thick sidewalls extending upwards from elevation -12' 6" below grade to 26' above grade and has interior dimensions of 41.5' x 37' x 38.5' The concrete structure is lined with stainless steel.

Structural steel supports a superstructure of protected metal siding which encloses the pool. The steel framing above the pool is designed for earthquake and tomado to prevent it from falling into the pool and damaging fuel assemblies.

The masonry wall at the south end of the Fuel Building is not designed for certain wind or earthquake loadings, and, therefore, an evaluation of the consequences of a wall collapse was performed. This analysis demonstrated adequate SFP cooling capability and structural rack integrity. (DSAR Sect.

3.2.1.4)

Instrumentation and alarms for monitoring general area radiation, exhaust ventilation radiation, SFP water level and temperature are located in this building and alarm in the Control Room. Access to this facility is controlled and monitored by the Security Staff.

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i 2.2 August 1998

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3.0 TYPES OF ACCIDENTS l

3.1 Radiological Accidents In the defueled condition, the spectrum of credible accidents is reduced to those involving the spent nuclear fuel and radioactive waste from the decontamination process. In these instances the immediate hazard is limited to personnel onsite at the time of the event. There are no credible design basis accidents or any other incredible postulated accidents that would exceed these limits at the Maine Yankee site boundary (refer to Maine Yankee DSAR, Chapter 5 for specific incident description and analysis results).

3.1.1 Fuel Handling Incident

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The fuel handling incident analyzed in the DSAR consists of dropping one assembly to the bottom of the SFP, rupturing all of the fuel rods in the assembly and eventually releasing fission products to the atmosphere. A reanalysis of this i

incident has determined that, one year after shutdown, the calculated whole body dose at the site boundary would be less than the US EPA PAGs. (Ref.1) 3.1.2 Spent Fuel Cask Drop The spent fuel shipping casks are designed to withstand a free fall of 30 feet onto an unyielding surface. The design of the Maine Yan'Kee spent fuel cask

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. handling system does not allow the casks to be at an elevation greater than 30 feet whenever the cask is not directly over the SFP. By system design, the spent fuel shipping cask does not pass over the spent fuel storage racks during transfer operations. At the current time, Maine Yankee is prohibited from lifting a spent fuel shipping cask over the SFP. Therefore, an accident analysis of a spent fuel shipping cask drop into the SFP is not required.

3.1.3 Radioactive Liquid Waste System Leaks and Failures These events involve release of radioactive materials from systems other than the Reactor Coolant System (RCS) and secondary system. Because of the continued processing of radioactive fluids during the defueled condition, the analysis of radioactive liquid waste system leaks and failures remains essentially the same as that used as the licensing basis for the plant during power J

operations. The use of the full power transient is used as representative of the maximum dose consequences associated with the offsite receptor due to a liquid and gaseous release. This transient is not a credible accident scenario in the defueled condition (DSAR 5.6.2). The analysis for this event assumes the Primary Drain Tank (PDT) contains undecayed, undegassed reactor coolant at the operational Technical Specification limits for activity. While the termination of reactor operations at Maine Yankee facility did not eliminate the postulated e

failure of the PDT, the production of radioactive liquids associated with reactor operation has ceased. Only the production of radioactive liquids from such functions as the SFP purification or decommissioning activities remain. Facility activities will be managed such that the doses resulting from radioactive liquid i

waste system failures will continue to be below the EPA PAGs.

3.1.4 Low Level Waste Storage Building Accident This accident involves the dropping of a highly loaded spent resin liner within the building, resulting in liner failure, spillage of the spent resin, and the release of a 4

i fraction of the radioisotopic contents as a cloud to the environment. The l

contents of this cloud form the basis for determining the radiological source term 3.1 August 1998

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at tha site boundary. Based on the analysis performed for this event, the sits boundary TEDE dose consequence equates to 110 millirem which is well below the EPA PAG lower limit of 1,000 millirem. As such, this accident is the 4

bounding radiological release event for Maine Yankee in the defueled condition.

1 3.2 Non-Radiological Events The spectrum of non-radiological events that could necessitate implementation of this Emergency Plan is also limited. The scope of these accidents involve events that could lead to a degraded response capability at the site or could lead to a more serious condition if not dealt rith in an expeditious and coordinated manner. These events fall into the category of general industrial incidents (e.g.

4 fire, explosion, toxic material release, etc.), natural and destructive phenomena (hurricane, tomado, etc.) or security events. These events are further. described in the DSAR Section 7.3. The determination as to which events are included is j

based on the probability of occurrence, the potential severity and the potential impact on the facility of the event.

i 3.2.1 Loss of System Monitoring Capabilities Various systems are employed to monitor the status of plant processes.

Although there are a limited number of conditions that could pose a threat to personnel onsite, the need to monitor system status is pertinent to the overall i

safety of the workers. Systems that need to be monitored include SFP cooling, j

fire detection and suppression, radiation area and process monitors and i

j meteorological monitors. An unexplained loss of any of these systems could constitute a situation requiring additional resources to both monitor the parameters and restore the monitoring capability.

3.2.2 Loss of Communications Systems The ability to maintain effective communications remains a key component of managing routine facility activities. In the event of an off-normal condition, the importance of basic communications capabilities to onsite staff and offsite organizations is elevated. The inability to contact either inplant staff or offsite organizations could result in a minor event escalating in severity such that station personnel are placed at risk.

3.2.3 Fire / Explosion and Toxic / Flammable Gas Exposures Events of this type are a concern since they may impact the ability to maintain the spent fuel in a safe configuration or alter the ability to monitor the status of the spent fuel and support systems. The need for a detailed assessment of systems and structures following a fire or explosion is emphasized in these situations since minor undetected damage could have an adverse impact on spent fuelintegrity.

Similarly, exposure to hazardous (toxic or flammable) gases could result in significant personnel safety issues that impact the facility operators' ability to perform required activities to maintain spent fuel integrity.

a 3.2.4 Security Compromise i;

Events that impact the security of the facility are discussed in the Security Plan.

In general, these events represent a threat to the level of safety of the plant duc to unauthorized access and physical evidence supporting a hostile intrusion into 3

designated secure areas.

3.2 August 1998

Evtnts that fill into thess creas V.'ill be categorized under the cpproprista category in the classification process discussed in Section 4, CLASSIFICATION OF ACCIDENTS.

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4.0 CLASSIFICATION OF ACCIDENT 4 I

There are no credible design basis accidents that would exceed the EPA PAGs at the l

Maine Yankee site boundary. Therefore, the Unusual Event and Alert are the only l

classifications recognized for all events. Events will be classified based on predetermined Emergency Action Levels (EALs). This approach provides a graded, i

predetermined response to the incident, allowing a coordinated and phased approach l

to the eventual mitigation of the conditions and restoring the facility to a safe status. In addition, it recognizes the limited potential hazard posed by the facility in the permanently defue'ed condition and fuel being stored in the SFP.

4.1 Definitions 4.1.1 Unusual Event Events are in process or have occurred which indicate a potential degradation of the level of safety of the plant. No release of radioactive material requiring offsite response or monitoring are expected.

4.1.2 Alert Events are in process or have occurred which involve an actual or potential substantial degradation of the level of safety of the plant. Any releases are expected to be limited to a small fraction of the EPA Protective Action Guide (PAG) Exposure Levels.

l 4.2 Categories of Events There are three categories of events that can lead to an event being classified as an emergency condition. These categories cover the spectrum of incidents that could pose a threat to the safe storage of spent fuel, facility staff, general population or any combination thereof (Table 4-1).

4.2.1 System Degradation Events that compromise the ability to monitor essential facility systems (SFP cooling, level, radiation monitoring, etc.) or the ability to establish and maintain communications (either within the facility or offsite).

4.2.2 Hazards / Security /ED Judgement These events pose a significant threat to safe operation of the facility and/or staff. In addition, the Emergency Director has the discretion to classify any event based on conditions that may not be included in the classification scheme, but may indeed threaten the facility / staff.

4.2.3 Abnormal Radiation LevelsIRelease of fiadioactive Materials During the decommissioning of the facility, the potential exists for elevated l

radiation levels to occur. Instances where the levels exceed anticipated values or radioactive materials are released in an uncontrolled manner that exceed l

i predetermined limits can lead to an emergency classification.

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l TABLE 4-1 EMERGENCY CLASSIFICATION SYSTEM EVENTS l

1.0 SYSTEM DEGRADATION 1.1 Loss of instrumentation j

1.2 Loss of Spent Fuel Pool (SFP) Cooling 1.3 Loss of Communications Capability 1.4 Spent Fuel Pool Leakage / Damage to Spent Fuel 2.0 HAZARDSISECURITY/ED JUDGEMENT 2.1 Fire or Explosion Affecting the Operability of Safety Systems Required to l

Maintain Nent FuelIntegrity 2.2 Natura Destructive Phenomena 2.3 Toxic or Hammable Gas l

2.4 Security Events l

2.5 ED Judgement 3.0 ABNORMAL RADIATION LEVELS / RELEASE OF RADIOACTIVE MATERIALS 3.1 Radiation Levels 3.2 Gaseous and Liquid Effluents l

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4.2 August 1998

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i 5.0 DETECTION OF ACCIDENTS 5.1 Area and Process Radiation Monitors 5.1.1 Area Radiation Monitors The Radiation Monitoring System (RMS) consists of various area monitors l

located throughout the facility. In the defueled condition, attention will focus on those monitors that provide an indication that the spent fuel has been compromised or a potential radiological hazard to workers in the facility exists.

The monitors of greatest interest are associated with the spent fuel pool building.

These monitors will be used to determine if an EAL has been met or exceeded, if evacuation is necessary for the area and to determine appropriate stay times for damage control / repair activities in effected areas. These monitors read out locally and in the Control Room.

5.1.2 Process Monitors l

The number and type of process monitors used for accident assessment is also limited to those which will indicate a compromise of the spent fuel, SFP integrity and radioactive waste processing systems. The monitor ofinterest is the Spent Fuel Building Exhaust Vent.

5.2 System Status Monitors 5.2.1 Spent Fuel Pool Parameters The SFP water level is maintained at a level to ensure the spent fuel remains covered with a sufficient volume of water to prevent exposing any elements under normal operating conditions. Systems are in place to provide makeup water to the SFP in the event of a system line break or liner rupture, in the event of a loss of water level, or under worst case boil off conditions (60 g.p.m.),

several sources of makeup water are available to maintain SFP level.

5.2.2 Fire Detection Systems There are numerous smoke and heat detectors throughout the plant, based on previously assigned Fire Zones. The system has visual and audible annunciators that alarm locally and in the Control Room. These systems provide input to the various fire suppression systems installed in the facility.

5.2.3 Meteorological Monitoring A meteorological tower is located onsite that monitors wind direction, wind speed, and ambient air temperature at elevations 197 feet and 35 feet. In addition, the system measures curnulative precipitation over a specific time span.

In the event the met tower is unavailable, meteorological information can be obtained from the National Weather Service (NWS) located in Gray, ME.

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5.1 August 1998 i

l 6.0 EMERGENCY RESPONSE l

Emergency Response Overview In the event of an accident at the facility, actions will be taken by facility staff to I

minimize the impact of the event. The primary objective of the initial responders is to assess the situation and minimize the risk imposed on workers and the general public. This involves operation / initiation of designated systems designed to mitigate a particular hazard. Subsequent actions include notifications, staff accountability and augmentation, implementation of onsite protective actions (sheltering and evacuation), contamination control, decontamination and first aid.

6.1 Notification and Activation When an emergency condition is recognized, the event is cla-ssified by the SM/ED and mitigative actions are taken to minimize the progression of the event.

These actions are initiated by available resources. As soon as practicable, the SM/ED will initiate notifications to augment the on-shift organization. The SM/ED l

will also request any offsite assistance that may be necessary due to the nature of the event. Following initial notifications, the NRC will be notified of the event and mitigative actions in progress or that have been completed.

i 6.1.1 Maine Yankee Staff The SM/ED will request Security to notify the ERO of the event. This will be accomplished by the paging service and/or commercial automated telephone dialing system. In the event the initiating conditions constitute a Security Event, these notifications will be carried out by the SM/ED or designee. Notifications to augmented ERO positions should be completed within 60 minutes of the event declaration.

6.1.1.1 Paging Service Maine Yankee contracts with a commercial vendor to provide individual and group-wide paging for key management and ERO staff. The contracted l

service covers the majority of the State of Maine, extends south into Southem New Hampshire and Northern Massachusetts. The system is capable of l

sending an alpha-numeric message to the individual pager-wearer to provide an indication of the level of severity of the event and reporting instructions.

This system is tested monthly to ensure individual pagers are operational and quarterly to verify ERO response capability. Personnel are assigned pagers based on their function in the ERO.

6.1.1.2 Computerized Automatic Telephone Dialing System A contracted service provides automatic dialing service to Maine Yankee staff. This system is activated coincident with the pager system to ensure a consistent message is delivered to augmciitation staff. The system is capable of contacting the home telephone of the specified employees, l

delivering either a pre-recorded message or one developed specifically for the incident and recording the estimated time-to-respond (TTR) of those members actually contacted. This system is tested quarterly and the lists of responders are reviewed and updated as necessary.

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6.1 August 1998

6.1.1.3 Manual Callout Process If the contracted paging service fails and/or the automatic telephone dialing system fails, members of the ERO will be contacted via a manual telephone cail out process, governed by an Emergency Preparedness Administrative Procedure.

6.1.2 Offsite Organizations Following notification of Maine Yan'<ee staff, the Maine State Police (MSP) will be contacted and provided pertinent information regarding the event classification, actions taken to mitigate the event and any potential assistance which may be necessary from State or local organizations (i.e. fire, ambulance, police response). Notification to the MSP shall be completed within 60 minutes of event declaration. Depending on the need for immediate outside assistance, these notifications may be initiated in an accelerated manner (i.e. Immediate need for firefighting capabilities or medical assistance). The MSP is staffed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months / day,7 days / week. The MSP have the capability to contact State and county emergency response personnel, if needed.

The MSP will initiate notification to State Officials in the Maine Emergency Management Agency (MEMA), Division of Health Engineering (DHE) and others as designated in the State's notification protocol, based on the event.

6.1.3 Information to be Communicated Following the declaration of an emergency and subsequent notification of the Maine Yankee ERO, the SM/ED will notify the State Waming Point (MSP) of the event. A prescripted format is used to ensure consistent information is provided to the MSP.

At a minimum, the following information will be provided during the initial notification of the event:

Event Classification; Datemme of Classification; Reason or events causing the condition; Status of release conditions (radioactive / chemical) and protective actions; Local meteorological conditions, as they apply to the situation; General description of damage to major structures / areas; Personalinjuries; Status of offsite assistance (fire / medical /other);

Name of person making notification; Date and Time of notification.

The information will be verified, via repeat back, to ensure it was accurately communicated.

6.2 Radiological Assessment Using the instrumentation available, as described in Section 5.0, the initial response to an event will be to ascertain the cause, mitigate further progression and determine the potential impact to ctation personnel and the general public.

Initial assessment will consist of verifying the parameters that indicate a release 6.2 August 1998

may be in progress and initiating a dose assessment based on that information.

Initial dose assessment activities will be performed by the Shift Manager.

As soon as practicable, facility staff should initiate general area radiation surveys and airborne samples to deterrnine the actual extent of a radiological release.

Results of the surveys will be analyzed by facility staff to formulate an action plan to mitigate the event and restore the facility to a safe condition. Survey data will also be used, as appropriate, in any dose assessment techniques.

Once the TSC is staffed, the Radiological Assessment Coordinator (RAC) assumes responsibility for dose assessment activities and coordination of radiological surveys. The methodology to be used may consist of nomograms or hand calculations, depending on the severity of the event and the point of release to the atmosphere. The primary objective of these methods is to determine the maximum dose rate at the site boundary. From this information, i

protective actions can be formulated and implemented to minimize the risk to facility staff.

Following the termination of the event, environmental surveys (including, but not limited to water, soil, vegetation, etc.) may be required to determine the long-term impact of the event.

6.3 Protective Actions 6.3.1 Relocation and Accountability in the event of an ALERT declaration, personnel not directly involved with the response may be directed to relocate to an assembly area. Staff will be notified using the general paging system. An assembly area will be established, based on the nature of the event, at the Staff Building, Career Center, or other location determined by the ED. Once site personnel have been relocated, personnel accountability for the Controlled Access Area (CAA) will be determined, with the 4

goal of completing accountability within one hour. Security will maintain accountability of personnel, report any missing persons to the TSC and participate in Search and Rescue efforts, as necessary. Accountability of t

personnel within the Industrial Area will be coordinated by Security in conjunction with contractor representatives.

6.3.2 First Ald/ Medical Response Personal injuries will be reported to the Control Room as soon as possible after discoven/ of the injured party. Medical Responders will report to the scene and initiate first aid treatment to stabilize the patient and prepare for transport to a medical facility. First Aid kits are located in various locations in the facility.

Injurics may be complicated by the presence of radiation and/or a contaminating substance (chemical or radiological). The patient will be assessed to determine if a life-threatening condition exists and appropriate actions taken to either contain or remove the contamination. In addition, environmental factors will be taken into account regarding the need to stabilize the patient in place or remove to a safer area (i.e. lower radiation levels, etc.). Maine Yankee maintains a Letter of Agreement with the Wiscasset Ambulance Service for transporting injured / contaminated workers from the site to a receiving hospital. In addition, agreements have been made with the Midcoast Hospital (Brunswick) and Maine Medical Center (Portland) for treating personnel with various types of injuries / conditions.

6.3 August 1998

6.3.3 Pcrscnnti Manitcring l

Personnel working in knowa radiation areas will be issued dosimetry in accordance with existing radiation protection procedures. During emergency conditions, they will retain their dosimetry and report to either their assigned emergency station or the assembly area, if a person suspects they may be contaminated, they will be monitored as they pass through the RC checkpoint-portal monitors and at the assembly area as soon as practicable, If there is a possibility of intemal contamination, the person will undergo bioassay /whole body counting as soon as practicable, based on the nature of the event.

Emergency response personnel, arriving without dosimetry, will be issued dosimetry as needed for assigned tasks (i.e. damage control teams entering the hazard area).

Exposure control will be done in accordance with the site Radiation Protection and ALARA programs. Dose extensions may be granted in excess of the limits of 10CFR20 for special circumstances. These extensions will be in accordance with EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents. Extensions above the 10CFR20 limits must be approved by the Emergency Director. The anticipated emergency exposures are within the limits specified in fable 6-1, l

TABLE 6-1 GUIDANCE ON DOSE LIMITS FOR EMERGENCY WORKERS N l

Type of Activity TEDEM Condition All 5 Rem Maintain ALARA and to the extent practicable limit emergency workers to these limits Protecting Valuable Property 10 Rem Lower dose not practicable.

Life Saving or Protection of 25 Rem Lower dose not practicable.

Large Populations

>25 Rem Only on a voluntary basis to persons fully aware of the risks involved, including the l

numerical levels of doce at which acute l

effects of radiation will be incurred and numerical estimates of delayed effects.

(a) From EPA-400-R-92-001, Manual of Protective Action Guides and Protective Actions for Nuclear Incidents (b) Sum of the deep dose equivalent from the extemal sources and the committed dose equivalent from the internal exposures to nonpregnant adults from exposure and intake during an emergency situation. Dose limits to the eye should be 3 times the listed value. Dose limits to any other organ (including skin and body extremities) should be 10 times the listed value.

6.4 August 1998

6.3.4 D5centimincticn if possible, injuries should be decontaminated prior to transport to a medical facility. Decontamination facilities are available in the first aid room. If it is not feasible to decontaminate the patient, standard contamination control procedures should be employed to prevent the spread of contamination during.

transport.

Decontamination of evacuating facility staff will be accomplished as necessary at l

the assembly areas. Decontamination kits are available in the Staff Building and l

can be easily transported to the designated assembly area. All decontamination l

activities will be performed in accordance with existing Radiation Protection Department procedures.

6.3.5 Contamination and Hazard Exposure Control Surveys will be conducted to determine which areas contain contamination of either a radiological nature or hazardous substance. These areas will be l

identified by either marking with boundary rope or tape and access will be limited l

and controlled according to either the Radiation Protection department or Health l

and Safety procedures. Monitoring of the area will be conducted using l

appropriate equipment, based on the type of conhmination. All personnel l

required to work in the area will be provided appopriate personnel protective l

equipment (coveralis, respiratory protection equipment, gloves, etc.). The level l

of protection will be determincd by the Radiological Assessment Coordinator.

6.4 Coordination with Offsite Agencies There is no response required from State or local govemment agencies. State government response is expected to be limited to recording the notification of the l

emergency, periodically receiving updated information on the emergency, and coordinating public information news releases. Upon request, local government l

agencies (i.e. fire, police, ambulance) will respond to the plant during an l

emergency.

If needed, provisions exist for limiting traffic on roads leading to the Maine Yankee site. These actions would be coordinated through local law enforcement agencies (Wiscasset Police Department, Lincoln County Sheriff's Department) and, as necessary, the Maine State Police.

1 In case of a potential or actual release of radioactive material, the following actions may be taken by the State:

Department of Health Engineering may dispatch field mcaitoring teams to l

sun /ey for radiological releases and to monitor environmental impact, l

including ingestion concerns to verify additional actions are not required to protect the health and safety of the public.

Activation of the State EOC to coordinate with Maine Yankee requests regarding implementation of traffic control, or other response actions which may be deemed necessary based on the situation.

i 6.5 Public Information i

information to the general public regarding an emergency will be disseminated as necessary by the Maine Yankee Public Affairs Coordinator.

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Naws rel=s:s will be provided to the Stata press information staff for tha coordination of news releases, as necessary.

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FIGURE 6-1 MAINE YANKEE INITIAL NOTIFICATION AND ACTIVATION PROCESS l

CONTROL ROOM

'l (SHIFT MANAGER) i-ENS D

NE STATE SECURITY NRC POLICE SUPERVISOR (MSP) i P

MAINE YANKEE p

ERO MAINE EMERGENCY DEPT.OF GOVERNOR MANAGEMENT HEALTH AGENCY ENGINEERING P

P - Paging System D - Dedicated Telephone STATE ERT ENS - NRC Emergency Notification System TEAM 6.7 August 1998

7.0 FACILITIES AND EQUlPMENT 7.1 Control Room l

The Control Room is the primary facility where plant conditions are monitored and controlleo and corrective actions are taken to mitigate any abnormal occurrence (Fig. 2-2). The Control Room has been designed with adequate -

sheilding and ventilation to maintain tolerable radiation and temperature levels for the operating staff. Systems that monitor the various processes necessary to maintain the spent fuel in a safe configuration have annunciators that alert the operating staff to abnormal conditions. In addition, the radiation monitoring system provides audible alarms in the Control Room.

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Emergency conditions classified as Unusual Events are managed by the SM/ED from the Control Room.

Onsite notifications will be made immediately upon recognition that an abnormal l

condition exists and are intended to inform personnel of the condition and any actions necessary to mitigate the event or to minimize personal risk to the workers. Offsite notifications will be completed withia 60 minutes of an event declaration and are intended to provide general information and/or to request specific assistance in dealing with the event.

l 7.2 Technical Support Center The Technical Support Center (TSC)is located on the first floor of the Staff Building (Fig. 7-1). This building is constructed of 12 inches of reinforced concrete. All walls are below ground level with the exception of approximately 50% of the south wall. The ceiling is constructed of solid concrete, varying in thickness from 8 % inches to 10 % inches.

Access to the Control Room and other areas of the plant during emergency l

l conditions may be via the personnel tunnel that connects the south end of the first floor of the Staff Building to the Turbine Building.

The TSC provides space for the designated members of the Emergen :y Response Organization (ERO) to conduct analysis and support functions for the Control Room staff 'n response to the event. The TSC will be activated for any event classified as en ALERT and may be activated for other reasons at the discretion of the Shift Manager / Emergency Director, in addition, the following functions will be coordinated from the TSC: emergency management, subsequent event classifications, offsite notifications and communication, Damage Control / Repair coordination and facility restoration planning.

The TSC is sized to accommodate approximately 35 responders performing general engineering and analysis tasks. Communication systems are available to allow interaction with the Control Room, general facility locations and offsite organizations, as necessary. Various equipment has been assembled and stored in or near the TSC for use by the ERO, including Personal Protective Equipment, SCBA, radiation monitoring and sampling equipment. The TSC has space to accomodate offsite officials.

7.3 Radiation Controls Checkpoint l

The Radiation Controls (RC) Checkpoint is located in the WART Building at the 7.1 August 1998

entranca to the Spent Fuel Pool Island area. There are portal monitors, friskors and a radiological emergency kit available in this location.

7.4 Assembly Areas Personnel that are directed to evacuate the Industrial Area will be directed to l

report to one of several predesignated assembly areas (Fig. 7-2). The Career Center is located diagonally across the access road from the Administration Building. It can accommodate approximately 100-150 people and is not intended to be used for any response activities or staging operations.

I The Staff Building is located in the Industrial Area, north of the Controlled Access Area and can accommodate approximately 200 people. Portions of the building provide some level of shielding from direct radiation.

7.5 Equipment Equipment is maintained for emergency response activities in various locations on site. The majority of equipment is located in the Staff Building, Room 116 and in the TSC. Additional equipment is located in the Control Room. Supplies are inventoried on a quarterly basis to ensure operability and availability at all j

times. Equipment for responding to radioactive or hazardous materials spills are i

maintained by the respective departments' processes.

l Controlled copies of facility documents (drawings, procedures, Technical l

Specifications, DSAR, etc.) are maintained in the areas adjacent to the TSC.

This information is readily available for ERO use.

l 7.5.1 Onsite Communication Systems 7.5.1.1 Commercial Telephone System The Commercial Telephone system (PBX) is the primary means of onsite communication during an emergency. The telephone system is normally powered from the station switchgear. The backup power source to the PBX system is an onsite emergency diesel generator. in the event of a loss of normal power to the station switchgear, there may be a period of up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months before the station emergency diesel is available to supply the PBX. To ensure continuous communications, several " power-fail" telephones are available in the TSC and Control Room. These telephones are powered from the Bell Atlantic System. This system has an independent backup power configuration which incorporates a combination of automatic transfer switches between batteries and an emergency diesel generator to ensure uninterruptable operation on a loss of normal power to their system.

7.5.1.2 Alternate Onsite Communications Systems 7.5.1.2.1 Plant Radio System Maine Yankee has several radio frequencies licensed through the FCC for use by plant staff for routine operations and maintenance activities. There are also frequencies for emergency preparedness activities and Security functions. Base stations and portable radios are located in the Control Room and TSC area. Radio coverage is supplemented by repeaters located onsite.

7.5.1.2.2 FEMCO System General plant paging and voice communication are available between the Control Room, Spent Fuel Pool Island and Staff Building.

7.2 August 1998

7.5.2 Offsits Communicitiona Systems 7.5.2.1 Dedicated Telephone to the Maine State Police A dedicated telephone circuit is maintained between the Maine Yankee l

Control Room and the Maine State Police (MSP). This is the primary method of informing State officials of a declared emergency at Maine Yankee. Both organizations maintain this line in a location that is staffed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months / day,7 days / week. Extensions of this circuit are located in the Maine Yankee Control Room and the TSC area.

7.5.2.2 Maine State Police Radio 4

In the event the commercial telephone circuit fails, the MSP can be contacted via radio from the Control Room, TSC area and from the Security Offices using either of two State Police frequencies installed on these radios (State i

Police - Zone 2 and state-wide car-to-car). These systems are further i

discussed in the Maine Yankee Security Plan.

7.5.2.3 Dedicated Telephone to Maine Emergency Management Agency (MEMA)

A dedicated telephone circuit is maintained between the Maine Yankee Control Room and the Maine Emergency Management Agency's Emergency Operations Center (EOC). This provides communication between Maine Yankee and the State's Emergency Management staff (when activated).

Extensions of this circuit are located in the Maine Yankee Control Room, TSC area and the State EOC.

7.5.2.4 NRC Emergency Notification System (ENS)

The ENS is a dedicated system maintained by the NRC. Thit, system connects Maine Yankee to the NRC Operations Center, in the event of an emergency at Maine Yankee, the NRC will be notified within one hour using the ENS system in the Control Room. Due to the anticipated nature of feasible accidents in the defueled condition, this line is not anticipated to be staffed continuously, but used primarily to provide periodic informational updates to the NRC.

l 7.5.3 Fire Suppression l

Fire suppression systems will be maintained in accordance with the Fire L

Protection Plan. Depending on the type of hazard, the area may contain water l

or Halon. The purpose of these systems is to contain the fire to the area of origin, minimize involvement of adjacent areas, and contain the fire until the fire brigade is assembied and dispatched to conduct more extensive fire suppression activities.

In addition to the sprinkler systems, fire hose stations, carts, SCBA, and protective clothing are provided to aid in responding to a fire emergency. This equipment is located throughout the plant in predesignated areas.

7.5.4 Ventilation The plant ventilation system contains various filter media to remove contaminants from the air. Under adverse conditions, normal ventilation flow paths are altered to isolate potentially hazardous areas from occupied spaces.

In addition, the system contains various process monitors to allow staff to assess

.the effluent flow and take actions as necessary to limit exposure.

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7.3 August 1998

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8.0 RESPONSIBILITIES 8.1 Organizational Control of Emergencies The Emergency Response Organization (ERO)is initially comprised of on-shift personnel. Detection and recognition of conditions that warrant declaration of an l

emergency, in accordance with the EALs, is the responsibility of the Shift l

Manager (SM). Upon declaration of an emergency, the on-shift organization assumes their emergency response duties and implements this plan. The minimum on-shift Emergency Response Organization required for initial emergency response consists of the SM, Operator and Security (Fig. 8-1).

Based on the discretion of the SM, the on-shift staff may be augmented by pre-designated Maine Yankee Staff assigned to the ERO. The goal of the ERO is to be fully staffed within two hours of the Emergency Director's decision to augment the on-shift staff. The ERO is depicted in Figure 8-2. Radiation Protection coverage is available to the on-shift ERO through call-in staff (Ref. 2) if not on-site. The ERO is designed and staffed to support 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months continuous staffing.

1 8.1.1 On-shift Organization l

8.1.1.1 Shift Manager / Emergency Director The Shift Manager (SM)is the management representative on-shift. The SM assumes the position of Shift Manager / Emergency Director (SM/ED) until relieved by a qualified ED. The SM/ED initiates any actions deemed l

necessary to mitigate the consequences of the emergency condition and restores the facility to a safe and stable configuration.

l The primary responsibilities of the SM/ED include:

initial classification and emergency declaration of the incident *;

overall response activities; e

direction and control of available personnel; notification of offsite agencies *;

=

Initiation of corrective actions; initial dose assessment / projection activities; coordinating response activities between Maine Yankee and governmental agencies *.

(ITEMS FOLLOWED BY AN ASTERIK CANNOT BE DELEGATED)

The SM/ED is responsible for maintaining the integrity of the SFP and all 7

operations activities in the facility. Upon being relieved of ED responsibilities, L

the SM reports to the Operations Coordinator.

8.1.1.2 Operator The Operator is responsible for informing the SM/ED of pertinent system status, initiating appropriate response procedures and carrying out the instructions of the SM/ED.

The primary responsibilities of the Operator are:

initial actions for accident mitigation; j

8.1 August 1998

verify habitability of the Control Room; Fire Brigade response, as nece.ssary; 8.1.1.3 Security Supervisor The Security Supervisor (SS)is responsible for maintaining plant security in accordance with the Security Plan.

The primary responsibilities of the Security Supervisor are:

Maintaining site security and access control; Personnel Accountability in the Controlled Access Area (CAA);

Notification of the ERO; Assist in site evacuation, as necessary; On-shift First Aid response; Search and Rescue coordination, as directed.

8.1.1.4 Radiation Protection Technician The Radiation Protection Technician (RPT), who is on-call if not on-shift, reports to the SM/ED.

The RP Technician's primary responsibilities include:

conducting radiological surveys; collecting airborne radioactive samples, determining stay time in areas that have elevated radiation Iavels;

~

advising the SM/ED of any radiological hazards that may affect the response to ari event; providing radiation protection support for search and rescue activities and medical emergencies.

8.1.2 Augmented Organization The need for augmentation response of the ERO is determined by the SM/ED on a case by case basis for the Unusual Event classification; ERO response is specified at the Alert classification. Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the decision to augment the on-shift ERO, sufficient staff should be in place to perform the minimum functions of the TSC. Within approximately 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the complete augmentation staff is expected to be in place to support response activities.

8.1.2.1 Emergency Director The Emergency Director (ED)is responsible for all aspects of the response to an emergency. After being briefed by the SM/ED, the ED may report to the Technical Support Center (TSC) to coordinate activities to mitigate the consequences of the event. Depending on the situation, the ED may remain in the Control Room and carry out designated functions from that location.

The primary responsibilities of the ED are:

Direction and control; Notification and interface with offsite agencies *;

Emergency classification *;

Authorization of onsite protective actions; 8.2 August 1998

\\

1 coordinating response activities between Maine Yankee and governmental agencies *;

Mitigation and recovery.

(ITEMS FOLLOWED BY AN ASTERIK CANNOT BE DELEGATED) in addition, the ED will make assignments, consistent with the event and available staff, regarding logistical needs, administrative support, and other

. activities as necessary.

8.1.2.2 Operations Coordinator The Operations Coordinator (OC)is responsible for coordinating the efforts of the ERO within the TSC and providing status reports to the ED.

l The primary responsibilities of the OC are:

Activating the TSC within approximately two hours of the emergency declaration; Ettablish priorities for the TSC staff; Coordinates logistical needs; Interface with the Control Room staff regarding system assessment;

. Coordination of Search and Rescue activities; Determination of the need for offsite assistance.

The OC reports to the ED.

8.1.2.3 Damage Control Coordinator The Damage Control Coordinator (DCC) directs staff activities relative to in plant corrective / repair activities.

The primary responsibilities of the DCC are:

Assessing the extent of damaged equipment; System status; Requesting maintenance personnel; Establishing initial repair priorities and deploying repair teams; Coordinates available resources to restore equipment and systems based on the direction of the OC; Assists with Fire Brigade activities, as necessary.

The DCC is also responsible for establishing and maintaining communications with deployed repair teams. The DCC reports to the ED.

8.1.2.4 Radiological Assessment Coordinator The Radiological Assessment Coordinator (RAC)is responsible for identifying l

actual or potential hazard-s to plant staff and environs and assessing the l

extent of the hazard. This involves obtaining data and analyzing the situation l-as it pertains to personnel safety.

In the event of a radiological release, the RAC will

. Coordinate radiological dose assessment activiiles to determine the extent of release and impacted areas; i

8.3 August 1998

Coordinate available Radiation Protection staff to conduct surveys, obtain air samples and support repair efforts.

For non-radiological events, the RAC (with input from the DCC and TRC) will determine appropriate response actions, relative to personnel safety / risk minimization, consistent with the hazard (i.e. respiratory protection, personal l

protective equipment, etc.). The RAC reports to the ED.

I 8.1.2.5 Technical Response Coordinator The Technical Response Coordinator (TRC) is responsible for coordinating technical support and engineering activities in support of the OC.

Engineering assessments of the cause of the event and damaged systems will be made to determine short and long-term repair needs. Coordination of non-maintenance staff is the responsibility of the TRC. The TRC reports to the ED.

8.1.2.6 Communications Coordinator The Communications Coordinator (CC) coordinates all communications from the TSC. The priority communications path will be via telephone to the Control Room. In addition, the CC will maintain the TSC status board and may be required to provide periodic updates to the NRC (this is not expected to be a continuously staffed line).

The primary responsibilities of the CC are:

Establishing communications with outside organizations, as directed by the ED, Managing various administrative functions (i.e. staffing needs, TSC Documentation, status boards) within the TSC, Providing updates to outside organizations, as directed by the ED.

The CC reports to the ED.

8.1.2.7 Security Coordinator The Security Coordinator (SEC) maintains overall command and control of the Security Force in accordance with the Security Plan. The SEC reports to the ED.

8.1.2.8 Public Affairs Coordinator The Public Affairs Coordinator (PAC) reports to the ED.

The primary responsibilities of the PAC are:

Preparing news releases based on current emergency conditions; Performing the rumor control function for the station; Monitoring media broadcasts, as needed. Reporting any misinformation to the ED; Maintaining liaison with the State information staff personnel to expedite the handling of inquiries and control of rumors during the emergency; Posting general and rumor control information concerning the emergency in the TSC.

8.4 August 1998

8.1.2.9 Support Staff Each functional area coordinator will be supported by facility staff called in as necessary to assist in the response. General Engineering staff will report to the TRC. Maintenance and Craft Supervisors and Operations Support staff will report to the DCC. Administrative support staff will report to the CC.

l f

8.5 August 1998

FIGURE 8-1 i

MAINE YANKEE ON-SHIFT ORGANIZATION SHIFT MANAGER (SM)

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RADIATION SECURW PROTECTION OPERATOR SUPERVISOR TECHNICIAN (On-shift OR On-call) l l

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8.6 August 1998 I

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m FIGURE 8-2 MAINE YANKEE EMERGENCY RESPONSE ORGANIZATION EMERGENCY DIRECTOR-(ED)

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TECHNICAL PUBLIC AFFAIRS C = *1ee cvy-(TRC) l TECHNICAL PUBUC AFFAIRS ON-SHIFT SUSYSTAFF l

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TECHNICAL SUPPORT CENTER 8.7 August 1998

9.0 MAINTAINING EMERGENCY PREPAREDNESS Station Management is responsible for the staffing of the Emergency Response Organization (ERO) and approval of the Defueled Emergency Plan and Implementing Procedures (EPIPs).

The Manager, Environmental Health and Safety / Emergency Preparedness (EHS/EP)is responsible for the maintenance of readiness of the on-site emergency response facilities and equipment; development and maintenance of l

the Defueled Emergency Plan; development and maintenance of the associated implementing procedures; preparation of scenarios for training drills and exercises; conduct of drills and exercises; and input to emergency preparedness training of the ERO. The Manager EHS/EP is responsible for assisting station management in maintaining the capability to implement the on-site actions required by the Defueled Emergency Plan and coordination of the Maine Yankee Emergency Preparedness program with State agencies and officials.

The Operations Director is responsible for scheduling, coordinating and conducting ERO training using qualified personnel. The Operations Director will obtain assistance as necessary from discipline managers in conduct of discipline specific training. The Operations Director is also responsible to provide support for the annual radiation protection / monitoring drills and medical emergency drills, 9.1 Training The Maine Yankee Defueled Emergency Plan Training Program consists of lesson plans designed to provide the skills and knowledge necessary to maintain ERO proficiency. Each EPIP will be reviewed to identify activities that are not l

considered to be a part of the assigned individuals day-to-day routine function (i.e. use of telephones, general communication protocol, etc.). Lessons will l

focus on non-routine and specialized activities that are particular to the assigned function and overall ERO actions. Training may consist of, but not be limited to, classroom lecture, practical demonstrations (where necessary, as specified in the lesson plan), interactive table-top sessions and comprehensive facility drills.

9.1.1 ERO Training Each individual selected for assignment to the ERO will be provided position specific training designed to familiarize the person with their duties, responsibilities and expected actions in the event of a condition that requires the ERO to be mobilized. This initial training will be completed prior to the individual being placed on the ERO roster.

Each ERO member will be provided continuing training for their assigned duties.

This training will be conducted during the calendar year. Continuing training addresses general changes to the Defueled Emergency Plan, facilities, l

equipment, regulations, policies and specific changes to their responsibilities j

(which are not considered part of their routine duties). It also addresses problem areas identified during audits, drills or exercises and relevant industry events, f

9.1 August 1998

Designated First Aid / Medical Responders will be provided specific training related to this function. Recertification, as necessary, will be completed within the specified time periods (i.e. CPR, First Responder, etc.).

9.1.2 General Employee Training (GET)

The GET program provides all employees and contractors the basic elements of the Defueled Emergency Plan and expected actions during an emergency.

Information is reviewed annually as part of site access training.

9.1.3 Offsite Assistance Training i

Organizations which may be called upon to render assistance onsite will be j

offered general facility familiarization sessions on an annual basis. These sessions may include a walkdown of the general facility, safety, building layout, access protocol, communications capabilities, security requirements and specific responsibilities for each group being trained.

9.2 Review and Updating of the Defueled Emergency Plan and implementing Procedures 9.2.1 Emergency Plan Review This plan, including all written agreements between Maine Yankee and other parties, will be reviewed annually. Approved clianges to the plan will be incorporated into the appropriate implementing procedures simultaneously with the plan changes. Letters of Agreement will be reviewed annually and verified to be in effect at the time of the annual plan review. This may be accomplished via written correspondence or documented telephone conversation.

This plan is a controlled document to ensure changes are incorporated into all distributed copies. Proposed changes are evaluated in accordance with 10CFR50.54(q) prior to implementation. Plan changes will be subject to management review and approval. Revisions will be noted by a bracket ([) in the left margin and the effected page will indicate the date of the revision (lower right comer).

9.2.2 Emergency Plan Implementing Procedure Review Emergency Plan Implementing Procedures (EPIPs) will be reviewed every 2 years and revised as necessary. Periodic revisions will be incorporated whenever a plan change is made that effects the procedure or other circumstances dictate a revision is necessary. EPIPs will be subject to management review and approval.

9.2.3 Periodic Surveillance Program Facilities and equipment will be maintained in accordance with departmental surveillance procedures. Inventories of emergency plan equipment will be conducted on a quarterly basis and after facility activation (actual event or drill activity). A walkdown of the TSC will be conducted on a quarterly basis to ensure facility readiness is maintained. ERO assignments will be reviewed on a monthly basis, and updated accordingly. A complete distribution will be made at 9.2 August 1998

i 1

the end of each quarter.

Telephone numbers that are important to emergency notification and are contained in the emergency preparedness telephone directory will be verified on a quarterly basis.

9.2.4 Communications Systems Checks 9.2.4.1 Onsite Systems The primary link between the TSC and Control Room will be via general facility telephone system. In addition, the FEMCO system may be used as necessary. Damage control / repair teams and site radiological survey teams will communicate via radio (radio frequencies are licensed to Maine Yankee).

Systems not utilized on a routine basis are tested quarterly and during periodic drills.

A contracted paging service is employed to notify key ERO staff. Plant staff not assigned a pager will be notified via a contracted telephone notification service. These systems are tested periodically in accordance with departmental surveillance and test procedures.

9.2.4.2 Offsite Systems The ERO will notify the State Warning Point when an Alert has been declared. The Primary State Warning Point (Maine State Police) will be contacted via dedicated telephone. This system will be tested during the quarterly TSC walkdown.

The NRC Emergency Notification System (ENS) circuit is tested quarterly during the scheduled communications surveillance.

9.3 Drills and Exercises In addition to the emergency plan training described earlier, the ERO will conduct periodic drills to enhance skills and knowledge of the practicalimplementation of the emergency plan Periodic drills will be scheduled with various objectives to demonstrate these capabilities. Some drills will focus on singular functions (such as communications capabilities) while others will involve the activation of the ERO. These evolutions serve as an extension of the tra'aing program, allowing interaction between evaluators and responders to reinforce procedural requirements and overall process implementation.

9.3.1 Drills The following periodic drills will be conducted annually until such time that the function is no longer necessary due to the needs of the decommissioning process:

Radiological Monitoring Drills demonstrating response to a spill of radioactive material, conducting general area sur/eys and airborne sampling and analysis; Medical Emerogncv Drill demonstrating the capability to transport an injured 9.3 August 1998

worker offsite, with potential for contamination of the individual (either radiological or chemical contamination).

Fire Drills will be conducted in accordance with the Fire Protection Plan.

9.3.2 Exercise An exercise will be conducted annually to demonstrate the capability to implement the emergency plan. Objectives will be developed to ensure major elements of the emergency plan are demonstrated and evaluated to ensure the appropriate level of preparedness is being maintained.

The exercise scenario should be based on credible events that could lead to an emer.qency declaration in the existing plant condition. Offsite response organizations will be invited to participate in annual exercises.

9.3.3 Drill and Exercise Evaluation The exercise and drills will be evaluated by facility staff. Expectations for evaluators will be included in the drill / exercise manual and discussed with each evaluator prior to the drill. Whenever possible, evaluators should have present or recent ERO responsibilities and be assigned to evaluate functions / areas consistent with their ERO assignment. Following the drill / exercise a critique of the evolution will be conducted. Comments will be evaluated, dispositioned and tracked by the company corrective action program. Comment resolution will be assigned to the appropriate department for final implementation.

9.4 Independent Program Review An independent review of the defueled emergency preparedness program will be conducted once every 12 months in accordance with 10 CFR 50.54(t), items to be reviewed should include, but not be limited to, adequacy of interfaces with State and local govemment agencies, implementing procedures, drills, exercises, and capabilities, i

1 i

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9.4 August 1998 r

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10.0 RECOVERY The primary objective of the ERO is to mitigate the consequences of an emergency and restore the facility to a safe condition. Restoration of the facility effectively begins with the first action taken in response to the event and terminates when the facility resumes normal operations. When appropriate, a Recovery Organization will be ;tablished to coordinate retuming the facility to a safe condition.

When conditions have stabilized and a full assessment of the event has been conducted, the ERO will focus on establishing a plan to verify operability of all i

systems / components necessary to maintain and monitor the integrity of the spent fuel.

The restoration of the facility will be coordinated by a Recovery Director (RD).

This position is filled by a designated senior manager or executive of Maine Yankee with demonstrated knowledge of the organization and technical aspects of the plant in the permanently defueled configuration. The RD has the authority to take the necessary actions to ensure the facility is retumed to a safe condition.

The responsibilities of the Recovery Director include, but are not limited to:

Maintain comprehensive hazard assessment of the facility; Maintain access control to the facility to minimize risk exposure to workers; Prioritize clean-up of affected areas / equipment; Isolate and repair damaged equipment / systems; Document all actions taken related to the emergency and recovery operations; Provide offsite officials with periodic condition reports regarding impact on the general public.

The Recovery Director will relieve the Emergency Director when they determina the conditions have stabilized to the point where restorative operations can commence and the threat of the situation deteriorating is minimized. The ERO will be notified when the Recovery Director has assumed responsibility for facility activities and a Recovery Organization will be established, as necessary.

l l

I 10.1 August 1998 I

11.0 OFFSITE ASSISTANCE Response from organizations that are not associated with Maine Yankee Atomic Power Company are not expected to be necessary, except for fire, medical emergencies or hazardous materials incidents. Letters of Agreement exist with organizations that may be called upon, on an as-needed basis, to provide assistance.

The Wiscasset Fire Department and Wiscasset Ambulance Service have standing agreements to assist Maine Yankee in the event of a fire or medical emergency.

Maine Yankee maintains Letters of Agreements with the Midcoast Hospital in Brunswick and the Maine Medical Center in Portland for treatment of radiologically contaminated and injured workers.

Response from the State of Maine will be limited to acknowledging notification of the event and monito-ing potential effect on local areas. No mitigative actions are anticipated to be necessary in response to an event at Maine Yankee.

Precautionary actions are anticipated to be similar to those taken in response to J

preparations for severe weather, etc.

Other agreements exist for specialized services which can be called upon as needed.

i i

11.1 August 1998

W

12.0 REFERENCES

1. Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA-400-R-92-001 (May 1992)

2. MY Letter to NRC, MN-97-110 dated September 19,1997 - Response to Request for Additional Information Regarding Proposed Technical Specification Change No.

206 - Facility Staffing and the Certified Fuel Handler Training and Retraining Program (TAC No. M99425).

12.1 Au0ust 1998

i APPENDIX l-ASSISTANCE AGREEMENTS ORGANIZATION EFFECTIVE DATE Duke Engineering & Services Mutual Assistance Agreement August 1998 US Department of Energy-Brookhaven Area Office 16 January 1997 Mid-Coast Hospital 28 May 1992 MOU between Maine Yankee, Mid-Coast Hospital and Maine 10 July 1992 Medical Center Wiscasset Fire Department July 1998 Wiscasset Ambulance Service 28 June 1991 Bath Fire Department 8 November 1982 Combustion Engineering Inc. Emergency Assistance 5 December 1983 Agreement l-1 August 1998

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DukeEngineering& Services Mutual Assistance Agreement Between Duke Engineering and Services Boston Edison Company Maine Yankee Atomic Power Company North Atlantic Energy Service Corporation Vermont Yankee Nuclear Power Corporation Yankee Atomic Electric Company

i l

TABLE OF CONTENTS Eage A.

INTRODUCTIO N.....................................................

1 B.

DE&S ROLE IN AN EMERGENCY SITUATION...........................

1 C.

TECHNICAL SUPPORT...............................................

2 D.

DE&S METEOROLOGICAL ANALYSIS SUPPORT........................

3 E.

DE&S ENVIRONMENTAL LABORATORY ANALYTICAL AND DOSIMETRY S ERV1C E S...........................................................

3 1

1.

General........................................................

3 2.

Portable Emergency Analysis Equipment.............................. 4 3.

Emergency TLD Service..........................................

4 Portable Body Burden Service......................................

5 d

F.

. MUTUAL ASSISTANCE AGREEMENT OF PARTICIPATING PLANTS.......

5 i

1.

G en eral.......................................................

5 2.

Trai nin g.......................................................

5 G.

ACTIVATION PROTOCOL.............................................

6 H.

APPLICAB LE TERMS.................................................

7 I.

RES P ONS IBILITIES...................................................

8 J.

S I GNATURES........................................................

8 ATTACHMENT 1 Primary Technical Expertise Categories.......................................... 15 ATTACHMENT 2 Letter of Agreement Between Massachusetts Department of Public Health and Yankee Atomic Electric Company RIN32

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

DE&S MUTUAL ASSISTANCE AGREEMENT A.

INTRODUCTION The Duke Engineering & Services (DE&S) organization has developed a cooperative arrangeme ut between DE&S Northeastern Region and the Yankee Plant, Vermont Yankee, Maine Yankee, Seabrook Station, and the Pilgrim Nuclear Power Station (here after referred to as " participating plants"). Under the Mutual Assistance Agreement (hereinafter referred to as "the Agreement"), an emergency at any participating plant would be met with additional support from the unaffected plants. The Agreement is designed to provide direct support when requested by the management of a plant experiencing an emergency. Plant emergency procedures provide the mechanism for initiating a request for mutual assistance.

B.

DE&S ROLE IN AN EMERGENCY SITUATION The role of DE&S in the Agreement is to assist the affected plant by coordinating technical staff, equipment, and resources availaMe from participating plants.

l When notified of an " Alert," " Site Area," or " General Emergency" at Vermont Yankee or l

Seabrook Statica, DE&S will activate its Engineering Support Center (ESC). At the discretion of Plant Management the ESC may also be activated if an Unusual Event is declared at any of these plants. Once notified, DE&S emergency response activities will be performed in accordance with the DE&S Emergency Support Plan. This plan is maintained by DE&S and is subject to audits. Mutual assistance for Boston Edison's J

l (BECo) Pilgrim Station and Maine Yankee will be limited to specific support as l

requested by the utility. The DE&S Engineering Support Center (ESC) will:

5.e activated unless DE&S Management detennines that it is necessary to support BECo.

4 Rl5\\l32 Page 1 of 16 August 1998

m.

_.y i

l C.

TECHNICAL SUPPORT L

l The Agreement identifies technical and administrative staff available to provide, but not

~ limited to, the following:

1.

Engineering, licensing, and radiological evaluation and consultation;

' 2.

Supplemental staff and equipment support; l

. 3.

Environmental dose calculations and projections; l

l.

4.

Evaluation of spent fuelincidents; i

5.

Meteorological evaluation support; l

l 6.

Health Physics liaison between the affected plant and other New England l

facilities; l

7.

Liaison with the Massachusetts Department of Public Health (MDPH) to r

l' coordinate and assist in securing medical treatment for personnel who have been l.

overexposed to mdiation or exhibit extensive radiological contamination; L,

8.

. Interface with State and Federal emergency response organizations; 9.

Evaluation of options regarding the radiological aspects of recovery operations; b

and i

- l' 10.

For the Yankee Plant, Vermont Yankee, Maine Yankee, and Seabrook Station, 3

.l evaluation of accident severity using sample results, monitor readings, and auxiliary parameters as prescribed in the core damage assess:nent methodologies.

i.

mun Page 2 of 16 August 1998 5

.r-

._____._.____.._._.._..________._____...._...y j

l D.-

DE&S METEOROLOGICAL ANALYSIS SUPPORT j

t-L l-DE&S meteorological services are available on a 24-hour emergency call basis to provide

.\\

L meteorological support for decision making and evaluation of environmental impact

)

c

-l during emergency conditions. DE&S maintains a subscription with a commercial l-weather service which allows access to the following information:

Hourly regional National Weather Service (NWS) observations; l

I Radar plots of regional activity;.

e p

e NWS regional weather forecasts; and l'

NWS severe weather statements.

l DE&S meteorological services personnel are available to assist participants dose l

. assessment personnel in evaluating the effects of plume transport and diffusion.

E.

DE&S ENVIRONMENTAL LABORATORY ANALYTICAL AND DOSIMETRY l

SERVICES 1.

General t-l i

The DE&S Environmental Laboratory in Westboro, Massachusetts, is equipped to provide radiochemical processing of all types of environmental media sampled as part of each participating plant's ongoing off-site environmental radiation surveillance programs. In the event of a radiological emergency at any

- participa+ing plant, Laboratory staff are available, on a 24-hour emergency call basis, to perform gamma isotopic analyses on samples taken by the plant's I

emergency monitoring teams. In addition to the availability of gamma spectrometers at the Laboratory, a portable gamma spectroscopy system can be deployed to a plant site to determine the presence and level of contamination in l

samples of various media in the event of an accidental release of radioactive i

amm Page 3 of16 August 1998

material. In addition to the analytical capabilities in the area of environmental surveillance, the Laboratory maintains a large scale environmental and personnel dosimetry processing operation in support of participating plants. Within hours of notification, a complete dosimetry processing system can be fully operational at a remote site for immediate turnaround of environmental and personnel dosimetry from plant staff and emergency sampling teams.

,2.

Portable Emergency Analysis Equioment Portable analysis equipment employed during an emergency response includes a shielded HPGe detector based gamma spectroscopy system complete with computerized spectral analysis capability. The system generates a report of plant-related nuclide concentrations, standard deviation, and Minimum Detectable

.l Concentration (MDC) which is forwarded to assessment personnel.

A four-wheel drive company vehicle is maintained at the Environmental Laboratory in Westboro and is used to transport required equipment. Following a request from a plant for assistance in assessing an emergency condition, laboratory personnel will be dispatched to a designated location within four hours.

Upon arrival, laboratory personnel will determine the presence and level of contamination in samples of various media (air cartridges, air filters, vegetation, l

water) collected by Plant Field Sampling Teams.

3.

Emergency TLD Service During an.mergency, one of the fully-automated TLD processing systems operated at the Westboro Laboratory, can be transported to the Emergency Operations Facility (EOF), or other remote location to allow a faster turnaround of

-l personnel and environmental dosimetry. During an emergency, additional TLDs Page 4 of16 August 1.W amm.

a 4

can be prepared by laboratory personnel. Remote site emergency TLD processing can be fully operational within twelve hours of a request.

4.

Portable Body Burden Service The Environmental Laboratory is prepared to provide whole body counts (WBC) for emergency workers. Although the WBC System is considered portable, it

~

requires setup in a permanent remote location with the required power supply.

The WSC System is comprised of a portable shielded HPGe detector, interfaced 3

to ; ~ -based ADCI/MCA and IBM compatible portable computer. The analytical methodology provides a whole body scan and identifies activity content of the lung, GI, and thyroid.

j A result report is generated for those plant-related nuclides found to be present at the 99% confidence level.

F.

MUTUAL ASSISTANCE AGREEMENT OF PARTICIPATING PLANTS 1.

General General assistance provided to a plant is supplementary in nature and noted in Attachments 1 and 2. Participating groups are Chemistry, Radiation Protection, Maintenance and I&C, Operations, and other support personnel from each participating plant.

2.

Iraming i

f i

1 Page 5 of 16 August 1998 amn2

Personnel operating under the Agreement are trained in their respective disciplines. Additional training may be provided through EP Training and participation in drills and exercises.

G.

ACTIVATION PROTOCOL Mutual assistance is requested and coordinated through the Engineering Support Center (ESC).* The ESC Director or designee has the authority and responsibility

)

to support requests for mutual assistance from participating plants. Mutual I

assistance is coordinated in the following manner:

a.

The ESC receives a request for mutual assistance from a participating l

plant experiencing an emergency.*

b.

The ESC Director or designee verifies the request by contacting the:

Emergency Operations Facility for Vermont Yankee, e

l Techniccl Support Center for Maine Yankee, Emergency Operations Facility for Seabrook Station, e

Corporate Support Center for Boston Edison, o

Technical Support Center for the Yankee Plant.

e Unaffected participating plants are contacted and requested to support the c.

request for mutual assistance.

~

l For Pilgrim Station, mutual assistance is requested in accordance with the Pilgrim l

Station procedures.

Page 6 of16 August 1998 RIN32

l 1

d.

The following personnel have authority to release resources from their j

respective facility:

i l

l l

Yankee Plant

- Vice President or higher authority l

Vermont Yankee

- Corporate Executive Management, or higher authority l

Maine Yankee

- Operations Director, or higher authority l

Seabrook Station -

- Executive Vice President, Station Director, or higher authority l

Pilgrim Station

- Vice President, Nuclear / Station Director, or higher l

authority l

ESC support staff develop a list of responding personnel, equipm ent, and e.

l the estimated time of arrival at the affected plant.

j j

f.

The ESC Director or designee contacts the affected plant and provides the names of responding personnel, equipment being provided, and the estimated time of arrival.

H.

APPLICABLE TERMS l

1.

Each of the organizations included in the Agreement has entered into and is a party to the " Nuclear Power Plant Emergency Respor,se Voluntary Assistance Agreement" (NPPERVA Agreement) administered by the Institute of Nuclear l

Power Operations. Those organizations that are permanently shutdown and l

defueled are not party to the NPPERVA.

.mm Page 7 of16 August 1998

2.

The provisions set forth in the NPPERVA Agreement which relate to compensation, liability, indemnification, and other related areas, specifically including all of Paragraphs 4 through 8, inclusive, are incorporated into thic Agreement by reference; the term Requesting Company, as used therein, shall be l

the plant experiencing an emergency and the term Responding Company shall be those organizations who provide assistance under this Agreement.

'1 I.

RESPONSIBILITIES

)

The Agreement is maintained by Duke Engineering & Services, Northeastern Region l

Emergency Planning Group. At a minimum, it shall be reviewed annually by all participants and updated as required.

1 I

J.

SIGNATURES l

The following companies agree to become a party to and be bound by all of the terms and conditions of this DE&S Mutual Assistance Agreement.

(Signature pages follow)

I l

l l

i i

l RtF132 Page '3 of 16 August 1998

---y

_. ~ _ _. _ _ _ _. _..

l:

l l

[ J.1 Yankee Atomic Electric Company

\\

1 The undersigned company agrees to become a party to and be bound by all of the terms and L

conditions of this DE&S Mutual Assistance Agreement.

l l

l 1

Yankee Atomic Electric Company l

Corporate Officer Signature

/Date' I

1 l

i l

I l

l l

l l.

l t

b i

J f

Page 9 of 16 August 1998 amm l

~.

i l. J.2 Duke Engineering & Services Company The undersigned company agrees to become a party to and be bound by all of the terms and conditions of this DE&S Mutual Assistance Agreement.

Duke Engineering & Services Corporate Officer Signature

/Date l

I-t.

nimin Page 10 of 16 August 1998

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

l J.3 Vermont Yankee Nuclear Power Comoany The undersigned company agrees to become a party to and be bound by all of the terms and conditions of this DE&S Mutual Assistance Agreement.

Vermont Yankee Nuclear Power i

Corporation Corporate Officer Signature

/Date I

l J

RIE132 -

Page11of16 August 1998 w

- +

.-w r-1

,,e--

l J,4

- Maine Yankee Atomic Power Comoany The undersigned company agrees to become a party to and be bound by all of the terms and i

conditions of this DE&S Mutual Assistance Agreement.

o -

((

Maine Yankee Atomic Power Company dorppfficer Signature

/Date 1

4 i

4 ainin Page 12 of16 August 1998

!I-l J.5 North Atlantic Enerev Service Corocratiom The undersigned company agrees to become a party to and be bound by all of the terms and conditions of this DE&S Mutual Assistance Agreement.

l l

North Atlantic Energy Service Corporation l

Corporate Officer Signature

/Date l

?

l l

l-l l

l i

i misun Page 13 of16 August 1998

.-~e.

g

l l

J.6-Boston Edison Company l

The undersigned company agrees to become a party to and be bound by all of the terms and conditions of this DE&S Mutual Assistance Agreement.

l l-Boston Edison Company Corporate Officer Signature

/Date l

l l

l i

I l

l l

I

(

i f

i nimu2 Page 14 of16 August 1998

ATTACHMENT 1 Primary Technical Expertise Categories m Categories DE&S VY MY SB BE Chemistry / Radiochemistry / Water Quality / Plant X

X X

Chemistry Containment / Containment Leak Testing X

X X

Data Systems / Computers X

X X

Electrical Engineering / Electrical Distribution System X

X X

Environmental Engineering / Air Quality /

X X

Meteorology / Biology Environmental Radiation Monitoring X

X X

X Fluid Flow / Hydraulic Systems / Heat Transfer /

X X

X Transient Analysis -

Fuel / Fuel Design X

X X

General Nuclear Background X

X X

i Health Physics / Radiation Protection / Dosimetry /

X X

X Personnel Monitoring / Decontamination Industrial Safety / Fire Protection X

X X

Inservice Inspection Engineering X

X X

X Instrument and Controls Engineering X

X X

Mechanical Systems Design / Mechanical Equipment /

X X

X l

Piping / Valves Metallurgical Materials / Materials Evaluation X

X I

Nondestructive Examination / Nondestructive Testing X

X X

X Nuclear Safety Analysis / Nuclear Engineering X

X X

Off-Gas Processing X

X L

Portable Gamma Spectroscopy System X

Portable TLD Processing System X

j Portable WBC System X

l Pump Design / Pump Analysis X

X X

j Page 15 of 16 August 1998

- usuu 5

1

ATTACHMENT 1 l

l (Continued)

Primary Technical Exnertise Catecoriesm I

l Categories DE&S VY MY SB BE Quality Assurance Engineering X

X X

Radioactive Waste Management / Radioactive Waste X

X X

Shipping Reactor Engineering / Core Physics / Core Cooling /

X X

X Reactor Hydraulics Scheduling X

X X

Security / Emergency Planning / Communications / Plant X

X X

Management Seismic Analysis / Earthquake Engineering X

Shielding X

X X

l Stress Analysis /StructuralDesign/ Vibration / Shock X

X X

X l

Welding X

X X

X l

l l

(1) Additional equipment suppliers and expertise from other than Yankee plants can be found in INPO's Emergency Resources Manual.

a Page 16 of 16 August 1998 aizin

1

?

ATTACHMENT 2 J

LETTER OF AGREEMENT BETWEEN MASSACHUSETTS DEPARTMENT OF PUBLIC HEALTH AND YANKEE ATOMIC ELECTRIC COMPANY

1. PUKPOSE The purpose of this Ltter of Agreement (LOA) is to establish arrangements with tbc Massachusetts Department of Public Health (MDPH) to coordinate and assist in securing medical treatinent fbr radiadon over exposure patients that may result from radiological accidents at nuclear power facilities owned or operated by Yankee Atomic Elemic Company or associated utilitics (YAEC).

2. AGREEh0L5T A. MDPH will establish and maintain a list of bospitals and/or medical facilities that have the

[

expertise and facilities to treat patients that have received an ovetuposure to radiation (herein

[

referred to as "the patient"). A copy of this list will be provided to YAEC.

B. When requested, MDPH will assist YAEC in securing medical treatment for patients that have received an overexposure to radiation at one of the facilities identified in {2.A above; C. In the event such medied treatment is required:

(

1. YABC (or the aHiliated utility) shall make anangements for tbc transport of the patient to the selected medical facility.

[

2. YAEC (or the afGliaicd utility) shaB provide a person from the Health Physics or Radiation Ccatrol Department to acconspany or meet the patjent at the selected medical facility.

[

3. YAEC (or the affilia:ed utility) shall collect and dispose of all contaminated material and shall decontaminate the sc1ceted medical facility's areas and equipment that wer:

_. [

., contaminated during.the treatment of the patient. YAEC (or the affiliated utility) will replace supplies and eqttipment that cannot be satisfactorily decentaminated.

4. The costs associated with the medical treatment of the patient shall be the responsibility of

(

YAEC (or the affiliated utility).

D. This letter of Agreement shall be effective immediately upon execution by the patties hereto.

Amendments to this Letter of Agreement will be proposed in writin consideration by both pa: ties prior to Jttne 30 of any calendar year. g by either party for Amendments approved by both parties become effective on January 1 of the subsequent year.

i Massachusetts Department of Pbblic Health:

Yanke omic El e Companyt 0.km 4

A Director Radiation control Prpgram WerPresident 4-9-9k!

9

[9 9(

r Date pa:e Page1of1 i

l

Department of Energy l

Brookhaven Group Building 464 P.O. Box 5000 Upton, New York 11973 JAN 2 01933 Mr. Jeff Temple Emergency Planning and Environmental Engineering Maine Yankee Atomic Power Company Edison Drive Augusta, ME 04336

Dear Mr. Temple:

SUBJECT:

RADIOLOGICAL ASSISTANCE This letter is a renewal of our agreement to provide radiological assistance. Since your nuclear facilities are located in Region I, the Brookhaven Group is charged with the responsibility for providing radiological assistance in the event of an emergency. Such assistance can be requested at all times by calling (516) 344-2200 and asking for radiological assistance, indicating the nature of the incident, the location, and which authorities have been notified so that we can coordinate our response with them.

The Department of Energy (DOE) will respond to requests for radiological assistance from licensees, Federal, State, and local agencies, private organizations, or individuals involved in or cognizant of an incident believed to involve source, by-product, or special nuclear materials as defined by the Atomic Energy Act of 1954, as amended, or other ionizing radiation sources.

Unless the DOE or a DOE contractor is responsible for the activity, ionizing radiation source, radioactive material involved, or the rendering of assistance to control the immediate hazards to health and safety, radiological emergency assistance will be terminated as soon as the emergency situation is under control. Therefore, responsibility for post-incident recovery, including further action for the protection of individuals and the public health and safety, should be assumed by the appropriate responsible Federal, State, or local government, or private authority as soon as the emergency conditions are stabilized.

If you have any questions, please contact Steve Centore of my staff at (516) 344-7309.

Sincerely,

" Dean Helms

[ Executive Manager cc: L. Gordon-Hagerty, DP-23, GTN

I LETTER OF AGREEMENT BETWEEN t

MAINE YANKEE ATOMIC POWER COMPANY AND

[

MIDC0AST HOSPITAL

[

The purpose of this Letter of Agreement is to update arrangements with Midcoast t

[ Hospital to accept and render treatment to radiation accident patients from Maine Yankee Atomic Power Company.

i The following shall be binding upon the Hospital and the Utility:

1.

The Hospital and Utility shall cooperate at all times in reviewing and updating procedures for treatment of radiation accident patients.

I

[

2.

The Hospital ~and Utility shall join in at least one biennial medical 3

drill.

The Hospital and Utility shall coordinate the scheduling of the medical drill.

3.

Selected Hospital personnel shall participate in at least one annual training session. Hospital and Utility shall coordinate the scheduling of the training sessions.

l

'4.

It.is the Utility's duty and obligation to notify the Hospital in a timely manner if radiation accident patients will be referred to the hospital for treatment.

4 5.

The Utility shall provide the Hospital with the data outlined in established procedures when patient are to be referred to the hospital.

[

6.

The Utility shall furnish a person qualified in radiological control procedures to accompany or meet the radiation accident patient at the Hospital.

This person shall evaluate the radiological situation, then advise and make appropriate recommendations to the senior hospital staff member in charge.

]

7.

The Utility shall collect and dispose of all contaminated material and shall decontaminate hospital areas and supplies, as required. The Utility shall replace all supplies and/or equipment that cannot be adequately decontaminated.

8.

The Utility shall inventory emergency equipment and supplies every six months.

In addition, the Utility shall inventory and replace emergency equipment /and/or supplies after each medical drill or actual treatment of a radiation patient.

..I 9.

The Utility shall be responsible for initially notifying the next of kin

[

of the situation.

10. The Utility is responsible for the release of information on the incident and condition of patient while at the plant. The Hospital is responsible Lt\\ jet \\mideoest. age l

)

f._

m I

,d for the release of information on the medical status of the patient while at the hospital within the limits of the patient's rights to privacy.

i Both the Hospital and the Utility, within their respective areas of 1

responsibility for release of information, shall work together in a coordinated manner.

{

l

11. This Letter of Agreement supersedes all previous agreements between l-

[

Hidcoast Hospital and Maine Yankee Atomic Power Company.

I

12. This Agreement shall be effective immediately upon execution by the parties hereto.

Do as.

m ~sk a w,,

Admi"nistrator

~

Vice President Midcoast Hospital Maine Yankee Atomic Power Co.

I Lt\\ jet \\midcoast. age

i MEMORANDUM OF UNDERSTANDING MEDICAL SERVICES FOR A RADIOLOGICAL EMERGENCY In an effort to provide optimal care for any persons contaminated and injured l

in an accident involving radioactive materials or radiation exposure, a cooperative plan has been developed between the Maine Yankee Atomic Power Company, Wiscasset,

[ Maine; the Midcoast Hospital, Bath, Maine; and the Maine Medical tenter, Portland, Maine. The plan takes into consideration the type of expertise available at each of the above facilities and serves as a guide to the most appropriate locations for l-management of contaminated or exposed persons in the course of emergency management.

[

The plan does not specify 6tnils of later or long-term patient care; it does make f

use of referral protocols already in place for other serious medical or surgical emergencies.

Depending upon the nature and severity of injury, radiation casualties will be cared for at different sites:

I.

Manaaement of Persons with Radioactive Contamination and Without Injury.

In general, these persons need not be transported to a medical facility.

Decontamination will be carried out on site at the Maine Yankee Atomic Power Company by Maine Yankee personnel.

Patients with non-removable I

[

surface contamination or with internal contamination may be transferred to

[

the Midcoast Hospital for evaluation and triage.

I II. Manaaement of Persons with Radioactive Contamination and Minor Injuries.

Includina Puncture Wounds.

Persons who have minor injuries and simultaneous radioactive contamination 1

[

will be managed first at Maine Yankee and transferred to the Midcoast Hospital if determined necessary by medical response personnel.

When La\\ jet \\midcoast. age f

.. _ -. ~

~.

possible, decontamination will be completed at Maine Yankee.

III. Manaoement of Persons with Ma.ior Iniuries and Radioactive Contamination.

In cases of severe injury and simultaneous radioactive contamination, the patient (s) will require immediate transportation to a medical facility capable of (a) treating their most urgent problems while (b) decreasing

[

the levels of radioactive contamination.

The Midcoast Hospital will be the primary recipient of such cases of significant trauma and simultaneous contamination. The Maine Medical Center, per normal trauma protocol, will

[

be requested to receive patients designated by triage from the Midcoast

[

Hospital, as determined necessary by Midcoast Hospital. Patients who have

)

severe burns, who require intracranial procedures or who require mechanical ventilatory assistance will be transported preferentially to the Maine Medical Center, along with a, Maine Yankee radiological controls staff member.

IV. Manaaement of Persons with Radiation Sickness With or Without Radioactive Contamination.

Any patients who exhibit signs and symptoms of acute radiation syndrome or who may have received a whole body exposure in excess of 100 R will be

[

transported to the Midcoast Hospital for observation and evaluation.

Decontamination initiated at the accident site will be completed at the hospital to the extent possible.

If blood counts indicate an exposure over 200 R or if there is any question of the clinical severity or course of treatment, the patient (s) may be transferred to the Maine Medical Center for evaluation and possible referral to other treatment centers.

Lt\\ jet \\midcoast. age

. =

=

V.

Local Radiation Exoosures.

Persons with extremity or other localized radiation exposures suspected to

[

be in excess of 80 R will be referred to the Midcoast Hospital for evaluation and later consultation arrangements.

The following duly authorized representatives of the Maine Yankee Atomic Power

[ Company, the Midcoast Hospital, and the Maine Medical Center have reviewed, understand and agree with the attached plan of action.

FOR Maine Yankee Atomic Power Comoany 8M Sb Mr. G. D. Whittier Date Vice President 9

FOR Midcoast Hosoital I

e8 S

2 Mr. Phil Ortolini

~

/Da(e Vice President 7-I6-fd FOR Maine Medical Center A.'

Mr. Michael Ryimbw Date Vice President i

i u gj t\\.iace.it..gr

T f."

u MaineYankee P.O. BOX 408 + WISCASSET, MAINE 04578 (207) 882-6321 LETTER OF AGREEMENT BETWEEN MAINE YANKEE AND WISCASSET FIRE DEPARTMENT The purpose of this Letter of Agreement is to update and continue anangements established by an Agreement dated April 1,1986, with the Wiscasset Fire Department to provide fire fighting support at Maine Yankee, when requested, and to establish authority for fire fighting on Maine Yankee property.

The Wiscasset Fire Department agrees to provide fire fighting assistance at the Maine Yankee Plant, when requested. Maine Yankee will provide escort for the fire department when entering the plant site.

Authorities for fire fighting on Maine Yankee property have been established as follows:

1.

Maine Yankee will have primary authority in the following areas:

All buildings and equipment inside the security fence associated with the l

a.

l Spent Fuel Pool Island (SFPI), including: the Fuel Building, the New l

Control Room, Transformers X-16, X-16A, X-16B, the SFFI Diesel l

Generator and the SFPI heat exchangers.

j l

b.

All buildings and equipment inside the security fence associated with the l

Radiological Control Area (RCA) portion of the plant, including the Wart l

Building and the Chemistry Trailer.

c.

The 115 KV and 345 KV Swithchyards and the 345KV Relay House.

d.

The Fire Pump House e.

The Low Level Waste Storage Building.

sALICENsEVMBWisLTRAG.WPD 1

)

2.

The Wiscasset Fire Department will have primary authority in the following areas:

s l

a.

Buildings and equipment inside the security fence not associated with the 1

SFPI or the RCA portion of the plant that are not specified in 1. a & b l

r.bove, including: the Turbine Hall, the Circulating Water Pump House, l

the Service Building and office trailers.

J b.

Buildmgs and equipment outside the Security fence that are not specified in '. c, d & e above, including:

i All warehouse buildings.

l The Staff Building and Trainmg Annex.

The Bailey House and Barn.

The Eaton Farm, including the house, garage and barn.

The Career Center c.

Other areas outside the security fence, including: brush, grass and vehicle i

fires.

This Letter of Agreement shall be effective immediately upon execution of the parties representing the organizations and will be in effect until superseded by another Letter of Agreement or notification of withdrawal of either party to the remaining party.

/ 7 4f15-k fll'l~ W m

George A. Zinke, Director date Robert Bla[Ien date Nuclear Safety & Regulatory Affairs First Selectman 6% MM/9 [

Ikobert. Pontau date 7/M, date Roy Barnes Third Selectman sALICENsEVMT\\WIsLTRAo.WPD

MaineYankee RELIA 8LE ELECTRICITY FOR MAINE SINCE 1972 EDISON ORIVE. AUGUSTA, MAINE 04330.(207) 622 4868 June 28, 1991 JMT-91-27 Wiscasset Ambulance Service Box 450, RFD #2 Wiscasset, Maine 04578 Attention:

Larry Gordon, First Selectman 1

Maine Yankee wishes to update the letter of agreement between Maine Yankee and l

tha Wiscasset Ambulance Service dated July 6,1982.

Accordingly, please consider this a " Letter of Agreement" between the Maine Yankee Atomic Power Company and the i

Wiscasset Ambulance Service in accordance with the requirements of the U. S. Nuclear Regulatory Commission.

When requested, the Wiscasset Ambulance Service does agree to:

l 1.

Respond to all incidences involving personal injury occurring at Maine l

Yankee Atomic Power Company at Maine Yankee's request.

Should both i.

ambulances be unavailable, Wiscasset Ambulance, through the dispatch

~

center, will arrange for another service to respond.

{

I 2.

Participate in at least one emergency medical exercise per year involving personnel from Maine Yankee Atomic Power Company.

The details will be i

mutually agreed upon at the time of each exercise.

j When requested, Maine Yankee Atomic Power Company does agree to:

1.

Provide the facilities and trained personnel to assist in the j

decontamination of all equipment used by the Wiscasset Ambulance Service 1

when responding to emergencies and/or exercises involving radioactive material.

j i

o l

f 2.

Provide instructions in the use of special equipment and procedures designed to minimize personnel exposure to radiation and the spread of radioactive contamination.

This Letter of Agreement shall be effective immediately upon execution of the parties representing the organizations and will be in effect until superseded by another Letter of Agreement or notification of withdrawal of either party to the j

remaining party.-

Fort}TownofWiscasset For the Maine Yankee Atomic Power Company Y

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S. E. Nichols, Manager' Qrry Gordon,'Fi'rst Sele [ man Nuclear Engineering & Licensing Town of Wiscasset jmt9127.1tr

NOV 12 at

,o.

RECEIVED m 1982 MARIE HAllHEE Arom/CPOWERCOMPARS*

gg & b*$"l $

h NUCLEAR SERVICES Q1@23 3521 9

November 8, 1982 SDE-82-105 Mr. Ronald Clark, Chief Bath Fire Department City of Bath l

Bath, Maine 04530

Dear Chief Clark:

Conf!rming our recent conversation, the United States Nuclear Regulatory l'

CcxImission has reccmnended that Maine Yankee Atomic Power Cmpany obtain a j

written agreement with offsite agencies for self-contained breathing apparatus i

(SCBA) support.

Q i

The following will serve as a letter of agreement between the Bath Fire

)

Department and Maine Yankee Atcxr.ic Power Capany (" Maine Yankee") regarding SCBA support.

j In the event of an emergency condition that requires SCBA support, Bath j

Fire Department will, upon request, fill Maine Yankee's self-contained j

breathing apparatus utilizing the air cmpressors at the Bath Fire Station.

l When Bath Fire Department determines that it must charge for ccxnpressed air, Maine Yankee agrees to pay the necessary and reasonable charges for this service ccmnensurate with Maine Yankee's usage.

4 This agreement is effective inmediately upon execution by the undersigned.

I If the foregoing statements are agreeable to you, please sign and return one copy of this letter to me for inclusion in our emergency plan.

Thank you for your cooperation on this matter.

/2

/

For Maine Yankee Atomic Power Ccxnpany For Bath Fire Department Cance11able - 10 days notice of either party.

SDE:pjp 0148L - SDE h.

Enclosure (2), Page 1, Revised D2ce:rber 5,1983 NUCLEAR INCIDENT EMERGENCY ASSISTANCE AGREPfENT This NUCLEAR INCIDENT EN ASSISTANCE AGREEMENT (the " Agreement") is made and entered into as of the 5th day of December

, 1983

, by and between Maine Yankee Atomic Power Company

, a corporation having its principal office at Edison Drive, Augusta Maine

(" Purchaser"),

and Ccxtbustion Engineering, Inc., a Delaware corporation with offices at i

Windsor, Connecticut ("C-E").

a WHEREAS, the Purchaser is the owner and operator of a nuclear pcser electric generating plant kncwn as Maine Yankee Atomic Power Co.

, Unit (s)

, and

, located in Wiscasset

, Maine

, ("the Plant") ; and hEEREAS, in the event of an emergency arising frcm a nuclear incident (as defined in the Atomic Energy Act of 1954) at the Plant, Purchaser may request C-E to furnish goods or services on a priority basis with respect to that incident; and 4

WHEREAS, in the event Purchaser and C-E agree on the goods or services to be furnished, C-E would be willing to furnish such gocds and services provided j

that they may be furnished without exposing C-E to any liability other than that expressly set forth in the Warranty article hereof; i

j NON THEREFORE, intending to be legally bound hereby, C-E and the Purchaser agree as follcus-1.

Assistance: Upon the request of the Purchaser in an emrgency during or imTediately after a nuclear incident at the Plant, C-E will_ furnish j

such_gcods and services as may be. mutually _ _ agreed upon_by...the parties 1

(" Assistance"). Any requesEliy the Purchaser for Assistance, if not originally in writing, shall be condr:ed within twenty-four hours by telegram referencing this Agreement. The follcwing officials of Pur-chaser are authorized to request Assistance hereunder:

John B. Randazza, Charlie Frizzle 2.

Termination: This agreement is an interim agreemnt which shall govern i

the furnishing of goods and services during a nuclear incident (as

!j defined in the Atcmic Energy Act nf 1954) at the Plant until acceptance by C-E of a purchase order frcm Purchaser for-such goeds and services under the current Equipxnent and Services Agreement between Purchaser and C-E.

All work, goods and services performed prior to issuance and acceptance of said purchase order will be subject to the terms and conditions of the Drergency Assistance Agreement. Subsequent to issuance and acceptance of the purchase order all work, goods and services will be governed by the terms and conditions of the currently existing Equip-ment and Services Agreement between Purchaser and C-E, Inc.

This agreertent may be terminated at any time by either party upon one-day written notice to the other.

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a 3.

Warranty J

C-E warrants that any goods manufactured by C-E and sold to the Pur-chaser hereunder will be free from defects in material and workmanship 1

. for one year after the date of shipment. If C-E is notified of a breach of this warranty within one year after the date of shipment, C-E will, at j

its election, either correct defective workmanship or material, or furnish replacement parts, F.O.B. original place of shipment. C-E shall have no obligation for breach of warranty if the Purchaser fails a) to store, operate or maintain the goods in accordance with generally approved industry practices, provisions set forth in this document or the provi-sions of any storage, operation or maintenance instructions furnished to the Purchaser, b) to notify C-E in writing as soon as any such defect i

becomes apparent, or c) to provide, at Purchaser's expense and within a reasonable time after the defect becomes apparent, unobstructed access to the goods and decontamination of the goods and their environs to accept-able levels of radioactivity.

THE EXPRESS WARRANTY STATED IN THIS ARTICLE IS EXCLUSIVE AND NO OTHER WARRANTIES OF ANY KIND, WHETHER STATUTORY, ORAL, WRITTEN, EXPRESS OR IltPLIED, INCLUDING ANY WARRANTY OF MERCHANTABILITY. OR FITNESS FOR A PARTICULAR PURPOSE, SHALL APPLY. THE PURCHASER'S' EXCLUSIVE REMEDIES AND C-E'S ONLY OBLIGATIONS ARISING OUT OF OR IN CONNECTION WITH DEFECTS IN SUCH GOODS, WHETHER BASED ON WARRANTY, CONTRACT, TORT (INCLUDING NEGLI-GENCE), STRICT LIABILITY OR OTHERWISE, SHALL BE THOSE STATED IN THIS

]' -

ARTICLE.

AS TO ANY OTHER ASSISTANCE (INCLUDING SERVICES AND OTHER GOODS) PRO-i VIDED BY C-E, SUCH ASSISTANCE WILL BE PROVIDED BY C-E ON AN "AS IS" BASIS, AND NO WARRANTY OR REPRESENTATION, WHETHER STATUTORY, ORAL, WRITTEN EXPRESS OR IMPLIED (INCLUDING ANY WARRANTIES OF MERCHANTABILITY

,0R FITNESS FOR A PARTICULAR PURPOSE), SHALL APPLY.

4.

Consideration for Assistance In recognition of the public interest served by providing Assistance, 1

C-E agrees that the consideration for services rendered as Assistance by C-E within twenty-four hours of the Purchaser's initial request for 1

Assistance shall be One Dollar. The then-current usual comercial prices of C-E shall apply to any other Assistance provided by C-E.

Purchaser shall pay C-E's invoices for Assistance within thirty days of receipt.

5.

Drills As part of a program to perfect its ability to tespond to a nuclear incident, Purchaser may conduct drills involving partial or full simula-tion of a nuclear incident at the Plant.

In the' event Purchaser so 06-01-84

requests, C-E will participate in' responding to such a drill in accordance with the terms and conditions of this Agreement, except that the first sentence of paragraph 4, Consideration for Assistance shall not J

apply.

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6.

Limitation of Liability The liability of C-E, its agents, employees, subcontractors and suppliers with respect to any and all claims arising out of the performance or non-perfonnance of obligations in connection with providing Assistance, whether based on contract, warranty, tort (including negligence), strict liability or otherwise, shall not exceed in the aggregate the price paid for Assistance hereunder and shall in no event include damages for loss of profits or revenue or the loss of use of either; loss by reason of 1

plant shutdown or inability to operate at rated capacity; increased expense of operation of plant or equipment; increased costs of purchasing i

or providing equipment, materials, supplies or services from others; costs r / replacement power or capital; claims of Purchaser's customers; inventury or use charges; or inc.idental or consequential damages of any nature.

This LIMITATION OF LIABILITY Article shall prevail over any conflicting

'l or inconsistent provisions contained in any of the documents comprising the Contract.

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7.

fluclear Insurance or Indemnity A.

The Purchaser, without cost to C-E, shall provide and maintain on behalf of C-E, its empi yees, s ppliers ano subcontractors the protection set forth in Sections i and 11 below:

i) Nuclear Public Liability Protection (a) Liability insurance from the Nuclear Energy Liability Property Insurance Association (NEL-PIA) and the Mutual Atcmic Energy Liability Underwriters, incidding any retrospective rating j

plan, in the amour.t and form as shall. meet the financial protection requirements of the NRC under the Atomic Energy Act of 1954, as amended (the "Act"), and (b) A government indemnity agreement with the NRC under subsection 170c of the Act.

(c) If the combined amount'of insurance and indemnity protection required by the imC becomes unavailable for any reason, or is reduced from that which at any time during the Protection Period (hereinafter defined) shall have been required by the imC, or if the limitation of liability of Section 170e of the Act becomes unavailable for any reason, the Purchaser shall provide and maintain the maximum amount of nuclear liability protection available to utilities in the United States.

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ii) Nuclear Property Damage Protection

. Nuclear property damage protection.

in the maximum amount available or in an amount equivalent to the value of all property on the Plant Site, whichever is less. Such i

insurance policy shall provide, among other things, for waiver by the insurer of any rights of subrogation against C-E, its employees, suppliers or subcontractors. The Purchaser hereby waives all right of recovery, whether based on warranty, contract, negligence, strict liability or otherwise, including any right to which another may be i

subrogated, against C-E, its employees, suppliers and subcontractors

(" Indemnitee (s)") as a result of damage to, or loss of use of, any property on the Plant Site arising from radioactive material including a nuclear incident, and agrees to indemnify and hold such Indemnitees harmless from and against, and shall at C-E's option undertake the defense of, any and all claims, losses, liability and damage, including reasonable attorneys' fees, which any Indemnitee might sustain or incur or which might be asserted by any person against any Indemnitee, whether based on warranty, contract, negligence, strict liability, or othemise, as a result of such property damage or loss of use of such property. The above waiver by the Purchaser shall not affect C-E's obligations as set forth in Article 3 with resp,ect to correction of defects in workmanship and materials.

The Protection described in Sections 1) and ii) above shall continue in effect until the Plant shall have been decommissioned and all radioactive material removed from any location which is under Purchaser's control or could be covered by Purchaser-procured pro-tection of the types provided in the foregoing Sections 1) and 11).

B.

Insured Parties; Certification, Direct and Indirect Claims i

The Purchaser agrees to name or include C-E, its employees, suppliers and subcontractors and any person owning or holding a substantial interest in property on the Plant Site as additional insured parties in all insurance policies obtained by the' Purchaser pursuant to Sections A.i and A.ii above. The Purchaser shall have no right or claim of any kind, whether based on warranty, contract, negligence, strict liabi -

lity, or otherwise, and no right to which another might be subrogated, against C-E, its employees, suppliers and subcontractors arising out of or in any way related to a nuclear incident or other damage attribu-table to radioactive material and hereby covenants that no such claim shall be brought by or through the Purchaser on any theory whatsoever.

The Purchaser shall promtly furnish C-E with copies of such policies

/

and of all riders, supplements and amendments thereto.

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s-s C.

Transfer of Rights and Location of Equipment The Purchaser agrees not to transfer or assign any of its rights or interests in any fuel or equipment furnished or serviced by C-E, or to locate such fuel or equipment for use in any nuclear applica-tion at any site other than the Plant Site, or-to transfer or assign any of its rights or interests in all or a substantial part of the other property located at the Plant Site, unless the protection to be afforded C-E following any of such events will be equivalent to that set forth in this article :nd pr:vid:d that th: "rch::;r 2:.11 gf'/: C E ;rf;r,;ritt;.. n: tic: Of th: tr:::::tfer 2-d 2::r :::: th:t th: pr;;;.;L., n:11 Le

. w: d 0;;;. Purchaser further agrees u

not to transfer or assign this agreement or any of its rights or i'

interests therein without the prior written consent of C-E.

i i

j 8.

Force Majeure Even if C-E agrees to a schedule for providing Assistance, C-E shall not be in breach of this Agreement as a result of any delay in perfonning its obligations if such delay is due to strikes or other labor troubles; j

inability to obtain raw materials, components, supplies or fuel for any reason, including default of suppliers or subcontractors; or any other cause which is beyond the reasonable control of C-E, whether of a similar s

or dissimilar nature and whether or not existing or foreseeable on the date of the Agreement or on the scheduled date of commencement of perfor-L mance. Should any such delay occur, the time for the perfomance of l

C-E's obligations shall be extended by a period.of time equal to the.

length of the delay plus such additional time as is reasonably necessary l

to enable C-E to resume perfomance of its obligations.

i j

Within a reasonable time after C-E beccmes aware of a cause entitling

.it to an extension of time in accordance with the foregoing paragraph, C-E shall give notice thereof to the Purchaser. C-E shall use reasonable efforts to minimize the delay but 1. hall not be required to subcontract work or to work additional hours for which premium time is payable or to schedule additional work shifts if such subcontracting, additional hours or shifts would not have been required to meet the schedule except for such delay, unless the Purchaser directs that it be done and agrees to pay all additional charges with respect thereto and provided that the performance directed is not prohibited by any applicable labor contract or law.

9.

Third party Beneficiaries The prov'i3 ions of this Agreement are solely for the benefit of the parties he.reto and not for the benefit of any other persons, except as l

may be expressly provided otherwise with regard to C-E's employees, i

suppliers and subcontractors.

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j 10.

Indemnification

)

In addition to its other obligations hereunder, Purchaser shall hold hannless and indemnify C-E, its officers, agents, employees, suppliers and subcontractors from and against all loss, damage, cost (including reasonable attorneys' fees and court costs), expense, claims and liability resulting from bodily injury (including death), including, but not ifmited 4

to, workman's compensation claims for injury to C-E's employees, or from damage to, destruction of, or loss of use of property, arising out of or in any manner connected with the furnishing of Assistance by C-E, whether or not any such loss, damage, cost (including reasonable attorneys' fees and court costs), expense, claims or liability result wholly or partially from the negligence or other fault of C-E or any of its officers, agents, employees, suppliers or subcontractors or persons employed by such suppliers or subcontractors. Purchaser hereby waives, for itself and for any other person who might assert a claim by, through, or under Purchaser, any right of recovery it may have or acquire based on such injury, damage, destruction or loss of use, whether such right is founded in contract, warranty, tort (including negligence), strict liability, or otherwise.

11.

Inteoration i

With respect to the subject matter hereof, this Agreement contains the entire agreement and understanding between the parties and merges with and supersedes all prior agreements, committments, representations, writings, and discussions between them.

12. 'Governine law This Agreement shall be construed in accordance with the laws of the State of Connecticut.

Ill WITilESS WHEREOF, the parties have executed this Agreement, as of the date first mentioned above.

1 PURCHASER C0!18USTION ENGIllEERIllG, IllC 1

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Date P. / / / 7N Date IA Y / N 06-01-84

APPENDIX 11 - SUPPORTING PLANS AND DOCUMENTS Defueled Safety Analysis Report (DSAR)

Maine Yankee Fire Protection Plan, June 1996 Maine Yankee Spill Plan, May 1997 Maine Yankee Security Plan, July 1998 l

Mid-Coast Hospital Radiological Emergency Plan Maine Medical Center Radiological Emergency Plan State of Maine Emergency Operations Plan l

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Il-1 August 1998

ML20154L482

Contents

Text

References:

SUBJECT:

1.0 INTRODUCTION

2.0 DESCRIPTION

4.0 CONCLUSION

5.0 REFERENCES

1.0 INTRODUCTION

12.0 REFERENCES

1.0 INTRODUCTION

RESPONSE

12.0 REFERENCES

Dear Mr. Temple:

SUBJECT:

Dear Chief Clark:

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