ML20033C538

Forwards Draft Review of Proposed Emergency Response Plan for Unit 1

ML20033C538
Person / Time
Site:	Pilgrim
Issue date:	12/14/1979
From:	Desrosiers A Battelle Memorial Institute, PACIFIC NORTHWEST NATION
To:	Pagano F NRC - EMERGENCY PREPAREDNESS TASK FORCE
Shared Package
ML112341174	List: ML19259D232 ML20033C534 ML20033C538 ML20033C545 ML20033C547
References
FOIA-81-283 NUDOCS 8112030380
Download: ML20033C538 (44)

Text

.

OBaHelle Pacific Northwest Laboratories P.O. Box 999 Richland, Washington U.S.A. 99352 Telephone (509) 375-2589 Telex 15-2874 December 14, 1979 Mr. Frank G. Pagano, Task Team Chief Emergency Preparedness Ted Force U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Pagano:

Attached is a draft review of the proposal emergency response plan of the Pilgrim I Nuclear Power Station. This review consists of an annotated work-book containing an outline of emergency planning considerations and a draft memordanum which summarizes our evaluation. The workbook is a compendium of NRC's emergency planning requirements, which are individually referenced, and suggestions for additional planning considerations or explanations of the requirements, which are unreferenced.

This draft material is being provided to the team leader as input to the Task Force's review of the proposed emergency response plan.

Please contact myself or Mr. Selby for further information or amplification relative to this review.

Sincerely, f

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A. E. Desrosiers

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Senior Research Scientist f'./ c S.*~ f, N.f}[i e

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Site File N.

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SUMMARY

-0F REVISED EMERGENCY.

> PLAN FOR~ PILGRIM I HPS The major items: identified in this review are:

• interrelationships with plans of offsite agencies are not summarized in section 2; communications.are not adequately described;

specific EALs are absent; the plan 'does not clearly. provide for prompt alerting and warning -

of local authorities; f

the plan do s not provide for continually informing state / local officials j

concerning the emergency status of the plant; manpower needs in relationship to the anticipated sequence and timing.

of events-is not given; L'

the description of the TSC' ECC and OSC are inadequate because job assignments are not stated;

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the plan relies upon environmental monit'oring for accident class)ification;

-l the plan does not discuss containment radioactivity monitoring

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in terms of EALs; I

i local authorities are not given recommendations for protective actions based upon EPA's-PAGs; f

p there are no action' criteria for protective cover;

,, ' evacuation routes are not analyzed; I

effluent release rates are not obtained from in-plant measurements; training provisions-do not provide assurance that.the plant's staff will correctly respond during an emergency.

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A' detailed review is attached.

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The State's plan has not been closely reviewed since it is being revised at present. However, the present version relies upon a tortuous ~ path for vital communications and an excessive reliance upon centralized.

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determination of emergency prot'ection actions'during the phases of an

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' EMERGENCY RESPONSE PLAN WORKBOOK S6SS M 0 1.

DEFINITIONS W

Definitions of any terms that are unique to yg the power plant under consideration or any

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connotations that differ from normally accepted usage.

(RG 1.101, Rev. 1)

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2.

SCOPE AND APPLICABILITY

.k Section 2 is intended to be gen.iral in nature, details should follow in subsequent-sections.

2.1 Emeroency Plan Coverage Define the unit, plant, station, or area to y6 3 which the plan is applicable.

(RG1.101, Rev. 1)

. Included should be a diagram of the locations of the reactor site, exclusion area, low population zone (LPZ), and kO emergency planning zones (EPZs-plume and ingestion).

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2.2 Plan Interrelationships 2.2.1 Implementing Procedures The licensee should commit that implementing

{fhb emergency procedures have been documented c

for all " Emergency Classes."

(RG 1.101, Rev.'1)

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2.2.2 Operational, Radiological, and Security Procedures The' licensee shall specify a summary of the yo (M emergency plan interrelationships with plant

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' operating, radiological control, and indus-trial security procedures.

(RG 1.101, Rev.1)

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s 2.2.3 Other Emergency Pla'ns The licensee shall identify all relevant interrelationships between the emergency

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plan and other emergency' plans of the company (i.e., an overall corporate plan).

/db (RG 1.101, Rev. 1) 1 2.2.4 Emergency Plans of Other Participating Agencies The licensee-shall identify all relevant jnterrelationshipsbetweentheemergency plan and emergency plans of other parti-cipating agencies, particularly the respon-sible State agency or other governmental g my authority having radiological. emergency planning responsibilities in the immediate offsite area. (RG 1.101, Rev. 1)

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2.2.5 Diagram of Emergency Respsonse Activities NO

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Identify and define by means of' a block dia-

-gram the interfaces between and among the onsite functional areas of emergency activ-ity, licensee headquarters support, local services support, and State and local

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_~ 5 government response organizations. _ The above shall include the onsite technical support center and the operational-support center as discussed in NUREG-0578.

(Acceptance Criteria) e 2.3 Emergency Facilities Summary 2.3.1 Physical Lay-out The licensee should provide graphic diagrams h\\lCS) depicting)the' locations ~(both principal and alternate cf:

. Emergency Control Center (ECC)

. Emergency Operations Center (EOC) (both state and local)

. Onsite Technical Support Center (OTSC)

. Control Room (no alternate)

. Onsite Operational Support Center (00SC).

(Acceptance Criteria) 2.3.2 Communications The licensee should provide graphic dia-gram (s) depicting the primary and back-up

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communications relationships and mode between (both the principal and alternate):

.E0C(localandstate)

. ECC (onsite and offsite)

. OTSC i

. Control Room (no alternate)

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. Onsite Operational Support Center

. Press Center

. Corporation Office (if applicable).

(Acceptance Criteria) e 3

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SUMMARY

OF EMERGENCY PLAN

- Section 3 is also intended to be' general in-nature, details should follow in subsequent

- sections.

3.1 Graded' Emergency Classifications The licensee shall provide a summary listing kC of all graded " Emergency Classifications".

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e To include the following or equivalent classes:-

. Unusual Event

. Alert 1 Site Emergency

. General Emergency (NUREG-0610) 3.2 Emergency Classifications Impact The licensee shall designate the relationship NO of each emergency class to the participation and' status of both onsite and offsite personnel and agencies.

(RG 1.101 Rev.1 and NUREG-0610).

4.

EMERGENCY CONDITIONS 4.1 Classification System The licensee's emergency plan shall have the following emergency classes or their p

equivalent:

. Unusual Event

. Alert

. Site Emergency

. General Emergency.

(NUREG-0610)

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a) Use a classification system compatible Q gg'N{

with systems used by the State and local

. government.- (RG 1.101, Rev. 1)

NOTE: Table ~or matrix to show how systems compare between. licensee, state, and local.

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4.1.1 Notification of Unusual Event

[dtvUpd a) Designate the criteria that would be used u

to recognize and declare the " Unusual Event" class.

(NUREG-0610) s S, gCC

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b) Designate types of events which may fall j'Qj r

in this class.

(NUREG-0610) g c) EALs - List specific instrument readings bp i

which constitute the EAls for this

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class.

Not all conditions in NUREG-0610 have corresponding-instrument levels.

These need to be sorted out.

4.1.2 Alert

.i a) Designate the criteria that would be used

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to recognize and declare the Alert Class, including potential for releases. '(NUREG-0610) b) Identify specific candidate situations kb for Alerts.

(NUREG-0610) c) EALs - list specific instrument readings which constitute the EALs for this class.

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Not all conditions in NUREG-0610 have 4

corresponding instrument levels, these need to be sorted out.

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4.1.3 Site Emergency a)' Designate the-criteria (EALs) that would be used to recognize and declare a site emergency.

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. Emergency action levels (EALs) for

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.ZA M declaring a Site Emergency should be 4

defined in terms of instrument readings

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room, including indications of the (Lp c, reactor. status, functioning of safety e U b-

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N systems and the readout from effluent monitors.

(NUREG-0610)

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. Alternately, emergency action levels for declaring a Site Emergency should be g

defined.in terms of specific contamina>

tion levels in environmental media, e.g.,

water, soil, vegetation, milk.

(RG 1.101, Rev.1)

. If a conflict exists between control room instrument reading classification and kC environmental classification, then the higher classification should be declared.

b) The licensee should explain the relation-g ship of the Protective Action Guides (PAGs) to the bases and criteria used to specify EALs.

4.1.4. General Emeroency gJ a) Designate the criteria (EALs) that would

'^'4 UAWMN-be used to recognize and declare a general emergency.

. EALs for. declaring a " general emergency" will include instrument readings and O M N[ M system status indications corresponding

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to an airborne fission product inventory within. containment.

(Acceptance Criteria)

. Alternately, emergency action levels for declaring a General-Emergency should be 6

defined in terms of specific contamina-

,y-Q tion levels in environmental media, e.g.,

water, soil,' vegetation, milk.

(RG1.101, Rev. 1)

. If a conflict exists between control room -

NO instrument' reading classification and environmental classification, then the higher classification should be declared.

b) Provedlan explicit methodology for

/V O relating EALs and PAGs.

(Acceptance Criteria) c) The licensee should have a coordination A/O /

6 bgg' plan with local. authorities to ensure the a

availability of mechanisms for early C

t warning of the-public.

(RG 1.101, Rev. 1)

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tg gg "l2A0teoM (WOW?h 4.2 Spectrum of Postulated Accidents The licensee should specify for each accident, postulated and analyzed in the FSAR:

1) its

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emergency, class membership 2) instrumentation k) b capability for prompt detection and continued assessment and 3) manpower needs in relation fM to the anticipated sequence and timing of events.- (RG 1.101, Rev. 1) gQ 5.

ORGANIZATION CONTROL OF EMERGENCIES 5.1 Normal Plant Organization The licensee should describe both day and night shift staffs (crews), indicating clearly c

who is in the immediate onsite position of jj responsibility for the plant or station and his authority and responsibility for declaring an emergency.

(RG_1.101, Rev. 1) 7

l S.2 'Onsite Emergency Organization 5.2.1 Direction and Coordination 5.2.1.1 Emergency Coor'dinator Provide for an Emergency Coordinator at all times, including an individual onsite at the time of an accident, having the authority and

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responsibility to initiate any emergency

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' actions within:the provisions of the emer--

-gency plan, including the exchange of infor-mation with authorities responsible for coordinating ~offsite emergency measures.

(Acceptance Criteria) a)

Describe the responsibilities of the

)d (3, h Emergency Coordinator for all emergency-classes.

b). Provide the line of succession for the

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/ L3 the lowest possible job assignment that may replace any of his or.her authority or responsibility.

5. 2.1.' 2 Notification Durina Site or General Emergency d

The licensee should notify the following personnel and agencies during a site or general emergency:

h a) State and local agencies responsible for support and coor.dination b)

Federal agencies (IRAP, NRC) c) Companypersonnel(offsite) h$

'd) Onsite personnel-

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-5.2.2 Plant Staff Emergency Assignments The emergency plan should specify the organi--

zational groups to which the following activ-ities are assigned, including an indication of how the assignments are made for both day and night shifts, and designate those assign-ments as filled from onsite and away from site manpower resources (RG 1.101, Rev.1):

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Emergency Coordination and Control (a) Plant Security and Access Control -

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. b) Personnel Accountability -

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(c)Recordkeeping Y86 (d) Offsite Agency Coordination'and Y6 $

Protective Action Recommendations -

_(e) Site Representation at the State EOC -

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2. Plant Systems Operation NS 22@ [83

3. Technical Support 3

4. Onsite and.0ffsite Communications

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For each emergency class, the licensee shall have primary and secondary communications to the following:

a) State /lecal network within 15 min. of the emergency.(only for " General Emergency" class).

b)Federalemergencyresponseorganizations c) Between the nuclear facility and the state / local emergency operation center (E0C).

5. Logistics and Supply Mb

6. Emergency Assessment Measures / Verification

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md 5%C' bed (a) Core Coolant Sampling (b)BoronandChlorideChemicalAnalysis

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l(c) Survey of Airborne Oose Rates, yN$

Airborne Iodine, and Contamination of a

Food Pathways X

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(e) Data' Reduction, Analysis. Reporting and Interpretation

-7. Emergency Corrective Measures

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b (a)Firefighting (b' Decontamination (c) Repair and Damage Control

8. Contamination Control (a) Isolation or Quarantine (b) Contaminated Item Distribution Control

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(c) Control of Water Supplies

9. Aid to Affected Persons fG _$

(a) Rescue (b)-First Aid (c) Decontamination (d) Ambulance Transport (e)MedicalTreatment (f) Hospitalization 5.2.2.1 Emergency Outy Station For each emergency duty station there should be a list of all job assignment responsibil-ities.

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-c) Control Room.

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5.2.2.2 Job Assignment': Diagram C-k$

The licensee shall define in both a graphic-diagram and; narrative text, job assignment (day and night crews).

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7 5.3 Augmentition of Onsite Emergency

-Organization

'5.3.1 Licensee Headquarters Support Headquarters management, administrative, and c

technical personnel should be prepared to

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' assist the plant staff in obtaining ' qualified,

individuals in the following areas:

Logistics Support for emergency j

personnel (e.g. transportation, temporary quarters, food and' water, sanitary facilities in the field, and special equipment and supplies procurement).

Reentry / Recovery Operations Authority Notification

.- Environs Monitoring.

Nus Media. '(RG 1.101, Rev. 1)

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,i 5.3.1.1~ Consultants Identify persons with special qualifications g(}f(-

such as consultants'who are not employees of'

. the licensee but may be' called in during an-emergency situation.- (10 CFR 50, ~ Part _ E).

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. 5.3.1.2 Contracts with Private Organizations If the licensee has contracted with private

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organizations for emergency supporting services -the_ following should be provided:

a) Nature and scope of services i

l-b) Emergency classes for which services are i

required

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c)-Time delay before services can be provided d) Quality assurance specifications of the contractors services e) Letter of agreement with the contractor f) Who will be responsible for notifying the contractor 5.3.2 Local Services Support The ifcensee should identify the extension of i fn the' organizational capability for handling

/ C emergencies to be provided by ambulance, medical, hospital, Land firefighting organi-zations.-

(RG 1.101, Rev.1) t 4

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5. 3.~ 3 Minimum Onsite Emergency Organization

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-r-Provide for the. augmentation of the minimum Mhhe'T' onsite' emergency organization within 60 minutes for all classes of emergencies above A;W8,._ _

the " alert" level.

(Acceptance Criteria)-

s 5.4 Coordination with Particioating Governmental Agencies b

The licensee should identify the principal State agency ~(designated State authority) and other governmental agencies (local, county, State, and Fede.ral) having action responsibilities for radiological emergencies in the area in which the plant is' located.

If the boundary line between two political i

entities, e.g., counties or States; passes within the EPZs (plume and ingestion),

agencies from both governmental entities should be included.

(RG 1.101, Rev. 1) 3 5.4.1 Agency's Authority and Responsibility A description of each agenc 9s authority and g

responsibility for emergency response, par-ticularly in relation to those of the licen-see and to those of other agencies.

(RG 1.101, Rev. 1) 5.4.2 Written Agreements The licensee should provide written agree-ments with each Federal, State, and local agency and other support organizations hav-

/ Vg ing an emergency response role within the A/

Emergency Planning Zones as discussed in NUREG-0396.

The agreements will identify 13

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the emergency. measures to be provided and

'the mutually acceptable criteria for their implementation.

(Acceptance Criteria) t

'5.4.3 Activation and Control of Agency Functions w

Activation of the agency function, including gC titles and alternates for both ends of the comunication links, and primary and alter-

.. native means of. communication. Administra-

-tive control methods-that will ensure the effective c' ordination and control of the o

emergency activities of support organizations should be established. '(RG 1.101, Rev. 1) 5.4.4 State / Local Emergency Operations Center The designation and location of the Emergency MO

' Operations Center of each State / local govern-ment agency.

(RG1.101,Rev.1) 5.4.4.1. Licensee Coordination with Offsite E0C_

-NO The licensee should designate an individual (job title) to be dispatched to the offsite-EOC whose responsibility will be coordin-ating with offsite agencies.

N 5.4.5 Interstate Coordination and Training Provisions should be made where applicable for interstate coordination and training in areas of joint concern, such as:

a) Public education

'b) Public announcements'and warnings 14

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1 c) Protective Action Implementation

- d) Environmental Surveys i

e) Comunications f) Comand and-Control g) Federal interface t

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EMERGENCY MEASURES 6.1 Activation of Emergency' Organization g

m j-The licensee should describe the communica-tion steps taken to alert or activate.

5 emergency personnel under each class of U

emergency.

In particular emergency action

. levels for notification of offsite agencies should be described.

(RG 1.101, Rev. 1) 6.1.1 Initiation of Emergency Response Coordination Designate the imediate steps to be taken

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t and time required by licensee to initiate its emergency response coordination and control measures.

. Initial assessment measures should assure prompt notification to offsite

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authorities within 15 min. of detection of the initiating event.

6.1.2 _Comunications Describe the onsite comunications capability Nb for assuring contact with the offsite author-4 ities responsible for implementing protective measures including a primary and backup means of comunications.

(Acceptance Criteria) i

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.l 6.1'.2.1 Diagram of Communication System

' Description'and diagram of primary and Nb backup communications between:

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.- Control Room-

. Technical Support. Center Operational Support Center L

State and Local Emergency Operations

' Center (EOC) 5

.- Alternate E0C

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Survey data c-llection points Site emergency control center (ECC) and press center (Acceptance Criteria) 6.1.2.2 Control Room a'nd ECC Communications Backup communications description between h

control room and ECC.

Number of radios Provisions for long-term operations Frequencies used should not be subject to overloading 6.1.2.3 Redundant Power Sources-MOT Redundant power sources for all centers required to perform vital emergency func-g %-C( F1 E O tions in transmission and reception of information.

6.2 Assessment Actions The licensee'should provide effective coor-dination and direction of all elements of 1

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the emergency or'ganization requiring con-

-k S tinued assessment throughout the emergency.

--(RG 1.101, Rev. 1) i 6.2.1 Magnitude of Radioactive Material Released i vN - [ f-

-t The magnitude of radioactive material

-- 4 O ^2 released sho'uld be determined from radiation moaitor readings as seen from the control Nh room.

(RG 1.101, Rev. 1) 6.2.2 Magnitude of Radioactive Contamination yQ{ b a) The plan should provide for timely dispatch of radiological monitoring teams to determine plume exposure pathways (inhalation and direct radiation).

Measurement points must extend to the -

Ncrr Wa r F i t=D boundary of the plume EPZ.

b) The plans should provide for taking precipitation, water, and vegetation Y{]

samples within the site boundary and

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ingestion EPZ to assess potential ingestion exposure pathways.

(NUREG-4 75/087).

d 6.2.3 Projected Exposures a) The plan should describe the means of providing real-time meteorological information to the ECC. Also, provide methods of updating weather forecasts (hourly) and how this information is integrated into plume pathway prediction.

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b)' Calculate plume centerline exposure rate

'as inversely proportional to distance (h

from release point, or use prepared isopleths to estimate' exposure rate in downwind area.

(EPA-520/1-75-001) c) Use calculated exposure rate and estimated exposure duration to convert to projected dose.

(EPA-520/1-75-001) d) When the licensee notifies ihe state / local M

agencies of an accident included should be a dose estimates at the site boundary and within the plume EPZ.

(EPA-520/1-75-001) 6.2.4 Emergency Action Levels (EALs) a) EAls for conthinment radiation monitors

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shall be defined for each emergency class.

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s EALs that will utilize the instrumenta-tion discussed in items 2.1.3 and 2.1.8 of NUREG-0578 must be included as soon 2

as possible and a connitment to do such must be provided.

Provisions to esti-mate offsite doses and containment levels before the " lessons learned items" are implemented must be des-cribed to include pre-calculated con-versions and other job aids to be used.

(NUREG-0578)

A h @k CE b) Each EAL should have one verification source independent of the specified EAL.

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c) Plots showing containment radiation monitor readings (in control room) vs.

time following an accident for incidents involving 100% release of coolant N (f,)

af activity,100% release of gap activity, and 1 and 10% of the fuel melting inventory, must be provided in the control room and be placed in the plan along with a' description of how they will be utilized as EALs.

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6.3 Corrective Actions Th'e licensee should identify those actions

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(e.g. fire control, repair, and damage control) in eme~rgency situations which can be taken to correct or' mitigate the situation at or near the source of the

. problem.

(RG 1.101, Rev. 1)

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Corrective actions for site and general e

emergency class should be designated.

6.4 Protective Actions 6.4.1 Protective Actions Based on Oose Provide for recommending protective actions

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to the appropriate State and local author-ities, based on projected dose to the population-at-risk, the projected time sequence of releases, physical form of release, and other appropriate considerations; in accordance with the recommendation set forth in Table 5.1 of the Manual of Protective Action Guides and Protective Actions for Nuclear Incidents, EPA-520/1-75-001.

Upon declaration of a

" general emergency", immediate notification shall be made directly to the offsite authorities responsible for implementing protective measures within the Emergency Planning Zone as discussed in NUREG-0396.

(Acceptance Criteria) 6.4.1.1 Preliminary Planning Preliminary planning should reflect provi- ~

sions for initiating protective actions for all exposure pathways, onsite and offsite, 00g A'lfgIC8p including:-

(a) Direct radiation exposure from a confined source in-plant, an airborne plume, and ground' deposition,

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'(b). Inhalation exposure from an airborne

, plume,'and

_(c) Ingestion exposure from contaminated water, milk,'and other agricultural products.

(NUREG-75/087)

C 6.4.1.2 ProtectiveActionduides Designate protective action guides (PAGs) to be used for implementing specific protective

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actions-in accordance with EPA, HEW /FDA FDF: NOT g@TleNC~O recommendations.

a) PAGs for whole body external. gama radia-tion and for inhalation of airborne plume should be consistent with 4

EPA-520/1-75-001.

b) - PAGs for human food and animal foods should be con'sistent with HEW /FDA(21 CFR Part 1090).

Preventive PAG Emergency PAG

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Emergency classifications are not to be e

based on dose or PAGs.

4 6.4.1.3 ' Emergency Situation

.Upon detection of HEW /FDA response level by the monitoring teams the site must recommend yb

-for protective actions consistent with HEW /

FDA ingestion pathway protective action.

The specific instruments and the readings which indicate the response levels must be included in the plan. The site or offsite agency responsible for implementation of the HEW /FDA protective actions within the ingestion pathway EPZ must maintain a list of the locations of dairy cows, major water sources, food or milk processing plants, etc. within ingestion EPZ along with a point of contact..

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6.4.2-; Protective Cover, Evacuation, 3

Personnel Accountability

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6.4.2.1.1-Action Criteria i

Action-criteria for protective cover and.

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evacuation measures.

(RG 1.101, Rev. 1)

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-.m 6.4.2.1.2 Warning Mechanism va The means and the time required to warn or s

advise persons involved, i.e.,

a) Employees not having emergency assiynments

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b) Working and nonworking visitors I

c) Contractor and construction personnel, and f

d) Other persons who may be in the public

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access areas on or passing through the r *-

site or within the exclusion area.

(RG 1.101, Rev. 1) s L

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6.4.2.1.3 Logistics ps,,

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l Evacuation routes, transportation of person-nel, and reassembly areas, including alterna-tives for inclement weather and'high traffic s

den.si ty.

(RG 1.101, Rev. 1) s Q

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6.4.2.1.4 Missing Persons Check-Missing persons check.

(RG1.101,Rev.1)

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~ 6.4 ; 2.1. 5 ' ' Radiol ogicai r Mo'n i tor ing -

l Radiological monitoring;of evacuees.

(RG t.1.101,Rev.'1)

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.6.4.2.1.6 Communication J1 stems 5

Communicationssyfntryshoul te eeded.f plant J

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evacuation'and e nelude an

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evacuation rm, a;. fire rm, and voice

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communica ons systems. Assurance should'be l

.given t features r plant evacuation and

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reeis y wil.1 be co a'tible with'the plant se' r'ity system d ' procedures.

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2 6~.i ;2'. 2 Offsite Areas

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6.4.2.2.1 Notification of Responsible Offsite Agencies Y

'Upon declaration of Site or General Emergency classification, nffsite agencies y

responsible for implementation and coordina-

!C tion of the protective action within the

/EPZs will be notified.and will be able to

. immediately undertake, appropriate protective

' actions.

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'6.4.2.2.2 Message' Formats for Notification l-

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Predetermined message. formats for.notifica-l-

. tion of all'offsite agencies.must be pro-l.

vided.. These must be developed for each j.,

class of protective action (i.e., shelter,

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evacuation, etc.) and be coordinated with the receiving agencies and the public

. announcements.

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6.4.3 Use of Onsite Protective Equipment and Supplies 6.4.3.1 RespiratoryPrhtection The licensee should have a plan for indi-vidual respiratory; protection for persons within the exclusion area to help minimize t

the effects of radiolci :a1 exposures.

(RG 1.101,Rev.'17' c

a) Criteria for-respiratir issuance x

b) Location of respirators' NO c) Means of distribution

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n 6.4.3.2 Protective Clothin; r

The licensee should have a plan for use of protective clothing for persons within the exclusion area.to help minimize radiation exposure and contamination problems.

(RG 1.101, Rev.1) /

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NO a) Criteria for clothing issuance b) Location of protective clothing N o c)Means'ofdistribution -

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6.4.3.3 Radioprotective' Drugs Thelicenseeshouldhavdaplanfortheuse.

of radioprotective drugs for persons within the exclusion area'to help minimize radiation exposure.

(RG 1.101, Rev. 1) a) Criteria for use of the: drugs b) Source of drugs c) Means of distribution

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23 4

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6.4.4 Contamination Control Measures 6.4.4.1 Plant Site The licensee should provide a plan for preventing or minimizing direct or sub-sequent ingestion exposure to radioactive materials deposited on the' ground or other surfaces within the exclusion area but out-side of fenced' security areas.

(RG 1.101, Rev.-1)

The plan should discuss:

a..Isolatic or quarantine and area access

control,

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b. Control of the distribution of affected agricultural products, including milk,

c. Control of water supplies, and

d. Criteria for permitting return to normal use.

6.4.4.2 Offsite Areas

/YO The licensee should provide a plan for preventing or minimizing direct or subse-quent ingestion exposure to radioactive materials deposited on the ground or other surfaces of ingestion EPZ.

(RG 1.101, Rev. 1)

The plan should discuss:

a. Isolation or quarantine and area access

control,

b. Control of the distribution of affected.

agricultural products,. including milk,

c. Control of water supplies,'and

' 24

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d. Criteria for permitting return to normal

. use.

6.5 Aid to Affected Personnel 6.5.1 Emeroency Personnel Exposure a

The licensee should specify exposure -guide-lines for entry or reentry to area in order.

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to (1) remove injured persons and (2) under-take corrective actions.

(RG 1.101, Rev. 1) 6.5.2 Decontamination and First Aid The licensee should describe capabilities for decontaminating personnel along with

\\[($'j the first aid. training and capabilities of

- appropriate members of the emergency organi-zation.- (RG 1.101, Re1. 1) a) Proposed locations and physical layouts cf first aid and personnel decontamina-tion facilities in the plant should be

/bV indicated.

Brief descriptions of pro-posed equipment ar.1 supplies for these facilities should be included.

(NUREG-75/087) 6.5.3 Medical Transportation The licensee should describe arrangements for transporting injured personnel, who may.

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also be radiologically contaminated, to

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medical treatment facilities.. (RG 1.101,

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Rev. 1) 25 o

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h)LProposed arrangements-for transportation of injured personnel from the site to a relatively nearby hospital should be h

adequate. to.accomodate at.least two persons who may also.be radiologically

. contaminated, within approximately one hour.

(NUREG-75/087)

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lt 6.5.4 Medical Treatment-The licensee should describe. arrangements 1<-

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4 made for local and backup hospital and r_/

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i medical s'ervices and the capability for the evaluation of radiation exposure and uptake.

In addition, all persons providin'g medical l

l assistance should be prepared and qualified to handle radiological emergencies.

(RG 1.101,Rev.1) 1-4 7.

EMERGENCY FACILITIES AND EQUIPMENT l

]

Some criteria listed in this section may i

have been discussed in other sections (4, 5, 3

6) and need not be repeated here.

f.

1 7.1 Emergency Control Centers t

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7.1.1 Onsite

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r The licensee should include the prin:ipal i'

and any alternative onsite locations from which effective l emergency control direction i

is given. One alternative offsite location under the jurisdiction'of the applicant should also'be described.

(RG 1.101, l

.Rev.1)

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7.1.1.1 Diagram of Onsite Emergency Locations Plan should include a diagram showing the locations of the following:

a) Emergency Control Center (ECC) b) Offsite Emergency Operation Center (E0C)

O c) 0nsite Technical Support Cent.er-(OTSC) s d) Onsite Operational Support Center (00SC).

e) Control room.

(Acceptance Criteria) 7.1.1.2 Onsite Technical Support Center Each operating nuclear power plant shall jVO L o c A n o M 6 1\\l @ J maintain an onsite. technical support center 4

separate from and in close proximity to the

$74pp. yo7 f CeWT1FtEO control room that has the capability to display and transmit plant status to those individuals who are knowledgeable of and responsible for engineering and management support of reactor operations in the event of an accident.

The center shall be habit-able to the same degree as the control room for postulated accident-conditions. ' The 4

licensee shall revis' his emergency plans as e

necessary to incorporate the role and loca-tion of the technical support center.

(Acceptance Criteria) a) The center should be activated at the 79/ (3)

" Alert" level or above; b)~ Licensee should provide for an alternate

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location should the original site be inaccessible.

' 27

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7.1.1.3 Onsite Operational Support Center knareatobedesignatedasthe'onsite operational support center shall be estab-

.lished.

It shall be separate from the. con -

trol room and shall be the place to which the. operations support personnel will report in an emergency situation.

Communications a

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with the control room shall be provided.

(Acceptance Criteria)-

a) The licensee must. provide communication

..O (primary and backup) with the onsite technical support center or the emergency control center (ECC).

'b)' Licensde should provide for an alternate k

location should the original site be inaccessible.

7.1.2 Offsite.

Provide for the dispatch of a representative to the principal emergency operations center established by the offsite agencies (not required if licensee's offsite emergency operation center is at the same location as the predetermined location of the Emergency Operations Center to be used for the coordination of all offsite emergency support activities.

(AcceptanceCriteria)

+

7.2 Comunications Systems

' The licensee should describe both onsite and M

offsite communications systems including redundant power systems (RG 1.101, Rev. 1)s

~ [3 The licensee shall define primary and alternate communications equipment, net-working and delimitation and verification methods for the principal message traffic, linking the following onsite and offsite of contact:

/V O centers, organizations, agencies and points -

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(1) Plant Site:

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'M u 5 I" e Emergency Operations Center e State. Emergency Operations Center 7gg{y f gggJ,

,e Control Room

- e Onsite Technical Support' Center e Onsite Operational Support Center

. Offsite Emergency Operations Center i

o Press Center (must be provided in the area of the plant-written agreement-with capabilities for about 25 telephone hookups and x

backup communicati~ ens.with the site and state E0C. Also, specific time following a declared emergency at

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which the center can be activated.

(2) State:

e Governor

. State Legislature e State Civil Defense / Emergency Service e Environmental or Health Departments e Highway Patrol Office (Headquarters) e National Guard

. Highway Department e Department of Agriculture (3) County or Local:

Usually either the county or local (mt. 'ciple-township) personnel are res asible for emergency actions.

(3a)

County:

e County Executive o County. Sheriff's Office

. Highway Department-e Department of Agriculture

. Civil Defense and Emergency Services e Environmental or Health Department

. County Fire and Rescue Departments (3b) local (Municipal or Township):

e Mayor / City Manager's Office e Civil Defense / Emergency Services 29

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. Police Department /LLEA

.. Fire and Rescue Departments

. Welfare / Social Servii:es

. Publi.c Utilities (4).

Federal (Regional):

. U.S. Nuclear Regulatory Commission (NRC)

. Federal Emergency Management e

Agency (FEMA) e U.S. Army Corps of Engineers s

. General Services Administration (GSA)-

e Department of Agriculture

. Defense Civil Preparedness Agency (DCPA) e Environmental Protection Agency (EPA)

. Federal Preparedness Agency (FPA-GSA)

. NWS/NOAA (National Weather Service /

~

National Oceanic Atmospheric Administration).

. FDA/ HEW 7.3 Assessment Facilities 7.3.1 Onsite Systems and Equipment 7.3.1.1 Geophysical Phenomena Monitors gQ The-licensee should include a list of the types of monitors to be used to measure geophysicalphenomena(e.g. meteorological, hydrologic, seismic) for-initiate emergency measures, as well as those to be used for continuing assessment. -(RG 1.101, Rev. 1) 7.3.1.2 Radiological Monitors ffD

• The licensee should include a list of the types of radiological monitors (process, iMhcN\\

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' area, emergency, effluent, and portable monitors.and sampling equipment) that are to be used to initiate emergency measures.

as well as those to be used for continuing

. assessment.

(RG 1.101, Rev. 1) 7.3.1.2.l~ In-Plant Iodine Instrumentation Each licensee shall provide equipment and

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associated' training and procedures for accurately determining the airborne iodine concentration throughout the plant under 1

accident conditions.

(NUREG-0578)

J 9

7.3.1.2.2 Inadequate Core Cooling UD C5 a) Licensee shall develop procedures to be i

used by the. operator to recognize inadequate core cooling with currently 4

available instrumentation. The licensee shall' provide a description of the existing instrumentation for the operators to use.to recognize these conditions.

(NUREG-0578) b) Licensees.shall provide a description of any additional instrumentatiori or controls (primaryorbackup)proposedfor the plant to supplement those devices giving an unambiguous, easy-to-interpret indication of inadequate core cooling. A description of the functional design requirements for the system shall also be included. A description of the proce-i 4

dures to be used with the proposed equip-ment, the analysis used in developing these procedures, and a schedule for installing the equipment shall be pro-vided.

(NUREG-0578)

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. - 4 7.3.1.2.3 Post-Accident Sampling Capability a) The reactor coolant and containment

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atmosphere. sampling systems should enable personnel to promptly obtain (less than 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) a sample under accident conditions without incurring a radiation exposure to any individual in excess of.3 and 18 3/4 i

Rems to the whole body or extremities, respectively. Accident conditions should assume a Regulatory Guide 1.3 or 1.4 release.of fission products.

(NUREG-0578) b) The radiological spectrum analysis-Yldr $95 b d

facilities should have the capability to promptly quantify (less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />)-

certain radioisotopes that are indicators of the degree of core damage. Such radionuclides are noble gases (which indicate cladding failure), iodines and cesiums.(which indicate high fuel temperatures), and non-volatile isotopes (which indicate fuel melting). The initial reactor coolant spectrum shbuld correspond to a Regulatory Guide 1.3 or 4

1.4 release.

(NUREG-0578) 7.3.1.2.4 Effluent Monitors

- 1AO M#b a) Noble gas effluent monitors should have u

an extended range designed to function during accident conditions as well as during normal operating conditions; multiple monitors are considered to be necessary to cover the ranges of interest.

Total range of concentration extending from a minimum of 10-7 pC1/cc (Xe-133) to a maximum of 10b pCi/cc (Xe-133).

(NUREG-0578).

b) Since iodine gaseous effluent monitors

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8 for the accident condition are not considered to be practical at this time, capability for effluent monitoring of radiciodines for the accident condition 32

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shall be provided with sampling ~ conducted by adsorption on charccal or other media, followed by onsite laboratory analysis.

(NUREG-0578) 7.3.1.2.5 In-Containment Radiation Level

- M'I (ANIAAmo o

Monitor In-containment radiation level monitors with a maximum range of 108 rad /hr or 107 R/hr shall be installed. A minimum of two such monitors-that are physically separated shall be provided. Monitors shall be designed and qualified to function in an accident environment.

(NUREG-0578)

_ gp gy;te;{d 7.3.1.3 Process Monitors The licensee should include a list of the types of process monitor (e.g., reactor coolant' system pressure and temperature, containment pressure and temperature liquid levels, flow rates, status lineup of equip-ment components) that are to be used to initiate emergency measures, as well as those to be used for continuing assessment.

(RG 1.101, Rev. 1) i 7.3.1.4 Chemical Analyses

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0 In addition to the radiological analyses, certain chemical analyses are necessary for monitoring reactor' conditions.

Procedures shall be provided to perform boron and chloride chemical analyses. assuming. a highly radioactive initial sample (Regulatory Guide 1.3 or 1.4 source-term).

Both analyses shall be capable of being completed promptly; i.e.,

33

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the boron sample analysis within an hour and the chloride sample analysis within a shift.

INUREG-0578) t 4-7.3.1.5 Fire Detection Devices h5 The licensee should include a list of the

. type of fire detection devices that are to s

be used to' initiate emergency measures, as well as those to be used for continuing

. assessment.

(NUREG-0578) j 7.3.2 Facilities and Equipment for Offsite Monitoring The licensee should include a listing of

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facilities and' equipment for offsite moni-toring.

(RG1.101,Rev.1) 7.3.2.1 Field Monitoring - Offsite

- M h h d c W T h e_.

Identify the capability and resources for field monitoring.in the environs of the plant including the additional dosimetry specified in the revised technical position issued by the NRC Radiological Assessment Branch for the Environmental radiological monitoring program.

(Acceptance Criteria)

" Forty Stations with two or more dosimeters l

or one instrument measuring and recording dose rate continuously to be placed as follows:

1) an inner ring of stations in the. general area of the site boundary and an outer ring in the four to five mile range from the site with a station in each sector of each ring (16' sectors x 2 rings = 32

~

stations).

The balance of the stations, eight, should be placed in special interest areas such as population centers, nearby residences, schools, and one to three in an area (s) to serve as a control' station (s)."

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-7.4 Protective Facilities and Equipment The' licensee should describe specif'ic k3C-

. facilities and equipment that are intended

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to serve a protective function (e.g. shelter j

facilities, assembly areas, and respirators).

(RG 1.101, Rev. 1)

O 7.5 First Aid and Medical Facilities The licensec should provide'a summary g; p )C description of onsite_and offsite first aid Jw and medical facilities.

(RG 1.101, Rev. 1)

)[kb by a) The identification of offsite hospital facilities shop 1d include:

- One facility relatively nearby which is willing and potentially capable of-handling patients from the plant site who may be radiologically contaminated, on an emergency basis, and

- A second hospital which is expected to be ' capable of providing definitive patient care for acute radiation injury.

(NUREG-75/087) 7.6 Damage Control Equipment and Sucolies D

~~~~'

The licensee should provide a summary description of onsite damage control equipment and supplies.

(RG 1.101, Rev. 1)

.8.

MAINTAINING EMERGENCY PREPAREDNESS 8.1 Organizational Preparedness a

35

m v

8.1.1'ITraining Licensee provided training objectiv'.s should e

include.the following minimal component specifications :

a) What training strategies and materials

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the' student will be given;-

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b)<How will the trainee be tested; and c) How well,(to wh'at performance s;andard)

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~the trainee must purform to demonstrate training objective mastery.

9 i.

8.1.1.1 Directors of Plant Emergency Organization The licensee should describe the specialized t.3 f

initial training and periodic retraining

~

l programs to be provided to the directors or

]

coordinators of.the plant emergency-.

organization.

(RG 1.101, Rev. 1) 1-i I

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8.1.1.2 Accident Assessment The licensee should describe the specialized

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initial training and periodic retraining programs to be provided to personnel respon-i sible for accident assessment including con-Rev. 1)

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(RG 1.101, trol room shift personnel.

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8.1.1.3 -Radiological Monitoring Teams hh The licensee should describe 1the specialized initial training and periodic retraining.

programs to be provided to radiological monitoring teams. -(RG_1.101, Rev. 1)

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v 8.1.1.4 Fire Control Teams The licensee should describe the specialized MO initial training and periodic retraining programs to be provided to fire control teams (fire brigades).

(RG 1.101, Rev. 1) t g

8.1.1.5 Repair and Damage Control Teams 0

The licensee should describe the specialized

~ initial training and periodic retraining programs tio b'e provided to repair and damage

~

control teams.

(RG 1.101, Rev. 1)

N 8.1.1.6 First Aid and Rescue Teams ND The licensee should describe the specialized initial training and periodic retraining programs to be provided to first aid and rescue' teams.

(RG 1.101, Rev. 1) 4 8.1.1.7 Local Service Personnel NO The licensee should describe the specialized initial training and periodic retraining programs to be provided to local service personnel.

(RG 1.101, Rev. 1) 4 8.1.1.8 Medical Support Personnel The licensee should describe the specialized l

initial training and periodic retraining programs to be provided to medical support personnel.

(RG 1.101, Rev. 1) 1

' 37 4

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8.1.1.9 Licensee's Headquarters Support Personnel.

The licensee should describe the specialized

. initial training and periodic retraining programs.to be provided to licensee's headquarters support personnel.

(RG1.101,

'Rev.1)-

4 8.1.2 Drills and Exercises 8.1.2.1 Initial Exercise The licensee should provide for an initial-exercise prior.to-loading of the first unit I.

to test the adequacy of timing and-content a

of implementing procedures and methods, to-

test emergency equipment, and to ensure that emergency organization personnel'are familiar with their duties.

(RG 1.101,-

Rev. 1)

Included.should be:

~

a) Proviitons for coordination with and p'articipation of offsite emergency

. personne's (State and local agencies).

b) Testing of communication's links and 1

notification procedures with offsite agencies to demonstrate that' capability for early warning of the public is 1

maintained.

1 c) The criteria for determining that an adequate emergency response capability exists at the facility.

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d) Corrective action for failure to meet the criteriainc).

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-8.1.2.2. Annual Exercises I

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k ir Theilicensee should provide'for.. annual exer-0b i

cises using. scenarios appropriate ~to the Site t

Emergency or General. Emergency Classifica =

tions to test the'adequancy of timing and-content of implementing. procedures and methods, to test. emergency.equ.ipment, and to ensure that emergency-organization personnsi~

.are familiar with their duties.

(RG 1.101, L

Rev..1).

. Included should be:

'A a). Provisions for coordination.with and participation of offsite emergency j( j' i

. personnel'(State and local agencies).

b)~ Testing of communications links and notification' procedures with offsite j

agencies to. demonstrate that capability m.

for early warning of'the public is F

maintained.-

c) The criteria for determining that an i

adequate emergency response capability exists at.the facility.

MO I

d) A mean's.to evaluate observer and_

participant comments and establish a method for assigning responsibility for implementing corrective actions,

[

specifying~ times by which corrective actions should be complete and for evaluation of the' adequacy of such g

corrective actions.- -

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f-8.1.2.2.1 Radiation Emergency Orill N

At least once each~ calendar year (and no gg

-sooner than 9 months or later than 15 months from the last drill) the licensee should

' conduct a radiation emergency drill.having a scope of response at least equivalent to a Site Emergency. This. drill.should be in "real-time" and unannounced as to time or scenario.

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-At least once every three years this drill

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8.1.2.2.2 Medical Emergency Orill k'

A medical emergency drill should also be conducted at least once each year'and involve the' actual transport of a " patient" and activation of the offsite medical support facility.

If the offsite medical facility supports several other nuclear facilities; the involvement of the medical facility may not be necessary each year.

In such cases, notification-to and verification of their response role should be ascertained.

8.1.2.3 Fire, Repair and Damage Control Exercises

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members, annual fire emergency drills con-itch taining provisions for a participation by an offsite fire department,.and annual drills C-[86fb 'J'"-

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an damage control teams.

(RG gQ VKci pp)tb 8.1.2.4 Joint Exercise - Federal, State, Local Provide, in addition to the drills and

[43 exercises identified in Regulatory Guide 1.101, a joint exercise involving Federal, State, and local response organizations.

The scope of such an exercise should test as much of the emergency plans as is reasonably achievable without involving full public 40

~

~4 participation.

Definitive performance e,

criteria will be' established for all levels

(()-7A/ Lux of participation to assure an objective evaluation.

This joint test exercise will be scheduled about once every five years.

(Acceptance Criteria) e

(

8.1.3 Emergency Planning Coordinator The licensee should establish and maintain an on the normal plant operating staff an h TV3su Emergency Planning Coordinator whose responsibility should include the coordina-tion of offsite emergency planning efforts.

Principal duties of this position may be described in this section.

(RG 1.101, Rev.1) 8.2 Review and Updating of the Plan and Procedures The licensee should have provisions for (a)

[

g annual review of the emergency plan and for

(

updating and improving procedures to incor-porate results of training and drills and to

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account for changes onsite or in the environs (b) means for maintaining all coordinate elements of the total emergency organization T

pd informed of the plan and revisions to the

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plan or relevant procedures should be des cribed, and (c) reviewing and updating all written agreements at least every two years.

(RG 1.101, Rev. 1) 8.3 Maintenance and Inventory of Emergency Equipment and Supplies

.The operational readiness of all items of emergency equipment and supplies should be 41 2

~.

3 ensured., The provisions for performing

.ma n enance, surveillance testing, and it inventory on emergency equipment and supplies should be described.

(RG 1.101, Rev. 1)

- c 9.

RECOVERY This secti6n should describe general plans, including applicable criteria, for restoring the plant as nearly as may be possible to a safe status.

(RG 1.101, Rev. 1)

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