Text

Radiological Contingency Plan.Two Oversize Maps Encl. Aperture Cards Will Be Available in PDR
	ML20030D661
Person / Time
Site:	07001113
Issue date:	08/28/1981
From:	; GENERAL ELECTRIC CO.
To:	;
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References
	19582, PROC-810828, NUDOCS 8109140321
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GENER AL $ ELECTRIC

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General Electric Company Wilmington Manufacturing Department 4

Wilmington, N. C.

SNM-1097, Docket #70-1113 i

l RADIOLOGICAL CONTINGENCY PLAN 1-

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TABLE OF CONTENTS Page No 1.

GENERAL DESCRIPTION OF THE PLANT / LICENSED ACTIVITY.......

1-1 1.1 Licensed Activity Description.......................

1-2 1.2 Site and Facility Description.......................

1-3 1.3 Process Description.................................

1-4 2.

ENGINEERED PROVISIONS FOR ABNORMAL OPERATIONS..'..........

2-1 2.1 Criteria for Accommodation of Abnormal Operations...

2-1 2.1.1 Process Systems..............................

2-1 2.1.2 Alarm Systems and Release Prevention.........

2-1 2.1.3 Support Systems..............................

2-2 2.1.4 Control Operations...........................

2-4 2.2 Demonstration of Engineered Provisions for Abnormal Operation........................................

2-4 3.

CLASSES OF RTDIOLOGICAL CONTINGENCIES....................

3-1 i

3.1 Cl a s s i f ica t ion S y s tem...............................

3-1 j

3.2 Recommended Classification Scheme...................

3-1 3.3 Range of Postulated Accidents.......................

3-2 4.

ORGANIZATION FOR CONTROL OF RADIOLOGICAL CONTINGENCIES...

4-1 4.1 Normal Plant Organization...........................

4-1 4.2 Onsite Radiological Contingency Response Organization.....................................

4-1 4.3 aftsite Assistance to Facility......................

4-2 4.4 Ccordination with Participating Government Agencies.

4-2 5.

RADIOLOGICAL CONTINGENCY MEASURES........................

5-1 5.1 Activation of Radiological Contingency Response Organization.....................................

5-1 5.2 Asseasment Actions..................................

5-1 5.3 Corrective Actions..................................

5-2 5.4 Protective Actions..................................

5-2 5.5 Exposure Control in Radiological Contingencies......

5-3 5.6 Medical Transportation..............................

5-5 5.7 Medical Treatment...................................

5-6 9

Nor LICENSE SNM-1097 DATE 8/28/81 PAGE DOCK 2T 970-1113 REVISION 0

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TABLE OF CONTENTS (Continued) s Page No 6.

EQUIPMENT AND FACILITIES.................................

6-1 6.1 Control Point.......................................

6-1 6.2 Communications Equipment............................

6-1 6.3 Facility for Assessment Teams.......................

6-1 6.4 Onsite Medical Facilities...........................

6-2 6.5 Emergency Monitoring Equipment.........

6-2 7.

MAINTENANCE OF RADIOLOGICAL CONTINGENCY PREPAREDNESS CAPABILITY...........

7-1 7.1 Wr i t t e n P ro ced u r e s..................................

7-1 7.2 Training............................................

7-1 7.3 Tests and Drills....................................

7-2 7.4 Review and Updating of the Plan and Procedures......

7-2 7.5 Maintenance and Inventory of Radiological Emergency Equipment, Instrumentation, and Supplies.........

7-2 8.

RECORDS AND REPORTS......................................

8-1 8.1 Records of Incidents................................

8-1 s

i 8.2 Records o f Preparedness Assurance...................

8-1 8.3 Reporting Arrangements..............................

8-1 9.

RECOVERY.................................................

9-1 9.1 Reentry.............................................

9-1 9.2 Plant Restoration...................................

9-1 9.3 Resumption of Operations............................

9-2 APPENDIX A - PIIOTOG RAPil E X II I B I TS.............................

A-1 APPENDIX B - MAPS............................................

A-2 A

NRC LICENSE SNM-1097 DATE 3/28/81 PAGE 0

ii DOCKET 470-1113 R EV I S I ON

1.0 GENERAL DESCRIPTION OF PLANT / LICENSED ACTIVITY On February 11, 1981, the General Electric Wilmington Manufacturing Department (GE-WMD) was requested by the Division of Fuel Cycle and Materials Safety to prepare a radiological contingency plan for its nuclear fuel fabrication facility.

The following plan is submitted in res anse to that request.

This Plan has been prepared in accordance with the

" Standard Format and Content for Radiological Contingency Plans for Fuel Cycle and Materials Facilities" published January 9, 1981 for the Office of Nuclear Safety and Safeguards of the Nuclear Regulatory Commission.

The required format for the Radiological Contingency Plan calls for extensive information much of f-which already exists in documents submitted to the NRC under License SNM-1097, Docket 70-1113.

To avoid unnecessary repetition and potential confusion, the following Plan submission contains many references to the existing documents.

Cross reference codes are as follows:

o License Renewal Application dated 5/27/81, abbreviated RA and followed by the Chapter or Figure or Table reference; i.e.,

RA Chapter 1.4.

o GE WMD Emergency Plan dated 2/27/79, abbreviated EP and followed by the Section or Figure or Table reference; i.e.

EP Figure 5.3.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET M70-1113 R EV I S I O N 0

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References internal to the WMD Radiological Contingency Plan are underlined and will be found within this document, i.e. Exhibit 1.

In accordance with established NRC practice, Chapters 1 - 8 of the License Renewal Application are considered licensed information and Chapters 9 through 17 are information to be followed by license demonstration.

The GE WMD Emergency Plan is licensed information.

The following GE WMD Radiological Contingency Plan reference to licensed information carries with it the implication that it is also licensed for the purpose of this Plan; where demonstration information has been presented, it maintains that classification in this Pliin.

Appendix A, photograph exhibits, located at the end of the text provide a pictorial display of tne Emergency

,1 Control Center and equipment used by the Emergency Organization.

1.1 Licensed Activity Description The types of activity that are performed at GE-WMD are described in RA Chapters 1.2, 1.5.1 through 1.5.5.

A general description of where these activities are performed is shown in RA Figures 1.1 and 1.2.

The types of products produced at GE-WMD are summarized in RA Chapter 9.3.

The types of wastes generated, treated, sampled and disposed of at GE-WMD are described in RA Chapters 5.1.1 through 5.1.3.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET #70-1113 REVISION 0

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The types, forms and quantities of special nuclear materials authorized to be ut d and possessed at GE-WMD are described in RA Chapter 1.4.

1.2 Site and Facility Description Site and general area maps are provided in Appendix B, map packet provided at the end of this document.

The GE-WMD plant layout is pravided in RA Figures 10.l.

The areas where nuclear materials are manuf actured, stored or treated are indicated in RA Figures 10.2 and 10.3.

A USGD 7.5' topographical map, Appendix B, 6emonstrates that GE-WMD is located in a rural area away from major populated areas.

Other aspects of the area's population are presented in RA Section 9.4.1.

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The map of the Wilmington, North Carolina metre area, Appendix D, identifies local routes of access, location of potential emergency facilities and other sites of potential emergency s:gnificance.

W NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET #70-1113 REVISION 0

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Criteria and ' specifications relevant to the GE-WMD facility operation are described in the following documents:

License Renewal Facilitv/ Operation Application General Process Flow Figure 16.1 Containment Systems Chapter 16 (all)

Table 3.1 Building Ventilation Systems Chapter 3.2.2 Figures 5.1 and 5.2 Radioactive Release Detection Systems Chapter 3.2 Chapter 13.2.1.1 Chapter 13.2.1.12 Chapter 5.1.1 Chapter 5.1.2 Criticality Safety Consideration Chapter 4.2.2 Chapter 4.2.3 Chapter 4.2.4

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Major Equipment Layout Figure 12.2 1.3 Process Description The fuel process is depicted in RA Figure

,6.1 which indicates the reagents, flow, waste streams and final product.

Specifics of the waste streams are presented in RA Figure 5.3.

Nuclear material types, quantities and areas are identified in RA Chapters 1.4 and 1.5 and 16 (all).

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NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET #70-1113 R EV I S I ON 0

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i 2.0 ENGINEERED PROVISIONS FOR ABN3RMAL OPERATIONS 2.1 Criteria for Accommodation of Abnormal Operations 2.1.1 Process Systems Radiological and nuclear safety detection and measurement systems capabilities including the alarms, interlocks and safety features and the purpose of these safety devices are described in RA Chapter 3.1.2.2 and RA Table 3.1.

Ventilation and containment design considerations and philosophy for normal and abnormal conditions are described in RA Chapter 3.2.4.1.

A description of the process / facility design philosophy for criticality control and prevention is presented in RA Chapter 4.1.1.

A description of the air sampling system and a discussion of alarm limits, action limits and protective or corrective action requirements are

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provided in RA Chapter 13.4.

2.1.2 Alarm Systems and Release Prevention Capability A description of the criticality alarm system and discussion of the technical aspects of the component are presented in RA Chapter 12.6.4.

A system plant diagram and a description of sensor locations within the fuel manufacturing areas are shown in RA Figures 12.1, 12.2, and 12.3.

The airborne effluent control systems are described in RA Chapter 5.1.1.

A block diac ram description of the ventilation system is provided in RA Figure 5.1 and 5.2.

A discussion of lower limits of detection calibration and standardization of measurements is provided in RA Chapter 5.1.1.4.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE 0

2-1 DOCKET 470-1113 R EV I S I ON

i A description of the areas for monitoring and control of liquid effluents is provided in RA Chapter 5.1.2.1.

The process flow and the site dam capability for control of liquid spills is described in RA Figure 5.3.

Action levels for control of liquid effluents are defined in RA Chapter 5.1.2.2.

A description of the continuous air monitoring system which provides an early warning of loss of containment control (as well as being used for cmployee exposure assignments) is presented in RA Chapter 13.4.5.

The criticality alarm system and continuous air monitoring systems have remote readout and alarm set, alert, and alarming capabilities on the console units in Radiation Erotection and the Emergency Control Center.

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2.1.3 Support Systems 2.1.3.1 Structural Performance versus Site Environmental Factors 2.1.3.1.1 Severe Natural Phenomena The design basis for containment under extreme conditions such as fire, wind, flooding, and earthquake is discussed in RA Chapter 10.6.1.

Designs of all fuel facility structures necessary for criticality safety are approved by certified civil engineers.

2.1.3.1.2 Accidents at Neighboring Activities Because the GE-WMD plant is located in a rural environment, removed from other industries, there is no accident foreseeable at any local industry which could adversely affect activities at GE WMD.

W NRC LICENSE SNM-1097 DATE _

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2.1.3.2 Access and Egress of Operating Personel and Emergency Response Teams 2.1.3.2.1 Onsite A description for evacuation to the normal staging area or to a remote staging area is provided in EP Section 7.4.

Emergency response team re-entry techniques are defined in implementing Emergency Procedures.

2.1.3.2.2 Near Site Offsite evacuation can be accomplished through the local Civil Preparedness Agency (see EP Section 7.4.3).

The offsite based emergency personnel who may have a need to respond to emergencies at GE-WMD are identified in EP Section 5.3.

The main north-south Highway (117) has no major obstacles (bridges, railways, etc.) that would prevent access or egress from GE-WMD during an emergency.

2.1.3.3 Fire and Explosion Resistance and Suppression A schematic of the GE-WMD fire protection system, a description of the fire protection program, and fire safety considerations in waste procedures are presented in RA Chapters 10.6, 10.6.4, and 10.6.5.

No special provisions for explosion suppression or resistance are utilized at GE-WMD.

2.1.3.4 Shielding Ventilation, containments, and the process equipment

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provide shielding to prevent internal exposure to radioactive materials such as uranium.

In the event of a criticality accident, immediate evacuation uses time and distance as the technique to limit exposure from radiation.

.m NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET 470-1173 REVISION 0

2-3

A tabulation of abnormal occurrences for the past three years is provided in RA Table 1.3.

There has been no criticality type accident since GE-WMD began operations in 1969.

2.1.4 Contial Operations The ntire Radiation Protection Program for protection and prevention of exposures for various operational aspects at GE-WMD is described in RA Chapter 12.0.

Included is a description of equipment, sampling, frequencies, limits, and protective respiratory equipment.

2.2 Demonstration of Engineered Provisions for Abnormal Operations Engineered provisions for abnormal operations have been discussed previously in sections dealing with i

ventilation, air sampling, criticality monitoring, and building safety.

Many of the systems are routinely checked to assure operability.

The criticality alarm system is activated weekly by source checking a detector with a sealed source causing the system to alarm.

This also provides an automatic signal generated on the fire system's autocall which causes a remote readout at a security guard station and the sounding of an emergency alarm through the fire horns.

The continuous air monitoring (CAM) system is routinely being monitored since it is a "real time" system capable of alerting by alarming in the Radiation Protection Of fice when conditions indicate an unfavorable trend, failure, or high alarms.

W NRC LICENSE S NM-10'9 7 DATE 8/28/81 PAGE 0

2-4 DOCKET #70-1113 REVISION

All ventilation systems are routinely checked to assure that differential pressure readings are within operating specifications and that air flows through openings such as hoods, doorways, meet license cc itions.

Emergency equipment is routinely checked.

Emergency radiation detection equipment is optimally checked and calibrated according to GE-WMD's calibration schedule.

Emergency drils and exercises, covering aspects of emergency preparedness, are routinely conducted and documented.

These exercise practices enable the organization and emergency teams to handle nonroutine incidents under varying conditions and problems.

Exercises are conducted yearly with of fsite support organizations to maintain a readiness to help GE-WMD in the unlikely event a radiation accident should occur, f

The auxiliary power supplies, which would provide emergency power to essential equipment and areas, are checked and routinely tested to assure they are capable of handling the function for which they are designed.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET 470-1113 REVISION 0

2-5

3.0 CLASSES OF RADIOLOGICAL CONTINGENCIES 3.1 Classification System Correlation betwuan the current GE-WMD emergency classification system and the recommended NRC standard format is shown below.

Also shown are the relevant references in the GE-WMD Emergency Plan.

EMERGENCY CLASSIFICATION EMERGENCY PLAN NRC GE-WMD Unusual Event Personnel Emergency Chapter 4.1.1 Local Plant Chapter 4.1.3.2.1 Emergency Alert Emergency Alert Chapter 5.1.2 Operational Plant Chapter 5.1.3.2.2 Emergency (i

Site Emergency

!ite Emergency Chapter 4.1.4 LJ General Emergency General Emergency Chapter 4.1.5 3.2 Recommenced Classification Scheme A representative classification scheme, Fire & Explosion, is outlined in Exhibits 3.1.1 through 3.1.4.

The implementing procedure has an emergency description, initiating signal, emergency personnel work stations, i n cl ud.8 ng identification of specific responsible individuals, an action sequence overview and communication requirements.

These descriptions are supplemented by detai3ed functiona procedures and instructions for identified individuals in the emergency organization that provide them with action sequences in a step-by-step logical sequence, sufficiently detailed for a qualified individual to perform the required activities.

NRC LICENSE Si W - 1 0 'J 7 DATE 8/28/81 PAGE D OC K riT M70-1113 REVISION 0

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3.3 Range of Postulated Accidents x.

The spectrum of postulated accidents, assessment of offsite impact, instrumentation capabi.lity for detection and continued assessment, manpower needs in relation to the anticipated sequence and timing of events are presented in EP Chapter 4.2.

The composition of the around-the-clock emergency response staff is shown in EP Table 5.3.

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NRC LICENSE SNM-1097 DATE 8/28/81 pact DOCKET #70-1113 REVISION 0

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EXHIBIT 3.1.1 J

Coorm T M AT ! F*3 S*;M"AHY FtTUATION FIN AND MR FtPLO IOM 1.

CI Ae f F f C AT t"*J trvrLt Local Plaa.t Imergency - A situation af f ect ing on1, a local area of the plant a mi involving r e a v. < e-l y few personnel.

It may reqeare v acu tton cf the affecteJ area, bat it ca.* controlled by the Pullding Manager av.J the resources normally at has disposal.

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Plant A situation whteS presents a hazard to Em rterzy or site a major portion of a plant operation, EEergency and/or to a signalicart nur.ber of gersonnel.

The Emergency Director, site emergency tea +s

&nd posstoly ofi-site apport agencies are reaattei. For site emergencies release of hazardous maternal to the environment ma/ t.=r involved to the extent that protective measces for off-stte individuals may te warran'ed.

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INitfA!!NO stCNAtr Local Plant Emergoney - Peport of Siturt v and/or Fire Alarm Operational *1 ant Emergenef or Fits turgency - Decision by Dailding Fanagar an' unling of Sscond Alarm 3

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rw r o9 r*:TY FEFS' NFL w W ST AT IO*3 (0-erational ?lant Emergency or site Emergency Only)

Ereraency Incident Feec'len cr,9 t r' saatar Lo' u t en Stari-Py Esergency Director X

Ba11 ding 4anaaer X

Indust rial Saf ety Manager X

Fire Prinnie X

Nelear safety Advisor

X Survey Tea **

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Hutliang Search 6 Fescue X

Facilities.4anager X

Entry Team X

Stagang Area Supervisor

X Plant Medical X

Recceder X

Environrent al Enginee r X

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Facilities Manager P' Mcivar Jd Sumtey N/A IMact rial 5ef et y Menaler CF SS1[ p C Hampt on Fit a Bric.2de Chief haclear Safet A1rinnr CE Powars

$P Mstray Red Prot Superv:sor staitnq Ar*a orarvinor RC l' a r e fMacean Fuel Support 51 t a P; ant Me dical Lea ler ER "lunsett PN Hallis Indantrial Narse becorder GW Pckentle H Stern hansing Site Manager

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CCt"F;iCATICf;S FEruf Rf t:Er;TS:

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LOCAL PL A?4T Ef'EEGE!;CY j

Wi:D Department Goncral !!anager At the discretion of the Building I'.a na ger

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llithin 30 days i

j Radiation Protection Branch of Within 30 days the f!.C. Department of Human 1

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i CPERATICf;AL PLA*lT f!!EPCE!;CY OR SITE Ef4ERGE!;CY i

i WlC Cepartnent General Manager

! mediate f;otification I

i f;uclear Energy Products At the discretion of the Emergency i

Division Geaeral Manager Director (Operational Plant Energency);

i Immediate f;otification (Site Emergency) i Manager - f:E"QA0 Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (Operational Plant j

Emergency); Inmediate I;otification j

(Site Emergercy) 1 1

lbnager - Safety & Licensing At the discretion of the Energency Operation (!;E Projects Div.)

Director

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i Manager - Taxes & Insurance Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months (l;uclear Encrgy Finance Cpn.)

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!=ediate fbtification Radiation Protccticn Eranch of Irrediate I;otification the !1.C. Ocpartment of Human Resources ft.C. Division of Environmcntal ImWiste !;otification if significant j

fianagement (Wilmington office) smoke release of f-site or if involving hazardous chemicals j

Environmental Protection Agency Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months - Site Emergency Only j

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In.ediate f;otifica' a of a Site i

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NRC LICENSE ST Di-10 9 7 DATE 8/28/81 PAGE l

DOCKET #70-1113 RE'ISION i

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EXHIBIT 3.1.4 Page 2 6.

C0ti:U :!CAi!C' S REC'JIPE!:E!;TS:

(FIRE AND/OR EXPLOSIO!!)

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CRITERIA

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t;ew Hanover licmorial Hospital

! mediate alert if injuries / contamination 0; den Pescue Squad Imediate t;otification if medical trans;ortation assistance is required (First Choice) f.ew Hanover County Rescue Squad

! mediate i.otification if medical transportation assistance is required (Second Choice) l Wrightstcro Volunteer Fire Imrrediate f:otirication if fire Department fighting assistance is required

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(Fi.st Choice)

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Castle Hayne Volunteer Fire Imrediate fotification if fire Department fighting assistance is requir'd (Second Choice)

Wilmingten Fire Depart cqt 1:rcediate flctification if fire fighting assistar.cc is required (Third Choiv2) ti.C. Department of Labor I;otify within 4S hours if a fatality occurs, or if 5 employees hospitalized Factory I'utual Engineering f;otify within one wu k American f.uclear Insurance l'pon recorrendation of Manager, Taxes and Insurance l

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NRC LICENSE SNM-1097 DATE _ 8/28/81 PAGE DOCKET 470-1113 REVISION 0

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g-n 4.0 ORGANIZATION FOR CONTROL OF RADIOLOGICAL CONTINGENCIES 4.1 Normal Plant Operation A description of the plant organization for normal operations is provided in EP Table 5.1 and EP Chapter 2.2.

4.2 On-Site Radiological Contingency Response Organization The on-site emergency organization of plant staff personnel for controlling each class of emergency for both day and night operations is shown in EP Section 5.2, EP Tables 5.2 and 5.3.

The Emergency Director has been delegated full responsibility and authority for the implementation and administration of the Emergency Plan in a letter of designation by ;he General Manager (EP Appendix D).

Exhibit 3.1.1 provides a line of succession by prime, s

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alternate and interim identification.

The position of Emergency Director has five alternates to assure coverage in the event of an emergency.

A discussion covering coordiaation and direction as an overview of the Emergency Director's functional responsibilities is presented in EP Section 5.2.1.

Upon notification of an emergency (alarms across plant site) the emergency organization assembles in the Emergency Control Center to assess the emergency, to determine what actions are required tc terminate the emergency, and to deploy the personnel necessary to control the emergency condition.

Radios and telephones are available to communicate needs, reports, or findings.

m NRC LICENSE SNM-10D7 DATE 8/28/81 PAGE DOCKET #70-1113 REVISION 0

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c'l 4.3 Off-Site Assistance to Facility The provisions and arrangements for assistance to on-site personnel during and after a radiological emergency is discussed in EP Section 5.3 The types of services are provided in EP Section 5.3.2.

Letters of agreement are contained in EP Appendix A and methods for notification are contained in the procedures listed in EP Appendix B.

Emergency Director assures all directional controls during the emergency as shown in EP Section 5.2.

4.4 Coordination with Participating Government Agencies State and other government agencies having action responsibilities for radiological emergencies in the area of the facility are identified in EP Section 5.4.

This Section also discusses related agency authority and

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responsibility for emergency activities.

Also included are the communication means (primarily by phone to central points) for each of the agencies.

Agreement letters as appropriate are provided in EP Appendix A.

NRC LICENSE SNM-1097 DATE 6/28/81 PAGE DOCKET 470-1113 R EV I S I O:4 0

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5.0 RADIOLOGICAL CONTINGENCY MEASURES v

5.1 Activiation of Radiological Contingency Response Organi 1 tion Activation of the GE-WMD emergency organization is discussed in EP Section 6.1.

It describes the communication step to alert or activate the emergency organization.

Alerting or calling together of the emergency organization is described in the implementing procedures identified in EP Appendix B.

This can be done by telephone oc by a coded signal through the fire alarm system that provides audibility throughout the site.

Call lists are posted on call boards in the Emergency Control Center and the Security office and are found in all the emergency procedure manuals.

Phone numbers of the emet ency organization members (primes and alternates), agencies, local support facilities, etc. are provided.

This information is graphically

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demonstrated in EP Table 6.1.

5.2 Assessment Actions To ensure effective coordination, provisions for assessment and for continuing reassignments throughout the course of the emergency situation are described in EP Section 6.2.

Methods for asruring each classification of emergency are d'ccribed in EP Section 6.2.1 through 6.2.3.

Dilution of air effluents is discussed in RA Chapter 14.1.2.1.

Based upon stability class, nomograms are available to quickly assess the exposure potentials.

m

/

!1 NRC LICENSE S NM-10'9 7 DATE PAGE DOCKET #70-1113 REVISION

~

The Regulatory Compliance staff provide the technical J

bases for determining regulatory and safety impacts for environmental or radiological type incidents as described in RA Chapters l i.5.8, 11.5.9, 11.5.10, 11.5.12, 11.5.13, and 11.5.14.

5.3 Corrective Actions General requirements and commitments to assure capable response for such actions as fire coetrol, repair and damage control are discussed in EP Section 6.3.

Emergency exposure criteria and protective or corrective actions are provided in EP Table 6.2.

Representative individuals responsible for initiating actions to mitigate emergencies are identified in Exhibits 3.1.1 and 3.1.2.

A matrix of severity classification, notification, and responsibility is presented in EP Table 6.1.

')

5.4 Protective Actions Measures to ptavent or mitigate potential consequences to individuals during or following an incident are described in EP Section 6.4.

Protective actions are based upon the limiting values identified in 10 CFR 20 and the criteria identified in EP Table 6.2 for protection or life saving actions.

The criticality alarm is the only audible alarm that requires immediate and total evacuation from the building should it sound.

Other alarms cause response by various members of the emergency organization.

Alarms and readout devices alert the Radiation Protection unit when levels are reached which require notification or evacuation.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE O

5-2 DOCKET 470-1113 REVISION

E Exhibits 3.1.3 and 3.1.4 include a list of offsite organizations to be notified and the timing when notification should occur.

Notification of offsite agencies is by calling one of the 24-hour telephone numbers of a support agency (i.e.,

Highway Patrol or Sheriff's Department) who are manned 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months a day.

The authentication scheme used at GE-WMD provides for verification that an accurate message was received.

Communication throughout the site is by telechone, portable, mobile or fixed radio station.

The check list for personnel accountability is included in the implementing procedures.

It is the responsibility of the manager, or in his absence the foreman, to account for their people and report to staging area manager.

A list of visitors who have

( ~

signed in but not out is provided to the staging area

~

manager by the guards for accountability.

Protective equipment is maintained at the emergency control center and is issued by a member of Radiation Protection.

The criteria for returning the facility to normal use are described in EP Section 9.

5.5 Exposure Control in Radiological Contingencies Exposure control criteria are discussed in EP Section 6.5.1.

Guidelines for lifesaving and corrective actions are provided in EP Table 6.2.

The table also provides guidelines for using volunteers.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET 470-1113 REVISION 0

5-3

Radiation ?rotection personnel routinely monitor the radiation and contamination levels for workers in the radioactive material controlled areas.

Equipment is available to monitor real-time radiation levels, airborne contamination levels and trends.

Portable equipment, capable of being transported to an area of interest, is also availshle.

In the event the office area becomes inaccessible, equipment in the Emergency Control Center located remotely from the Fuels building can provide radiation readings, backup portable instrumentation, air samplers, and emergency generators.

During any emergency, the Emergency Director, with concurrence of the Nuclear Safety Advisor, may authorize Odditional exposure up to the limits specified in EP Table 6.2.

In the event of a criticality, a whole-body counter, normally used for routine monitoring of personnel

)

working in the controlled area, would be available to s_

count and evaluate the extent of the internal deposition of fission fragments.

The laboratory on site would perform urinalysis for the evaluation of internal contamination, and support agencies could evaluat. fuel samples and urinalysis as required.

Self reading dosimeters are available in the Emergency Control Center for personnel who may have to be exposed to radiation as members of the response team.

The Nuclear Safety Advisor will be responsible for monitoring exposure as work progresses.

All exposure records would become part of the Nuclear Safety Engineering's file of the individual's exposure history.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET 470-1113 REVISION 0

5-4

Exposure from airborne contamination is normally controlled by the wearing of protective clothing and respirators as required, and by monitoring stations as personnel exit through control points.

Contamination is considered present when the instrument identifies counts significantly above background and alarms.

Decontamination is accomplished with soap and water and/or with chemicals.

A decontamination kit and wash stand is located at the medical treatment center and is used by medical personnel in treatment of injuries.

For situations other than criticality, showers and sinks are available for contamination removal.

Items and liquids are treated as contaminated and controlled accordingly.

Protective clothing is kept at the Emergency Control Center to provide a change of clothing as necessary should conditions warrant.

i V

Public transportation is available as backup for employees at GE-WMD in the event they cannot use their own transportation.

5.6 Medical Transportation Arrangements for medical transportation h.tve been made with local ambulance services and agreement letters are found in EP Appendix A.

Medical transportation is d is cu ssed in EP Section 6.5.3.

W NRC LICENSE SNM-1097 DATE 8/2d/81 PAGE DOCKET #70-1113 REVISION 0

5-5

5.7 Medical Treatment

(

Medical facilities capable of treating patients who have injuries complicated with radioactive contamination are discussed in EP Section 6.5.4.

Copies of the agreement letters are to be found in EP Appendix A.

New Hanover Memorial llospital has an emergency plan for radioactive / contamination accidents, and its personnel have undergone drills and training to increase their proficiency (EP Appendix E).

,/

\\__/

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET =70-1113 REVISION 0

5-6

6.0 EQUIPMENT AND FACILITIES 6.1 Control Point The onsite emergency control location and alternates are discussed in EP Section 7.1.

The site map in Appendix B provides relative location of the onsite staging areas.

The local civil preparedness agency is located on the third floor of the Wilmington Police Department building, seven miles from the plant site.

6.2 Communications Equipment The communications systems are discussed in the EP Section 7.2.

Exhibit 6.1 provides a layout of the Emergency Control Center (ECC) including a pictorial of where equipment is available.

Portable radios and fixed radios providing three channel

((

capability are available to the emergency organization.

Routine use of the equipment assures availability and operability.

Sufficient pottable radios and batteries have been made w. ilable to assure adequate coverage at any time.

These radios and batterics are maintained at the security office at the ECC.

6.3 Facility for Assessment Teams The Emergency Control Center houses equipment for monitoring and assessing radiological consequences (see Exhibit 6.1).

Additionally, EP Section 7.3 discusses monitoring systems that are used to provide alarms which trigger emergency response measures as well as those used for continuing assessments.

m m

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE 0

6-1 DOCKET M70-1113 REVISION i

Manuals, calibration sourcec, maps and diagrams are maintained at the ECC for use by appropriate emergency response team members.

Exhibits 6.2, 6.3, 6.4, and 6.5 provide a checklist as well as listing of equipment maintained in the ECC and the emergency vehicle.

6.4 The facilities and medical supplies are discussed in EP Section 7.5.

Also included and available at the facility are a decontamination wash tub, decontamination kit, and sampling kit.

The plant physician has received specialized training at the Oak Ridge National Laboratory.

6.5 Emergency Monitoring Equipment Onsite systems and equipment used for assessing radiological condition are described in EP Sections 1'

7.3.1 and 7.3.2.

Exhibits 6.2, 6.3, 6.4, and 6.5 indicate the types of equipment available, and routine checks of the equipment are made on a weekly and monthly basis within the ECC.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET 470-1113 REVISION 0

6-2

EXHIBIT 6.1 O

E""CC"?CY CO?: TROL CE!;TER E!'.:RCT:??CY UC E CRITICALITY TIRE & EXPLO3IO!!

RADICLCCICAL CIIE:!ICAL SPILL -

CO::PPO::TATIC::

LCF.B T !PIAT EMERCE!:CY ECCIPf *E!!T STORACE L:: VIRO :ME::T7 L AIR BPIATIIII:G RADIOLOCICAL PORTABLE PA SYSTEMS I

a g

/.

{

f CO:0:t::ICATIO::S T

o-TELEPHONES (3) f e

if I

L~~

U.

2 UtsY RADIO SEC"n!TY

[

\\'-l !

]

C Ip;TERCCM

{

i FMO PA SYSTEM i

i "N

S 1

\\

l NI N

4.

\\

~ lERGE!:CY DTPECT30'S

.\\

onsK I

/

I

!N WHOLELODY COUNTING CC" PLEX

\\

)

.Cc :FERE!!CE ATEA

\\

L T

%w

/

PA 'q

\\ C:17si X POA F ""

g,,,g

'J BUILDI::CS COU::TY LOCALE l

Pc. T n onx.;I :cq l

NRC LICENSE S NM -- 1 0 9 7 DATE 8/28/81 PAGE DOCKET #70-1113 REVISICN 0

i 6-3

i EXHIBIT 6.2 hST LMEMihCf C011%'JL Cl!1TER CLECtVIT

$(:P i

1.

WFirtY CUTCA Check the inventory of inster ca ts. air saislers unr1 r<;spiritnry

.L

~ "

equipTnt, etc. as pr ord u1 at tached fra m.

'a. Operationally soin s e c8.ck ill radi$ tion J..ter tir.a ire.ts wwnts M Perform battery (Mt.k on all radiation detcrtii.n instrum nts.

hm, Check all dosimeters aul dosi:aetcr charger.

M e.

Insure that all inst runent calibraticn date, are curr ent.

J $ f.

Replace an'/ equip.cnt er suglic'. that are deficiert as a result of the at:ove checks.

J h g.

Run all "ALL STAT" on rLerline corputcr terminal an.t chect paper a 13 r1LLen.

the b h.

Complete the chedout thcet and file in the "Evergcncy Equipr9t" fila.

e M i. Sand a copy of checkcut. ?heet to "D1t RCTir.Y PREfKtto'.ESS C00imAir.A" 2.

!T*1i:1LY CWlK s

Perfor t tha sterkly ch:cks listeJ atave.

a.

b.

Check at;d replace mnh eith recenditioned casks it necessary, Check the spare canisten to deternina that thry niv2 rot excceae i tteir c.

~

shelf life, (if a canister wal is bruten. char.tje it as scen as pnsi ble. )

d.

Replace any c<patra.cnt that is defici< nt as a result of the above chects, Check b3tteries in por tatile bJll hhf15.

CCplJCC Js neces$ary, e.

f.

Perfar." a co nolete rat iation detection ins trwent inventory. ir,clu k t

v rial arci Wel r. c krs of tLe n.eter s.

a l

Cceplem the ched. cut : hat ir:d file in ther "ft:crgency fquh rent" g.

file, h.

Chany ILU b hbys duri'r; ther M.'fj/f{ an't JP]jf mont hl/ ched.

i.

5 n3 a copy of checwut %t to "Uto:r.rNcy recruo.L's occis/Ma"

\\

NRC LICENSE SNM-1097 DATE R/2R/91 PAGE DOCKET 970-1113 REVISION 0

6-4

-e M

EXHIBIT 6.3 WF t:KI.Y.

- We'Titt.Y A

() fA RTt.nf.Y l

{

FvCPr! ?;rY r n'C90f, CYt:

T) R rin rK FIOCA1. WK. 8 i Re rm i t.* d Ok I, f *:" f1ttSPNTAT in'4 DATE/TIMI[/

[87(

j Ion Cloimierr Ec;a Gam.

All'ha 5

7 Teletector 2

1 v

reutron Counter 3

v II. DOSI'#1.Ti(Y Pocket Ch.irAcra Ix"< Raare 7

liigh 'arg.'

2 Ch1rr.et y

I R D Badgm

/

6 III. pan!ct.nc tcAI. Un':

j IPerr Full Taca n uk Sparc Cani.ters 4

Air S.1991ers m 4

/

- t-F.lectric lilter Parer 1

Styns

2come, y

Check Sources v

Decon Kit 2

v f,uoports, Postiry I

/

d I V. PR9 FCTIVE C10T!:1!.'C Coveralls 1.ab Coits r,

Caps 6

P.ubber Gloves 6

W Nuther Shc.: Covers 6

/

(,

f V. LMFtG NCY ITrCf.DtMit S"rN.fl.S Crfd.' hrs f.a rce f r'a l 1 2

H.In Drawings 1

Flash)Ights Per IJst fecn FPT. SAit MO P?%2 /

Lanterns 2

P.i t t e r i e s & Ibs t h.-;

E J

i ce rrcor v *.uru l s d

f l<npe, 1" Tate (Pla*. tic 2

'. M n k t v ),,

Tlantic tags, "ottles, !!(sc. Of f ic -

se,w n e n s

/

sg Qf/

Tu nniticn JM'II <N '/

.a~

. + -

m t;RC LICEMgg SnM-109, O n. I e R/28/81 PAGE 1

DOCKET 570-1113 REyIslON 0

M

l EXHIBIT 6.4 nV E7$ff!LY fl.'Ti PWi&E I!!'IRTirATIrt; M. TSfilB L'IHP 9FII*f71 RSLtif rnq If fl O'#?fR 5

A!_2 86.$4 M3 A0dB d/W 20 3 Vla

/2o 3 VS$

A03 TETn rG+n 5

/193 6-5~20 3 99

(

/o!9 (52 3 l._

. //97

+

4/ 7

//e/-G

/

ll!M 2

4'/V

/BIM TdECTECTra 1

f3Sg iStPfl CariEP 1

3'777 ppf-y' II'E/TdE 878d / f of,/g o'rDB vi gk%W '

/

fXlM l'BTI3iE<TS hyAw C(l py g i <r.fp.2~,ff<i/c',,,f, sos. m + Ri n.y c:n e o,:

L $^

C/H'C"W "'/"b fewd

(,

jpi f)< sin <An

~

NRC LICENSE SNM-1097 DATE 8,/28/81 P 'sG E 0

DOCKET #70-1113 REVISION 6-6

EXHIBIT 6.5 P.C :

J. Bradterry FMicMENCY @fCLE INVENTORY g'jl!ST ltems As Oaq'd Comm ts yes No 1.

Check gasoline tank level f) k%*

i 2.

Start engine and let run while taking hM

inventory.

3.

/ ire Extinguishers Two CO, One Metalex Two Cry Chemical Two Water 4.

One Bolt Cutter 5.

Two Emergency Lights 6.

Two Fire Axas 7.

Two Shovcis 8.

400 Ft. 1-1/2" Fire Hose 9.

Three Scot; Air Packs with Three Spare Air Tanks

10. Crc Stretcher (fold-up) 11.

Eight Complete Rain Suits with Helmets and Ecot:

12. Cr.e Wrecking Bar

13. Two Aluminum Ladders (1 14' Hock Ladder &

1 14' Extension Ladder) 14 Two Spanner Wrenches 15.

Three Wool B'ankets

16. Hydrant Tcols

17. One Fire Froof Blanket

18. 200 f t. Polyester Rape 19.

2 Safet/ Belts 20.

No::le (Spray) 1-1/4" 21.

Two No::les (Direct Tyre) 1-1/4"

22. Disposable Plastic Acid Suit

23. Pair Rutter Sloves 24 "Y" Gate Valve

25. Hard Held Megartene 2C

.'*o Canvis Orca Clott 10 x 12 27, 2C0 ft. 2" Fira How 23.

Hird hats will be prov1 M in ven'c' f

//

r.'9 " fet. / 2?C--

Intcect:d b i:

R.E. C r:tell cate: _i - /7 f/

1 PAGE NRC LICENSE SNM-109/

DATL-RpR/91 DOCKET 970-1113 REVISION O

6-7

7.0 MAINTENANCE OF RADIOLOGICAL CONTINGENCY PREPAREDNESS CAPABILITY 7.1 Written Procedures The Emergency Preparedness Coordinator is responsible for the maintenance and implementing procedures and the coordinatica of emergency procedures as described in EP Section 8.1.3.

Implementing procedures are described in EP Appendix B.

The emergency plan provides for an annual review and updating including incorporation of knowledge gained from training exercises and drills (see EP Section 8.2).

Exhibit 7.1 provides a mechanism to assure the review cycle with allowance for concurrence / acknowledgement and approval by dated initialing.

7.2 Training 7",

Initial training and periodic retraining is presented in EP Section 8.2.

Drills and exercises are also discussed in EP Section 8.1.2.

WMD has provided training to support organizaticns such as rescue squads, sheriff's department, Wilmington police department, hospital personnel at the Pender County and New Hanover hospitals located in and near Wilmington.

Instructions include basic radiation science, contamination control, notification procedures, communication of instsructions between external and GE-WMD onsite personnel when onsite actions must be taken at the scene.

l NRC LICENSE SNM - 10'9 7 DATE 8/28/81 PAGE 0

7-1 DOCKET 670-1113 R EV I S i ]N

7.3 Test and Drills x

Test and drills are performed periodically to maintain proficiency in emergency response.

A test is conducted annually to integrate all aspects of the emergency response capabilities including offsite support agencies such as rescue squads, sheriff's department, hospital and fire departments.

At least annually a drill is conducted to involve day, swing, and graveyard shift personnel.

All drills and tests are critiqued to provide for update and improvement.

Different types of scenarios are provided.

This topic is addressed in EP Section 8.1.2.

Drills are conducted to test onsite capability with the fire brigade, radiological monitoring teams (especially during simulated criticality incidents), and medical teams t.hrough simulated injuries.

7.4 Review and Updating the Plan end Procedure

()

The Emergency Plan is reviewed annually per EP Section 8.2.

Exhibit 7.1 provides the functions and titles of those in the review cycle.

7.5 Maintenance and Inventory of Radiological Emergency Equipment, Instrumentation, and Supplies Maintenance and inver. tory of equipment and supplies are discussed in EP Section 8.3 and EP Table 8.1.

Exhibits 6.1, 6.2, 6.3, and 6.4 provide a demonstration of the tests and frequency for various emergency equipment.

Independently the Industrial Safety component routinely checks the self-contained breathing apparatus, fire extinguishers, and fire horns.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET 470-1113 REVISION 0

7-2

EXHIBIT 7.1

\\

CI:!!!:RAL PLECTRIC Wii.'tI!!GTO : f'/J:Url,CTURTf;G DTTARTMEt;T E!'ERCE!!CY PIRUPPOCFDURES RECOPD C" CO!!CURRE!!CE INITIALS DATE E.

A. Lees Emergency D*.~ector J.11. BrrJberry Emergency Preparedness Coordinator A CE!!O';f.E DG!'.E!;T J.

E. Dergman Eldg. Mgr. - FMO W. T. Ross Bldg. Mgr. - FCO W.

W.

McMahon Eldg. Mgr. - ELO W.

J. !!cndry Regulatory Cc: pliar.ce i

C.

?!. Vaughan Licensing & Compliance Audits F.

11. Paucette Enployee & Corr. unity Relations J.

A.

Long General Manager J.

L.

!!armon Manufacturing Technclogy

& Engineering Operations t;R C LICENSE SNM-109/

DATE 9/28/81 PAGE 1

DOCKET #70-1113 REVISION 0

7_3 l

8.0 RECORDS AND REPORTS i

8.1 Records of Incidents Investigation and reporting of off-normal occurrences are discussed in RA Section 2.9.

RA Table 2.1 provides an outline of categories and classification for each type of incident.

RA Figure 2.1 provides an overview of responsibility and retention requirements.

A WMD procedure specifies the types of information to be included in the report.

8.2 Records of Preparedness Assurance Records from drills and tests which include the type of emergency, basic situation, attendees, significant events, attachments, critique summary and action items with responsibility and date to be accomplished are maintained by the Emergency Preparedness Coordinator.

A typical format is provided as Exhibit 8.1.

L, 8.3 Reporting Arrangements The Manager, Licensing and Compliance Audits, is responsible for maintaining an appropriate list of agencies to be notified and for notifying the agencies as required per RA Section 2.9.2.7.

Emergency telephone numbers are routinely updated.

Call boards for the emergency organization are maintained in the security office and the conference area of the ECC.

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE 0

8-1 DOCKET 470-1113 REVISION

Exhibits 3.1.3 and 3.1.4 provide a typical notification list with timing requirements.

Phone numbers for each of the titles identified are found in the emergency manuals.

The Manager, Employee and Community Relations, is responsible for communicating with the news media and is required to report to the ECC for access to what is happening, data being generated, and current status.

The licensing function has the responsibility for continuing communications with government agencies.

)

'._/

n NRC LICENSE SNM-1097 DATE 8/28/81 PAGE 0

8-2 DOCKET #70-1113 REVISION

EXHIBIT 8.1.1 I

1 1

RLPOR1 f40.

PAGE tiMD EME RGEt4CY PL Af1 REPORT -

SUMMARY

FORM DATE

>;PE EMERGEtiCY BASIC SITU 6Tt0!!

j 2

KEY EVEtiT Tl!1ES:

START i.,

j F i fil S H

{

P A R T ! C I P A riT S EMERGEilCY DIRECTOR O

GErtER AL MAf1AGER O

f BUIL0ltiG MAliAGER O

' tiR C j

O NUCLEAR SAFETY ADVISOR O P&QA0 O

)

RECORDER O

MGR. SAFETY & L I C E fiS i t4G O

STAGif3G AREA !!ANAGER O

RAD. PROT. - NCS O

riccH S o

l PLANT MEDICAL 0

N.H. SilERIFF DLPr.

O

)

LICENSING & COMP. E f1G. O f4.H. CIVII PREP. COORD.

O SURVEY TEAM i

O N.H. MEff 0RI AL HOSPITAL 0

SITE EtiTRY TEAM O

OGDEN RESCUE SQUAD 0

1 DLDG. FIRST A!D 0

rt. H. REStu[ squad o

FACIL I TIES M A!1 AGER O

OTHER I

O EfiV I RONt E NT A L E flG.

O O

Ef1E R. PREP. COORD.

O O-EMPLOYEE RELATIONS O

Vis! TORS (busERVERS1

(; y Date NRC LICENSE SNM-1097 DATE _8/28/81 r>AG E DOCKET M70-1113 REVISION 0

8-3

EXHIBIT 8.1.2 m..

REPORT fiO.

PAGE WfD EMERGEfiCY PLAfi j

REPORT - SCEllARIO FORM S C Eil A R I O ACTUALO ORlLL0 T^BLE TOP O LYPE

{4 Basic slTUATIost 1

i SPECIFICS

)

I i

1 i!O i

l i

i i

i by Date 1

l 1

l NRC LICENSE SNM-1097 DATE 8/28/81 PAGE 0

l DOCKET #70-1113 R EV I S I ON 8-4

EXHIBIT 8.1.3 l' L i' O R T N O.

PAGE witD EMERGENCY PL AN REPORT - SIGNIFICANT EVENTS SEQUENCE FORM OATE TIME O C_C U i! R E fiC E COMMENT a

1 O

.e, m

BY DATE 1

9 f;R C LICENSE Sf;M - 10 9 7 DATE 8f3 /g1 PAGE DOCKET P70-1113 REVISION o

8-5

EXHIBIT 8.1.4 f

H L P U R I liU.

!O

" ^ "

,j WitD EMERGEf1CY PLAft REPORT - CRITIQUE SUMitARY FORM 1

i DATE fio.

MAlf! PO!!1TS BY:

I i

i 4

4 i

f 1

4 J

i 1

4 l

^

i l

I lt Y :

DATE i

l f 4R C LICENSE S t P 1-10-9 7 DATE 4/99/91 PAGE DOCKET #70-1113 REVISION 0

8-6 1

t

EXHIBIT 8.1.5

\\

REPORT fl0.

1 PAGE into EMERGE!!CY PL Ah 3

REPORT - A T TACil!1E;1TS

FORfi

{

DATE a

1 ft 0.

SilB J E C T i

_BY 4

i l

t 1

1 i

4 l

1 i

i 4

l 4

4

)

4 O

i

~

1 1

a J

i i

i l

l I

l 1

BY L1 A T E 6

I 1

i i

.i 1

NRC LICENSE S t M - 10 *) /

DATE g/2p/91 PAGE DOCKET 470-1113 REVISION 0

8-7

--.--n.-

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

uJ a.

REPORT

!. 0.

k y

WMD EMERGENCY PLAN PAGE CD DATE REPORT - ACTION ITEMS FORM IN RESPO?tSE TO:

ACTION ITEM

?;0.

A C T I O!J RESP.

DATE STA!us O

Y V

=

N CC m

h~

N cc g

.o 1

"w X

tu -

s >

w

< tu C C4 rs CS O

I E

O

,m

~

v4 b

m CD 2

N L;

e U

- H J tJ

'l U U C?

O Z Q O

O 7

_._3

--,-----.wr--

.-y

k 1

9

's 9.0 RECOVERY lb 9.1 Reentry 1

Plans and criteria for reentering an affected area are specified in EP Section 9.1.

It includes a discussion l

relative _to saving human life, reactivation of alarms, and availability of emergency equipment.

The Emergency Director, with concurrence of the Nuclear Safety Advisor, is the only one who can authorize reentry.

The-

)

Nuclear Safety Advisor has resonsibility for maintaining.

1 i

exposure records.

Erposure criteria are specified in EP t

Table 6.2.

]

9.2 Plant-Restoration i

l After termination of the emergency, all the information that has been gathered will be reviewed.

The Nuclear 1

^

Safety Advisor, Nuclear Safety Engineering, Health Physics, and Radiation Protection personnel will assess the radiation and contamination problems that will be j

encountered by the restoration and cleanup crews.

j Decisions will be made by this group to assure that any l

operations performed will be done to minimize exposure and control contamination spread.

I Safety equipment will be evaluated for operability and restored to operation as quickly as possible.

New and/or additional equipment will be placed into service to assure that safety related areas are fully restored prior to commencing work in any of the areas so that i

exposure, both external and internal, are kept below regulatory limits.

e i

I.

i -

i i

NRC LICENSE SNM-1097 DATE 8/28/81 PAGE l

DOCKET #70-1113 R EV I S ION 0

9-1

,1

,e 9.3 Resumption of Operations

~'

After the termination of the emergency, i.e.,

people accounted for, emergency condition under control, and no further excursion can occur, an evaluation of conditions will~be made.

An investigation will be made to l_

determine the cause of the incident, the potential for reoccurrence, and necessary-conditions required to return the operations to normal activities.

All problems related to health and safety will be resolved prior to commencing ' operations.

Normal access i

areas, contamination control procedures, exposure l

controls and related safety equipment will be made operational prior to resumption of operations.

Additional operations resumption information is given in EP Section 9.2.

i 4

j l

1 i

i a

1 j

3 NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET M70-1113 R EV I S I ON _ 0 9-2 j

r',

APPENDIX A i;

PHOTOGRAPH EXHIBITS 1.

Emergency Control Center 2.

Radio Communications Equipment within Security 3.

Equipment Storage and Counting Area 4.

Storage Cabinets and Counting Equipment 5.

Counting Equipment 6.

Storage Cabinet 7.

Counting Table 8.

Control Center Conference Area 9.

Emergency Reference Manuals 10.

Wind / Speed Output Console 11.

Radiation Monitoring Output Console l

12.

Area Topographical Map 13.

Folding Map / Chart Board 14.

Communication Center 15.

Communication Mode 16.

Emergency Organization Call Board 17.

Portable Field Generators NRC LICENSE SNM-1097 DATE 8/28/81 PAGE DOCKET 470-1113 R EV I S I ON O

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