IR 05000254/1982022
| ML20028C912 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 12/21/1982 |
| From: | Axelson W, Paperiello C, Phillips M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20028C903 | List: |
| References | |
| 50-254-82-22, 50-265-82-24, NUDOCS 8301140295 | |
| Download: ML20028C912 (29) | |
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1.1 U.S'.' NUCLEAR-REGULATORY COMMI'SION S
REGION III'
Reports No.'50-254/82.-22(DEPOS);-50-265/82-24(DEPOS)
Docket'Nos. 50-254; 50-265
~ Licenses No. DPR-29; DPR-30 Licensee:
Commonwealth Edison Company _
Post Office Box-767-Chicago, IL 60690 Facility: Quad-Cities Nuclear. Generating Station, Units 1 and 2 Safety Evaluation Report C ucted: November 1982 Inspector M. P.
111ps MM
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Emergency' Preparedness Analyst Approved By:
W..L. Axelson, Chief b
/b Emergenc Preparedness Section
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J. Pap riello, Chief Emergency Preparedness and Program Support Branch Safety Evaluation Report Summary:
Safety Evaluation Report - November 1982 (Report Nos. 50-254/82-22(DEPOS);
50-265/82-24(DEPOS))
Routine Safety Evaluation Report of the Generating Stations Emergency Plan (GSEP) and the Quad-Cities site specific annex dated November 1981 and June 1982 respectively. The inspection involved 38 inspector-hours by one NRC inspector.
Results: The licensee's GSEP and Quad-Cities site specific annex related to emergency preparedness at the Quad-Cities Nuclear Generating Station, Units 1 and 2 meet the planning standards of 10 CFR 50.47(b) and the requirements of 10 CFR 50, Appendix E.
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Safety Evaluation Report-related to the operation of
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Quad-Cities Nuclear Generating Station, Units 1 and 2-Docket Nos. 50-254; 50-265 NRC' Operating Licenses No. DPR-29; DPR-30-
- Commonwea).th Edison Company-
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U.S. Nuclear Regulatory Commission
November 1982
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INTRODUCTIONL
' The Commonwealth Edison. Company:(hereinafter, referred:to as the licensee,.
Lthe company, CECO)1 filed with.the Nuclear Regulatory Commission revisions-
-to the Commonwealth Edison Generating Stations Emergency-Plan (GSEP)
submittals dated January 3, 1980; April 24, 1980;-June 4, 1980;cJuly 30,
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1980; December'31, 1980; March 27, 1981;. March 24, 1982;'and-July 30, 1982.
The GSEP is a generic emergency plan applicable to,all nuclear generating.
stations ~-operated by CECO. Each~GSEP contains a site specific ~ annex that contains additional:information and guidance specific to each nuclear station.
The Commission staff conducted a: review of the PSEP and the Quad-Cities site specific annex dated April 1981 (both are hereinafter referred'to as the plan)
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against the requirements of 50.47(b) and Appendix-E of 10 CFR 50, and the criteria of the 16 planning standards in Part II of thei"Criteris'for Prepara-tion and Evaluation of Radiological Emer'gency Response Plans and Preparedness in Support of Nuclear Power Plants," NUREG-0654/ FEMA-REP-1, Revision 1, dated November.1980. Comments resulting from this review were submitted to the licensee'in.a letter dated March 1, 1982, from Mr. James G. Keppler'to Mr. Cordell Reed. The licensee responded to these comments by-letter dated
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May 26, 1982, from Mr. T. J. Rausch to Mr. James G. Keppler and by issuing Revision 3 dated November 1981 to the GSEP and Revision 2 dated June 1982 to the Quad-Cities site specific annex.
We have completed our review of the November 1981 GSEP and April 1982 Quad-Cities site specific annex and pertinent correspondence dated December 31, 1980, from Mr. L. 0. De1 George to Mr. H. R. Denton; March 27, 1981, from Mr. L. O. De1 George to Mr. D. G. Eisenhut; June 1, 1981, from Mr. J. S. Abel to Mr. D. G. Eisenhut; and July 31, 1981, January 19 and February 16, 1982, from Mr. L. O. De1 George to Mr. James G. Keppler.
This emergency preparedness safety evaluation report lists'each standard in order followed by a summary of applicable portions of the plan as they apply. principally to the licensee's planning standards. The final section of this report provides the staff review results and conclusions.
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~ SAFETY EVALUATION REPORT ~
A.
' Assignment of Responsibility (Organization Control)
Planning Standard a.
Primary responsibilities for emergency response by the nuclear facility licensee, and by State and local' organizations within the Emergency
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Planning Zones have been_ assigned, the emergency responsibilities of
.the various supporting organizations have been specifically established, and each principal response organization has staff to-respond and to augment its initial response on a continuous basis.
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The GSEP organization consists of three groups, each with a specific area-of responsibility. The three groups are the-Station Group, Recovery Group, and the Corporate Command Center (CCC) Group. The Station Group functions under a Station Director responsible for organizing and coor-dinating the emergency efforts at_and within the immediate vicinity of the station. During emergencies of limited extent the CCC Group fune-tions under a director and his staff, who are responsible for evaluating, coordinating, and directing the overall company activities involved in coping with the emergency. During more serious emergencies, such as any Site Area or General Emergency, the CCC Director-is responsible for activating the Recovery Group. This group functions under the Recovery Manager, and would' report to the nearsite Emergency Operations Facility (EOF). The CCC Group then becomes a support staff to the Recovery Group.
The Recovery Manager's responsibilities include the evaluation, coordina-tion, and direction of the overall company and industry response and management of the nuclear plant recovery operations.
The Shift Engineer of the Quad-Cities Station is initially designated as the Station Director. When an abnormal condition arises, it is his responsibility to make the initial determination of the severity of the emergency and to implement the plan. There is 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day communi-cation capability between the station and Federal, State, and local response organizations to ensure the rapid transmittal of accurate notification information and emergency assessment data.
The offsite GSEP organizations shown in Figures 1 (limited activation)
and 2 (full activation) specify the function and responsibilities for major elements and key individuals by title. Emergency response func-tions which are addressed in both organizations are as follows: command and control, logistics support, engineering support, medical care, manpower requirements, health physics, communications, accounting, legal environmental, and public information. The full response offsite GSEP
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CORPORATE COMMAND CENTER DIRECTOR
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I I-I STAFF HEALTH PHYSICS INFORMATION STAFF ACCOUNTING COMMUNICATIONS DIRECTOR DIRECTOR OlRECTOR DIRECTOR u
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ERP DIRECTOR STAFF STAFF I
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ENVIRONS STAFF DIVISION DIRECTOR DIRECTOR a...........
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Figure 1 Limited response offsite GSEP organization
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orga'nization (Recovery'Oxoup) ihcludes the following additiona1L func-tions: technical support, scheduling and planning, design and construc'-'
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-tion support, waste' systems radiation control' support, training, admin-istrativeDsupport, and advisory support. 'The'CCC Director.is responsible for initial coordination with governmental _ agencies and for manning the nearsite EOF. After the EOF is functional, the ' responsibility for coordination with governmental agencies shifts 1to the Recovery Manager.
The licensee has a sufficient pool of trained' personnel available from other nuclear stations operated by CECO to ensure'that all GSEP organi--
zations are capable of continuous operations for a. protracted period of time. _This'is ensured through= corporate and station procedures delineat-ing the responsibilities of;the Administrative Director, Administration and Logistics Manager, and the Manpower and Logistics Director.
Formal agreements exist on file with appropriate agencies-and organiza-tions including' law enforcement, fire protection, ambulance services, medical and. hospital support,. Institute for Nuclear Power Operations
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(INPO), Department of Energy (DOE), radiological support, and Federal, State and local authorities responsible for implementation of protective measures for the public.
The staff finds this element of emergency preparedness, as described in the GSEP and Qued-Cities site specific annex, to be adequate.
B.
Onsite Emergency Organization (Closed, 254/82-02-11; 265/82-02-11)
Planning Standard On-shift facility licensee responsibilities for emergency response are unambiguously defined, adequate staffing to provide initial facility accident response in key functional areas is maintained at all times, timely augmentation of response' capabilities is available, and the inter-faces among various onsite response activities and offsite support and response activities are specified.
Emergency Plan The normal station organization is shown in Figure 3.
The Quad-Cities Station is managed by a Station Superintendent who is responsible for direct management of the station. During an emergency situation (normal working hours) the Station Superintendent is the Station Group Director.
During periods when the Station Superintendent is unavailable, his responsibilities are delegated to alternates who satisfy the requirements of ANSI N18.1-1971, " Experience Requirements for Plant Manager."
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'The. Shift Engineer (on duty 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day) is the initial Station-Group Director and as such has the' authority for declaring an emergency.
.and-recommending protective actions to local authorities. He is relieved'
of'these duties upon arrival of the' designated Station' Director..Those responsibilities of the Station Director that may not be delegated.are.
specified in the. Annex, and include the responsibility for declaring an.
emergency, recommending protective actions to local authorities, and-authorizing emergency radiation exposures in excess.of 10 CFR 20'.101
. limits.
The onsite ' emergency organization '(normal working hours) is called the Station Group. Figure 4 shows this organization. The majorgrespons-
~ibilities and' duties of the Station Group Directors are defined in the -
plan. As described in Section A, the.onsite emergency organization is augmented by the Corporate Command Center and the Recovery Group.
- The onsite emergency organization for non-normal working hours, backshifts,
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and holidays is described in the plan. Emergency assignments have been made, and the relationship between this emergency organization and the normal staff complement is shown in the plan.
Positions and/or titles-and qualifications of shift and plant personnel both onsite and offsite who are assigned major emergency-functional duties are listed.. Minimum-shift manning requirements are in the plan, and guidance for shift aug-mentation based on the emergency classification is provided.
The plan has established.the framework for a long-term augmented emergency organization. This organization is under the command and control of the Recovery Manager. Full activation of the Recovery Group is required for any Site Area or General Emergency. For accident situations classified as Unusual Events or Alerts, the Recovery. Group
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would not be activated and the offsite GSEP organization would consist of the Corporate Command Center Group.
Interfaces between and among the CCC staff, Recovery Group staff, station staff, governmental and private sector organizations, and technical and engineering contractor groups have been specified in the plan.
The minimum onshift staffing levels discussed in the plan meet the objectives of Table B-1 in NUREG-0654, Revision 1.
This onshift staff includes the following expertise: one Shift Engineer (Senior Reactor Operator (SRO)); one Shift Foreman (SRO); two Nuclear Station Operators (three if both units operating); three equipment' operators / attendants (four if both units operating); two radiation chemistry technicians (RCTs); and one Shift Technical Advisor (STA).
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The licensee's program for onshift augmentation within the first hour of
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a significant emergency is described in the plan. This augmentation will include 28 persons with the following expertise:
all eight Station Group Directors; the Environs Director; seven RCTs for inplant, onsite, and
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offsite surveys; four radiation / chemistry personnel for protective actions;
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three engineers for plant system engineering; two electrical / mechanical l
personnel; one Instrument and Control Technician; one radwaste operator for equipment repair and corrective action; and one dedicated communicator.
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STATION
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OPERATIONS TECHNICAL MAINTENANCE STORES Dlii:CTOR DIRECTOR DIRECTOR DIRECTOR
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Figure 4 GSEP station group organization
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LThese personne1' provide the necessary functions defined'in Tablei -1 of-
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NUREGa0654,' Revision 1.
The licensee has: established a 24-hour duty--
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' call individual'who would be notiffed first after 'a station emergency.
~This individual would initiate a call tree notification procedure.~ :.This
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1 call. tree:is specified'in the. plan. 1Ne procedurejidentified individuals'
iwho are' capable of. performing.the specific response functions'which are-identified in Table B-1 of NUREG-0654, Revision 1, and' establishes.a priority for notification based on;the travel time to the facility.,
Further,' unannounced offshift notification' drills.willibe conducted atL least every six months to ensure that the' design objectives of Table B-1 can be achieved.. Records will be maintained for inspection.
For activation.of the EOF,'the licensee'has developed a Recovery Manager
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notification call list which will enable.the responsible Corporate Duty-Officer to notify the Recovery' Manager who.would require the least travel
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' The staff finds this element of emergency preparedness, as described in the GSEP and Quad-Cities 1 site specific annex,_to_be. adequate.
C.
Emergency Response Support and Resources
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Planning Standard.
Arrangements-for requesting and effectively using assistance resources have been made, arrangements to accommodate State and local staff at the licensee's nearsite Emergency Operations Facility have been made, and other organizations capable of augmenting the planned response have been identified.
Emergency Plan Arrangements for requesting and. utilizing outside resources have been made including authority to request implementation of the DOE Radiological Assistance Plan and the Interagency Radiological Assistance Plan. Further, the licensee retains contractors to provide supporting services to the Quad-Cities Station. Among those services provided are the following:
technical experts for accident analyses from the Institute of Nuclear Power Operations (INPO), environs radiological monitoring.and radiochem '
ical analyses; health physics support, meteorological support; and personnel dosimetry support.
Either the_ Station Director, Recovery Manager, or CCC Director may request DOE assistance if that assistance is necessary or desireable.
The plan det 'ibes the present. radiological laboratories at each CECO nuclear strajsn (Zion, Dresden, Byron, and LaSalle). Because each nuclear station's management and resources are similar, each station can make available some of its equipment, manpower, and counting facilities to a station affected by an emergency situation.
The Ceco organization provides for dispatching licensee representatives-to the principal offsite governmental Emergency Operations Centers if i
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n the licensee's nears'ite_ EOF. The EOF'is the' central point for pro-i i
vidingninformation needed by primary response agencies'for implementa-
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tion of protective actions. Completion and ataff evaluation of'the.
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permanent EOF which meets.the guidance oflNUREG-0696 and SECY-82-111B~
will be addressed in a. separate report.-
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.The staff-finds'this element'of emergency preparedness, as described in
the GSEP and Quad-Cities: site specific annex,=_to be adequate._
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- D.
Emeraency Classification-System (Closed.- 254/82-02-12; 265/82-02-12)
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A standard emergericy classification and action-level scheme, the bases
of which include facility system and effluent parameters, islin.use by-
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the nuclear facility. licensee, and State and local response plans call
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j-for reliance on'information provided by facility licensees for determina -
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tions of minimum initial offsite response measures.
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Five standard emergency classes (Transportation Accident, Unusual Event, j
Alert, Site Area Emergency,,and General Emergency) have been established.
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Emergency Action Levels (EALs) are indicated in the plan-based on onsite
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and offsite radiation monitoring information and based on: readings from)
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j various plant sensors (such as pressure and temperature in containment,
l response of vital electrical systems or: emergency core cooling systems,
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and vital equipment status). EALs for' natural phenomena such as earth-
quakes, floods, and tornadoes have been developed. These EALs'are used
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for rapid classification of emergency situations.
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Direct effluent readings.of the main chimney monitors are not yet avail -
able. After. installation and calibration of the'. monitors, EAL #17 should i
be revised to reflect the appropriate readings for each classificati a
j level. This will be examined by the NRC' staff upon completion.
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The plan states that predetermined emergency actions will.be taken by
i the licensee in the event of an emergency. These emergency actions ~are
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j consistent with the guidance in Appendix 1 of'NUREG-0654, Revision 1.
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Further, the plan has identified. example emergency conditions for each
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i-standard emergency classification. These initiating conditions include-
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_the examples given in Appendix 1 of NUREG-0654, Revision 1, and the
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l analyzed accidents in the Quad-Cities _ Final Safety. Analysis Report (FSAR).
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EAL #16afor a General Emergency refers to imminent loss of the third-r fission product barrier.
Both Appendix 1 of NUREG-0654, Revision 1, j
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and the class description.in the annex define a General Emergency as-
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" Events in progress or have occurred which involve actual or imminent substantial core' degradation or melting with potential for loss of'
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containment integrity." The term potential should be used for EAL #16 i
to.be consistent.with the class definition.
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The' staff;findsthisElementof.emergencypreparedness,'as" described"in-
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the GSEP and Quad-Cities' site specificiannex,sto-be adequate; however,
' additional. changes to the EALs as described above should ba made in1the next annex revision.
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- E.
-Notification Methods and Procedures (Closed. 254/82-02-13; 265/82-02-13).
Planning Standard Procedures have been established for notification, by the licensee of.
State and local response organizations and for. notification of emergency.
personnel-by.all? response organizations; the contentlof initial and:
. followup messages'to response organizations and the public has been established; and means to provide early notification and clear instruc -
tion to the populace within the. plume exposure pathway Emergency Planning Zone'have been established.'
-Emergency Plan Procedures have been established for notification of State and. local response organizations in case of emergency. The Shift Engineer ~has the authority and responsibility as Acting Station Director for initiating the emergency notification to these agencies'during non-normal working hours. This notification scheme is shown in Figure 5.
This notification system has been developed by the State of Illinois and agreed to by the licensee and the State of Iowa. A duty Corporate Command Center Director and System Power Load Dispatcher are available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. The plan-
'has established procedures which describe mutually agreeable bases for-notification of offsite response organizations consistent with the standard emergency classification and action scheme set forth'in Appendix 1 of NUREG-0654, Revision 1.
The plan has established procedures for notifying, alerting and mobiliz-ing licensee emergency response personnel. These procedures include both station and corporate personnel, and have been developed.to ensure that-personnel with the least travel time to the Station or EOF will be noti-fled first.
The contents of the initial emergency messages to be sent from the plant have been established. The contents of these messages include:
Informa-tion about the class of emergency, whether-a release of radioactive material has taken place, potentially affected population and areas,.
and whether protective measures may be.necessary. The notification procedures used also include means for verification of messages.
Ceco and the States have developed predetermined written messages in-tended for the public and consistent with the emergency classification scheme. These messages are part of the States' emergency plans and are not included in the licensee's plan.
The plan has established provisions for followup messages to State and local authorities. These messages include necessary information about
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g the accident that would be needed to determine the appropriate' protective measures to be taken'in both theLingestion and plume ~ exposure pathway emergency planning zones (EPZs), following the guidance in NUREG-0654,
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Revision 1.
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The prompt public notific'acion system which is installed at' Quad-Cidies.
'
is described. The' design of this system consists of three parts as follows:
(a) a permanently installed. outdoor siren notification ~ system-within the-0 to 5 mile radius which will essentially cover.all inhabited
- areas-with a minimum noise 1evel_of 60 db; (b) a permanently' installed-outdoor siren notification' system covering -he heavily populated areas within the 5 to'10 mile radius; and-(c) a mobile notification. system for the remainder of the area within the 5fto 10 mile radius. State, Ccunty, and other_ local agency emergency vehicles will be utilized for this mobile notification capability. The notification capability consists'of.
-64 fixed alerting sirens and a maximum of 114 emergency vehicles equipped s
with public address systems. Sounding of the alerting sirens by local government will alert the public to the_ fact that they should turn.on radios to a local radio station for detailed information on.the situation.
The sounding of the alerting sirens and the deployment of the emergency
. vehicles is outlined in.the State and local emergency response plans.
The purpose of this-notification system is to advise citizens to either;
_;
take shelter or evacuate and to instruct them to tune to designated
'
emergency information radio stations.
The staff finds this element of emergency preparedness, as described
_
in the GSEP and Quad-Cities site specific annex, to be adequate.
F.
Emergency Communications I
Planning Standard i.
Provisions exist for prompt communications among principal response organizations to emergency personnel and to the public.
The plan has established an extensive and' reliable system for communi-
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cations among the Quad-Cities Station, System Power Load Dispatcher
'
(SPLD), division load dispatching, nearsite E0F, and the CCC. The system includes the use of normal and dedicated telephone lines, radio,
,
L mobile radio units, microwave voice channels, and handi-talkies, thus providing both a primary and several backup means for communications.
A dedicated telephone communications sytem, the Nuclear Accident Reporting
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System (NARS) is provided for the notification of State and local authori-ties in the event of an emergency. The NARS system'11nks together the station control room,.CCC, onsite Technical Support Center-(TSC), SPLD, nearsite EOF, and State and local EOCs.
Initial contact points are
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manned 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per' day.
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'A microwave / radio.communicati~on system is provided-for the purpose of
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-voice communication,between the CCC, station, mobile units, and. field teamsL(handi-talkies). ;The system consists of two microwave channels,.
one voice' channel and the other controlling a base radio station at-the plant.
Operating' locations for the base radio station as well as access
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to the voice channel are the onsite TSC, the nearsite EOF, and the Shift
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-Engineer's office.
The NRC has installed dedicated. telephones from the Quad-Cities Station control room, TSC, and EOF to.the NRC; Incident Response Center in-Washington, D.C. and the regional NRC office in Glen Ellyn, IL.
Also, there is a separate dedicated telephone (Health Physics' Network) between the NRC and the Quad-Cities Radiation Protection Office, TSC, and EOF.
Dedicated telephone communications exist between the CCC and_the' State
of Illinois Department of Nuclear Safety Radiological Emergency Assessment-Center-(REAC). This. link provides communication for the environmental monitoring and. accident assessment efforts between CECO and the Illinois Department of Nuclear Safety REAC.
The staff finds this element ~of emergency preparedness, as' described in the GSEP and Quad-Cities site specific annex, to be adequate.
G.
Public Education and Information Planning Standard Information is made available to the public on a periodic basis on how they will be notified and what their initial-actions should be in an emergency (e.g., listening to a local broadcast station and remaining indoors), the principal points of contact with the news media.for dissemination of information during an emergency (including the physical location or locations) are established in advance, and procedures for coordinated dissemination of information to the public are established.
Emergency Plan The plan provides for the dissemination of information to the public regarding how they will be notified and what their actions should be during an emergency. This information includes educational information on radiation, methods for notification during an emergency, protective actions planned if an emergency exists, and instructions on how to obtain additional information especially for the disabled or their caretakers and those without transportation. This public information brochure is
mailed to all residents in the plume exposure EPZ of each nuclear station and is also provided to city halls,. gas stations, state parks, campgrounds, and other areas where a transient population may obtain a copy. These public information brochures will be distributed on an annual basis.
These actions should ensure that the public information program reaches the permanent and transient adult population within the plume exposure EPZ.
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The EOF provides' support' and interface between CECO, State, and local
,
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agencies, and the news media.~ The plan provides for dispatching.the Emergency News _ Center Director to the E3F. An Emergency News _ Center functions under:the direction of this person and is the single point'
contact for disseminating information to the public. The Emergency.
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News Center Director's responsibilities include. coordinating information releases with Federal, State,-and local agencies, and establishing-coor-dinated arrangements for dealing with rumors.
A technical spokesperson knowledgeable about the affected station and its
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operations will.be available to brief the press at the Emergency News Center.
CECO will offer programs at least annually to acquaint news media with-the GSEP, information concerning radiation, and points of' contact for.
release of public information in an emergency.
The staff finds this element of emergency preparedness, as_ described in the GSEP and Quad-Cities site-specific annex, to be adequate.
-H.
Emergency Facilities and Equipment (Closed, 254/82-02-14; 265/82-02-14)
Planning Standard Adequate emergency facilities and'eqaipment to support the emergency response are provided and maintained.
Emergency Plan Emergency facilities.needed to support an emergency response have been provided including a TSC, EOF, CCC, and Operational Support Center (OSC).
The TSC and OSC will be activated for any Alert or higher emergency classification. The EOF will be activated for any Site Area or General Emergency classification, and the CCC may be activated for lesser emergencies.
The TSC is located in the'former station gatehouse. The building has been modified and an addition added to provide space for 26 persons and supporting equipment. Personnel in the TSC are protected from radio-logical hazards, including direct radiation and airborne contaminants under accident conditions to the same degree as control room personnel.
To ensure adequate radiological protection, permanent radiation monitor-ing systems have been installed. These systems continuously indicate
radiation dose rates and airborne radioactivity inside the TSC while 4-in use.
In addition, protective breathing apparatus and thyroid blocking agents are available for use as needed. The TSC has access to a complete set of as-built drawings and other records, including general arrangement diagrams, P& ids, piping system isometrics, and the electrical schematics.
The OSC is located adjacent to the TSC and functions as a support center to the TSC. Operations support personnel will report to the OSC for
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assignment. A limited inventory of supplies are kept in the OSC. This j
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[ inventory $ includes portable lighting,: respirators, protective clothing,
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1 and portable : survey' instruments'.' - Communications and1 management = controls
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_from the OSC?and toLthe'TEC-aci control room are provided.
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The CCC is located ~on the 12th floor of'the Edison Building in downtown -
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yChicago, and is the-location from which the CCC. Director will normally
.
Jdirect;overall company. activities involved in~ coping with an; emergency.
If,the Recovery (Group is activated at.the EOF,nthen:the'CCC will.be the-
location for.a support'staffsreporting to the Recovery Group. -In addi-l tion to:the above-functions, the'CCC will serve'as.theicorporate e'nviron--
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' mental center 'where : environmental' monitoring will be directed and offsite -
dose projections performed under'the" direction.of the CCC Environmental'
1 Director. The CCC has dedicated communications with the control room,
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State of Iowa Office of Disaster Services,. Illinois REAC, company cars, and field' radios.
The temporary nearsite EOF is' located at-the: Quad-Cities-Nuclear Informa-tion Center. Should the EOF become uninhabitable, individuals at the.
EOF would relocate.to an alternate center. 1The EOF will be utilized to evaluate'and coordinate the emergency. reentry / recovery operations on a continuing basis b; the licensee. Liaison with Federal, State, and, local officials-will be maintained at'this center, which.will also be
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used for receipt and analysis of field monitoring data submitted by-field teams.
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CECO submitted by letter dated June 1, 1981,-a detailed description of
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the-emergency. response facilities (TSC, EOF, and OSC),' Safety Parameter Display System (SPDS), and other upgrades discussed in NUREG-0696.
Completion and staff evaluation i>f the permanent. EOF, TSC, OSC, and SPDS which meet the guidance of NUREG-0696 and SECY 82-111B will be addressed in a separate report.
Emergency preparedness procedures have been developed including quarterly.
inventory and operational readiness of emergency equipment and supplies.
Sufficient equipment for emergency kits exists to ensure a minimum in--
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ventory in case of replacement delay. The station maintains portable
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- survey instrumentation to assess inplant, onsite, and offsite contamina-tion levels, exposure rates, and airborne gaseous, radioiodine, and particulate concentrations. Additionally, emergency equipment and'
supplies can be obtained from an alternate CECO facility such'as Byron or LaSalle.
Onsite monitoring systems have been identified and' established that are
!
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to be used to initiate emergency measures in accordance with Appendix 1~
of NUREG-0654, Revision 1, as well as those monitors used for conducting l-assessment; e.g., seismic monitors, process and radiological monitors, and fire and~ combustion monitors. These' systems include a meteorology
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system 'with wind speed and direction and temperature capability, in-stalled process radiation monitors to measure upward deviations in radiation levels in specific locations in the station, portable dose rate and radiation detection instruments, nonradiological process
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- monitors 1(suchlas containment pressure'and temperature, reactor. system
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4 pressure and temperature,wetc.), and laboratory counting andLanalysis-facilities.'
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Provisions'for offsite; monitoring. equipment have,been made. - Seismic data,' respiratory protection. equipment,' portable detection'instrumenta-
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' tion,'and counting room' equipment can be obtained from the Zion, Byron,-
LaSalle and Dresden stations. 'The'I111nois Department of Nuclear Safety
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maintains-a mobile laboratory' equipped.with1 radioassay capability to
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trespondLto: radiation emergencies. Offsite meteorological data can' cur->
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- rently be obtained from any of=thel licensee's o'ther nuclear stations'as well as the. weather-service. Hydrological' data may be obtained from.
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the onsite river level gauge,.the U.S.. Army, Corps of: Engineers, and'the National Weather Service.
'The Environmental Emergency Coordinator-is responsible for the receipt:
and' analysis of all field monitoring ' data and the determination of-where environmental sample media will be taken for: analysis.
-The meteorology equipment'at the station currently meets the criteria
of Regulatory Guide' 1.23, "Onsite Meteorological Problems," dated
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February 17, 1972. CECO is currently upgrading the meteorological'
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measurements' program' to meet the guidance in Task ' Item III. A.2 of -
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NUREG-0737, " Clarification of TMI Action Plan Requirements." This upgrade includes the offsite dose calculation system (ODCS). The plan describes the ODCS and its objectives. These-objectives include the-following:
(a) meet the meteorological criteria of NUREG-0654, Revision-1; (b) provide, whera possible, redundant independent pathways of data..
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transmission.and redundant data processing computers for use in an emergency situation; (c) provide quick and reasonably accurate estimates
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of radiation dose to persons living offsite, including preparation of
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procedures and training of. users required to accomplish this assessment; and (d) provide a method for meteorological contractors to secure meteorological data for assessment of routine releases and to detect equipment-failure quickly. The plan indicates:that EAL alarms based i
on offsite dose rates in accordance with Appendix 1 of NUREG-0654,
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l Revision 1, will be factored into the Class A model. The station pro-cess computers will process this information and will produce initial
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transport'and diffusion estimates within 15 minutes following classi-fication of an accident. This information will be immediately available
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to the control room operators. The completion of this upgrade will be.
accomplished in accordance with the guidance provided in.SECY 82-111B,
'and will be addressed in a separate report.
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'I The staff finds this element of emergency preparedness, as described j
,
in the GSEP and Quad-Cities site specific annex, to be adequate.,
.
I.
Accident Assessment
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Planning Standard
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-Adequate methods, systems, and equipment for assessing and monitoring
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actual or potential offsite-consequences of a radiological emergency
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eThe plan.contains several;systemfand r'adiological. effluent parameter
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valu.as characteristic'of a spectrum of.off-norma 11 conditions and acci '
dents. -Parameter values and other reliable information:are tabulated
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to cross-reference initiating. conditions forfeach of the. emergency? ~
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classes. Specific alarm setpoints, both visual and audio,Lare in the'
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r-control room to alert the operator.
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The onsite radiation monitoring and-sampling system' consists-of tho'
'following: ;(1)"a' process and radiological monitoring and sampling' system, l~
- (2)Lan' effluent: radiological monitoring.and sampling system, (3) an air-
- borne radioactivity monitoring system,.(4) an area radiation' monitoring
. system, and-(5) portable survey and counting equipment.
The plan described the' offs'ite dose calculation system (ODCS),which.
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' meets the design objectives of the NRC Class A model The system will;
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be computerized and used to predict 1offsite doses on a real-time basis I:
.using effluent andEmeteorological. monitors. The ODCS provides access
sto meteorological information at.any' CECO facility'on a real-time basis, and can be accessed from the control room, TSC, EOF, and CCC.. Provisions
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have been made in the system to' allow' access to meteorological data by l-the-NRC and the Illinois Department of Nuclear Safety. The ODCS can determine.the magnitude of a release or potential release by using any
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of.the following: - (1) evaluation of: plant conditions, - (2) ofisite
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radiological measurements, and (3) dose projections offsite.
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I The plan describes the. post-accident primary coolant and conta'inment atmosphere sampling system. The post-accident primary coolant sampling
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system provides samples from the reactor recirculation loops,- deminera-
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lizers, drywell and torus-drains, and other primary points for isotopic
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analysis from undiluted or diluted samples (1000 to 1), and analysis of I
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. dissolved hydrogen. The system will allow sample collection and analysis.
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. within exposure guidelines given in NUREG-0737. The containment atmosphere
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sampling system will provide representative grab samples at'the time of
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an accident-and fixed intervals thereafter. The containment air sampler will also include: monitors that will detect particulates and iodine-131 within a range of 1 E-11 to 1 E-6 mci /cc, and noble gases within a range
of 1 E-6 to 1 E-2 mci /cc.
High range effluent monitors which measure noble gases will be installed
in the effluent stream which enters the main chimney and the Reactor Building vents. These monitors will have a range of 1 E-7 mci /cc to
1 E+5 mci /cc and will-be used to provide an estimate of the release.
l Actual-releases will be determined periodically by collecting grab i
samples,-counting the samples, and calculating the releases. This method provides accurate results regardless of.whether the instrumenta-tion used for assessment is inoperable or off scale. High-range. con-
tainment radiation monitors are installed in each of the units. These
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redundant monitors have a range from 1 R/hr to 1 E+8 R/hr. Plots of.
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assessment of core damage.- These values'are;related to EALslfor-rapid-classification of an emergency condition.
The plan describes the inplant radioiodine instrumentation and radio-
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iodine and particulate effluent monitors. Sample media are analyzed'
"in the station counting room using. a' GeLiL isotopic-analyzer ' system.
The iodine cartridges are; purged to reduce the.leveltof. entrapped
.
noble gases, hand silver zeolite cartridgesTcan be used to further
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,,r' educe the interference from noble gases. Portable monitors.(for;
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example,:an Eberline SAM-2)~are also used to measure increasing'lovels.
of radiolodine during emergencies.
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The plan describes the;offsite radiological; environmental. monitoring-program,' including fixed continuous-air samplers and a fi_xed thermo-
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r luminescent dosimeter-(TLD) monitoring network which meets the NRC-
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. Radiological-Assessment Branch Technical Position for Environmental'
Radiological Monitoring Program. Maps 'are provided showing the TLD :
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.and air sampler locations.
The plan describes the capabilities and resources for-field monitoring-
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Lwithin the. plume. exposure EPZ. _ Teams will have' adequate monitoring
!
equipment to locate and find the plume, and make-airborne measure-l ments of radiolodine to levels of 1 E-T mci /cc. Adequate communica -
l
.tions systems for the field teams;are provided.
l The staff finds this element of emergency preparedness, as-described
in the GSEP and Quad-Cities site. specific annex, to'be adequate.
l
. J.
Protective Response (Closed, 254/82-02-15; 265/82-02-15)
.
Planning Standard A range of protective actions have been developed for.the plume exposure pathway EPZ for emergency workers and the public.
- Guidelines
for the choice of protective actions during an emergency, consistent.
with Federal. guidance, are developed and in place, and protective
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. actions for.the ingestion exposure pathway EPZ appropriate to the L
locale have been developed.
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The plan describes the protective actions to be taken by onsite
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. personnel. Onsite predetermined assembly areas are designated. The station has a siren system to signal personnel to assemble in these areas. Persons'not'having an emergency response' assignment, including visitors and contractor personnel, are required to assemble when noti -
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.fied by the siren. Onsite accountability is the responsibility of g
the Quad-Cities Station Security Director, who will: account for. all-
- individuals within the protected area at the time the assembly is announced and be able to ascertain the names of missing individuals within 30 minutes,
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Plant).
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i If Aite evacuation.is necessary;(such as,fo'r a Site' Area. or General s
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i i Emergency), personnel will be: relocated'and monitoredcat:one or moral-oflthe following' locations:..(1);Riverdale' Senior High School;L(2)
LAlbany. Park;.and.(3) Byron. Nuclear. Generating" Station. The plan o
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-indicates the evacu'ation' routes:to each of the relocation centers.
Traffic contro1 for on' site' areas'during a.s'ite..evscuation will-be-
the responsibility of the station security force-The plan, describes ^
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!how radiologica14 monitoring ~and decontamination (if-necessary)~will
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,be provided for evacuees at the offsite relocation-site (s).
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The plan makes zprovisionsi for respiratory protection,~use of protective.
I-clothing,-and use'of radioprot'ective drugsgfor'onsite emergency workers.
The criteria for issuance of these protective measures are: described i
in CECO' radiation protection standards and' radiation / chemistry procedures.
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The plan provides the basis-for recommendations for protective actions'
for the public. These' protective. action recommendations.sre consistent with the guidance set forth in Table 5.1 of the Manual of Protective
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Action Guides and Protective Actions for Nuclear Incidents
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(EPA-520/1-75-001) and.the guidance of the U.S. Food and DruglAdminis--
tration covering the contamination of human food and animal feed'
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(Federal Register, Vol. 43,ENo. 242, December 15, 1978). The plan
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summarizes possible recommended protective actions to be made.to State
and local agencies during an emergency. The plan clearly indicates
that a prompt notification will be made directly.to offsite authorities i
responsible for implementing protective measures within the plume exposure
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pathway and ingestion exposure pathway EPZs.
Population distribution by sector and distance within a 50-mile radius.
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have been compiled and are included in the plan. Maps indicating. major evacuation routes for the public and station personnel are provided in'
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the plan. -Detailed evacuation routes-(maps) for the general public~are contained in the State and local emergency plans.
Evacuation time estimates for the plume exposure pathway.EPZ'for adverse weather conditions, special facilities, and normal conditions have been-specified. The time estimates are genarally in accordance with Appendix 4 of NUREG-0654, Revision 1.
The staff finds this element of emergency preparedness,.as described
in the GSEP and Quad-Cities site specific annex, to be adequate.
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Radiological Exposure Control P
Planning Standard Means for controlling radiological exposures'in an emergency are i'
-established for emergency workers. The means for controlling radio-
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-EPA Emergency; Worker and Life Saving ActivitycProtective: Action Guides.
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3 Emergency response personnel.may receive ra'diation~ exposure:in excess'
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of'the-limits; imposed by-10 CFR 20.
Whenever possible, prior.authori ~
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- zationt of the Station Superintendent, CECO Medical Director,f and the =
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station's Radiation" Protection Supervisor should be obtained.. The!
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. plan contains" emergency guidelines for whole-body and; thyroid doses-consistent.with EPA Emergency; Worker.and. Life Saving Activity _ Pro--
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tective-Action Guides.
- The station.provides and distributes a'self-reading-add accumulative
type dosimeter to personnel ~ involved in emergency onsite response',
'1regardless of company affiliation. Dose records - for workers will: be maintained ~and checked dailyithroughout.the emergency.
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Onsite contamination control procedures for personnel, equipment, and accessfcontrol are in place. ; Decontamination of personnel and'
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equipment.is required when the contamination level' exceeds predeter -
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mined values.- -Criteria for permitting return of contaminated areas-l and their contents:to normal use are stated in the.appr'opriate con-
- l tamination control procedures.
.Thel station will supply clothing and. decontamination materials-to
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onsite personnel required to relocate and found to be. contaminated.
In addition, the station will provide bioassay capabilities-at the relocation sites.
The staff finds this element of emergency preparedness, as described in the GSEP and Quad-Cities site specific annex,'to be adequate.
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Medical and Public Health Support Planning Standard Arrangements are made for medical services for contaminated injured individuals.
Emergency Plan The station provides for onsite first aid capability. Radiation protection personnel and selective supervisors are, trained and qualified-to administer first aid. At'least one of these individuals is available on shift at all times.
Because of the specialized-nature of the diagnosis and treatment of
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radiation' injuries, CECO's Corporate Medical Officer maintains a roster of physicians especially competent in this area of medicine
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Jand available for the care of persons with these special problems.
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In addition, Radiation Management Corporation (RMC) provides medical i
p support, including bioassay-result interpretation.
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.. CECO has made arrangements, confirmed in writing, with Jane Lamb Memorial Hospital in Clinton. This hospital is capable of_ receiving and treating contaminated or' overexposed persons..This hospital will-be utilized for decontamination and initial treatment of-persons with.
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injuries involving radioactivity and requiring immediate hospital care'.. CECO will provide ~ medical. consultants to aid'in any special-care necessary'at this hospital. Backup medical support, confirmed in writing, is available at Northwestern Memorial Hospital ~in Chicago.
-This. hospital would be used to treat significant_ radiological emergencies requiring extended specialized treatment. CECO will have available to.the staff _of this hospital its specialist who will provide the direction of the special care necessary for the treatment of persons having radiological injuries ~.
CECO had made arrangements, confirmed in writing, with the Dailey -
Gibson Funeral Home and Illinois Hospital in East-Moline to provide for transporting persons with injuries involving radioactivity from the Quad-Cities Station to a designated hospital. This service is available 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> per day. Radiation monitoring will be.provided by the station whenever it_becomes necessary to use the ambulance-service to transport a contaminated person.
The staff finds this element of emergency preparedness, as described in the GSEP and Quad-Cities site specific annex, to be adequate.
M.
Recovery and Reentry Planning and Post-Accident Operations Planning Standard General plans for recovery and reentry are developed.
Emergency Plan Procedures have been developed for entry to previously evacuated areas for the purpose of saving lives, search and rescue of missing and injured persons, or manipulation, repair, or recovery of critical equipment or systems.
The plan describes an extensive Recovery Organization (Figure 2)
which follows the recommendations of the Atomic Industrial Forum and the Institute for Nuclear Power Operations. The Recovery Organization will be activated upon activation of the EOF, which will automatically take place for any Site Area or General Emergency.
Designated CECO personnel will assemble at the EOF and assume additional respon-sibilities for assigned positions. These responsibilities are described in the plan. There will be three major emergency functions at the EOF as follows:
(1) the Recovery Center, (2) the Emergency Control Center, and (3) the Emergency News Center. The Recovery Center is the command post for direction of all recovery operations.
The Emergency Control Center functions as a location from which to evaluate emergency situations (such as radiation releases) that affect the public. -The Emergency News Center functions as the single contact point for disseminating information to the public.
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The plan provides a method'forlestimating tota'l population exposure.
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i The-Recovery Manager is. responsible /for determining.that a recovery...
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' mode may be entered. lThe Recovery' Manager is-the designated individual from CECO who has requisite authority,' management ability, and technical =
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knowledge to manage _ recovery operations. The primary Recovery Manager _
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is the Division Vice-President, Nuclear _ Stations. - Procedures have
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'been developed which-describe'how emergency; classifications Nill _be reduced and closed out,;and how members of the_ emergency response
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. organizations will be informed'of' accident status changes.
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.The staff findr this_ element of emergency preparedness,'as described
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Lin the-GSEP anf luad-Citiesisite specific annex,.to'be adequate.
N.
- Exercises and Drills (Closed, 354/82-02-16;-265/82-02-16)-
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' Planning Standard-Periodic exercises are (will be) conducted to evaluate major portions of emergency response capabilities ~,zperiodic drills are (will be).
conducted to develop and maintain key skills, and deficiencies identified as a result of exercises or drills are (will be) corrected.
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The_ plan ensures that an annual' exercise is conducted at Quad-Cities:
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Station to test the adequacy of timing and content of implementing procedures and methods, to test _ equipment and communications networks,
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and to ensure that emergency personnel are familiar with their duties.
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Once every six years, an exercise should be scheduled between the hours of 6:00 'p.m.
and midnight, and another between midnight and
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6:00 a.m.
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Full-scale exercises which test as much of the plans (licensee, State, and local) as is reasonably achievable without mandatory public participation will be scheduled in order to permit agencies to fulfill their full-scale exercise frequency requirements-as delineated-in
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10 CFR 50, Appendix E, Section IV.F.1 and IV.F.2.
Small-scale exercises which test the adequacy of communication links, establish that emergency response agencies understand the concept of
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EALs, and test at least one other component of the offsite emergency response plans.will be conducted each year that a full-scale exercise is not conducted.
A written scenario will be prepared for each annual exercise. This scenario will include the following:
(a) the basic objectives of the exercise; (b)'the date,. time period, places, and participating organizations; (c) the simulated events; (d) the time schedule of real and simulated initiating events; (e) arrangements for qualified
observers; and,(f) a narrative summary describing the conduct of the
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exercise"to include suchfthings as simulated casualties,' rescue of.
personnel,= deployment' 'of > radiologic'al-- monitoring: teams,; and public'
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information activities.
ALcritique w'ill be conducte'd as'soon as!. practical.after each' exercise.
1The critique'will evaluate the: ability. of the GSEP organization-toi respond to a ' simulated emergency ' situation as called.for in the plan.
The Supervisor of Radioecology and Emergency Planning will ensure that
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~ when deficiencies in the plan.or-corresponding implementing procedures
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are discovered.during' exercises and/or drills, such documents will be revised as necessary to ensure corrective actions are implemented.
' Medical emergency drills, involving a simulated contaminated'indi--
vidual, will contain provisions for participation by local support services agencies (i.e.. ami;1ance and offsite support hospital) and will be conducted annually. Health physics drills will be conducted semiannually. These' drills will include responso.to, and analysis of, simulated airborne and liquid samples within the plant. At least annually, these drills.will include's test of post-accident sampling systems.. Plant environs and radiological monitoring. drills will be conducted annually. These drills will' include collection and analysis'
of sample media such as soil,' water, grass,. and air. _ Fire drills will continue to be conducted'in accordance with the station's Technical Specifications. The GSEP communications system described in Section~7.2 of the-generic GSEP will.be tested annually. Thes'e systems include communications between the station, State, and local ~ Emergency Operations Centers (EOCs),'and field assessment teams. The capa-bility to notify the NRC from the control room, TSC,-and nearsite EOF will be demonstrated at le'ast monthly. The capability to notify other Federal emergency response organizations will.be demonstrated from the corporate office at least quarterly. -The capability to notify Illinois EDSA,' Iowa Office of Disaster Services, and appro-priate local agencies will be demonstrated at least monthly.
The plan also-includes an Operator's Response Drill, Offshift Augmentation Drill, and Assembly and Accountability Drill. The Operator's Response Drill will be conducted annually to observe the operator's response to a reactor problem scenario. This drill may or may not be concurrent with the GSEP exercise. The'0ffshift Augmentation Drill will be conducted.at least every.six months to implement Quad-Cities' notification procedure. This drill will-be unannounced on an offshift and documented to include the time each person is notified. This drill will serve to demonstrate the capability to augment the staff in a short period of time after declaration of an emergency. The Assembly and Accountability Drill will be conducted annually and includes identifying the locations of
F all individuals within the protected area after-an assembly.is announced.
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Although the staff is not opposed to the addition of these three drills
in'the emergency plan, we wish to make it clear that operator response
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to reactor problem scenarios, and an assembly and accountability drill
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tare major components of an onsite emergency exercise that must be tested
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. staff stilliexpects.these objectives.to.belincluded in the annual exercise to demonstrate compliance with~10 CFRiSO, Appendix E requirements.
The staff findsithis.' element of emergency preparedness,;as described.
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Lin'the.GSEP and' Quad-Cities site specific annex, to be adequate.
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Radiological Emergency Response Training Plannina-Standard'
Radiological emergency response' training.is provided to.those who may'be called'on to assist in'an-emergency.
Emersency Plan All Quad-Cities station personnel,-including contractor personnel,
.will' receive.an initial orientation and annual review of the GSEP.to l
ensure that they are aware of actions they should take during an
emergency.. Ceco personnel with specific duties during an emergency-(for example, directors in the GSEP organizations,-accident assessment-personnel, radiological monitoring teams, fire brigades, firstiaid
' teams,fand security personnel) will receive initial and annual retraining on applicable portions of the plan..The proficiency of'
these emergency' response personnel is ensured by the following means:
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(1) assigning persons to emergency duties which are similar to those,
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performed as a part of their regular work assignment;. (2): initial and annual retraining of emergency personnel on applicable generic and
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site-specific portions'of the.GSEP and corresponding Emergency' Plan Implementing Procedures (EPIPs); and (3) participation in exercises and drills designed to sharpen those skills which they are expected to use during a radiological emergency. Records are maintained regarding all emergency personnel training.
Quad-Cities Station makes an annual written offer to train those non-CECO organizations referenced in the plan which will provide
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specialized services during a radiological emergency (such as fire--
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fighting, medical services, transport of injured, and other-local support services personnel such as ESDA). This training is designed to acquaint the participants with the special problems potentially encountered during a radiological emergency, notification procedures,
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and their expected roles. Those' organizations that-must enter the.
site also receive training in site access procedures and the identity (by position and title) of those persons;in the onsite organization who will control their support activities.
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The staff finds this element of emergency preparedness, as described in the GSEP and Quad-Cities site specific annex, to be adequate.
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P._
Responsibility for the Planning Effort: Development, Periodic Review
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and D! stribution of Emergency Plans s
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Planninz Standard
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Responsibilities.for plan development'and review:and-for distribution
~of. emergency. plans.are established, and planners are properly trained.
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Emergency Plan-The Division Vice-President, Nuclear Stations has overall responsi$1'lity for' radiological emergency response planning within CECO.~
A staff
'assignedito the Division Vice-President, Nuclear Starions.has the responsibility for developing and updating the GSEP and coordinating the'GSEP with other response organizations. This staffLis headed by
'the Supervisor of Radioecology and Emergency Planning. Training of emergency planning staff will be performed as a matter of practice.
Actual training received is subject to the availability of appropriate courses and the availability of individuals to be scheduled for those Courses.
To ensure that the plan and the corresponding implementing procedures are'kept current and updated..the Supervisor of.Radioecology ande Emergency Planning will ensure the following:
(1) each plan will be assigned a serial number; (2)'an as' signed record will be maintained of all plans; (3) plans will be distributed on a controlled basis-to-
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all individuals requiring-them; (4) the plan will be reviewed and certified current on an annual basis and updated as needed; (5) all changes to the plan will be reviewed and approved by offsite and onsite review committees; (6) all persons in possession of the plan will receive authorized changes, which will be marked and dated to show where changes have been made; (7) names and phone numbers of
'GSEP organizations and support personnel will be reviewed and-updated
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at least quarterly; and (8) EPIPs for all GSEP organizations will be reviewed at least annually.
Each plan contains a detailed listing of supporting plans and their source.. A section in the plan outlines the required content of
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implementing procedures, and lists the subjects of procedures l-required to implement the plan. The plan contains a specific table of contents.
An independent audit of the emergency plan and implementing procedures will be conducted on an annual basis by the CECO Quality Assurance Department. Actions shall be taken for evaluation and correction of all audit findings.
f The staff finds this element of emergency preparedness, as. described in the GSEP and Quad-Cities site specific annex, to be adequate.
Conclusion
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Based on our review of the GSEP and Quad-Cities site specific annex-
for onsite emergency preparedness at Quad-Cities Station, we conclude
.that the licensee's emergency plan meets the planning standards of
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10.'CFR 50.47(b)'and the requirements of 10 CFR 50, Appendix E; The
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- review of the permanent Emergency. Response Facilities (ERFs)'will be
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discussed in a separate report.
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