0CAN019410, Forwards Rev 17 to Emergency Plan for Ano
| ML20063E244 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/28/1994 |
| From: | Yelverton J ENTERGY OPERATIONS, INC. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 0CAN019410, CAN19410, NUDOCS 9402090157 | |
| Download: ML20063E244 (4) | |
Text
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9 ENTERGY O'!"JL Tet 501964 8883 Jerry W, Yelverton Vrc heskM anwemo
!f January 28,1994 0CAN019410 U. S. Nuclear Regulatory Conimission Document Control Desk Mail Station PI-137 Washington, DC 20555 P
Subject:
Arkansas Nuclear One - Units 1 and 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Emergency Plan Revision 17 Gentlemen:
In accordance with 10 CFR 50.4 and 10 CFR 50 Appendix E, Section V, enclosed is Revision 17 to the Arkansas Nuclear One (ANO) Emergency Plan.
Revision 17 I
incorporates changes resulting from implementation of the revision to 10 CFR 20 and-other minor changes. A complete list of changes is provided as Attachment 1.
A 10 CFR.50.54(q) evaluation was performed and concluded that these changes do not decrease the effectiveness of the approved Emergency Plan. The updated Emergency Plan continues to meet the requirements of 10 CFR 50.47(b) and 10 CFR 50, Appendix E.
Please place the attached pages in your controlled copy (Copy No. 75) of the Emergency Plan, sign, and return the enclosed acknowledgment.-
Should you have any questions regarding this submittal, please contact me.
Very truly yours,
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U. S. NRC January 28,1994 j
OCAN019410 Page 2 i
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Mr. Leonard J. Callan Regional Administrator j
i U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 1
Arlington, TX 76011-8064 (Controlled copics #77 & 78)
NRC Senior Resident Inspector Arkansas Nuclear One - ANO-1 & 2 1
Number 1, Nuclear Plant Road Russellville, AR 72801 Mr. Roby B. Bevan, Jr.
NRR Project Manager Region IV/ANO-1 U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint North 11555 Rockville Pike l
Rockville, MD 20852 Mr. Thomas W. Alexion NRR Project Manager, Region IV/ANO-2
- i U. S. Nuclear Regulatory Commission NRR Mail Stop 13-H-3 One White Flint Nonh 11555 Rockville Pike Rockville, MD 20852 Ms. Greta Dicus, Director Division of Radiation Control and Emergency Management Arkansas Department ofIIcalth-4815 West Markham Street Little Rock, AR 72201 i
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ARKANSAS NUCLEAR ONE EMERGENCY PLAN, REVISION NO.17 FACILITY OPERATING LICENSE NOS. DPR-51 AND NPF-6 DOCKET NOS. 50-313 AND 50-368 Revision 17 changes are noted with side bars. Please remove the affected pages from your manuals and replace with Revision 17 pages.
ACKNOWLEDGEMENT I have received and incorporated the Arkansas Nuclear One Emergency Plan, Revision 17, into my Controlled Manual, (Copy No. 75).
SIGNED DATE COPY NO.
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ATTACIIMENT 1 ARKANSAS NUCLEAR ONE EMERGENCY PLAN REVISION 17 CHANGES The changes included in Revision 17 are listed below.
j The Definitions section incorporates measurement units required for the implementation ofrevised 10 CFR 20.
Tables D-1 and D-2, sections I, J, K., and M incorporate changes from MPC to dose rates as required for implementation of revised 10 CFR 20.
Table K-1 incorporated changes referenced in the revised 10 CFR 20 and in EPA -
guidelines (Table 2-2). was revised to delete Emergency Planning Implementing Procedure (EPIP) 1904.007 " Protective Action Recommendations"
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EMERGENCY PLAN REVISION 17
. Revise the Emergency Plan with the attached pages. Revised pages are u
identiffed by' revision number and vertical bar indicating the area-of change.
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REMOVE REPLACE WITH i
Cover Sheet Cover Sheet Signature Page~
Signature Page IRI1RX XKIXHX xxi xxi D-4 D-4 D-6 D-6 D-8 D-8 D-10 D-10 D-12 D-12 D-14 D-14 D-16 D-16 D-18 D-18 D D-25 I-11 1-11 I-13 I-13 J-l J-1 J-3 J-3 J-5 J-5 J-8 J-8 J-12 J-12 K-1 thru K-10 K-1 thru K-10 M-6 M-6 M-8 M-8 3-2 3-2 i
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.3 ARKANSAS NUCLEAR ONE EMERGENCY PLAN JANUARY 1, 1994
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REVISION 17 01/01/94 i
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& nt;:rgy ENTERGY OPERATIONS INCORPORATED 1
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operations ARKANSAS NUCLEAR ONE 11,, 11 Unit:
o ANO-1 Date:
December 3. 1993 o ANO-2 Change Identifier: Revision 17 5 Generic (Amend. No, Revision No, etc.)
Document:
o SAR o OL*
O QAMO ta EP o TS*
- Analysis regarding no significant hazards considerations must.be attached.
Section(s):
Definitions, D.
T.J K.M. Annendiv 3
' i (Attach revised pages) i
==
Description:==
(give narrative) The major changes in this revision are as follows:
1.
Implementation of New 10 CFR 20 changes.
2.
EAL changes for Radiological Effluents for NUE and ALERT Classifications.
1 3.
Establishing new Emergency Dose Limits.
4.
Deleting reference to EPIP 1904.007
- USE ATTACHMENT 1 0F 1062.003 FOR THE REQUIRED CONCURRENCE / APPROVAL SEQUENCE -
INDICATE SEQUENCE BY CHECKING BLOCKS AT LEFT --
V Prepared By:
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Date: / O '* /0 ~ T3 C "nizant icens % Individual
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Concurrence:
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Date: /M/i f7
/ '
or, Licensing e
[ Concurrence:
/
Ar/7Ar1 Date: 22 - /7-N A
icab1e fanager
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5 g(f o Concurrence:
Date:
Director, Quality
! Concurrence: h o b n-Date:
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l PSC Chairman o Concurrence:
Date:
y General Manager, Plant erations Concurrence / Approval:
E Date:
/
7 f#
(as applicable)
Direydr, /L{ce'asing
/
o Concurrence:
Date:
j SRC Chairman
[ Concurrence / Approval: kdY/
Date: /
/'/
3 (as applicable)
/
Vis(e President, Operations
/
/
[ NRC Approval Required:
Yes a No o NRC Approval Obtained:
Date:
Director, Licensing eb.ad 'I iMJ'4 esNd 6.,4fw agh. xT. mi erAN n [L w. ;--tr, (
LICENSINGDOCbMENTCHANGE
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""* D CONCURRENCE / APPROVAL FORM 1062.003B 2 PC-1 i
.c DEFINITIONS (Continued)
Dose Rate Projections - The calculated estimate of a radiation dose rate to individuals at a given location, determined from the rate of radioactive material release and the appropriate meteorological transport and dispersion parameters (units typically in millirem, i.e.,
mrem /hr).
I Dose Prolections - The calculated estimate of a radiation dose to individuals at a given location, determined from the Dose Rate Projection at that location and the Projected Exposure Time interval during which the dose rate is expected to exist (units typically in millirem, i.e., mrem).
Emercency Action Ixvels (EALs) - A plant or onsite condition which has exceeded predetermined limits which would categorize the situation into one of the following four Emercency Classn:
Notification of Unusual Event Alert Site Area Emergency General Emergency Emercency Direction nnd Control - Overall direction of facility response which must include the non-delegable responsibilities for the decision to notify and to recommend protective actions to Arkansas-Department of Health personnel and other authorities responsible for offsite emergency measures. The direction of facility operations to mitigate accident consequences remains with the TSC Director in the Technical Support Center and/or the Shift Superintendent in the Control Room.
Emercency News Center (ENC) - An offsite location used by Entergy Operations, the state, local, and other governmental agencies for the purpose of addressing the news media of conditions at ANO.
Emercency Notification System (ENS)
Dedicated emergency phones to the Nuclear Regulatory Commission Operations Center used as the primary means for the site to report emergencies and other significant events to the NRC.
l Emercency Onerations CentpJt (EOC) - An offsite location used by State, local, and other governmental agencies to coordinate their activities during a response to an emergency -
situation.
Emercency Operations Facility (EOF) -
A near-site emergency facility located approximately 0.65 miles northeast of the reactor buildings (Figure J-4 indicates the location of the Emergency Operations Fac'ility).
1 Revision 17 January 1,1994 xxi l
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TABLE D-1 i
i UNIT ONE EMERGENCY CLASS INITIAIING CONDITIONS NOTIFICATION OF UNUSUAL EVENT 1.
PRIMARY SYSTEM EVENTS a)'
Actuation of ECCS components resulting in flow to the core.
b)
RCS activity indicates >0.1% failed fuel.
2-.
REACTOR COOLANT SYSTEM LEAKAGE a)
RCS leakage.> T.S. limits requiring a plant S/D or C/D.
3.
SECONDARY SYSTEM EVENTS a)
Uncontrolled OTSG depressurization resulting in MSLI actuation.
b)
OTSG tube leakage 2.347 gpm.
l 4.
ELECTRICAL POWER FAILURES a)
Degraded power 5.
RADIOLOGICAL EFFLUENTS a)
Projected or measured activity at the site boundary, averaged over one hour, is d
greater than or equal to.05 mrem /hr TEDE or.15_ mrem /hr Child Thyroid.
6.
SAFETY SYSTEM FUNCTION a)
Initiation of plant S/D or C/D for Technical Specification L.C.O. compliance or' deviation from Technical Specification L.C.O.'s (10 CFR 50.54x) b)
Loss of dose assessment capabilities, j
c)
Loss of communications 1
.1 1
Revision 17 January 1,1994 D-4
TAuLE D-1 (Continued)-
UNIT ONE EMERGENCY CLASS INITIATING CONDITIONS ALERT 1.
PRIMARY SYSTEM EVENTS a)
RCS activity indicates > 1% failed fuel.
2.
REACTOR COOLANT SYSTEM LEAKAGE g
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a)
RCS leakage > normal makeup capacity.
1 3.
SECONDARY SYSTEM EVENTS a)
OTSG tube leakage > 10 gpm concurrent with ongoing steam release.
3 4.
ELECTRICAL POWER FAILURES l
l a)
Station Blackout.
b)
Loss of all vital DC power.
5.
RADIOLOGICAL EFFLUENT _S a)
Projected or measured activity at the site boundary, averaged over one hour, is greater than or equal to.5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid.
b)
High radiation / airborne levels.
6.
SAFETY SYSTEM FUNCTION 1.
a) -
.RPS failure to complete an automatic trip.
b)
Loss of control room annunciators.
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c)
Control Room evacuation.
d)
Loss of decay heat removal systems.
Revision 17 January 1,1994 D-6 L
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i TABLE D-1 (Continued)
UNIT ONE EMERGENCY CLASS INITIATING CONDITIONS SITE AREA EMERGENCY 1.
PRIMARY SYSTEM EVENTS i
a)
Core damage indicated with an inadequate core cooling condition.
i b)
Containment radiation readings which indicate LOCA and > 1% cladding failure.
2.
REACTOR COOLANT SYSTEM LEAKAGE a)
RCS leakage > normal makeup capacity with > 1.0% failed fuel conditions b)
3.
SECONDARY SYSTEM EVENTS a)
OTSG tube leak > 1 gpm with > 1% failed fuel with ongoing steam release, j.
b)
OTSG tube rupture with primary to secondary leakage > normal makeup.
l capacity.
4.
ELECTRICAL POWER FAILURES a)
Blackout for more than 15 minutes.
H b)
Loss of all vital DC power for more than 15 minutes.
5.
RADIOLOGICAL EFFLUENTS a)
Radiological effluents are greater than or equal to 50 mrem /hr TEDE or 150 mrem /hr Child Thyroid at the Site Boundary.
l b)
Spent fuel accident.
l Revision 17 January 1,1994 D-8 i
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s TABLE D-1 (Continued)
UNIT ONE EMERGENCY CLASS INrrIATING CONDITIONS GENERAL EMERGENCY l.
PRIMARY SYSTEM EVENTS a)
Containment radiation readings which indicate LOCA and >50% fuel overheat, b)
Core melt.
c)
Loss of or challenge to all three fission product barriers.
2.
REACTOR COOLANT SYSTEM LEAKAGF; N/A 3.
SECONDARY SYSTEM EVENTS N/A 4.
ELECTRICAL POWER FAILURES N/A 5.
RADIOLOGICAL EFFLUENTS a)
Radiological effluents are greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr Child Thyroid at the site boundary.
6.
SAFETY SYSTEM FUNCTION q
N/A 7.
. HAZARDS TO STATION OPERATION a)
Ongoing security threat within the Control Room or vital areas.
Revision 17 January 1,1994 D-10
e TABLE D-2 i
UNIT TWO EMERGENCY CLASS INITIATING CONDITIONS NOTIFICATION OF UNUSUAL EVENT
)
1.
PRIMARY SYSTEM EVENTS
.]
a)
Actuation of ECCS components resulting in flow to the core.
b)
RCS activity indicates >0.1% failed fuel.
2.
REACTOR COOLANT SYSTEM LEAKAGE a)
RCS leakage > Technical Specification limits requiring a plant S/D or C/D.
i 3.
SECONDARY SYSTEM EVENTS i
a)
Uncontrolled S/G depressurization resulting in MSIS actuation.
b)
S/G tube leak > Technical Specification limits.
j 4.
ELECTRICAL POWER FAILURES
)
l a)
Degraded power.
5.
RADIOLOGICAL EFFLUENTS a)
Projected or measured activity at the site boundary, averaged over one hour, is greater than or equal to.05 mrem /hr TEDE or.15 mrem /hr Child Thyroid.
6.
SAFETY SYSTEM FUNCTION i
a)
Initiation of plant S/D or C/D for Technical Specification L.C.O. compliance or deviation from Technical Specification L.C.O.'s (10CFR50.54x).
b)
Loss of dose assessment capabilities.
.l c)
Loss of communications.
Revision 17 January 1,1994 D-12
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. TABLE D-2 (Continued)
UNIT TWO EMERGENCY CLASS INITIATING CONDITIONS P
ALERT l.
-PRIMARY SYSTEM EVENTS 1
a)
RCS activity indicates > 1% failed fuel.
2.
REACTOR COOLA~NT SYSTEM LEAKAGE a)
RCS leakage > 44 gpm.
t 3.
SECONDARY SYSTEM EVENTS a)
S/G tube leak > 10 gpm with an ongoing steam release.
4.
ELECTRICAL POWER FAILURES i
a)
Station Blackout.
b)
Loss of all vital DC.
5.
RADIOLOGICAL EFFLUENTS a)
Projected or measured activity at the site boundary, averaged over one hour, is
. greater than or equal to.5 mrem /hr TEDE or 1.5 mrem /hr Child Thyroid.
t b)
- High mdiation/ airborne levels.
6.
SAFETY SYSTEM FUNCTION I
a).
RPS failure to complete an automatic trip.
b)
Control Room evacuation.
c)
Loss of decay heat removal systems.
j
. Revision 17 January 1,1994 D-14 i
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TABLE D-2 (Continued)
UNIT TWO EMERGENCY CLASS INITIATING CONDITIONS l
SITE AREA EMERGENCY I
d 1.
PRIMARY SYSTEM EVENTS a)
Core damage indicated with an inadequate core cooling condition.
b)
Containment radiation readings which indicate LOCA and >1% cladding failure.
2.
REACTOR COOLANT SYSTFM LEAKAGE a)
RCS leakage > 44 gpm with ICC conditions.
3.
SECONDARY SYSTEM EVENTS
)
i a)
S/G tube rupture > 44 gpm with an ongoing steam release.
)
4.
ELECTRICAL POWER FAILURES a)
Blackout > 15 minutes.
b)
Loss of ALL vital DC for > 15 minutes.
5.
RADIOLOGICAL EFFLUENTS a)
Radiological effluents are greater than or equal to 50 mrem /hr TEDE or 150 mrem /hr Child Thyroid at the site boundary.
b)
Spent fuel accident.
6.
SAFETY SYSTEM FUNCTION a)
RPS failure to complete a manual trip.
b)
Control room evacuation and control of shutdown systems not established in.15 minutes.
i c)
Loss of both S/Gs as a heat removal method.
Revision 17 January 1,1994 D-16 1
i TABLE D-2 (Continued)
UNIT TWO EMERGENCY CLASS INITIATING CONDITIONS GENER AL EMERGENCY 1.
PRIM ARY SYSTEM EVENTS a)
Containment radiation readings which indicate LOCA and >50% fuel overheat.
b)
Core melt.
c) less of or challenge to all three fission product barriers.
2.
. " CTOR COOLANT SYSTEM LEAKAGE N/A 3.
SECONDARY SYSTEM EVENTS N/A 4.
ELECTRICAL POWER FAILURES N/A 1
5.
RADIOLOGICAL EFFLUENTS a)
Radiological effluents are greater than or equal to 250 mrem /hr TEDE or 500 mrem /hr Child Thyroid at the Site Boundary, i
6.
SAFETY SYSTEM FUNCTION N/A 7.
HAZARDS TO STATION OPERATION a)
Ongoing security threat within the Control Room or vital areas.
1 4
Revision 17 i
January 1,1994 D-18 i
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I ACCIDENT ASSESSMENT i
2.0 ASSESSMENT
CAPABII.ITIES (Continued) 2.2.7 Radiological Dose Assessment Comouter System (RDACS) i The Radiological Dose Assessment Computer System (RDACS) provides an initial estimate of the radiological conditions at the ANO Exclusion Area Boundary, provides information to determine the Emergency Action Level for subsequent classi-fication into one of the four Emergency Classes, defines the offsite area (s) potentially affected by an airborne radiological release, provides. an estimate of the Total Effective Dose Equivalent (TEDE) and Child Thyroid dose rates, formulates protective action recommendations, and rennes projections based on availab!c field monitoring data. This system meets the intent of 10CFR20 and Appendix I to 10CFR50 using the methods recommended in Regulatory Guide 1.21, 1.109, 1.111, NUREG-0472 and NUREG-0133. 2.2.8 Safety Parameter Displav System (SPDS) The function of the Safety Parameter Display System (SPI;S) is to continuously provide concise displays of critical plant parameters to the control room operators to aid them in rapidly and reliably determining the safety status of the plant. The system is especially useful during abnormal and emergency conditions to assess whether the conditions warrant corrective action by the operators to avoid a degraded core. SPDS data [ display systems are also located in the Technical Support Center i and in the Emergency Operations Facility. t 2.2.9 Emergency Response Data System (ERDS) I A channel over which the raw reactor parametric data, ie., [ SPDS information, is transmitted from the site to the NRC Operations Center, (NRCOC). This system is activated from the RDACS terminal located in the Control room and should be activated with-in one hour of-an ALERT or highter emergency j class declaration. Revision 17 January 1,1994 I-11 l 1
z; I ACCIDENT ASSESSMENT
2.0 ASSESSMENT
CAPABILITIES (Continued) .t 2.3.2 Personnel a. Onsite Monitorine Section The Onsite Monitoring Section consists of members of the Emergency Radiation Team. Their activities are coordinated initially by the Shift Superintendent and then by the Health Physics Supervisor. The Onsite ' Monitoring Team focuses their attention on obtaining onsite radiological data. Duties of the Onsite Monitoring Team are outlined in Section B.2.0 f b. Offsite Monitorine Section The Offsite Monitoring Section consists of members of the Emergency Radiation Team. The' Offsite Monitoring Section performs air. sampling and measures radiation-levels in the outlying areas of-the plant site. Their activities are directed by the Offsite. Monitoring Supervisor. Survey results are-forwarded to the Dose. Assessment Supervisor. Duties of the Offsite Monitoring' Section are further detailed in Section B.2. ANO Nuclear Chemistry personnel collect samples of water, vegetation, soil, and air and the environmental. TLD's for analysis in accordance with ANO procedures. L 2.3.3 Eouioment i Appendix 4 of this Plan lists the emergency kit contents and their locations. Emergency Plan Implementing Procedures describe the equirment utilized by the monitoring teams in more detail. Portaole equipment capable of measuring gaseous activities of lx10-' pCi/cc are included in field monitoring kits. Revision 17 January 1,1994 I-13
J PROTEC'ITVE RESPONSE i 1.0 - PROTECTIVE RESPONSE FOR ONSITE PERSONNEL l.1 NOTIFICATION l Onsite personnel are notified of a nuclear emergency via the ANO Public Address System. The Shift Superintendent, or his designee, will announce the f emergency classification (for Alert Emergency Classes and above) and any other pertinent information. The announcements to be made am identified in the Emergency Plan Implementing Procedures. Persons within the protected area are notified of plant emergency status (for Alert Emergency Classes and above) via the Public Address System. Notification to persons within the exclusion area is accomplished through security. In conformance with emergency classification and severity, evacuation within the exclusion area is initiated for non-essential personnel for Site Area and General Emergencies in accordance with EPIPs. The sounding of the plant evacuation alarm occurs for both classifications. 1.2 LOCALIZED EVACUATION A Iecalized Evacuation is initiated if any condition exists which in the opinion of the Shift Superintendent or TSC Director may pose a threat to the health and safety of plant workers. The threat must be confined to a localized area (i.e., the area selected for evacuation should have well-defined boundaries and be easily controllable). 1.3 PLANT EVACUATION A Plant Evacuation is considered when the Shift Superintendent or TSC Director determines that general area radiation levels outside of a l Radiologically Controlled Area exceed 2.5 mrem /hr or unevaluated airborne 3 radioactivity exceeds IXIO* pCi/ce, which is attributed to a loss of control of radioactive material and the threat cannot be confined to a well-defined area. i A Plant Evacuation could also be considered in the event of an uncontrolled toxic gas leak where the hazard is not confined to a local area. In addition, a i Plant Evacuation is considered ' for non-essential personnel if a Site Area Emergency or General Emergency is involved. Certain extenuating conditions may preclude or delay plant evacuation. The decision is based upon the action i which presents the least risk to non-essential personnel. Revision 17 i January 1,1994 J-1 i i 6
J PROTECTIVE RESPONSE 1.0 PROTECTIVE RESPONSE FOR ONSITE PERSONNEL (Continued) 1.4 EXCLUSION AREA EVACUATION An Exclusion Area Evacuation, which is the orderly withdrawal of all personnel from that portion of the exclusion area affected by the emergency, is l initiated if it is determined that area radiation levels greater than 2.5 mrem /hr exist outside the Pmtected Area (Security Fence) and within the Exclusion Area boundary. The following personnel aedons are taken in the event of an Exclusion Area Evacuation: When notified that an Exclusion Area Evacuation has been declared, a. Security personnel take action according to established procedures to verify that an orderly, safe withdrawal of personnel within the affected portion of the Exclusion Area takes place. Security personnel are responsible for personnel noti'ication and accountability within' the Exclusion Area. Under most conditions, the Exclusion Area can be evacuated / verified within one hour of the declaration of an evacuation. Thereafter, Security patrols the Exclusion Area every two hours to notify anyone found within the area to leave. b. Personnel evacuating from the affected areas of the Exclusion Area follow designated evacuation routes under the supervision of Security personnel while on site. Once offsite, personnel proceed as directed by state and local authorities. Portable loudspeakers and the Arkansas Nuclear One boat are used by Security, as required, to direct the evacuation of the Exclusion Area. Evacuees use any available means of transponation and proceed as directed by the evacuation announcement. 1.5 EOF EVACUATION An EOF Evacuation is initiated if any condition exists, which in the opinion of the EOF Director, poses a threat to the health and safety of emergency response personnel at the EOF. These EOF emergency response personnel, if conditions allow, relocate the alternate EOF to AP&Ls Russellville District Office. P j Revision 17 .I January 1,1994 J-3 i i l l i I l
P l -J PROTECTIVE RESPONSE 1.0 PROTECTIVE RESPONSE FOR ONSITE PERSONNFL (Continued) permanent security badges are obtained. Emergency Response Organization personnel rema:ning on-site log in at any security-card reader for accountability purposes. Security personnel then request a computer print-out of any personnel who failed to (ither log off-site or log on-site for accountability purposes. Search and rescue efforts are then initiated for these individuals. Following a plant evacuation, continuous accountability is maintained for all persons remaining on-site. Reentry into the plant is made under an Emergency Plan Implementing Procedure related to personnel rescue or reentry to evacuated areas. 1.7 PROTECTIVE MEASURES 1.7.1 Whole Body Exposure It is the policy at ANO to maintain personnel radiation exposure at levels which are as low as is reasonably' achievable and in compliance with NRC regulations. Personnel entering the evacuated area (s) to conduct investigations are supplied with appropriate monitoring devices, and every effort is made to keep i j their doses within the limits of 10CFR20. Reentry is made in accordance with an Emergency Plan Implemertirg Procedure. Individuals entering Radiologically Controlled Areas wear personnel monitoring devices capable of measuring the dose received from external sources of ionizing radiation. The official and permanent record of accumulated deep dose equivalent is normally obtained from a TLD badge. The pocket dosimeter provides a day to day indication of deep dose equivalent. Additional personnel monitoring equipment is available in the emergency kits as identified in Appendix 4. s Revision 17 January 1,1994 J-5 t
} J-PROTECTIVE RESPONSE 2.0 PROTECTIVE
RESPONSE
FOR INDIVIDUALS WITHIN THE PLUME EXPOSURE PATHWAY 2.1 PROTECTIVE ACTION RECOMMENDATIONS 2.1.1 ANO Guidelines Arkansas Nuclear One is designed and equipped with a series of safety systems engineered to meet 10CFR100 criteria for reactor safety. ANO management recognizes that in any accident situation, it would be prudent and logical to make every effort .\\ to further reduce and minimize dose to the public. The protective action guides for the general population for thyroid dose due to inhalation from a passing plume and whole body exposure to airborne radioactive material, as recommended - by the Environmental Protection Agency (EPA), are listed below: Total Effective Dose Equivalent (TEDE) 1 Rem l Child Thyroid Dose (CDE) 5 Rem 2.1.2 Initiation of Recommendation Recommendations originate from the Control Room, TSC, or Emergency Operations Facility based upon data dedved from implementing procedures relating to offsite dose assessment. The procedures establish methods for determining pmjected dcse to the population-at-risk. Total population exposure is estimated in accordance with Emergency Plan Implementing Procedures. Recommendations are made in accordance with agreements with the Arkansas Department of Health. Whenever possible, the message formats provided in procedures are utilized. The implementing procedures relating to Protective Action Guidelines assure that the recommendations are determined through an approved process. Offsite Protective Action Recommendations are approved by the individual responsible for Emergency Direction and Control. Revision 17 January 1,1994 J-8 i
J PROTECTIVE RESPONSE 2.0 PROTECTIVE RESPONE FOR INDIVIDUALS WITHIN THE PLUME EXPOSUP.E PATHWAY (Continued) 5. The ADH Communication Center then alerts, using the Early Notification System, EBS stations in the area as to which RIM form l will be used and requests that all concerned get their file copy of the' proper message. After giving the alerted parties time to obtain their file copy message, the ADH operator then reads the message-emphasizing the information for the blank spaces. 6. The ADH Communication Center then confirms, by phone, that KARV radio station in Russellville has received the message. 7. The ADH Communication Center then requests that ANO disable its radio repeator on Mt. Nebo. 8. The ADH Communication Center then activates its Siren System. 9. EBS Stations read pre-planned message to the public at designated time. The preplanned Radiological Incident Messages to be used by the Arkansas Department of Health are found in Appendix 6. The preplanned messages are maintained at the local radio stations by the Arkansas Department of Health. If protective action for offsite areas is indicated and the Arkansas Department of Health cannot be contacted, the individual responsibic for Emergency Direction and Control is responsible for taking the following action: 1. If the projected or measured dose rates at the site boundary exceed 50 mrem /hr TEDE or 150 mrem /hr Child Thyroid for actual meteorological conditions, the sheriff (s) (or t Revision 17 January 1,1994 J-12
1 '1 'i K RADIOLOGICAL DOSE CONTROL 1.0 DOSE GUIDELINES .] l Radiation dose control is of utmost importance at Arkansas Nuclear one. Therefore, it - ) is deemed appropriate that detailed radiation protection measures be established and utilized. These measures are included in Emergency Plan Implementing Procedures, Radiation Protection Procedures and/or Health Physics Procedures, as appropriate. A description of applicable radiation control measures follows, i 1.1 DOSE LIMITS ANO Radiation Protection Procedures provide the specific actions undertaken to determine and record individual occupational doses on a 24-hour per day basis. These procedures state that each emergency responder entering a radiologically controlled area shall be issued appropriate personnel monitoring. devices i consisting of one or more of the following types: thermoluminescent dosimeter (TLD), self-reading pocket dosimeter, neutron badges and extremity dosimetry devices. The Radiation Protection and Radwaste Manager is responsible for ensuring that all personnel (employees, vendors, contractors, and visitors are appropriately monitored for dose to ionizing radiation at ANO. Allowable emergency doses and accidental doses to individuals have been established. Table K-1 outlines ANO's permissible emergency dose limits. Restriction to further exposure are placed on exposed individuals, if necessary. To determine accumulative doses, any TLDs of individuals exposed to radiation prior to the event are read and added to the emergency events doses promptly. In all cases and events, administrative control and restriction of('ose to radiation is monitored by the Radiation Protection and Radwaste Manager and the Health Physics staff. EPA-400, " Manual Of Protective Action Guides and Protective Actions for Nuclear Incidents", Table 2.2, is used to establish additional dose guidelines for life saving actions and protection of property. These guidelines are described in the Emergency Plan Implementing Procedures. a l Revision 17 January 1,1994 K-1 . i 1 .~ i
i: L\\>1. e K ' R ADIOLOGICAL DOSE CONTROL I 1.1 DOSE LIMITS (Continued) l 4 All questions of radiation doses for emergency workers above administrative limits are directed to the Shift Superintendent, TSC Director or EOF Director. These individuals have the authority in emergency situation to authorize emergency workers to receive doses in excess of 10 CFR Part 20 limits. After ERO activation, the TSC Director will typically assume the responsibility for approving on-site personnel doses exceeding 10CFR20 limits and the EOF Director will typically assume the responsibility for approving off-site personnel doses exceeding 10CFR20 limits. 1.2 PERSONNEL DOSIMETRY q P The capability to determine radiation dose to emergency respona personnel is-available twenty-four hours per day. Dosimetry personnel issue TLDs and dosimeters maintain TLD and dosimeter logs, and keep < the Radiation Protection and Radwaste Manager informed of personnel doses. The self-reading dosimeters are read by the Health Physics staff upon entry and exit from radiologically controlled areas and recorded for each individual. The permanent TLD is read, as necessary, in order to establish dose trends and control individual dose. 2.0 CONTAMINATION CONTROL 2.1 AREA ACCESS Controls have been established at ANO to en'sure that there is no detectable fixed or loose contamination (beta-gamma or alpha) outside of the Controlled Access Area under normal and emergency conditions. All personnel and equipment leaving the Controlled Access Area are monitored to ensure that the limits for contamination levels are met. Contamination control actions for off-site areas are planned for the Emergency Planning Zones with provisions to extend the actions to areas beyond this limit' if necessary. These contamination control actions are described in the State Emergency Operations Plan. Revision 17 January 1,1994 K-2 )
i l K RADIOLOGICAL DOSE CONTROL I 2.2. PERSONNEL 2.2.1 Under Normal Conditions Personnel working practices within the Controlled Access Area are Controlled by Health Physics personnel. Radiation Work Permits are required by all personnel working in the Controlled Access Area. Specific instructions, precautions, and limitations are listed on the work permits. Individuals are listed on the work permits. Individuals leaving Radiologically Controlled Areas are monitored for contamination-before entering the ' uncontrolled area of the plant. Personnel are again monitored as they pass through the portal monitor before leaving the Guard Stations, thus making it unlikely that a contaminated person could leave the site undetected. 2.2.2 Under Emergency Conditions In the vent of personnel contamination, Radiation Protection Procedures are implemented. - These procedures detail. methods for contamination removal from wounds, the whole body, hair, nostrils, and under fingernails. Wounds, eyes, ears, and mouth are treated with utmost care to prevent internal deposition and infections. all other body parts are washed with soap and water repeatedly under Health Physics personnel supervision.- the .F procedures list supplies for decontamination;
- however, c
intamination is accomplished by use of soap and water unless. u3e of another agent is approved by the Radiation Protection and Radwaste Manager or his designee. All decontaminations are recorded and, if not effective or if sickness an/or wounds are involved, personnel are taken to St. Mary's Hospital. Further decontamination is carried out at the hospital facility. the types of supplies and ' detection instrumentation maintained by ANO at the hospital are listed in Appendix 4. Certain agents such as titanium dioxide, EDTA. cream, surgical soap, and potassium permanganate solution are common hospital supplies and are not listed. Health Physics personnel assists hospital personnel in surveying the patient and in contamination control. Hospital radiological department facilities for waste disposal are used. Revision 17 January 1,1994 K-3
,= i K RADIOLOGICAL DOSE CONTRO1 i 2.2.2 11nder Emergency Conditions (Continued) i R 1 If an accident occurs in a Radiologically Controlled Area, and the i patient requires medical aid, he is checked for contamination and, ) if found to be below the levels for personnel contamination, he is taken to the Nurse's Station for treatment. If additional treatment is necessary, the Shift Superintendent calls the Pope County Emergency Medical Service for transportation to St. Mary's Hospital. If the patient is contaminated to unacceptable levels, reasonable efforts are made to decontaminate him. IF this cannot be done due to the nature of the injury and/or hospitalization is immediately necessary, medical treatment and/or transportation to a hospital takes priority over decontamination activities. The injured individual (s) is placed in clean protective clothing or wrapped in plastic if time allows, to minimize the spread of contamination. A person trained in health physics accompanies the patient. I When the patient arrived at the nospital, the staff of the hospital follows their procedure to handle this type of patient. Health j Physics personnel conduct surveys to ensure that contamination levels are kept to a minimum and control contamination until clean-up has been satisfactorily completed. Contaminated personal items are confiscated if successful decontamination cannot be completed. The Emergency Radiation Team performs radiological survey and establishes Radiation Area boundaries. The criteria for boundary placerr..-. is found in the Health Physics Implementing procedures. Controls normally include use of a personnel entry _ log, a frisking station, hourly air sampling, and dose rate records' every quarter hour. The establishment of such areas control and contain contamination. Decontaminated items and areas must meet normal radiation level standards before returning to normal use and release from Health Physics control. q Revision 17 January 1,1994 K-4
i [ K RADIOLOGICAL DOSE CONTROL 1 2.3 WATER AND FOOD SUPPLY 2.3.1 Onsite Supplies Radiological surveys of the emergency response centers and the f primary assembly are performed on a frequent basis. Portable water for ANO is obtained from the Russellville Water Supply. i It is unlikely that any airborne release of radioactive material could affect this supply. Contaminated areas are posted as described in Section K.3.2. Drinking, eating, and smoking are prohibited in radiologically controlled areas. 2.3.2 Offsite Supplies Selected offsite wells are analyzed for radioactivity as part of the Environmental Radiological Monitoring Program. In addition, surface water samples from Lake Dardanelle upstream and downstream of the plant discharge and at the intake to-the Russellville water supplies on the Illinois Bayou are analyzed for gross activity. Vegetation and milk samples are also analyzed as part of the Environmental Radiological Monitoring Program. In the event of an airborne release of radioactive materials, samples are collected and analyzed. Results are provided to the Arkansas Department of Health for appropriate protective action. 2.4 TOOLS AND EQUIPMENT 'l All tools and items of equipment used in the Radiologically Controlled Areas are checked for contamination before being taken from these Areas. If the item is found to be contaminated and decontamination is not practical, the item remains in the Radiologically Controiled Area. j Equipment and tools are unconditionally released for use outside of the Radiologically Controlled Areas only if fixed and movable contamination is not 'J detectable. i Revision 17 January 1,1994 K-5
1 K RADIOLOGICAL DOSE CONTROL 2.4 TOOL AND EQUIPMENT (Continued) 2.4.1 Site Equipment Contamination Control Equipment, such as vehicles, normally stored outside the plant buildings are surveyed and decontamination. ' Normal decontamination procedures of wiping, vacuuming or water spray. are performed, dependent of the magnitude and type of the contaminant. Vehicles leaving the site are monitored and decontaminated. Emertency' vehicles on lifesaving missions are not delayed for decontamination when leaving the site. Large equipment on site which is contaminated, but not required - for emergency recovery, is normally covered with plastic film to contain loose contamination. 2.4.1 Plant Eauipment Contamination Control Small contaminated tools and equipment are wrapped in plastic-and stored in radiologically Controlled areas of the plant until-decontaminated. 12rge equipment outside Radiologically Controlled areas. is covered with plastic film and decontaminated lby methods described in radiation control procedures. Large equipment inside the Radiologically Controlled Areas of the plant is normally located within compartment. Access and ventilation to these rooms are individually controlled. Contaminated plant equipment is decontaminated and/or controlled by methods described in radiation control procedures. Revision 17 January 1,1994 K-6
_l K ~ RADIOLOGICAL DOSE CONTROL 3.0 DECONTAMINATION 3.1 PERSONNEL DECONTAMINATION 3.1.1 Recontamination Facilities Contaminated personnel are dressed in clean protective clothing to contain the contamination and transferred to the decontamination are to be decontaminated in accordance with Health Physics Procedures. Normal personnel decontamination is accomplished in the Controlled Access Area Unit 1 exit Control-Point decontamination area located in the Auxiliary Building. All drains lead to the Radwaste System where the liquid is processed ' and monitored prior to discharge. The domestic fresh water. systera supplies water to all the rest rooms and showers. During site emergency evacuation conditions, personnel decontaminations can be accomplished at the Emergency Operations Facility. A decontamination shower and supplies for - decontamination of personnel are maintained at the EOF. 3.1.2 Decontamination Process Personnel decontamination is conducted by members of the HP staff, under the direction of the Radiation Protection and Radwaste Manager. Decontamination is conducted in accordance with Health Physics Procedures. 3.2 AREA DECONTAMINATION Area decontamination is performed in accordance with Radiation Protection Procedures. Revision 17 January 1,1994 K-7
l K R ADIOLOGICAL DOSE CONTROL 3.2.1 Clean Area For areas outside of the Radiologically Controlled Area,~ surface contamination is kept below the following: y a. Removable Contamination and Fixed Contamination - Beta-Gamma or Alpha In accordance with-Health Physics Implementing Procedures. 3.2.2 Contamination Areas Contamination Areas are defined in Health Physics Procedures ' " Radioactive Material Control". Contamination areas have been-divided into three categories: " Contamination' Areas", "High Contamination Areas", "Very High Contamination-Areas". The - degree of contamination control required changes with the level of contamination present. a. Contamination Area - Is defined in Health Physics Procedures, " Radioactive Material Control". b. High Contamination Area'- Any area with beta-gamma. contamination greater than or equal to 50,000 dpm/100 2 cm is a "High Contamination Area", c. Very High Contamination Area'- Any area with beta-gamma contamination greater than or equal to 100,000 2 dpm/100 cm is a "Very High Contamination Area". i 3.2.3 Priorities for Area Decontamination i Priorities for area decontamination.are determined by the TSC Director or the Emergency Operations Facility Director. Revision 17 January 1,1994 K-8 )
q 4.0 WASTE DISPOSAL UNDER EMERGENCY CONDITIONS. Liquid and gaseous wastes are processed using normal methods during emergency conditions. Emergency conditions may, however, require that additional resources of-i processing and disposal of waste be obtained. A Process Control Program (PCP) is used at Arkansas Nuclear One to ensure that radioactive waste management result in solid waste products meeting the criteria .{ contained in the Code of Federal Regulations, state regulations and radioactive waste. burial site license criteria for solid radiological waste shipment and disposal. In order to minimize the possibility of an accident involving radioactive waste 'a occurring in an uncontrolled area, radioactive wastes are packaged and stored in a facility designed to prevent radiological releases to the environment. The waste.is prepared, loaded and shipped to a federal or state' licensed radioactive waste' disposal facility (burial site) in accordance with Arkansas Nuclear One approved procedures t and/or qualified vendor procedures which have been approved by Arkansas Nuclear One. These procedures provide specific instructions which ensure the shipments meet the intended burial site license requirements as well as applicable federal and state i regulations. I i \\ 1 Revision 17 January 1,1994 K-9 j i i .] s
TABLE K-1 DOSE LIMITS Normal ANO permissible dose limits for NOTIFICATION OF UNUSUAL EVENT Emergency Classification and below are in accordance with Radiation Protection Procedures. ANO Emergency Permissible Dose Limits With Complete Records for the Current year ALERT Emergency Classification and above 5 Rem TEDE
- Protecting valuable property 10 Rem TEDE
- Life saving or protection oflarge populations 25 Rem TEDE
- Life saving or protection oflarge populations
>25 Rem TEDE Note:
- These limits are allowed with proper authorization.
This limit is allowed with proper authorization and only on a voluntary basis to persons fully aware of the risks involved. Revision 17 January 1,1994 K-10
M RECOVERY AND REENTRY PLANNING AND POST ACCIDENT OPERATIONS 3.0 REENTRY 3.1 PURPOSE The purpose of a reentry plan is to provide a means to regain access to an onsite or offsite area that was previously made inaccessible due to an emergency i situation. 3.2 AUTHORITY The individual responsible for Emergency Direction and Control authorizes reentry into a previously evacuated onsite area. In the event the ERO is deactivated, the Vice President, Operations ANO has the responsibility for authorizing reentry into a previously evacuated area. 3.3 IMPLEMENTING ORGANIZATION The implementation of the reentry plan is carried out by the ERO depicted in Figure B-6 or the normal ANO organization shown in Figure M-1 and discussed in Section M.2. These organizations have access to all information, documents, equipment, and personnel required to support a reentry effort. Actual reentry is accomplished by recovery personnel under the control of the TSC Director or the Director, Operations. 3.4 REENTRY - EMERGENCY RADIATION EXPOSURE DOSE JUSTIFICATION Although every effort is made to keep dose as low as is reasonably achievable (ALARA), it is understood that there are emergency situations which transcend the normal requirements for limiting dose. When such situations exist, the individual responsible for Emergency Direction and Control makes the determination as to the amount of radiation exposure that will be permitted based on the guidelines set forth below. Revision 17 January 1,1994 M-6 i i
M RECOVERY AND REENTRY PLANNING AND POST ACCIDENT OPERATIONS 3.0 REENTRY 3.5 REENTRY GUIDELINES (Continued) Recovery personnel perform their duties in the most safe and efficient manner possible. Once their operations have been completed, the recovery personnel follow self-monitoring and personnel decontamination procedures as specified by the Radiation Protection and Radwaste Manager. All questions which relate to exceeding occupational dose limits are directed to the individual responsible for Emergency Direction and Control. 1 8 Revision 17 January 1,1994 M-8
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-s y l EMERGENCY PLAN IMPLEMENTING PROCEDURES (Continued) - .l l '1904' XXX Series 1904.002 Offsite Dose Projections - RDACS Computer Method 1904.004 Estimating Airborne Release Rates 1904.005 Atmospheric Stability Class Determination 1904.008 Use of WSI Weather Information Service 1904.010 Duties of the Initial Dose Assessor 1904.011 Duties of the Dose Assessment Team 1905.XXX Series 1905.001 Emergency Radiological Controls 1905.002 Offsite Emergency Monitoring 1905.003 Radiological Protection. Requirements for Post Accident Sampling of Reactor Coolant 1905.004 EOF Radiological Controls 1905.030 Airborne I-131 Determination Using MS-2/ SPA-3 1905.031 Airborne I-131 Determination Using an RM-14/HP-210 For a description of the contents of a procedure and a cross-reference to the Emergency Plan, refer to Procedure 1903.001, " Organization and Use of Emergency Plan - Implementing Procedures." ? Revision 17 January 1,1994 3-2 f .}}