ML19326C235
| ML19326C235 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/01/1977 |
| From: | Phillips J ARKANSAS POWER & LIGHT CO. |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| 1141-1-017-9, 1141-1-17-9, NUDOCS 8004220808 | |
| Download: ML19326C235 (11) | |
Text
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7(% C PEM 193 U.S. NUCLEAR r.EGULATORY AMISSION DOCKET NUMT E R
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'A NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL TO:
Mr D L Ziemann FROM: Arkansas Pwr & Light Co OATE OF DO ME Little Rock, Ark J D Phillips DATE RECEIVED
[ LETTER ONOTORIZEO PROP (NPUT PORM NUMBER OF CCPIES RECEIVED
- BURICfN AL huNC LAS$1FIE D
- OCOPY one signed DESCRIPTION ENCLOSURE Ler trans the following:
Amdt #52 to t'h'd'Emew-y-Plan: 'Consis ting of deletion of Certain requirements with regard to evacuation, maintainence of separate isol-ation ward & Conduction of evacuation drill...
THIS DOCUMENT CONTAINS P00R QUAUTY PAGES
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,p PLANT NAME: Arkansas #1
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4 SAFETY FOR ACTION /INFORMATION _ vwrun 2-4-77 ehf ASSIGNED AD:
ARRTENPn An.
2JRANCH CHIEFr "Z l c_m a n 6 i S)
RRANEH EHTFT.
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PROJECT MANAGER:
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- sJ INTERNAL DISTRIBUTION i FILEl SYSTEMS SAFETY PLANT SYSTEMS SITE SAFETY &
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NKU UUK HEINEMAN TEDESCO ENVIRO ANALYSTS
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MIPC MACARRY KTRKWOOD ERNST CASE KNICHT BALLARD HANAUER SIINEIL OPERATING REACTORS SPANGLER HARLESS PAWLICKI STELLO SITE TECH.
PROJECT MANAGEMENT REACTOR SAFETv OPERATING TECH.
GAMMILL BOYD ROSS
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SHA0 HULMAN HOUSTON ROSZTOCZY
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BAER PETERSON CHECK
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BITTLER SITE ANALYSIS MELTZ
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.m H EL PIN G BUILO ARKANSAS A AK ANS AS POWER & LIGHT COMPA NY A 0. 80X 551 LITTLE AOCK. A AK ANS AS 72203.(5011371-4000 February 1, 1977 r.
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Director of Nuclear Reactor Regulation
,'h.l;j eg N AT'IN: Mr. D. L. Ziemann, Chief
'4E bC.?r j Operating Reactors Branch #2 4
U. S. Nuclear Regulatory Commission
,q My Washington, D. C.
20555 N --
Subject : Arkansas Nuclear One-Unit 1 Docket No. 50-313 License No. DPR-51 Emergency Plan Amendment (File: 0467)
Gentlemen:
Attached find eighty (80) copies of Amendment No. 52 to the Arkansas Nuclear One Emergency Plan. This amendment deletes the requirement that Arkansas Power 4 Light Company has the responsibility for evacuating the public from Bunker Hill and a portion of Round Mountain as the Company has no jurisdiction to evacuate people from their private homes. Also i
included in this amendment is the deletion of the requirements that a special decontamination room be maintained at St. Mary's Hospital, an addition to Table J-1 concerning items in the Control Room Emergency Kit, and a more flexible statement concerning the conducti.on of the drill defined in Section 5.6.4.5.
Very truly yours, 1
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AMENDMENT NO. 52 ARARKANSAS POWER 6 LIGifT COMPANY ARKANSAS NUCLEAR ONE-UNIT 1 The following sheets of Arkansas Power S Light Company's Arkansas Nuclear One-Unit 1 Emergency Plan are to be removed and, where specified, additional sheets dated February 1,1977, should be inserted:
Remove Insert MAIN BODY 28, 29 28, 29 37, 38 37, 38 i
APPENDIX E E-1, E-2 E-1, E-2 E-3, E-4 E-3, E-4 E-5, E-6 E-5, E-6 Figure E-1 Figure E-2 APPENDIX J J-1 J-1 1
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Nts4.2.2.2 Area Evacuation
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An a\\rea evacuation is the orderly withdrawal of all personnel from that by the\\of the public area surrounding the plant which has been affected portio emergency.
An area e ' cuation will be initiated if any of the following conditions occur:
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a.
It is timated that individuals beyond the site boundary could receive 'a dose of 2 Rem or greater to the whole body; I
b.
It is estimated that a dose of 10 Rem to a child's thyroid, skin of the whole\\ body, or any organ could be received by individuals beyond the si boundary; or c.
In the event of potential or actual release of radionuclides from the plant whhch exceeds an average concentration at the site boundary of Sdq times the anrestricted maximum pemissible concentratio.. (MPC) 'specified for.the material released for a 24-hour period.
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In the event of a potential or a ual uncontrolled or accidental release of radionuclides from the plant which exceeds an average concentration at the site boundary of MPC for the mat'e, rial released for a 24-hour period, the' Arkansas State Department of Health will be notified.
In addition, f
ANO personnel will commence off-site m6nitoring to establish the radiological
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hazard off-site.
Further controls, if.r'equired, will be specified by the 39 Arkansas State Department of Health.
The following personnel actions will be take'ns in the event of an Area 1
Evacuation:
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The Division of Radiological Health is rbsp(onsible for the directio a.
and implementation of the necessary protect ve actions specified in the State of Arkansas Radiological Responi, Assistance agencie e Plan including noti-fication and coordination of state and local N
b.
If evacuation of public areas is indicated prior 't,o the arrival of the State Radiological Response Team Captain anchhe cannot be contacted, the Emergency Control Officer, in concgrence with the Duty Emergency Coordinator, makes a recommendation \\to the Pope ~ County Sheriff or his designated representative thht the affected area be evacuated.
If radio contact is established with lhe State Radiological Response Team Captain, recommendations for eva'cyation of public areas will be made through him.
In making the decisio o
Amendment No. 39 June 20, 1973-s.
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This evaluation is based upon the performa:.ce of the participants in follow-ing emergency procedares and the adequacy of these procedures to limit the effects of the emergency condition. The Plant Safety Committee is then responsible for any necessary changes in particular Emergency Procedures.
5.6.4 SPECIFIC DRILLS The drills and alarm tests listed below are conducted at least annually.
More than one type of drill may be initiated simultaneously s'uch that the nature of the drill is varied (e.g., Local Emergency involving fire and personnel injury.)
5.6.4.1 Local Emergency Local Emergency, including evacuation, initiated by a simulated alarm from the area radiation monitor system, the plant gas monitor reaching its alarm set point, an unexpected increase in the level of radiation in a work area as indicated by portable radiation monitors, or the containment evacuation alarm. This drill requires, but is not necessarily limited to, initiating the following Emergency Procedures:
a.
EP 1202.35, " Radiological Incidents" b.
EP 1202.41, " Evacuation Procedure" The additional Emergency Procedures listed below may also be incorporated i
into the drill:
a.
EP 1202.38, " Fire or Explosion" b.
EP 1202.39, " Personnel Injury" c.
EP 1202.40, " Refueling Accident" d.
EP 1202.42, " Recovery and Re-Entry Procedure" 5.6.4.2 Physical Plant Area Emergency Physical Plant Area Emergency, including evacuation, initiated by a simulated alarm condition from the area radiation monitor system and the plant vent gas monitor reaching its alarm set point. Note: Assume accident conditions such that evacuation of the Exclusion Area is also required.
This drill would re-quire, but not necessarily be limited to, initiating two or more of the follow-ing Emergency Procedures:
a.
EP 1202.35, " Radiological Incidents" b.
EP 1202.37, " Determining Magnitude of Release" c.
EP 1202.41, " Evacuation Procedure" d.
EP 1202.42, " Recovery and Re-Entry Procedure" i
APPENDIX E ANO MEDICAL EMERGENCY PLAN E.1 EMERGENCY CARE PROCEDURES L
Injuries, radiation, or contamination resulting from nuclear emergencies are divided into two categories for emergency care procedures.
E.1.1 ACCIDENT REQUIRING IMMEDIATE MEDICAL ATTENTION - ST. MARY'S HOSPITAL Personnel requiring immediate medical attention for serious in-juries sustained in a nuclear accident will be transferred directly to St. Mary's Hospital, Russellville, Arkansas, for ur-gent medical care in accordance with the terms of the existing agreement with AP&L.
(See ANO Emergency Plan Appendix H)
In order to provide adequate control of radioactive contamination and radiation exposure of attending hospital personnel, a special Decontamination Room equipped with decon shower, lavatory, storage locker, emergency treatment area and an absolute filter in the ventillation exhaust, has been constructed in St. Mary's Hospital (Figure 1).
Entratce to the Decontamination Room will be made from the Ai5ulance Entrance in the rear of the hospital, down a ramp directly to the Decontamination Room (Figure 2).
If there is a possibility of contaminating the ramp, a polyethylene or plastic covering will be placed on the ramp prior to the patient's arrival.
AP&L has supplied the hospital with contamination supplies (Table
- 1) which are kept in the decontamination room storage area.
If, in the consulting physician's opinion, contamination control or decontamination must be sacrificed in order to provide proper emergency care to the patient, the physician's directions shall be followed.
For those injuries in which delay of hospitalization does not re-sult in any risk to the injured person, the persennel decontamina-tion area or first aid room at the plant will be utilized to en-sure that radioactive contamination is reduced to safe levels or localized. Every effort shall be made to reduce the radiation emitted from the body to less than 2 R/ hour at contact. Follow-ing decontamination, health physias personnel or a member of the Emergency Medical and Decontamination Team will accompany the patient to the hospital.
AP&L personnel who accompany a patient to the hospital or are directed to proceed there shall act in a consulting, advisory, and monitoring capacity as outlined herein and as requested by attending medical personnel.
E-1
m b.
In the case of less severe injuries, the patient will be sent to the personnel decontamination area to remove as much contamina-tion as possible before he be taken to the first aid room or te St. Mary's Hospital.
c.
If the radiation emitted from the patient's body is excessive or if external exposure is suspected to have exceeded 50 R, the pa-tient will be transported directly to the University of Arkansas Medical Center. All dosimetry will be removed from the patient's body, including items which may have become activated during ex-posure, and turned over to health physics personnel for dose eval-uation and subsequent handling. If the transportation of the ex-cessively contaminated patient to the University of Arkansas Medical Center is impractical because of severity of the physical injury, the consulting physicians may elect to go to ANO to admini-ster emergency treatment until conditions permit transfer to the appropriate hospital. In all cases every reasonable effort will be made to reduce the level of radioactive contamination on the patient before transfer from the plant.
E.3 AMBUIN TE TRANSPORTATION TO ST. MARY'S HOSPIT*.L OR THE UNIVERSITY OF ARKANSAS MEDICAL CDmut Where the decision has been made to transport the injured person by ambu-lance, the Shift Supervisor will take the following action:
a.
If the Energency Medical and Decontamination Team is not yet on site, the Shift Supervisor will assign an ambulance driver for the ANO am-bulance and call in additional ANO personnel as required.
b.
Notify the St. Mary's Hospital or the University of Arkansas Medical Center that an injured person is being sent by ambulance to the hospi-tal for emergency treatment. The extent and type of injury will be described. As much information pertaining to the radiological aspects as is available will be given to hospital personnel. In addition the approximate ambulance arrival time will be given.
c.
If health physics personnel are not on site when the asbulance departs they will be notified to meet the ambulance at the hospital. The ANO Ambulance Emergency Kit contains monitoring instruments, personnel dosimetry and other radiological control supplies.
(See ANO Emergency Plan Appendix J)
If additional equipment or supplies are needed they will be sent from ANO as required.
l d.
If more than one ambulance is needed, AP&L has established an agree-ment with the Pope County Ambulance Service. Russellville, Arkansas, to furnish additional vehicles. Protective devices such as clothing, monitoring devices, etc. will be available at the plant. Attendants 4
will be periodically trained in radiological aspects associated with this service.
E-3
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Chemical methods such as acetone or acid e.
Disposal To be considered free of contamination the instruments and equipment should meet the following guidelines:
Type of Contamination Transferable
- Fixed
- 2 2
Alpha 30 dpm/100 cm 300 dpm/100 cm 2
Beta, gamma 200 dpm/100 cm 0.05 mrad / hour No individual should pass the checkpoint without monitoring his person and personal clothing. This monitoring will be provided by ANO per-sonnel at St. Mary's Hospital. Should any contamination be detected, instructions will be given on what steps should be taken. In some cases it may be necessary to utilize decontamination facilities at ANO where special control facilities such as containment of contaminated liquids are available.
After the patient has been removed from the decontamination room to be treated in a normal manner, the protective coverings such as sheets will be carefully rolled up or folded by personnel wearing protective clothing and placed in large plastic bags and removed to ANO. All po-tentially contaminated instruments and quipment will be handled as out-lined in Section E, Paragraph 1.
All potentially contaminated surfaces will be checked by ANO personnel for both loose and fixed contamination. The release limits specified in Section E, Paragraph 1, will also apply in this case. Decontamina-tion services at the hospital will be provided by ANO if required by the hospital representative.
All used TLD and pocket dosimeters will be turned over to ANO health physics representatives. The TLD dosimeters will be processed 'at ANO by health physics personnel and exposure date will be forwarded to St.
Mary's Hospital.
- These values represent normal background radiation levels.
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't TABLE J-l CONTROL ROOM EMERGENCY kit -
QUANTITY DESCRIPTION 1
Count rate survey meter with shielded pancake probe
- and holder for personnel or area monitoring and checking smears or air samples 1
High range ion chamber type survey meter (0-500R/nror 0-1000R/hr) 1 AC powered personnel frisker with hand held thin end window probe
- 1
' scaler / timer with detector for smears or air samples 1
Air sampler with filters 6
High range pocket dosimeters (3 ea. 0-10R, 3 ea. 0-200R) 10 Low range pocket dosimeters (0-500 MR) 1 Dosimeter charger 2
Respiratory equipment - Full face, filter /cannister type (with spare filters or cannisters) 2 Respiratory equipment - Full face, self contained (with spare air bottles) 10 Complete sets of protective clothing 3
Flashlight's Spare batteries and/or charger for rechargable batteries in portable instruments and flashlights Spare flashlight bulbs Poly bags, tape, survey sheets, clipboard, pencils, chalk, radiation warning signs, barrier tape and smears preloaded in envelopes Copy ANO Emergency Plan and Procedures Overlays and instructions for determining the magnitude of releases Drawings of plant, site, and area around the site
- These probes are interchangable J-l