ML19326C390
| ML19326C390 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 02/28/1974 |
| From: | Phillips J ARKANSAS POWER & LIGHT CO. |
| To: | Anthony Giambusso US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8004220931 | |
| Download: ML19326C390 (9) | |
Text
J AEC DIS" ' BUTION FOR PART 50 DOCKET MATE (TEMPORARY FORM)
CONTROL NO:
1731 FILE:
FROM:
DATE OF DOC DATE REC'D LTR MEMO RPT OTHER Arkansas Power & Light Courpany Little Rock, Arkansas 72203 2-28-74 3-4-74 x
J. D. Phillips TO:
A. Giambusso 3 signed SENT LOCAL PDR X
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CLASS UNCLASS PROP INFO INPUT NO CIS REC'D DOCKET NO:
xxxx TO 50-313 DESCRIPTION:
ENCLOSURES:
Ltr re our 2-8-74 ltr.............trans the Supplementary Information: notarized 2-28-74, following:
consisting of......
(1) Addl info on radioactive materials sources i
DO NOPREMOVE ACKNOWLEDGED PLANT NAME: Arkansaa Unit #1
( 3 Orig & 67 cys rec'd )
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H GL PIN G B UIL O ARrCANSAS ARK ANS AS POWER & LIGHT COMPANY sTH & LoutSIANA STAEETS. LITTLE A CK. A AK ANSAS 72203.(5013' 72-4311 J
February 28, 1974 Mr. A. Giambusso Deputy Director for Reactor Projects Directorate of Licensing Office of Regulations United States Atomic Energy Commission Washington, D. C.
20545
Subject:
Arkansas Power & Light Company Arkansas Nuclear One-Unit 1 Docket No. 50-313 Supplementary Information
Dear Mr. Giambusso:
Mr. A. Schwencer's letter of February 8,1974, requested that we provide additional information on radioactive materials sources at Arkansas Nuclear One-Unit 1 to allow issuance of an operating license with broad possession and use limits on these materials.
The attached infonnation is in response to Enclosure 2 of Mr. Schwencer's letter.
The Technical Specifications were revised in Amendment No. 43 to the FSAR dated February 22, 1974, in response to Enclosure 3. did not require a response.
Very truly yours,
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J. D. Phillips nn' 4
co TMicr Vice President s
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STATE OF ARKANSAS SS COUNTY OF PULASKI J. D. Phillips, being duly sworn, states that he is a Senior Vice President of Arkansas Power & Light Company; that he is authorized on the part of said Company to sign and file with the Atomic Energy Commis-sion this Supplementary Infonnation; that he has read all of the statements contained in such Infonnation, and that all such statements inade and matters set forth therein are true and correct to the best of his knowledge, information and belief.
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SUBSCRIBED AND SWORN T0 before me, a Nothry Public in and for the County and State above named, this at d day of 6LA.uu.%,
_, 1974.
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1.
!!ATERIALS SAFETY PROGRAM i
1.1 SPECIAL NUCLEAR MATERIAL Arkansas Power G Light Company has implemented a " Nuclear Fuel Safeguards and Accountability System" to assure control of the special nuclear material-under title to, or in the possession of, the Company.
The use, storage and control of the special nuclear material at the operating station is done according to the operating procedure entitled " Control and Accountability Procedure for Nuclear Fuel".
This procedure is part of the Company's fuel accountability program, and the procedure references the operating procedures that are used in receiving, handling and storing the fuel assemblies containing the special nuclear material.
Special nuclear material contained in unirradiated fuel assemblies is stored in non-critical arrays in either the new or spent fuel pools, both of which are seismic Class I structures as described in Section 9.6 of the FSAR. The new fuel assemblies are.aoved and inserted into the reactor according to approved fuel handling and loading procedures and by using the fuel handling equipment, as described in Section 9.6 of the FSAR.
Irradiated fuel assemblies will be handled and stored under water, as described in Section 9.6.2.3, and licensed shipping casks will be used to move the fuel from the site.
1.2 SEALED NEUTRON SOURCES FOR REACTOR STARTUP The neutron sources used for reactor startup consist of source pellets encapsulated to form a complete neutron source set.
The neutron sources are handled, assembled and stored unuer water according to the provisions of the " Neutron Source llandling Procedure".
The sources are stored in either the shipping cask or the neutron source holder until the sources are loaded into fuel assemblies.
The fuel assemblies containing the neutron sources are then returned to the spent fuel storage racks or inserted into the reactor under the control of the. initial fuel loading procedure.
1.3 OTIIER SEALED SOURCES The Radiological Safety Program is described in Section 11.2.7 of the Unit 1 FSAR and is further clarified in the Radiation Protection !!anual and procedures.
In addition, sealed sources (with the exception of the startup source) containing a sufficient quantity of radioactive material to create a high radiation area will be locked in a shield or in the shielded position when not in use.
When in use and unattended the rooms in which these sources are used will be posted and locked.
4 2.
FACILITIES AND EQUIPflENT 2.1 FACILITIES The Radiochemistry lab has been constructed for ease of decontamination.
The lab is designed for the preparation and analysis of reactor coolant samples.
There is a stainless steel lined fume hood in the Radiochemistry Laboratory with a designed exhaust flow of 800 cfm.
Two exhaust fans draw air from the fume hood, Radiochemistry Lab, Satple Room and Counting Room as well as other areas in. the Auxiliary Building.
One fan will start automatically if the other fan stops.
If both fans fail, an alarm will sound in the Control Room.
Drains from the fume hood and sinks are con-nected to the liquid waste storage system provided in the plant.
Additional information on laboratory facilities is given in Section 11.2.7.4. of the Unit 1 FSAR.
2.2 PORTABLE SURVEY AND MONITORING INSTRUMENTS Information on radiation survey instrumentation is given in Section 11.2.7.5 of the Unit 1 FSAR.
A description of portable survey and monitoring instruments and their use is given below.
These instruments or their equivalent will be used.
Radiation Detection Instruments Window Radiation Sensitivity Thickness 2
Type of Instrument Detected Range (mg/cm )
Use 1.
Portable GM Count beta, gamma 0-280K cpm 30 Monitoring Rate / Survey !!eter 200 mR/hr (Batt) 2.
Portable Gli Count alpha, beta 0-500K cpm
<2 Monitoring Rate Meter (Batt) gamma 3..
Survey '(Batt)
Portable GM beta, gamma 0-1000 R/hr 30 Survey 4.
G!! !!onitoring alpha, beta 0-50K cpm 30 Or Monitoring Instrument (AC) gamma
<2 5.
Gas Flow Propor-alpha, beta 0-500K cpm
<2 Contamination tional Survey Survey lkter (Datt) 6.
Portable Ionization alpha, beta 0-500 R/hr
<2 Survey Survey Meter (Batt) gamma 7.
Portable Ionization beta, gamma 0-1000 R/hr 30 Survey Survey Meter (Batt) 2
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8.
Portable Ionization alpha, beta 0-300 mR/hr
<2 Survey Survey fleter (Batt) gamma 9.
Portable BF3 fast neutron 0-500K cpm Survey Neutron Flux Survey slow neutron
!!eter (Batt)
- 10. BF Portable REM neutron-0-500 mR/hr Survey 3
Counter (Batt) 2.3 PORTABLE AIR MONITORING EQUIP!!ENT Portable air monitors consist of air samplers that are capable of continu-ously monitoring and recording particulate,and gaseous activity.
Th,ese monitors can be set to alarm on high particulate or gaseous activity.
In addition, these monitors can be equipped with an iodine collection cartridge that can be counted in the laboratory.
Partable air sampling equipment is also available to obtain airborne grab-samples for particulate, gaseous or iodine.
2.4 LABORATORY COUNTING EQUIPl!ENT Laboratory counting equipment includes internal gas flow proportional counter scalers, thin window GM counter scalers and gamma spectroscopy equipment.
2.S INSTALLED AREA RADIATION !!0NITORING SYSTE!!
TPe Area Radiation Monitoring System is ' described in Section 11.2.6 of the Unit 1 FSAR.
2.6 INSTALLED PROCESS RADIATION MONITORING SYSTEM The Process Radiation Monitoring System is described in Section 11.1.3.4 of the Unit 1 FSAR.
2.7 PERSONNEL !!0NITORING DEVICES The personnel monitoring equipment is described in Section 11.2.7.1 of the Unit-1 FSAR.
3.
PERSONNEL AND PROCEDURES e 3.1 PERSONNEL' j
The site Nucicar Engineer is designated as the Nuclear ?!aterials Custodian and is responsible for the physical accountability of the special nuclear material and provides the-storage, movement and loading sequences to j
minimize the handling of the fuel assemblies. -The Operations Supervisor j
is responsible for the safe movement and handling of-fuel assemblies according.to written plant procedures.
Plant operations personnel I
trained in the use of fuel handling equipment are used in moving the material and on-site Shift Supervisors are responsible for fuel handling
- operations on their shift.
c 3
p Section 12.1.3 of the Unit 1 FSAR gives the description of the positions for the Chemical and Radiation Protection Engineers.
The qualifications of the Chemical and Radiation Engineers is given in Appendix 1 paragraph 1.1.6 of the Unit 1 FSAR.
3.2 PROCEDURES All new or temporary employees shall receive a radiation protection orientation prior to their assignment of work in the Controlled Access Area. The orientation will include instruction in the Radiation Protec-tion Fhnual.
Visitors must be escorted within the Plant unless they have completed the radiation protection orientation.
The general radiological safety rules that have been established are:
1.
All plant personnel who may be exposed to ionizing radiation must familiarize themselves with the safe practices and procedures applicable to their work as outlined in the Radiation Protection Manual.
2 Personnel shall contact Health Physics for any information they need about radiation safety and the protective measures required for their job.
3.
All work with radicactive materials or radiation may be performed only under an appropriate, signed, Radiation Work Permit (or Special Work Permit).
4.
No one should begin work with radioactive materials until:
a.
He has a complete working knowledge of the procedures that will eliminate or minimize radiation exposure to himself and to other personnel.
b.
He. is able to evaluate his exposure for the operation in relation to the permissible dose limits.
c.
He is aware of the proper procedure to follow in case of an accident.
5.
Each person who works with radioactive materials has.a responsibility to:
a.
Protect himself and others from overexposure to external radi-ation.
b.
Prevent or minimize the uptake of radioactive materials.
c.
Prevent the spread of radioactive contamination.
4
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Assigned personnel monitoring badges and. pocket dosimeters will be worn at all times in the Plant Area.
7.
Protective clothing and equipment listed as necessary for a job on a Radiation Work Permit (such as coveralls, lab coats, gloves, caps, rubbers, respiratory equipment, etc.) shall be worn as required.
They shall never be worn or taken out of the Controlled Access Area or other contaminated area.
8.
Personnel shall assure themselves that adequate monitoring has been performed by Health Physics before work is begun in any radiation, high radiation or airborne activity area.
9.
Personnel working in radiation areas where general levels could rise above 100 mrem /hr will have a survey meter with them or have continu-ous Health Physics surveillance.
10.
Personnel shall notify Health Physics of the malfunctioning of any radiation protection equipment.
11.
Keep work areas clean and tidy and observe contamination limits.
12.
When work ~ involves radioactive contamination, monitor protective clothing at intervals during the day, while on the job,'and monitor body surfaces after removin'g protective clothing and before eating, drinking, smoking, or leaving the plant.
13.
There will,be no eating or preparation of food or drink in the Controlled Access Area or other contaminated areas.
Smoking will be limitedtolocationsasdesignatedbyHealghPhysicswherecontamin-ation is not present (i.e., 200 dpm/100 cm beta-gamma).
14.
No materials or equipment shall be removed from the Controlled Access Area or other contaminated areas unless released by Health Physics
'and tagged as such.
15.
Maximum practical distance and shielding and minimum working times shall be utilized for protection in working with external sources of radiation where significant exposure is likely otherwise.
16.
Low level radioactive solid waste (contaminated trash) shall be bagged or packaged as necessary to preclude the spread of contamination and deposited in Radioactive Waste Containers for pickup and disposal.
17.
Containers of radioactive material must be labeled as such.
18.
To' avoid possible unknown exposure to radiation, inform affected persons of 'all radioactive materials transferred to their~ location.
l 19.
Each individual is responsible for keeping his own occupational expos-ure, as low as possible, consistent with the work to be done.
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20.
Respiratory protective equipment must be worn for all work where the concentration of airborne radioactive particulates or iodine exceeds or is likely to exceed mpe levels of 1(-9) uCi/cc for unknown mixtures
-of beta-gamma emitters.
21.
Notify the Shift Supervisor, Health Physics, and the Plant Superintendent as soon as possible of all emergencies involving radiation or radio-active materials (spills, leaks, etc.) and of all radiation accidents involving personnel (wounds, contamination, overexposure, etc.).
22.
Personnel must be thoroughly familiary with their assignments in case of an emergency.
23.
Visitors and/or persons unfamiliar with plant radiation safety regul-ations will require an escort when entering the plant.
4.
REQUIRED MATERIALS At present therc are no plans to have any radioactive materials onsite that exceed the limits specified in Enclosure 2 to f.hr. A. Schwencer's letter to Mr. J. D. Phillips of February 8, 1974.
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