ML20147J376
| ML20147J376 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/06/1978 |
| From: | David Williams ARKANSAS POWER & LIGHT CO. |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7812280125 | |
| Download: ML20147J376 (7) | |
Text
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ARKANSAS POWER & LIGHT COMPANY j,
POST OFFICE BOX 551 LITTLE ROCK. ARKANSAS 72203 (501) 371-4000 December 6, 1978 s
j 1-128-6 t-Director of Nuclear Reactor Regulation ATTN: Mr. R. W. Reid, Chief 1
Operating Reactor Branch #4 1
i U. S. Nuclear Regulatory Commission Washington, D. C.
20555 i
Subject:
Arkansas Nuclear One - Unit 1 l
Docket No. 50-313 4.
License No. DPR-51
{
Operating License Amendment, K-85 i
(File:
1510)
Gentlemen:
4 Our letter of August 16, 1978, requested an Operating License Amendment to allow possession, storage and use of a Krypton 85 source exceeding l
the allowable limits of our current Operating License.
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As a result of subsequent telecons with.the Staff, the attached marked-
{
up pages of the ANO-1 FSAR are submitted.
These changes will be in-j corporated in the ANO-1 FSAR. These pages supersede the corresponding pages attached to our August 16, 1978, letter.
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Very truly yours, j
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I Daniel H. Williams Manager, Licensing DHW:JTE:vb Attachment i
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4 l1. 3 RADIOACTIVE MATERIALS SAFETY
!!. 3. l MATERIALS SAFETY PROGRAM l L. 3.1 l Special Nuclear Material Arkansas Power 6 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 assemblics containing the special nuclear material.
Special nuclear material contained in unirradiated fuel assemblies is l
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 f.44 I.I,FLe.l ct s s ea l>l t e 3 a t e.
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- 22. Irradiated fuel assemblies will be handled and stored under water, as described in Section g.4.2.2.and licensee shipping casks will be used to move the fuel f1com the site.
12/4.1.2 Scaled 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 t
.are handled, assembled and stored under water according to the provisions of the " Neutron Source Handling Procedure".
The sources are stored in either the shipping cask or the neutron source holder until the sources are loaded into fuel assemblics.
The fuel assemblics containing the neutron sources are then returned to the spent fuel storage racks or i
inserted into the reactor under the control of the initial fuel loading procedure.
11 3. l..t Other Scaled Sources The Radiological Safety Program is described in Section 11,J.7 and is further clarified in the Radiation Protection Manual and procedures.
In addition, scaled sources (with the exception of the startup source) containing a sufficient quantity of radioactivgayerial to create a high radiation area will be locked in a shield or41n the shielded position when not in use.
h' hen in use and unattended the rooms in which.these sources are used i
will be. posted and locked.
/I.3.2. FACILITIES AND EQUIPMENT
- 11. 3. 2. ]
Facilities The Radiochemistry lab has been constructed for ease of decontanination.
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The lab is designed for the preparation and analysis of reactor coolant sampics. 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, Sample 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 i
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.
Additiemi information on laboratory facilities is given in Section il. 2 7. Y, 11,3.',t.l.l Present Facilities, Control and Use A.
At present Oca<. Arc.two Cs-137 instrument calibration sources.
One source is 100 mil 11 curies with permanent collimator and is electrically operated.
A cart and track arrangement was built to make use of the inverse squarc law for obtaining the 1
desired exposure. 'The other source is a 50 Curie source.
This source has a self-contained exposure cavity with a 1 cad glass viewing window and is mechanically interlocked to prevent personnel exposure during use.
The desired exposure is obtained by placing I
Icad attenuators in the beam.
j Both sources are locked in the shicided position when not in use.
These sources are used by and the storage areas controlled by Health Physics personnel. Whenever the sources are in use and unattended,'
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the areas in which they are located are locked / When the 100 Pc 51* d
- millicurie source is in use, the area is posted as a radiation area,
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There are two rooms being used for instrument calibrations. One is located adjacent to the Unit 1 Health Physics office and the other is in the Unit 1 Turbine Building basement. 6etk roems er* ""'"//r m t n ses t u n d tec n e d it n d. + k < +oess c.*,s +-cr t n i n 1 he. co c.u r ie. c, s - n ? so ur ce.
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B.
There are two calibration sources used to check and calibrate the out of core detectors. One is a 4.71 Curie Pu-Be source
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and the other is a 500 millicurie Co-60 source.
When not in
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use both sources are locked in their storage containers and the j
keys are controlled by Health Physics.
Presently, Health Physics
. personnel are present whenever the sources are handled.
Instrument Department personnel may handle the neutron source *
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af ter they are feataed by Hes./+4. PA v uc5 Fe4 5w n el ; n Handling the sources requires the issuance of a Special Work Per k cl uu r,u dt,f o a*< d k e t i
C.
Smaller check sources are used to check or calibrate some radiation fues.
instruments. There.is a 20 microcurie Co-60 and a 39 millicurie Cs-137 source used to check the installed radiation monitors. The beam is collimated and directed into a cylindrical cavity that fits down over the detector..This cavity acts as a beam stop.
These sources are stored under health physics control but may be used by other plant personnel in addition to Health Physics for checking area nonitors.
(Personnel will be +re toed by Heal H. pay s.'c s pe se>m'e I la 4aad //g f 4 <-
s o m e e. e > be free. 4 hy a re. a //med & tt s e. Hr e.m),
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11, 3, 2',1, 1 -Future Facilities, Control and Use A.,
The.500 mi111 curie Co-60 source may be used as a calibration source for i
portabic instruments in the future.
If so, it will be used in a ' suit-able configuration to limit personnel exposure and, will be used by Health Physics personnel.
( In t,est A)
B.
The calibration sources described 4 n I l 3. 2.1. 8 A above may be moved to Unit 2.
If so, they will be in rooms or areas controlled by Health C.
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' " & I" ll. 3,2.2.
Portable Survey and Monitoring Instruments Information on radiation survey instrumentation is given in Section /t.2.7 55 A description or portable survey and monitoring instruments and their use 'is given below. These instruments or their equivalent will be used.
RADIATION DETECTION INSTRUMENTS Min.
Window No.
Radiation Sensitivity Thickness Type of Instrument Avlb.*
Detected Range (mg/cm )
Use
- 1. Portable GM Count 4
gamma, beta 0-280K cpm 30 or <2 Monitor-Rate (Batt) ing
- 2. Portable GM Survey 2
beta, gamma 0-1000 R/hr 30 Surv'ey
,(Batt)
- 3. GM Monitoring 4
alpha, beta 0-50K cpm.
30 or <2 Moni tor-Instrument (AC) gamma ing
- 4. Cas Flow Propor-2 alpha, beta 0-500K cpm
<2 Contamina-tional Survey tion Surve)
Meter (Batt)
- 5. Portable Ionization 2
gamma,' beta 0-500 R/hr
<2 Survey Survey Meter (Batt)
- 6. Portable Ionization 2-beta, gamma 0-1000 R/hr 30 Survey Sbrvey Meter (Batt)
- 7. Portable Jonization 1
alpha, beta 0-300 mR/hr
<2 Survey Survey Meter (Batt) gamma
- 8. Portable BF 1
fast neutron G-500K cpm Survey Neutron Flux' Survey slow neutron
-Meter (Batt) 9.-BF3 Portable REM 1
neutron 0-500 mR/hr Survey Counter (Batt)
- All for use in Units 1 and 2.
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II. 3 2 3 Portable Air Monitoring Equipment Portabic air monitors consist of four air samplers that are capabic of con-tinuously monitoring and recording pmrticulate and gaseous activity. 'Ihes e monitors can be set to alarm on high particulate or gaseous activity.
In addition, these moni' >rs can be equipped with an iodine collection cartridge that can be counted in the laboratory.
(Particulate and gaseous activities o f 3 x 10 11 and 1 x 10-7 pCi/ce, respectively, can readily be detected in low bnckground areas.
In higher background areas, particulate and gaseous activities of 3 x 10-10 and I x 10-6 pCi/ce, respectively, can be detected.;
Two portable air samplers are also available to obtain airborne grab samples-for particulate, gaseous or iodine.
(For normal sample and counting times, activities of 2 x 10-10, 5 x 10-10 and 5 x 10-7 pCi/cc are readily detected for particulates, iodine and noble gases, respectively.
By increasing collection and/or counting times lower levels of activity may be detected.)
/1, 3 2. 'l Laboratory Counting Equipment Laboratory counting equipment includes internal gas flow proporational counte:
scalers, thin window GM counter scalers and gamma spetroscopy equipment.
11 3 2, r Installed Area Radiation Monitoring System The Area Radiation Monitoring System is described in Section i 1. 2. 6,
ll. 3 2 4 Installed Process Radiation Monitoring System The Process Radiation Monitoring System is described in Section 11. 1. 5 4.
1132.7 Personnel Monitoring Devices The personnel monitoring equipment is described in Section 11. 2. 7. I.
/43.3 PERSONNEL AND PROCEDURES
- 11. 3 3. l Personnel The site Nuclear Engineer is designated as the Nuclear Materials Custodian and is responsible for the physical accountability of the special nuclear material and provides the storage, movement and loading sequences to mini-mize the handling of the fuel assemblies.
The Supervisor of Plant Opera-tions is responsible for the safe movement and handling of fuel assemblies according to written plant procedures.
Plant operations personnel trained in the use of fuel handling equipment are used in moving the material and on-site Shift Operating Supervisors are responsible for fuel hatidling operations of their shif t.
Section 12. l. 3. I gives the description of the positions for the Health Physics Supervisor and Radiochemistry Supervisorg'Ihe qualifications of the Health Physics Supervisor and Radiochemistryi Supervisor are given in 4 p pem d, x 'l.
d o a r e. + 11 e key pu snne l tespom G ble, fu % d ung an d m n.%,' <y ed sa e / ve rn A 4 e r e' c4 l s.
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l j, y,3 Procedures All new or temporary employees shall receive a radiation protection orien-tation prior to their assignment of work in the Controlled Access Are,'.
The orientation will include instruction in the Radiation Protection Manual.
Visitors must be escorted within the Controlled Access Area or othe radia-tion and/or contamination areas unless they have completed the required radiation protection orientation.
Radiological safety rules and guidelines are specified in the Arkansas Nuclear One Radiation Protection Manual and associated procedures. Instruc-tions contained in these procedures require that personnel:
1.
Familiarize themselves with radiological safety practices and procedures; 2.
Contact licalth Physics for any additional radiological safety informa-tion they need; 3.
Be signed in on a valid Radiation Work Permit (or Special Work Permit) before working with or around radiation or radioactive materials; 4.
Be aware of proper procedures to follow in an emergency; 5.
Protect themselves and others from overexposure to external radiation;
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6.
Minimize the uptake of radioactive materials; 7.
Prevent the spread of contamination; 8.
Wear assigned personnel monitoring equipment within the plant; 9.
Follow requirements and instructions on radiation work permits;
- 10. Assure themselves that adequate monitoring has been performed prior to starting a job;
- 11. Notify Health Physics of malfunctioning of any radiation protection
. equipment.
- 12. Monitor themselves prior to leaving the Controlled Access or other contaminated areas;
- 13. Utilize time, distance and shielding as practicable to minimize exposure;
- 14. Bag contaminated waste;
- 15. Maintain their exposure as low as practicable;
- 16. Notify the Shift Operating Supervisor and Health Physics as soon as possible of incidents involving radiation or contamination.
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Othcr general radiological safety rules are:
1.
There will be no eating, smoking, drinking or preparation of, food or drink in contaminated areas.
- 2.. No materials or equipment shall be removed from the Controlled Access or other contaminated areas unless released by Health Physics.
3.
The limit for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week exposure to unevaluated mixtures of beta-gamma emitting air particulate activity is 1 x 10-g pCi/cc.
T REQUIRED MATERIALS At present there are no plans to have any radioactive materials onsite that exceed the limits specified below.:
Material Form and Use Possession Limit A.
Any byproduct, As reactor fuel; as sealed As required for source and special sources for reactor start up; reactor operation nuclear material as sealed sources for reactor instrunent and radiation monitoring equipment cali-bration; and as fission detectors B.
Any byproduct, Any form for sample analysis 100 millicuries each source or special of instrument calibration isotope; any by-nucicar material
- P product material 100 milligrams each isotope; any, source
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or special nuclear l
material A C.u Weyf %. GT nte s 4 s aa
,% 5 fru.u u h to I.%o 4 au wwc e-fl Cseces (s-I57 45 a C,% s / r u su eu Y ca l l b m]- f o-A. So u e t s.
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