ML19210B169
| ML19210B169 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/28/1974 |
| From: | US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML19210B166 | List: |
| References | |
| REGGD-01.070.03, REGGD-1.070.03, NUDOCS 7911040098 | |
| Download: ML19210B169 (5) | |
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- REGULATORY GU DE 8,,
DIRECTORATE OF,NEGULATORY STANDAROS g
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REGULATORY GUIDE 1.70.3 d
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' ADDITIONAL IN FORMATION RADIOACTIVE M ATERIALS SAFETY FOR NUCLEAR POWER PLANTS A. INTRODUCTION report as indicated below. Section 12.4 sbo.d.i be addid as followv in October 1972, the Commission issued Revision 1 of the " Standard Format and Content of Saf ety Analysis Reports for Nuclear Power Plants."' Tlus document 12.4 Radioactive Materials Safety il ulu provides a standard format for the safety analysis reports rcquired by the Commi>sion's regulations and identifies the principalinformation needed by the Regulatory staff 12.4.1 Materials Safety Programs in order to conduct its safety evatustions.
Describe the program which wiil be imp'.,m d to in its review of recent applic.aans for construction assure the safe simare. handhn;. and uw a n
! rJ unsealed special nuclear. sour e.
ai.d hie
'm-permits and operating licenses, the Reculatory staff has identified information that has often b'cen missing from nuterials. Othe: scettons of the 15\\R nm be these safety analysis reports. To obtain the infomiation referenced to the degree they are appheabl needed to perform its evaluation the staff has had to request this infurnutsun by directing written questions 12.4.2 Facilities sed Equipment to each applicant. The Foreword of the Standard Format states: "Any revisions of the Commission's Describe the laboratory facdities and eqm~acnt needs for information will be conveyed to the industr>
such as hoods. ghveboxes, fiber. survev and re-r -
and the public in various ways such as (1) smendments instruments. and momtoring devieet Other v te or to the Stsndard Format. (2) in the Information Guide the FSAR may be referenced to the degree the are series. (3) as part of future Safety Guides.-or (4) in applicable.
Public A n no u n ce me nts."
This guide identifies information related to radioactive materials safety that has often been missing from the applicant's safety 12.4.3 Personnel and Procedures analysis report at the operating license stage of review.
Describe the experience and qualifiestions of the The Commission plans to revise the Standard key personnel responsible for handling and monitorme Form:tt within the next year to include this the matesists.ldentify and summarae the content a: ti e modifiestion. In the interim. the information requested radiation safety instructions to working persennel here shoubt be included in safety snalysis reports appropriste to the operations to be covered. Otner submitted for AEC review.
sections of the FSAR nuy be referenced to the degree they are applicable.
B. ADDITIONALINFORMATION The additional information requested should be 12.4.4 Requ. d Materists ur Incorporated into Chapter 12 of the safety analysis Provide a listing of isotope. quantity, form.and use
- The " Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants" has been deugnated as for all required byproduct, source, and specul nu", fear Regulatory Guide 1.70.
materials which exceed the amounts m Table 1.
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.a 79110400 p
s Table 1 Material Ft.,em and Use Po:.e.s.on L,m,y A. Any byproduct, As reactor fuel; as Amount requireil fi r source, and special scaled neutron suurecs reacios operation nuclear material for reactor startup; as scaled sources for calibration of reactor
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_c c fission detectors B. Any byproduct Any form for' sample 100 millicuries each material analysis or frutrument isotope calibration C..Any source or Any form for sample 100 milligrams each special nuclear analysis or instrument isotope material calibration 1537 002 1.70.3 2
e Technical Specification Addition MisceklaneousRadioactiveMaterialsSources Surveillance Requirement
- Source Leakage Test Tests for leakage and/or contamination shall be performed by the licensee or g
Specification by other persons specifically authorized W
by the Comission or an agreement State, as follows:
Radioactive sources shall be leak tested for contamination, 1.
The leakage test shall be capable of detecting the presence fac 0u ce jec t cr lux cn I
of 0.005 microcurie of radioactive material on the test fl e
t 11 d o n t a h"t rt a
sample.
If the test reveals the presence of 0.005 microcurie
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i este or more of removable contamination, it shall imediately be fU r
a a
n s no e,
mn withdrawn from use, decontaminated, and repaired, or be 2.
The periodic leak test required doe.
l disposed of in accordance with Comission regulations.
{ ore d ot gue The sources / excepted from this test shall g
Those quantities of by-product material that exceed the be tested for leakage prior to any use or transfer to another user unless L'
quantities listed in 10 CFR 30.71 Schedule B are to be leak they have been leak tested within six C7 months prior to the date of use or tested in accordance with the schedule shown in Surveillance transfer.
In the absence of a certificate from a transferor in-c; c-Requirements.
All other sources (including alpha emitters) dicating that a test has been made within six months prior to the t,a containing greater than 0.1 microcuries are also to be leak transfer, scaled sources shall not be put into use until tested.-
tested in accordance with the Surveillance Requirements.
2 Surveillance Requirement (Cont'd) 3.
Startup sources shall be leak tested prior to and following any repair or maintenance and before being subjected to core flux.
O Bases Ingestion or inhalation of source material may give rise to total body or organ irradiation. This specification assures that leakage from radioactive material sources does not exceed allowable limits.
In the unlikely event. hat t
those quantities of radioactive by-product materials of interest to this specification which are exempt from leakage testing are ingested or inhaled, they represent less than llh one maximum permissible body burden for total body
[3' irradiation. The limits for all other sources (including co alpha emitters) are based upon 10 CFR 70.39(c) limits for
'<J c:3 plutonium.
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3 Reporting Requirements Frequency as per Regulatory Guide 1.16 Operations Summary Results of required leak tests performed on sources if the tests reveal the presence of 0.005 microcurie or more of. removable contamination Records Retention A complete inventory of radioactive materials in possession shall be maintained current at all times.
Records required' to be maintained for five years:
1.
Test results, in units of microcuries, for Teak tests performed pursuant to Specification 2.
Record of annual physical inventory verifying accountability of sources on record.
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