ML20037B290
| ML20037B290 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 01/29/1975 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Abel J COMMONWEALTH EDISON CO. |
| References | |
| NUDOCS 8009100961 | |
| Download: ML20037B290 (9) | |
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kr. cr.venith icisen Co.pany I I ". t :
..r..i. S. Abel i uclear Liccr.sini Aum ini t.t ra t o'r l
Loilinc Water heccters rest Office Lex 7c7
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Cnicay.o, Illinois 60f.;90 f
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EI1.-2, !4E-19 c6 i t h-2 ',
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A: A result ci the Cec-ission's cont inuity ct tort s to sicplify tbu licensinc, process, we have reviewed the ecnners in shicn specisi nuclear, bypreduct, anc; ecurce raatericls used in cornecticr. sita
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the oreratice of nuclear power facilitics are licensec.
Our revieu disclosed that =cr.y licenses list each itet: separate ly, therepy recuirinp. t license et.endment for aleost eny chcuse in licensec roterials.
Peser applications for liccuse sr.icndr..cnt s m:10 ce recessery if the licensing provisions for these ncteriais scre c.; set forth in the enclosec Standarc Lictnse lorrct li n e lc r u r e.
11
.culctory cuide 1.70.3 "!idditiontl Inf or=atien L diorctivc
..ctericis Saf ety fer buclear rc,ver Pla.nt s" dated lebruary 1k74 (inclosure 2) ident ifies the inforcistion necessary tc seostentiate ti.e r, ore generalized license provision.
C.r objective is to incorporcte the pencraliced provicicn i n t <.,
existing licenset se cr. to reduce the nurber ot' lic(nrirr actient thct are rcquired.
To accomplisn this, we renucct tbst you trcvide the inicrust ion descritaco in the following pararrtph prior to or in ce-junct io:t with the next occasien you hcvc to recucst crendccet to this portion 01 your liccuse.
Lxpe r icr.c c rts shcen thet the need to chenpc pcerestica liraits cuitt citer l
- itco Lt.o i e c t.s h cne CW c h t'n <' c is reeded vere u i c i. c'.
It ec i c t i.e : e c t iL i. i t;. c1 Eclcys i:r tech iretem te, yci -
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cririnals ano t hirty-e,cven aed it iencl copies anc c.welu incluu :
1.
A prope:cd a.cenduer.t te the license conc'itiene r<letinr t c.
I r e e s c r r i e., rod ute limits in the f er:: t rt.N c 5 t ec in Irclonre 1.
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Cornonwealth Edison Company Materials required in excess of the quantities identified in Table 1 of Regulatory Guide 1.70.3 should be specifically identified in your application; 2
Proposed tcchnical specifications and bases for leah testing and surveillance of sealed sources similar to those in the sample provided as Enclosure 3; and I
3.
A revision to your FSAR containing the information described in Regulatory Guide 1.70.3.
Conctonwealth Edison currently holds Byproduct Material License 12-05650-01, as amended, which authorizes various quantitiec and types of byproduct caterials being used in connection with the Dresden Nuclear Power Station.
Furthermore, there are two pending requests for amendment to this license dated December 31, 1974, with a supplement dated January 14, 1975, addressed to Dr. Frank R. Markwell of the Cournission's Materials Branch. The caterials authorized by the above license and the pending requests appear to be used solely in connection with operation of Dresden Units 1, 2 and 3.
Therefore, your application for amendment in the manner suggested in the previous paragraphs of this letter should also include those items currently licensed under the byproduct material license and the pending requests. The materials required in excens of those listed in Table 1 of Regulatory Guide 1.70.3 should be identified separately for each of the Dresden Units 1, 2 and 3.
After Facility Licenses DPP-2, -19 and -25 are amer. dad to include those materials authorized by the byproduct license, consideration will be given to a request for termination of the byproduct material license.
Please advise us of your plans for sub::titting the suggested application for a license amerdment.
Sincerely, Qridect ricm!by Drnts L. L, m Dennic L. Zier.nnn, Chief Opercting Pcacters Dranch E2 Divir:ica of Practor Licensing
Enclosures:
DISTRIBUTION:
PU0'Connor DLZiemann 1.
Standard License Format NRC PDR RDSilver ACRS (16) 2.
Regulatory Guide 1.70.3 Local PDR ORB-2 Reading JBell, MB 3.
Technical Specifications Docket R}'Digg s KRGoller OGC
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Commonwealth Edison Co=pany __
cc w/ enclosures:
John W. Rowe, Esquire Isham, Lincoln & Beale Counselors at Law One First National Plaza Chicago, Illinois 60670 Anthony Z. Roiscan, Esquire Berlin, Roiscan and Kessler 1712 N Street, N. W.
Washington, D. C.
20036 Morris Public Library 604 Liberty Street Morris, Illinois 60451 l
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Enclesure[
- 03IFICATIO:: TO STA :DARD LICI::EE B.
(2) Pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear raterial as reactor fuel, in accordance uith the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemanted and amended; (3)
Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any tine any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed cources for reactor instrunentation and radiation tonitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10 CFR Part 30, to receive, possess and use at any ti=c 100 tillicuries each of any byproduct natorial uithout restriction to chenical or physical forn, for sample analysis or instrument calibration or associated uith radioactively contaninnted apparatus.
(5) Pursuant to the Act and 10 CFR Parts 40 and 70, to receive, possess and use at any time 100 milligrans cach of any source or special nuclear raterial without restriction to chemical or physical fore, for sanple analysis or instrument calibration or associated with radioactively contaminated apparatus.
(6)
Pursuant to the Act and 10 CTR Parts 30 end 70, to possess, but not separate, such byproduct and special nuclear raterials as nay be produced by operation cf the facility.
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F:bruary 1974 U.S. ATOMIC ENERGY CLMMISSISN I
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DIRECTORATE OF REGULATORY STANDARDS
,,crs oi R EG ULATORY GUIDE 1.70.3 ADDITION AL INFORMATION l
RADIOACTIVE MATERIALS SAFETY FOR NUCLEAR POWER PLANTS l
A. INTRODUCTION report as indicated below. Section 12.4 should be added as follows:
In October 1972, the Commission issued ReWsion 1 cf the " Standard Forrnat and Content of Safety Analysis Reports for Nuclear Power Plants."' This document 12.4 Radioactive Materials Safety (FSAR) provides a standard format for the safety analysis reports required by the Commission's regulations and identifies the principalinformation needed by the Regulatory staff 12.4.1 Matenals Safety Programs in order to conduct its safety evaluations.
Describe the program which will be implemented to in its review of recent applications for construction assure the safe storage, handling, and use of seded and unsealed special nudear, source, and byproduct permits and operating licenses, the Regulatory staff has materials. Other sections of the FSAR may be identified information that has often been mtssing from these safety analysis reports. To obtain the information referenced to the degree they are applicable.
needed to perform its evaluation, the staff has had to request this informanen by directmg written questions 12.4.2 Facilities and Equipment to each apphcant. a ne Foreword of the Standard Forma t states: "Any revisions of the Commission's Describe the laboratory facilities and equipment needs for information wir be conveyed to the industry such as hoods, gloveboxes, filters, survey and me.:surin; and the pu'ohe in various ways such as (1) amendments instaments, and monitorin; devices. Other sections et l
to the Standard Format. (2) in the Information Guide the FSAR may be referenced to the degree they rre series, (3) as part of future Safety Guides, er (4) in appbcable.
Pubhc A n n o u n c e rn e nts."
This gu:de identifies information related to radioactive materials safety that has often been miss:rg from the apphcant's safety i
12.4.3 Personnel and Procedures l
analysis report at the operating license stage of review.
The Commission plans to revise the Standard Desnibe the experience and qualifications of the Format within the next year to include this key pusonnel responsible for handlmg and monitoring modification. In the intenm, the information requested the materials.ldentity and summarize the content of the radiation sarety instructions to working persennel here should be induded in safety analysis reports submitted for AEC review.
appropriate tc the eperations to be covered. Other sections of the FSAR may be referenced to the degree B. ADDITION AL INFORMATION they are apphcable.
The additional infer nation requested should be incorporated into Chapter 12 of the safety analysis 12.4.4 Required Materials
' The " Standard For-.at and Content of Safety Arulysis Provide a hsting of isotope, quantity, form, and use Reports for Nuclear Pou er Pants has been des:gr.ated as for all req tired byproduct, source, and special nuclear Regulatory Guide 1.70 materials which exceed the amounts in Table 1.
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Table 1 Mr.;rhi~
Fermtruf Use Posessun Limit A. Any byprot:ct, As reactor fuel; as Amount required for-so.:rce, and special sealed neutron sources reactor operation nucicar t:.a teri_-!
for reactor startup; as sealed sources for calibration of reactor instruments and radiation monitorire, equipment; and as fission detectors B. Any byproduct Any form for sample 100 millicuries each material analysis or instrument isotope calibration C. Any source or Any form for samp'e 100 milligams each s pc cial nucleat analysis or instrument isotope msterial calibtation f u'. '
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9
Encionure 3 Technical Specification Addition Mircellaneous Radioactive Materials Sources
' Surveillance Requirement-Tests for leakage and/or contamination Source Leakage Test shall be perfonced by the licensee or by other persons specifically authorized -
Sneci fica tion by the Conmission or an agreement State.
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""5 Radioactive sources shall be leak tested for contamination.
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d The Icakage test shall be capable of detecting the presence f0C 0u uWe rc t
n of 0.005 microcurie of radioactive material on the test t
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(Il than thirty a
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If the test reveals the presence of' 0.005 microcurie
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age an o or ar a o at g or more of removable contamination, it shall irnacdiately be Q withdrawn from use, decontaminated, and repaired, or be 2.
The periodic leak test required does PP te sea ds ces that are M disposed of in accordance with Commission regulations.
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sources excepted from this test shall Q
be tested for leakage prior to any gThose quantities of by-product material that exceed the use or transfer to another user unicss dquantities listed in 10 CFR 30.71 Schedule. B are to be leak they have been l'eak tested within six months prior to the date of use or M tested in accordance with the schedule shown in Surveillance trans f er.
In the absence of a certificate froa a transferor in-g - +.c",uirements.
All other sources (including alpha emitters) dicating that a test has been made within six months prior to the 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.
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2 Surveillance Requirement (C_on t'd) 3.
Startup sources shall be leak tested prior to and following any repair or maintenance and before being subjected to core flux.
Bases Ingestion or inhalation of source material may give rise to s
total body or organ irradiation. This specification assures that leakage from radioactive material sources does not exceed allowable limits.
In the unlikely event that f
those quantitics of radioactive by-product materials of interest to this speci.fication which are exempt from leakage tes' ting are ingested or inhaled, they represent less than one maximum pemissible body burden for total body 5
irradiation.
The limits for all other sources (including cipha emitters) are based upon 10 CFR 70.39(c) limits for plutonium.
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Reporting Requirements Frequency as per Reculatory Guide 1.15
_0pera tions' Suma ry 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 two years:
s 1.
Test results, in units of microcuries, for leak tests performed pursuant to Specification
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2.
Record of annual physical inventory verifying accountability of sources on record.
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