ML19326C269
| ML19326C269 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/24/1975 |
| From: | Ziemann D Office of Nuclear Reactor Regulation |
| To: | Phillips J ARKANSAS POWER & LIGHT CO. |
| Shared Package | |
| ML19326C270 | List: |
| References | |
| NUDOCS 8004220835 | |
| Download: ML19326C269 (3) | |
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E:. 2:k IHIS DOCUMENT CONTAINS j Arkanscs'Fower & Light Cocpeny AT11!:
Er. D. Plyillips P00R QUAUTY PAGES
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g Senior Vice President
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Fredcetion, 'Iransmiss ion.
E cnd Engineerin, Sixth and Fine Streets d
Fine bluff, Arkeness 71601
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License to:
LFR-51 Facility:
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p As a result of. the Cc;=niscica's conticuing ef forts to siraplify the licensing process, we have reviewed the ectners in uhico speciel
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nuclear, bypredt'et, anc source snaterials used in connection with p =...
the operation of nuclear power facilities are licensed.
Our review 0
disclosed that tany licenses list each iten separr.tcly, thereby requirirg's license arcedrent for almost any chcngc in licensed ratericls.
Fcuer applict:ticas for licccse scendnents would bc necctscry if the licenting provisions.for these ceterials were on cet torth in the enclosed Etenderd License Format (1.nclosure 1).
i l'erulatory Cuide 1.70.3 "/.dditional inferr.ation Eadioactive L
Deterinic Eatety for Kuclear Power Plants" dated Ecbruary 1974 f =Ej (tnclosure 2) identifics the iniorestion necessary to substcntiate p
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q Gur ot>jective is to incorporate the rencralized provisicn inte existir.c licenses so ac to reduce the number of licensin;; ections c
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To acecr.plish this, we recyest that you
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request crer ; < en t to this pcrtion of your license.
Experience has rhevn that the need to cbc9pe possession liaits quito citen crises unexpectedly ano the chsn; e is needed very quickly, lo avoic the possibility of deleys in such inctccces, you ccy vien
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to crend ycur license provisiens ceparately r.nd in cdvcnce of TI any specific necd.
Your' application r,bould bc sutnitted uith three sinned ar.d notericcd p:.
oririncle and' thirty-seven cecitional copies cnd should incitcc:
- 1. - A proposed ceer.ccent to the fict.nse conditicns relating te
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possession ar'd use linits in thc format suppested in 1.nclosure 1.
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Arkansas Fower & Light Company JAN i s 1975
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haterials required in excess of the quantities identified in Table 1 of Regulatory Guide 1.70.3 should t,e specifically
,55 identified in your application;
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2.
Proposed technical specifications and bases for leak testing
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and surveillance of sealed sources similar to those in the sample provided as Ecclosure 3; and
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A revision to your FSAR containing the information described in Eegulatory Guide 1.70.3.
Please advise ut of your plans for submitting the suggested application for a license a:endment.
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Sincerely,
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- Origin:a si.;.%.'s by ihe'r.nis L.21c. taxa Dennis L. Ziemann, Chief Operating Reactors Branch #2 Division of heactor Licensing
Enclosures:
DISTRIBUTION g
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Standard License Format AEC PDR 2.
Refulatory Guide 1.70.3 Local PDR 3.
'lechnical Specifications Docket KRGoller cc e/ enclosures:
TJCarter Sec r. ext page FDAnderson ORB #2 Reading RMDiggs OGC R0 (3)
DLZiemann ACRS (16)
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Arkansas Power & Light Company JAN 2 41975 cc w/ enclosures:
Horace Jewell Horace, Holms & Jewell 1550 Tower Building Littie Rock, Arkansas 72201 Mr. William Cavanaugh, III Production Department
.st Office Box 551 Little Rock, Arkansas 72203 Arkansas Polytechnic College Russellville, Arkansas 72801 e
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ENCLOSIiRE 1 U.S. ATOMIC ENERGY COMMISSION R EGU Ln TO RV G.C B DE DIRECTORATE OF REGULATORY STANDARDS Fis o REGULATORY GUIDE 1.70.3 ADDITIONAL INFORMATION
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RADIOACTIVE MATERIALS SAFETY FOR NUCLEAR POWER PLANTS A. INTRODUCTION report as indicated below. Section 12.4 should be added as follows:
In October 1972, the Commission issued Revision 1 of the " Standard Format and Content of Safety Analysis 1
Reports for Nuclear Power Plants."' This document provides a standard format for the safety analysis reports 12.4 Radioactive Materials Safety (FSAR) required by the Commission's regulations and identifies the principalinformation needed by the Regulatory staff 12.4.1 Materials Safety Programs in order to conduct its safety evaluations.
Describe the program whien will be implemented to In its review of recent applications for construction assure the safe storage, handling, and use of sealed and permits and operating licenses, the Regulatory staff has unsealed special nuclear, source, and byproduct identified information that has often been missing from materials. Other sections of the FSAR may be 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 information by directing written questions 12.4.2 Facilities and Equipment to each applicant. The Foreword of the Standard Format states: "Any revisions of the Commission's Describe the laboratory facilities and equipment needs for information will be conveyed to the industry such as hoods, gloveboxes, litters, survey and measurine and the pu'olic in various ways such as (1) amendments
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to the Standard Format, (2) in the Information Guide nstruments, and monitoring devices. Other sections of series, (3) as part of future Safety Guides, or (4) in the FSAR may be referenced to the degree they are applicable
- Public A nno un ce me nts."
This guide identifies information related to radioactive materials safety that has often been missing from the applicant's safety 1
P d W We analysis report at the operating license stage of review.
The Commission plans to revise the Standard Describe the experience and qualifications of the Format within the next year to include this key personnel responsible for handling and monitoring modification. In the interim, the information requested the materials.ldentify and summarize the content of the radiation safety instructions to working personnel here should be included in safety analysis reports submitted for AEC review.
appropriate to the operations to be covered. Other sections of the FSAR may be referenced to the degree
- 8. ADDITIONALINFORf.1ATION they are applicable.
'Ihe additional information requested should be incorporated into Chapter 12 of the safety analysis 12.4.4 Required Materials
- The " Standard Forrnat and Content of Safety Analysis Provide a listing of isotope, quantity, form, and use Reports for Nuclear Power Plants" has been desigr.ated as Resutatory Guide 1.70.
y USAEC REGUI.AToRY CUIDES sa
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