ML20197C124
| ML20197C124 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos Nuclear Center |
| Issue date: | 11/06/1978 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Darmitzel R GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 7811210002 | |
| Download: ML20197C124 (7) | |
Text
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UNITED STATES 4
" NUCLEAR REGULATORY COMMISSION MW h-h November 6,1978 ]h W l~
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Oocket No. 50-73 Mr. R. W. Darmitzel, Mar.ager Irradiation Processing Product Section General-Electric Company Vallecitos Nuclear Center Post Office Box 460 Pleasanton, California 94566
Dear Mr. Darmitzel:
Your License No. R-33 for your " Nuclear Test Reactor" (NTR) will expire July 21, 1979. Renewal of your license requires an application that demonstrate the NTR can continue to be operated safely and that the reactd ents and systems will be capable of withstanding prolonged use over ferm of the renewal license. General requirements are provided in Title 16 Code of Federal Regulations, (10 CFR) Parts 50, 51, 55 and 73.
Enclosed are specific items that will be reviewed prior to renewal of your license.
You are reminded that 10 CFR 2.109 requires a ticaely filing (at least 30 days prior to expiration of your current license term) of your application.
The data you submitted in response to our letter of November 7,1977, pursuant to the Order to Show Cause of October 24, 1977, is still under review and evaluation. As part of the renewal process, the whole issue of seismic considerations will be reviewed. Therefore, your revised safety analysis should involve any additional information supporting the assurance of safe operation even though a major seismic event occurs.
The foregoing has been provided to assist you in the license renewal process.
Please do not hesitate to contact Steve Ramos (301-492-7435) who has been assigned project manager for your facility.
Sincerely, j
781121b E bert W. Reid, Chief s
Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
License Renewal Review Items cc w/ enclosure: see next page
4 General Electric Company cc w/ enclosure:
Mr. Cunningham General Electric Company Vallecitos Nuclear Center P. O. Box 460 Pleasanton, California 94566
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LICENSE RENEWAL REVIEW ITEMS A.
QLntents'ofApplication 1.
General Infomation (10 CFR 50.33) l Provide applicable infomation delineated in the reference regulation. The following 10 CFR 50.33 paragraphs obtain:
(e)
Include all licenses issued for use on the Vallecitos Nuclear Center (VNC) complex.
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(f) Financial Considerations - The review process to satisfy 10 CFR 50.33(f) requires informatic, that will show that the licensee possesses the funds ne essary to cover estimated operating costs or that there is. reasonable assurance of obtaining the ~ funds for the period of the license renewal plus the estimated costs of pemanently shutting down the facility and maintaining it in a safe condition. To facilitate reviewing the f.inancial aspects, it is requested that the following infomation'be provided in three signed and notarized originals and si< additional copies:
(1) The most recent published annual statement of operations of the VNC.
Indicate, or provide separately, that portion of the budget which clearly delineates the sources of funds to be utilized to cover costs of operation of your reactor facility.
(2) The estimated annual costs to operate the reactor for the additional license renewal period and a certification that amounts designated in your application for renewal of the facility will be included in future budgets.
(3) The estimated costs of permanently shutting down the reactor, a listing of what is included in these costs, the assumptions made in estimating the costs, the type of shutdown contemplated, and the source of funds to cover these costs.
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A' estimate of the annual cost to maintain the (4) n shutdown facilities in-a safe condition.
Indicate what is included in this estimate, assumptions t
made in determining the cost, any interest rates assumed, and the source of funds to cover this in perpetuity.
2.
Filing of Applications Provide applicable information as delineated in 10 CFR 50.30 as follows:
(e) riling Fees - Submit your fee in accordance with 10 CFR 170.12. This article takes precendence over 10 CFR 50.30(e).
A renewal is categorized a Class VI action as defined in 10 CFR 170.22.
(f) Environmental Considerations - Attached is a memorandum,
Environmental Considerations Regarding the Licensing of Research Reactors and Critical Facilities" dated January 28, 1974, from D. Muller to D. Skovholt, that-provides the general environmental impact of research reactors and may be used as a reference in developing an Environmental Impact Appraisal (EIA). As a result of the attached memorandum, it was determined that an Environmental Impact Statement (EIS) is not required for research reactors authorized to operate at 2 MW(t) and less. However, an EIA is i quired; and, therefore, sufficient information must be Nnitted to develop l
the EIA.
3.
Technical Information (10 CFR 50.34)
(a) FSAR - (applicable portions) of 10 CFR 50.34(b)
A complete review of ycur Safety Hazards Report (SAR) will be conducted to ensure no significant safety hazard i
exists. Data should be included to update the SAR with l
regard to natural and unnatural phenomena. This information must use current analysis techniques and information.
Further, a description and analysis of the structures, systems and components of the facility, with emphasis on the operational performance and the ability to function l
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. properly and safely for the term of the license. This is particularly important because the original license was evaluated for a specific term. As some parts have obviously worn and there is some deterioration of the structure, the ability of the facility to operate safely for the requested term is a safety questions (b) 10 CRR 50.34(b)(6) - Applicable portions The following pertains to specific items:
(v) Emergency Planning The plan should contain, but not be limited to, the elements listed in Section IV of Appendix E to 10 CFR Part 50. Attached are draft copies of ANS 15.16 " Standard for Emergency Planning for Research Reactors", and Regulatory Guide 2.XX, " Emergency Planning for Research Reactors". Although in final draft fonn, they are being used by staff reviewers to ensure compliance with Appendix E.
You are therefore requested to use these documents in preparing the emergency plan portion of your application.
(vi) Proposed Technical Specifications (T.S.) in accordance with 10 CFR 50.36).
Attached is a copy of the University of Michigan's technical specifications and a draft copy of ANS 15.18 " Standard For Administrative Controls for Research Reactors". Although there are considerable differences between the NTR and UM's facility, the basic outline and fonnat is that desired for technical specifications.
In the course of license renewal, it is appropriate to upgrade technical specifications and to make them as standard as physical and operational-constraints permit. You are, therefore, requested to use the attached technical specifications and ANS as guides to review your technical specifications.
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The following was the subject of previous correspondence and is provided herein as a reminder for items that-should be included.
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(a) ALARA consideration should be included in the technical specifications, as delineated in 10 CFR 50.36a.
(b) Provision regarding the insertion and irradiation of explosives must be included in the technical specifications or not be handled at all. All research' reactors licensees were advised of this requirement June 1971.
Previous concerns are reiterated in the following:
"An increasing number of programs being performed at research and testing reactor facilities involve the radiography of explosives. The presence and irradiation of explosives in a reactor-facility must be evaluated carefully because of the potential for damage to the reactor. The use of explosives within a reactor facility is considered to be an unreviewed safety question pursuant to Section 50.59 of 10 CFR Part 50 unless such usage has been' reviewed and approved by the Commission.
If you presently receive, or have plans to receive and handle explosives, an evaluation of the consequences of accidental explosions should be made and submitted to the Commission's Division of Operating Reactors. Proposed operating restrictions that provide for safe usage of explosive materials should be submitted for inclusion in your Technical Specifications.
In this context,
" explosives" include all materials that would constitute Class A, Class B and Class C explosives as described in Title'49. Parts 172 and 173 of the Cod.' of Federal Regulations, regarding transporcation of explosives and other dangerous materials.
The Technical Specifications should contain sufficient information to establish operating restrictions; should indicate the maximum quantity of explosives (in pounds of equivalent TNT) allowed in the facility, the form of the explosives, the controls exercised when handling and storing explosives, the cumulative radiation ' exposure limits for explosives, the utilization of explosives within the facility, and the maximum quantity
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., of explosives that could be involved in postulated accidents; and should include an assessment of the probability and the potential consequences of an explosion occurring".
(c) Also attached is one set of Regulatory Guides (2.1-2.5) that pertain to research reactors that should also be used in revising your technical specifications.
(c) Operator Licenses and Requalification Training Program U O CFR Part 55)
(10 CFR 50.34(b)(7) and (8).
(d) Physical Security Plan (10 CFR 50.34(c))
Your physical security plan will be reviewed in accordance with guidance provided in June 1974 (copy attached) and 10 CFR Part 73 changes published since then.
If required, submit six copies of your revised physical security plan (PSP) with your renewal application.
As your PSP will become part of the license and referenced as such in the renewed license, it is further requested that the plan be reconciled into a single document. To facilitate future revisions made in accordance with 10 CFR 50.54(p) and amendments submitted for approval, it is requested that the PSP be submitted in loose-leaf format.
B.
Standards and Regulatory Guides For your information, concomitant to the review of items in A above, all documents will include a perusal to ensure you have included references and use of applicable ANS/ ANSI standards and NRC Regulatory Guides (2.1-2.5) for research reactors.
- Note:
1.
All items from referenced 10 CFR articles not listed above are self-explanatory.
2.
Above subparagraphs are keyed to 10 CFR paragraphs.
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, j Attachments:
1.
Muller /Skovholt Memo did.1/28/74 2.
Draft Copy ANS 15.16 - Emergency Planning 3.
Draft Copy Reg Guide 2.XX - Emergency Planning 4.
University of Michigan Technical Specifications 5.
Regulatory Guides 2.1-2.5 6.
Draft copy ANS 15.18 " Standard for Administrative Controls for Research Reactors" 7.
Physical Security Plan Guidance
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