ML20207E791
| ML20207E791 | |
| Person / Time | |
|---|---|
| Site: | Dow Chemical Company |
| Issue date: | 08/20/1974 |
| From: | Collins P US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Hoyle H DOW CHEMICAL CO. |
| Shared Package | |
| ML20207E796 | List: |
| References | |
| NUDOCS 8701050088 | |
| Download: ML20207E791 (2) | |
Text
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sM, UNITCD STATES TOMIC ENERGY COMMISSION
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wasnincron. o.c. mos4s AUG 2 01974 Docket No. 50-264 Dow Chemical, USA ATTN:
Mr. H. R. Hoyle, Chairman Radiation Safety Committee DIG Chemical Biology Research 1707 Building Midland, Michigan 48640 l
Gentlemen:
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We have reviewed the proposed Dow Research Reactor requalification program for licensed operators and senior operators submitted on March 4, 1974, and'the additional information submitted on July 2, 1974.
Based on our review of the material submitted, we have determined the program meets the requirements of Section 50.54(i-1) of 10 CFR Part 50 and Appendix A of 10 CFR Part 55 provided:
1.
that a licensed individual failing to achieve an overall grade of at least 70% on the annual written examination will be relieved of licensed duties and placed in an accelerated training program until he can achieve a grade of at least 70%.
This criteria clarifies.the wording in the second paragraph, page 3 of your July 2, 1974 submittal.
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2.
that the annual written examinations are similar to the AEC written examinations for licensed individuals.
The program adequately describes the following items.
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I 1.
The lecture series to be administered, including subjects and duration.
2.
The specific manipulations of controls to meet the requirements of Section 3a of Appendix A.
3.
The methods to be employed to assure individual review of design, procedure and license changes.
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. s AUG 2 01974
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4.
The methods to be emoloyed to assure individual review of ab' normal and emergency procedures.
5.
The specific evaluation criteria for determining attendance at a specific lecture, required participation in an accelerated requalification program and other additional training, as applicable.
6.
The records to be maintained to document each individual's i
participation in'the program.
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Sincerely, 1
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f.,p, A Paul F. Collins, Chief Operator Licensing Branch Directorate of Licensing 4
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UNITED STATES E'
NUCLEAR REGULATORY COMMISSION o
3 WAINNGTON, D. C. 20555 1.,.....f July 11,1983 TO ALL NON-POWER REACTOR LICENSEES t
l Gentlemen:
Subject:
Issuance of NRC Form 398 - Personal Qualifications Statement - Licensee (Generic Letter No. 8312A)
- e Generic Letter 83-12, subject as above, dated February 24, 1983 was sent recently to all power and non-power reactor licensees, enclosing NRC Form 398 (1-83). However, both the form and the transmittal letter. appeared to be applicable only to the power reactor connunity.
It was our intent that both types of facilities be included. This generic letter is intended to correct any misconceptions the previous letter may have caused.
Even though Form 398 contains many questions that do not apply to operators
.at non.-power reactors please use that form, completing only those questions that are clearly applicable, and explicitly indicate "not applicable" (NA) in the remainder.
In the set of instructions for completing this form, Item No.12 - TRAINING, is not correct as applied to non-power reactor licensees. As you know, it is currently NRC practice to use the criteria contained in ANSI /ANS-15.4(1977)
N 390 for operators of non-power reactors, not those in ANSI /ANS 3.1 which apply only to connercial power reactors. Therefore, for Item No.12, please follow the guidance provided in ANSI /ANS-15.4(1977). We intend to correct the instructions on this item in future revisions to Form 398.
The remainder of the guidance in Generic Letter (83-12) is applicable to both nt:n-power and power reactor licensees.
You should begin using the new Form 398 within one month of the date of this letter.
Sincerely,
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[ Darrell G. Eisenhut, Director Division of Licensing Enclosure :
NRC Form 398 Personal Qualifications Statement -
License OMB Clearance Number 3150-0090 I
(expires August 31,1985) l MID427-*
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UNITED STATES
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gg jj WASHINGTON, D. C. 20555
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December 13, 1985
'f Docket No. 50-264
'l Mr. C. W. Kocher Reactor Supervisor H&E S/I.H 1602 Building
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Chemical Research Center Dow Chemical Company Midland, Michigan 48674
Dear Mr. Kocher:
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SUBJECT:
RENEWAL OF OPERATING LICENSE R-108 k
This letter is to remind you that the Operating License No. R-108 for the
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Dow Chemical Company research reactor is scheduled to expire on December 20, 1986, and to provide you guidance for preparing your application for a renewal of the license. Title 10 of the Code of Federal Regulations (10 CFR 2.109) allows continued operation under your current license until the L
Nuclear Regulatory Commission (NRC) acts upon an application for renewal I
i provided the application is received at least 30 days prior to the expiration date of your current license.
The NRC considers the renewal of a non-power reactor operating 1.icense to be equivalent to reissuing the license. Therefore, renewal is not merely a routine administrative step, but involves in-depth reviews of all L
documentation related to the facility, an on-site review, and publication L
in the FEDERAL REGISTER of a notice of your request that provides the
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opportunity for public participation, as well as a notice of the results of our review of your application.
p Your renewal application should address the requirements in applicable i
sections of Title 10 of the Code of Federal Regulations, and should demonstrate that the reactor can continue to be operated safely and without adverse impact on the environment or the public.
For the review of your renewal application, the NRC staff will apply the guidance contained in the NRC Division 2 Regulatory Guides for Research Reactors (Enclosure 1) and the industry standards in the American Nuclear Society ANS-15 Series for research reactors.
In order for us to perform an adequate review, you are requested to include, as part of your application, all of the following documentation, in 4
accordance with 10 CFR 50.33 and 50.34:
1.
Updated Safety Analysis Report (SAR)
A complete updated edition of your Safety Analysis Report (SAR) and
-TdDiliical Specifications are required to be submitted with your renewal aplMTEation.
The SAR T ould include information that describes
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C. W. Kocher the facility and all changes made during the license period;- the design bases and limits on its operation; and a safety analysis of the structures, components and systems to ensure that they will,be able to g
continue to perform their intended functions.
Potential and i
reasonable accident scenarios and their consequences should be analyzed using the best current input data and computational techniques, and should be compared, wherever possible, with facility operating experience.
Furthermore, the SAR should include updated information and analyses on demography, meteorology, geology, seismology and other natural and l
unnatural phenomena.
l 2.
Financial Qualifications to Continue Operation [10 CFR 50.33(f)]
This infonnation must show that there is reasonable assurance that you will be able to obtain the funds necessary to cover estimated operating costs for the period of the requested license renewal plus the estimated costs of permanently shutting down the facility and either decomissioning it or maintaining it in a safe condition. To facilitate our review, we request that the following information be provided, appropriately certified:
a.
The most recently published annual financial statement of the 1
Corporation.
Indicate the source of funds utilized to cover costs of operation of the reactor facility, b.
The estimated annual cost to operate the reactor for the requested period of renewal, the underlying assumptions and bases of the estimate and certification that future budgets will I
include these funds, and c.
The estimated costs of eventually shutting down the reactor and safely disposing of it, a listing of what is included in these costs, the assumptions underlying these-estimated costs, the type of shutdown contemplated, and the source of funds to cover these i
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costs.
3.
Environmental Report (10 CFR 51) i Your Environmental Report (ER) should include sufficient operational data, analyses and discussions to provide a substantial basis for NRC j
to develop its environmental assessment (see enclosure for an example of an Environmental Report).
4.
Technical Specifications The content and format for Technical Specifications should be in conformance with ANSI /ANS 15.1-1982, "The Development of Technical o
Specifications for Research Reactors." Because your Technical Specifications are currently in a format no longer being approved by NRC, major changes will be required. Any substantive changes to the
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l C. W. Kocher I
current Technical Specifications should be proposed and justified at the time of the license renewal application so they can be evaluated during the review. Note that in following the ANSI /ANS 15.1-1932 format, bases must be included to support all " specifications."
5 5.
Operator Requalification Program (10 CFR 50.54 (1-1) and 10 CFR 55, Appendix A)
A copy of your current and implemented operator requalification program must be submitted to ensure that it is reviewed with your renewal application and meets current NRC requirements for non-power reactors (guidance contained in ANS 15.4-1978).
6.
Emergency Plan (10 CFR 50.54(q) and (r) and 10 CFR 50, Appendix E)
As your revised Emergency response Plan (ERP), dated February 1984 has been approved by NRC, you need only reference those respective Dow Company and NRC documents. However, if your wish to modify your ERP, any changes must be submitted for NRC review in accordance with the L
above-cited regulations.
7.
Physical Security Plan (10 CFR 73.67)
You have an approved Physical Security Plan on file with NRC which we shall review. Accordingly, you need only reference the license amendment containing that documentation. However, if you wish to modify your Physical Security Plan, changes should be made in accordance with the requirements of 10 CFR 50.54(p) or 10 CFR 50.90.
8.
Filing of Application The requirements for submitting your renewal application and all other formal documentation relating to your license with respect to addressee, notarization, signatory and number of copies are defined in NRR Generic Letter No. 84-18, " Filing of Applications for Licenses and Amendments," from Darrell G. Eisenhut to All Non Power Reactor Licensees, dated July 6, 1984. Please follow the guidance in this letter (Enclosure 2).
l 9.
Fees (10 CFR 170)
In accordance with the regulations in effect at the time of your appli-cation for renewal, prescribed fees will be due and payable for NRC 4
efforts expended.
Recent experience indicates that such effort is likely to amount to approximately 12 professional staff-months.
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- 10. Staff Visit u
As a part of our review of your facility, members of the NRC licensing l
staff will expect to visit your facility for a few days. This visit will be coordinated with you following receipt of your application for l'
renewal.
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C. W. Kocher '!
i for your further guidance in preparing the proper information to be j
included in your license renewal application, we are enclosing a copy of a
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license renewal package recently issued for a reactor facility (UND, ) similar to yours. This includes the staff's Safety Evaluation Reports and Environmental Assessment, and the new license for the reactor.
Upon completion of our review and a favorable evaluation of your faci.lity,
.I similar documents will be issued in conjunction with renewal of your reactor operating license. We emphasize that these enclosures, except for the Technical Specifications, were developed and issued by the staff and P
are provided as examples of the types of findings we must make.
Your documentation must provide the technical and descriptive information that will support our issuance of similar evaluations for your facility.
If you have any questions,
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for your facility, at (301)please' contact Robert Carter, our' project manager I
492-9795.
Sincerely, b-erbert N. Berkow, Director Standardi;ation and Special Project, Directorate Division <f PWR Licensing-B L
Enclosures:
As stated cc: See next page L
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