ML20197H900

Responds to RAI Re Proposed Amends to Ostr Ts.Replacement Pages to Amends Proposed in 971125 Ltr,Encl.Changes to Personnel Shown in Encl Organization Chart of Ostr Ts,Per TS 6.7.c.3,noted

ML20197H900
Person / Time
Site:	Oregon State University
Issue date:	12/19/1997
From:	Dodd B Oregon State University, CORVALLIS, OR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
TAC-MA0200, TAC-MA200, NUDOCS 9801020030
Download: ML20197H900 (7)

Text

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a RADIA11oM CENTER

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9 ORECON STATz Umvenstry 100 Ra&stian eerder. Cervallin. oregon 97331 3903 Telel>une 541737 2341 ras 541737 0480 December 19,1997 U.S. Nuclear Regulatory Commiss;cn Document Control Desk Washington, D.C. 20555

Reference:

Oregon State University TRIGA Reactor (OSTR)

Docket No. 50-243, License No. R-106

Subject:

a) Request for Addition Information (TAC No, MA0200) on Proposed Amendments to OSTR Technical Specifications.

b) Notification of Personnel Change Gentlemen:

The following information is in re;ponse to your request for additional information on proposed amendments to the OSTR Technical Specifications.

1. In updating the title of the Vice Provost for Research, it was our intention that it be corrected in all locations within the Technical Specifications. We wouid therefore like to request that it be changed in Technical Specification 6.1.a as well as in 6.1.b. As stated before, this jcst keeps the Technical Specifications current and does not involve any changes to lines of communication, te reporting channels or to responsibilities.

s 2. In addition to fim previously requested changes to Technical Specification 6.7 we would also like to replace t he word " telegraph" with the word " fax" in both Technical Specification 6.7.a /j and in 6.7.b.l. This merely updates the Technical Specifications w.'th respect to modern '/

communication methods and does not change the information required or its timeliness. [l

3. In the retype of Technical Specification Page 35 there were in fact two periods which were unintentionally omitted.

Attachment A contains the corrected replacement pages should you agree to the amendments proposed in the letter of November 25,1997 and this letter.

In a separate matter, I would like to provide notification of changes to personnel shown in the organization chart ofthe of the OSTR Technical Specifications as required by Technical Specification 6.7.c.3. Oregon State University has announced that the Vice Provost for Research vacancy will be 9001020030 971219 Ill PDR ADOCK 05000243 II, l l',

pg PDft 1,11,, ll ,it ,il1.,1,]!g.'l1,1 1,

i U.S. Nuclear Regulatory Commission Page 2 December 19,1997 filled by Dr. Wilson C. Ilayes. Dr. Ilayes will be starting part-time in January and gradual) increasing his workload at OSU until he is full time on May 1,1998. The Interim Vice Provost for Pescarch, Dr. Richard Scanlan will continue to provide the necessary coverage and overlap in the meantime.

I am also pleased to notify you that we have been successful in recruiting Gary M. Wachs as our new reactor operator. Mr. Wachs is currently undergoing training and is expected to take his Senior Reactor Operator examinations towards the end of February 1998.

!Yours sin ely,

\ W I

h iBrian Dodd, PhD i

Director c: Al Adams, Senior Project hianager, Non-Power Reactors and Decommissioning Projects Directorate, U.S. Nuclear Regulatory Commission, M.S. 0-11-B-20, Washington, D.C.20555 Oregon Department of Energy,625 Marion Street, NE, Salem, Oregon 97310, Attn: David Stewart-Smith Wilson C. Ilayes, Vice Provost for Research Richard A. Scanlan, Interim Vice Provost for Research Stephen E. Binney, Chairman Reactor Operations Committee Jack F. Iligginbotham, Reactor Administrator David S. Pratt, Senior IIcalth Physicist Arthur D. IIall, Reactor Supervisor

9 U.S. Nuclear Regulatory Commission Page 3 December 19,1997 State of Oregon )

) ss County of Benton )

Brian Dodd, being first duly sworn on oath, deposes and says that he has aflixed his signature to the letter above in his offic:al capacity as Director, Oregon State University Radiation Center; that he has signed this letter requesting Technical Specification changes as required by 10 CFR 50.4b(5)(ii); that in accordance with the provisions of 10 CFR 50.30(b), he is attaching this affidavit; that the facts set forth in the letter witlJn are true to his best information and belief.

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@womasa:macSeru. 3 swing, u mtsse masim,mm \Pi Driin Dodd, Director tl Subscribed and sworn before me, a Notesy Public, in and for the County of Benton, State of Oregon, this 19th day of IM66"b(T .A.D.,1997.

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Notary P w dal 9hhi My Cominissi'on Expires

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L-L Attachment A 4

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- 6.~ ADMINISTRATIVE CONTROLS i

6.3 t talANIZAH(E ,

a. The facility chall be under the direct control of the Radiation Center ,

Director or a licensed senior operator designated by the Director to be in direct control. The Radiation Center Director shall be responsible to' Oregon State University's Vice Provost for Research for the safe owation and maintenance of the reactor and-its associated equipment.

Tie Radiation Center Director, or an individual appointed by the Director, shall be responsible for assuring that all operations are ';

conducted in a safe manner and within the limits prescribed by the facility license and the requirements of the Reactor Operations Committee.. The Radiction Center Director shall enforce rules for the protection of personnel against radiation,

b. The safe operation of the OSTR shall be related to the Uciversity ANinistration as shown in the following chart:

J Proeident, Oregon State Univoretty 4

Provost & Executive Vice Proeident l -I I I Vlos President for Rnence end

, Vice Provoet for Reneerch Administration OSU Radiation l - Safety

.cc,o,. R n c.nter .

Reactor

,,e,e,,,no _

l-L l a=*a=

Achidnistrator 0

I Reeotor Supervisor 1

OSTP. Redetion Center Operations Health Physica steff staff Normel administrative reporting channel Techniosi review fas et, communioetiens end eceletanos 30- Amendment No. 16

C o'

4 g, Offsite environmental monitoring surveys.

2 h, Fuel inventories and transfers,

1. Facility radiation and c ptamination surveys.

j. Radiation exposures for all personnel,

k. Updated, corrected, and as built drawings of the facility.

6.7 REPORTING REQUIPIMENTS -

In addition to the requirements of applicable regulations, and in no way substituting therefore, reports shall be made to the NRC as follows:

a. A report within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone or fax to the NRC Operations Center of:

1. Any accidental release of radioactivity above applicable limits in unrestricted areas, whether or not the release resulted in property damage, personal injury, or exposure:

2. Any violation of a safety limit; *

3. Operation with a safety system setting less conservative than speci-fied in Section 2.2. Limiting Safety System Settings:

4. Operation in violation of a Limiting Condition for Operation:

5. Failure of a required reactor or experiment safety system component which could render the system incapable of performing its intended safety function unless th.: failure is discovered during sintentuce tests or periods of mactor shutdown:

6. Any unanticipated or uncontrolled change in reactivity greater than

$1.00:

7. An observed inadequacy in the implementation of either administrative

, or procedural controls, such that the inadequacy could have caused the existence or development of a condition which could result in operation of the reector r,tside the specified safety limits; and

8. A measurable release of fission products from a fuel element.

b. A report within 14 days i writing to the NRC, Document Control Desk.

Washington, D.C.

1. Any accidental release of radioactivity above permissible limits in a

unrestricted areas, whether or not the release resulted in property damaga, personal injury, or exposure; the written report (and, to the 2xtent possible, the preliminery telephone or fax report) shall describe, enalyze, and evaluate safety implications, and outline the corrective measures taken or planned te prevent-reoccurrence of the

. event:

34- Amendment No. 16 I

m .

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• 2. .Those events reported as required by Sections 6.7.a f. through 6.7.a.8.

c. A report within 30 days in writing to the NRC. Document Co': trol Desk, Wushing-ton, D.C.

1. Any significant variation of measured values from a corresponding pre-dicted or previously measured value of safety connected operating charac-teristics occurring during operation of the reactor:

2. Any significant change in the transient or accident analyses as described in the Safety Analysis Report:

3. Any changes in facility org:nization or personnel: and

4. Any observed inadequacies in the implementation of administrative or procedural controls such that the inadequacy causes or could have caused the existence or development of an unsafe condition with regard to reactor operations,

d. A report within 90 days after completion of starting testing of the reactor (in writing to the NRC, Dccument Control Desk, Washington, D.C.) upon receipt of a new facility license, or an awndment to the license authorizing an increase in reactor power level, describing the measured values of the operating conditions or characteristics of the reactor undar the new cenditiens including:

1. An evaluation of facility performance to date in comparison with design '

predictions end specifications,

2. A reassessment of the safety analysis submitted with the license applica-tion in light of measured operating characteristics when such measurements indicate that there may be substantial variance from prior analysis,

e. An annual report by November 1 of each 3 ear (in writing to the NRC, Document Control Desk, Washington, D.C.).

1. A brief summary of operating experience including experiment = performed

)' and changes in facility design, performance characteristics and operating procedures related to reactor safety occurring during the reporting period, and results of surveillance test and inspections.

2. A tabulation showing the energy generated by the reactor (in megawatt-hours), hours reactor was critica's, and the cumulative tctal energy output since initial criticality.

3. The number of emergency shutdowns and inadvertent scrams, including reasons therefcre,

4. Discussion of the major maintenance operations performed during the period, including the effect, if any, on the safety of the oparation of the reactor and the reasons for any corrective maintenance requ' red.

35- Amendment No. 16

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