ML20203C109

Forwards Response to RAI Dtd 990127 Re Univ of Il Advanced Triga Reactor Facility

ML20203C109
Person / Time
Site:	University of Illinois
Issue date:	02/03/1999
From:	Holm R ILLINOIS, UNIV. OF, URBANA, IL
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9902110203
Download: ML20203C109 (8)

Text

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Radiation Science Laboratory UnivCrsity of Illinois at Urt>ana-Champaign Departrnent of Nuclear Engineering / College of Engineering K j.. s..

[h-- 214 Nuclear Engineering Laboratory 217-333-77550866

[b$ef 103 South Goodwin Avenue 217-333-2906 fax .

• W//s'- ' Urbana,IL 61801 2984 ,

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Aeninistator HeaNh Phvsicist

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Rchard L. Holrn r-holmquiuc.edu Mark Kaczor m-kactorQuluc.edu g

February 3,1999 Docket No. 50-151 Document Control Desk U.S. Nuclear Regulatory Commission l Washington,DC 20555 i l

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Dear Sir,

i Please find enclosed response to the Request for Additional Information (TAC NO. MA4177) dated January 27,1999. j i

If there are any questions please do not hesitate to contact me. l Sincerely,  ;

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Richard L. Holm Reactor Administrator C: A. Adams Regional Administrator, USNRC, Region III file l  !

[AG2O f 9902110203 990203 I PDR ADOCK 05000151 4 P .. PDR _j i

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a STATE OF ILLINOIS' COUNTY OF CHAMPAIGN Richard L. Holm, being first duly sworn on oath, deposes and'says that he has affixed his  ;

signature to the letter above in his official capacity as Reactor Administrator, University of -  ;

Illinois Nuclear Reactor Laboratory \; that in accordance with the provisions of Part 50, Chapter  !

1, Title 10 of the Code of Federal Regulations, he is attaching this affidavit \; that the facts set j forth in the within letter are true to his best information and belief. i I

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Richard L. Holin  !

Reactor Administrator I I

i Sub' scribed and sworn to before me, a Notary Public, in and for the County of Champaign, State ofIllinois, this ddday of 64o m .A.D.,1999.

O b, n s Atl- S'16 r)Cni)

No(ary Public ofIlliny(s My Commission Expires i

OFFICIAL SEAL KATHLEEN M. DYSART i

' NOTARY PUBUC,8 TATE OFILUNOIS l

WY C0thilS810N EXPIRES 8-10-2000 :

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Response to Request for Additional Information (TAC NO.

MA4177); Dated January 27,1999 University of Illinois Advanced TRIGA Reactor l l Facility License No. R-115 Docket No. 50-151  ;

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1. TS 4.7 d. . Your proposed TS refers to fuel element storage in the suberitical assembly, wet

, storage racks and Bulk Shielding Facility. To match the wording used in TS 3.9, would it-be simpler to say fuel element storage in the Bulk Shielding Facility and TRIGA pool?

Please explain the purpose of moving fuel elements to "other storage."

Appropriate changes were made to 4.7d, please see attached sheets. Thepurpose of moving elements to "other storage" would be to isolate a leaking element or minimize corrosion of thefuel cladding in the event that the conductivity of the pool should be excessive.

2. TS 4.7 f. This TS refers to checking pool level in the Bulk Shielding Facility. Should this TS also refer to the TRIGA pool when is is used for fuel storage?

Appropriate changes were made to 4.7f, please see attached sheets.

3. TS 6.2.1 c. This TS refers to reactor operating staff. Please propose wording that reflects the permanent shutdown status of tim facility.

Appropriate changes were made to 6.2.1 c, please see attached sheets.

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- l 4.7 Subcritical Experia=4 and Fuel Storaec Using the Bulk Shieldinn Facility  ;

.Anolicability -

' his specification applies to the surveillance requirements associated with the subcritical assembly and storage i offuel elements in the bulk shielding facility. ]

Obiective j q

To ensure safe operata of the subcritical assemblyr, to ensure that the radiation monitoring equipment is  ;

operating properly, and that the pool level is maintainedfor radiation protection. l 1

Spopification a) De reactivity worth of the control rod shall be determined annually (interval not to exceed fifteen months).

He surveillance may be deferred indefinitely when the subcritical assembly is not being utilized, but shall be the first operation performed when the subcritical assembly is to be operated, b) Control rod drop time shall be determmed annually (interval not to exceed fifteen months). %e drop time from the fully withdrawn to 90 percent of full reactivity inserta shall be less than one second. He surveillance may be deferred indefinitely when the suberitical ast,ambly is not being utilized, but shall be performed prior to operation of the assembly.

c) De radiation monitor utilized for a high radiation signal scram shall be calibrated and verified operable annually (interval not to exceed fifteen months). We surveillance may be deferred indefinitely when the i suberitical assembly is not being utilized, but shall be performed prior to operation of the assembly.  !

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d) Approximately 210 % ofthe fuel elements in the = bed!=1 =x;ityBulk Shielding Facility or TRIGA

= pool, shall be visually inspected annually for sny indication of deterioration or distortion (interval not to ~

exceed fifteen months) such that all of the elements ir. $c =bedi=! =n.;bly are inspected over a Aveten year period (interval not to exceed Aveten and one half years). If any indication of deterioration or distortion i

' is noted the element shall be removed frenumee to other storage and all elements in the Bulk Shielding Facility shall be inspected.within one week Other storage shall be any other approvedfuel storage area at  !

the Nuclear Reactor Laboratory.:

e) De manual and high radiation scrams shall be verified operable daily prior to operation of the suberitical assembly. His specification is only applicable on days when the subcritical assembly is to be operated.

f) The Bulk Shielding Facilitypoollevel and TRIGA poollevel shall be checked on a weekly (not to exceed ten days) basis when usedforfuel storage.

Basis ne reactivity worth is measured to assure that control of the subcritical assembly can be maintained. He control rod drop time verifies the scram capability of the control rod. Calibration and verification of the operability of the radiation monitor verifies the scram capability of the monitor. He visual inspection of the fuel elements specified had bem shown to be adequate based on prior experience with a lack of fuel deterioration over time.

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" -26a-f0.7 Shritical Experi==* and Fuel Storane Usina the Bulk hm- Facility

.Anolicability q I

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! . His specification applies to the surveillance requirements associated with the suberitical assembly and storage l

, . of fuel elements in the bulk shielding facility. )

i L Obiective j l

To ensure safe operation of the suberitical assembly, to ensure that the radiation monitoring equipment is

, operating properly, and that the pool level is maintained for radiation protectim. .

l Specification a) De reactivity worth of the control rod shall be determmed annually (interval not to exceed fifteen months).

He surveillance may be deferred indefinitely when the subcritical assembly is not being utilized, but shall be the first operatim performed when the suberitical assembly is to be operated. ,

I b) Control rod drop time shall be determined annually (interval not to exceed fifteen months). He drop time - )

i from the fully withdrawn to 90 percent of full reactivity insertson shall be less than one second. %e surveillance may be deferred mdefinitely when the subcritical assembly is not being utilized, but shall be l performed prior to operation of the assembly.  !

- c) He radiation monitor utilized for a high radiation signal scram shall be calibrated and verified operable l g annually (interval not to exceed fifteen months). He surveillance may be deferred indefinitely when the j l suberitical assembly is not being utilized, but shall be performed prior to operation of the assembly.

i d) Approxunately 10 % of the fuel elements in the Bulk Shielding Facility or TRIGA pool, shall be visually l inspected annually for any indication of deterioration or distortion (interval not to exceed fifteen months) {

such that all of the elements are inspected over a ten year period (interval not to exceed ten and one half ')

years). If any indication of deterioration or distortion is noted the element shall be removed to other storage and all elements in the Bulk Shielding Facility shall be inspected within one week. Other storage shall be any other approved fuel storage area at the Nuclear Reactor Laboratory.

e) ne manual and high radiation scrams shall be verified operable daily prior to operation of the suberitical assembly. His specification is only applicable on days when the suberitical assembly is to be operated.

~ f) He Bulk Shielding Facility pool level and TRIGA pool level shall be checked on a weekly (not to exceed ten days) basis when used for fuel storage.

Basis

! he reactivity worth is measured to assure that control ofthe subcritical assembly can be maintained. De control rod drop time verifies the scram capability of the control rod. Calibration and verification of the

(! operability of the radiation monitor verifies the scram capability of the monitor. He visual inspection of the fuel elements specified had been shown to be adequate based on prior experience with a lack of fuel deterioration over time, c

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t 6.2 Review and Audit .

6.2.1 Charter and Rules ,

a, ne Reactor Committee shall be wiyosed of at least five voting members, one of whom shall be a Heakh .

Physicist designated by the campus Radiation Safety Officer for the University, and one whom shall be the ,

Reactor Admmistrator, and one whom shall be the Reactor Health Physicist. %reeThe remaining  !

members shall be appomted by the Head of the Department of Nuclear Engineering, ehesen hem the f:n&y of th:k:: 'h;i.uch; ;o as to maintain a balanced knowledge of reactor safety and regulation.  ;

""r " sect ".:21 Syib: i:1! b: : := eming .._..Sc.  ;

b. He Reador Committee shall have a wntten statement defining such matters as the authority ofthe l comnuttee, the subjects within its purview, and other such admmistrative provisions as are required for the .

I effective functioning of the Reador CammW= Minutes of all meetings of the Reactor Cammhaa shall be kept.

j c.' A quorum of the Reador Ownminee shall be a majority of not less than one half of the members and the .j '

L .l reactor operateg-staff shall not consttute a voting majority.

d. The Reactor Cammi*aa shall meet at least quavterlysemiannually not to crceednine months -with-the j l '

i' inte=15;:c.;;.. ==thg:::: to exc=d 5 ==th::.'

i 6.2.2 Review Function  ;

The review function of the Comnuttee shall include, but is not linuted to the followmg a.' Determination that proposed changes in equipment, systems, tests, experiments, or procedures do not involve l an unreviewed safety question. .;

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b. All new procedures and major revisions thereto having safety significance, proposed changes in reactor facility equipment, or systems having safety significance.  ;

c. All new experiments or classes of experiments for determination that an unreviewed safety question does not  ;

exist.

d. Proposed changes in the technical specifications or license.

e. Violations of technical specifications or license.

f. Operating abnormalities having safety significance.

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. g. Reportable occurrences as listed in 6.8.

h.' Audit reports.

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! A wntten report or minutes of the fmdings and recommendations of the Committee shall be submitted to the Head,

Department of Nuclear Engineering; and the Reactor Committee numbers in a timely manner after each meeting.

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• l 6.2 Review and Audit

, 6.2.} Charter a_n4 Rules

a. He Reactor Committee shall be composed of at least five voting members, one of whom shall be a Heahh Physicist designated by the campus Radiation Safety Officer for the University, one whom shall be the Reactor Administrator, and one whom shall be the Reactor Heahh Physicist. %e remaining members shall be appointed by the Head of the Department of Nuclear Engineering, so as to maintain a balanced knowledge of reactor safety and regulation,

b. He Reactor Commi*aa shall have a wntien statement defining such matters as the authority of the committee, the subjects within its purview, and other such administrative provisions as are required for the effective functioning of the Reactor Committee Minutes of all meetings of the Reactor Committee shall be kept.

c. A quomm of the Reactor Comnuttee shall be a majority of not less than one half of the members and the reactor staff shall not constitute a voting majority.

- d. He Reactor Comnuttee shall meet at least semiannually not to exceed nine months 6.2.2 Review Function ne review function of the Committee shall include, but is not limited to the following:

a. Determination that proposed changes in equipment, systems, tests, experiments, or procedures do not involve an unreviewed safety question.

b. All new procedures and major revisions thereto having safety significance, proposed changes in reactor facility equipment, or systems having safety significance.

c. All new experiments or classes of experiments for determination that an unreviewed safety question does not exist.

d. Proposed changes in the technical specifications or license,

e. Violations of technical specifications or license.

f. Operating abnormalities having safety significance.

g. Reportable occurrences as listed in 6.8.

h. Audit reports.

A written report or minutes of the fmdings and recommendations of the Committee shall be submitted to the Head, Department of Nuclear Engineering, and the Reactor Comnuttee members in a timely manner after each meeting.

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