ML20154G042
| ML20154G042 | |
| Person / Time | |
|---|---|
| Site: | University of Illinois |
| Issue date: | 10/05/1998 |
| From: | Holm R ILLINOIS, UNIV. OF, URBANA, IL |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20154G045 | List: |
| References | |
| NUDOCS 9810130039 | |
| Download: ML20154G042 (10) | |
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l Radiation Science Laboratorv !
University of Illinois at Urbana-Champaign l N. .
.. Department of Nuclear Engineering ICollege of Engineering - l
_T 214 Nuclear Engineering Laboratory 217-335775S0666 jkq ' 103 South Goodwin Avenue Urbena,IL 61801-2964 217-333-2906 fax ,- 3 l
A&miningrator HaaNh Phvalciet '
Richard L. Holm Mark Kaczor t-holmquiuc.edu m-kaczorquiuc.edu I
October 5,1998 '
Docket No. 50-151 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station PI-137 Washington,DC 20555
SUBJECT:
Technical Specifications in Support of SAFSTOR for the UIUC Nuclear Reactor Laboratory l Please find enclosed the following documents in support of the SAFSTOR option for decontamination and
' decommissioning of the University ofIllinois Nuclear Reactor Laboratory:
1.. Changes to the Facility License in Support of SAFSTOR for the UlUC Nuclear Reactor Laboratory.
- 2. Justifications for License Amendment in Support of SAFSTOR status for the UlUC Nuclear Reactor Laboratory.
- 3. Technical Specifications Changes with Revision Bars in Support of SAFSTOR for the UlUC Nuclear Reactor Laboratory.
- 4. Technical Specifications Changes "To Bc Inserted" in support of S AFSTOR for the UlUC Nuclear Reactor Laboratory.
These documents revise the facility license and Technical Specifications in support of the SAFSTOR status at the University ofIllinois Nuclear Reactor Laboratory. The changes prohibit operation of the reactor, but allow possession of all associated materials until such time that they are able to be shipped for storage. This will be !
further explained and justified in the forthcoming Decommissioning Plan to be submitted in the next few months. j I~ If there are any questions please do not hesitate to contact me.
Sincerely,
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l Richard L. Holm -
Attach. /
f C; Regional Administrator, Region Ill, USNRC p h ,1 e3 9~ l Alexander Adams, Jr., Project Manager, USNRC file l
9810130039 981005 PDR ADOCK 05000151l P PDR( _
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STATE OF ILLINOIS .-
! COUNTY OF CHAMPAIGN l- Richard L. Holm, being first duly sworn on oath, deposes and says that he has aflixed 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 l
1, Title 10 of the Code of Federal Regulations, he is attaching this affidavit \; that the facts set forth in the within letter are true to his best information and belief.
< Y Richard L. Holin Reactor Administrator l
i Subscribed and sworn to before me, a Notary Public, in and for the County of Champaign, State ofIllinois, this /> day of 8#dA . A.D.,1998.
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My Commission Expires l N6tary PublicMIlliitojf(
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l OFFICIAL SEAL i
KATHLEEN M. DYSART NOTARY PUBLIC, STATE OFILLIN0IS WY COMMISSION EXPIRES 8-19-2000, l
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! Changes to the Facility License In Support of SAFSTOR for the UIUC Nuclear Reactor Laboratory l (9/98) 1
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Paragraph 2.A. should be amended to read as follows:
" Pursuant to Section 104c of the Act and Title 10, Chapter I, CFR, Part 50, " Licensing of Production and Utilization Facilities", to possess, use-and-but not to operate the reactor as+ utilization 4acility-in accordance with the procedures and limitations described in the application and in this license;" l The amended version is as follows: l
" Pursuant to Section 104c of the Act and Title 10, Chapter I, CFR, Part 50, " Licensing of Production and Utilization Facilities", to possess, but not to operate the reactor in accordance with the procedures and limitations described in the application and in this license;"
Paragraph 2.B. should be amended as follows:
" Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," to receive, and-possess,-andaise up to 9.6 kilograms of contained uranium-235, of which 7.0 kilograms of contained uranium-235 iswas for use in connection with the operation of the reactor and up to 2.6 kilograms of contained uranium-235 iswas for use in connection with operation of a suberitical assembly in the Bulk Shielding Facility of the reactor; up to 20 grams of the contained uranium-235 is of any enrichment in the form of fission chambers and the balance is contained uranium-235 enriched to less than 20 percent in the isotope uranium-235 in the form of reactor fuel; up to 1.0E-5 grams of plutonium in the form of reactor fuel transferred from Facility Operating License No. R-117; and to possess, but not to separate, such special nuclear material as may have been be-produced by the operation of the facility; and" l The amended version is as follows:
" Pursuant to the Act and 10 CFR Part 70, " Domestic Licensing of Special Nuclear Material," to receive and possess up to 9.6 kilograms of contained uranium-235, of which 7.0 kilograms of contained uranium-235 was for use in connection with the operation of the reactor and up to 2.6 kilograms of contained uranium-235 was for use in connection with operation of a suberitical assembly in the Bulk Shielding Facility of the reactor; up to 20 grams of the contained uranium-235 is of any enrichment in the form of fission chambers and the balance is contained uranium-235 enriched to less than 20 percent in the isotope uranium-235 in the form of reactor fuel; up to 1.0E-5 grams of plutonium in the form of reactor fuel transferred from Facility Operating License No. R-117; and to possess, but not to separate, such special nuclear material as may have been produced by the operation of the facility; and" e
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1 Paragraph 2.C. should be amended as follows:
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" Pursuant to the Act and 10 CFR Part 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material," to receive, atul possess-erduse up to 0.2 curie of byproduct material in the form of components for-the+peration+f a subcritical assembly in the Bulk Shielding Facility of the reactor transferred from Facility Operating License No. R-117; to receive,and possess, userbut not to separate up to 0.5 curie of byproduct material in the form of reactor fuel for4teoperation+f a suberitical assembly in the Bulk Shielding Facility of the reactor transferred from Facility Operating License No. R-117; and to possess, userbut not separate except for l byproduct material produced in experiments, any amount of byproduct material as may have beenbe produced by the operation of the facility."' l The amended version is as follows:
" Pursuant to the Act and 10 CFR Part 30, " Rules of General Applicability to Domestic Licensing of Byproduct Material," to receive and possess up to 0.2 curie of byproduct material in the form of components of a suberitical assembly in the Bulk Shielding l F tility of the reactor transferred from Facility Operating License No. R-117; to
.ive and possess, but not to separate up to 0.5 curie of byproduct material in the
. m of reactor fuel of a suberitical assembly in the Bulk Shielding Facility of the
. ictor transferred from Facility Operating License No. R-117; and to possess, but not !
separate except for byproduct material produced in experiments, any amount of l byproduct material as may have been produced by the operation of the facility."
Paragraph 3.A. should be amended as follows:
" Maximum Power Level The licensee mayshall not operate the reactor.-at-power 4evels-noHo+xceed4500 kilowatts 4 thermal)+nd;-ifHhe-pulseanoderwith4eaetivity4nsertionSmoHotMeeed 4-60%"
The amended version is as follows:
" Maximum Power Level The licensee shall not operate the reactor."
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I Paragraph 3.B. shouki be amended as follows:
" Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 910, are hereby incorporated in the license. The licensee shall operatemaintain the facility in accordance with the Technical Specifications."
l The amended version is as follows:
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" Technical Specifications The Technical Specifications contained in Appendix A, as revised through !
Amendment No.10, are hereby incorporated in the license. The licensee shall i maintain the facility in accordance with the Technical Specifications." i 1
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4 Justifications For License Amendment In Support of SAFSTOR Status for the UIUC Nuclear Reactor Laboratory 9/98 1
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PAGE l JUSTIFICATION AND/OR EXPLANATION FOR CHANGES i e Added title to table of contents
- Corrected title for section 3.9 to include fuel storage for the Bulk Shielding Facility il e Corrected title for section 4.7 to include fuel storage for the Bulk Shielding Facility 17 * (3.7 Objective) Increased objective to include fuel movement since the ventilation system will normally be secured once in SAFSTOR i
. (3.7 Spec (fication/3.7.d) Added that fuel shall not be moved unless the ventilation system is in operation so that in the event of a fuel cladding breach l
the filters will be in service.
19 e (3.9) Changed the title, applicability and objective to include fuel storage in the Bulk Shielding Facility.
e (3.9 Objective) Added requirement for radiation monitoring and poollevel to l objective. l
- (3.9.e) Added specification for an area radiation monitor (ARM) and i l
continuous air monitor (CAM) when pools are being used for fuel storage.
Other technical specification requirements of this type are for reactor operation only. The ARM and CAM may be out of service for up to ten days providing that no fuel handling is performed. This will allow for maintenance and surveillances on the equipment.
l . (3.9.f) Added specification for minimum water level above the fuel elements.
This level is based on experience with fuel elements in storage in the past and verification by direct measurement of the radiation levels that adequate shielding is present.
20 . (3.9 Basis) Ajded justification for minimum water level. This level is based on experience with fuel elements in storage in the past and verification by direct measurement of the radiation levels that adequate shielding is present.
20b e (3.11 Applicability) Changed applicability from TRIGA " core" to " pool" to more accurately reflect that fuel is stored throughout the pool, notjust in the core.
21 * (4.1 Specifications) Deleted the requirement for measurement of the B and C l ring elements annually. This requirement existed due to the higher stresses the elements endured in terms of heat generation during reactor operation. Since the reactor is shutdown this requirement is no longer valid.
22 . (4.2.a,b.d.e) Specifications a, b, d, and e have been deleted since they require
- reactor operation to be performed. Since the reactor will no longer be operated j these sarveillances are both unnecessary and irrelevant.
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- (4.2 Bases) Changed the bases to reflect that the visual inspection of the fuel follower control rods is for deterioration of the cladding, not for operability of l
2 the control rod.
23 * (4.3.d,e) Deleted specifications d and e. Both specifications require reactor
PAGE l JUSTIFICATION AND/OR EXPLANATION FOR CHANGES operation and are only relevant to an operating reactor.
24 . (4.4) Deleted all of section 4.4. The facility is now in support of fuel storage, not reactor operation. There is no longer any issue with heat generation from the fuel in an emergency shutdown situation. The emergency core cooling system is not needed for decay heat from the fuel in storage.
25 . (4.5 Applicability) Added section 3.9 to the applicability of this section since it now requires radiation monitoring equipment.
. (4.5 Specifications) Decreased the requirement for verifying the alarm set points from weekly to monthly. Experience has shown little or no drift in the alarm set points of the radiation monitoring equipment over the past ten years (or more depending on the equipment) making a weekly verification an unnecessary task. The potential for airborne or other changes to radiation levels is also substantially reduced with the reactor shutdown and no other experiments ongoing in the reactor bay that would change radiation levels.
26a . (4.7) Added clarification that the Bulk Shielding Facility is for fuel storage also.
. (4.7 Objective) Added radiation monitoring equipment and pool level to the 4 objective in support of fuel storage. l
. (4.7.d) Modified requirement for inspection of fuel in storage to 10% every J year such that all the fuel gets inspected over a ten year period. This ]
inspection period is based on 38 years of fuel inspections at this facility with no evidence of deterioration of the fuel cladding. Other requirements on water conductivity ensure a pure environment for the fuel to be stored in.
. (4.7.f) Added a requirement to verify the Bulk Shielding Facility poollevel on i a weekly basis. During reactor operations the pool level was checked on a i' daily basis with no problems in changing pool level including those extended periods when the reactor was shutdown and the Bulk Shielding Facility pool level was not required to be checked.
26b . (4.8 Applicability / Specification) Changed the applicability and specification from " core" to " pool" to more accurately reflect the conditions of fuel storage.
30 . (5.4) Deleted section 5.4. The emergency core cooling system is no longer needed since reactor operation has been discontinued.
31 . (6.11 Charf I) Deleted the Operations Supervisor and Operations Staff from administrative chart as these position have ceased to exist with reactor operations discontinued.
32 . (6.1.2.a) Deleted minimum staffing requirements for reactor operation since facility is shutdown.
. (6.1.2.a,b)Added minimum staffing and on-call requirements to reflect those necessary for a shutdown facility. This requirement is similar to what had previously been in the facility Rules and Regulations.
. (6.1.2 a) Added requirements that the Reactor Administrator and Reactor
( l 11ealth Physicist shall meet the requirements from ANSI /ANS-15.4 for a Level
PAGE l JUSTIFICATION AND/OR EXPLANATION FOR CHANGES Two and Level Three individual respectively.
. (6.1.2.b) Added the Campus Radiation Safety Officer to the call list. This individual is on the Nuclear Reactor Committee and is very knowledgeable of the facility even though he does not possess an operator's license.
e (6.1.2.c) Deleted reference to core movements within the core region to make requirement for Senior Reactor Operator presence more inclusive to all fuel or control rod relocations.
33 e (6.2.1.a) Added the Reactor Health Physicist as a voting member of the Nuclear Reactor Committee. This change (the Reactor Health Physicist was previously a non-voting member) reflects the belief that more of the issues before the committee will be radiologically oriented rather than operations.
The requirement that the reactor staff cannot constitute a voting majority remains.
e (6.2.1.a) Deleted the requirement that the remaining members of the committee be chosen from the nuclear engineering faculty. This will allow for a greater breadth of possible sources of individuals to serve on the committee. The i stipulation still remains for a balanced knowledge of reactor safety and regulation.
e (6.2.1.d) Changed the meeting requirement for the Reactor Committee from quarterly to semiannually. Once the facility is in a SAFSTOR status the need for Reactor Committee meetings will diminish. It is believed that a semiannual meeting frequency will be more than adequate to review materials and information. Meetings can be arranged on a more frequent basis if needed with little difficulty.
36 e (6.4) Deleted the reference to an Operations Supervisor since the position no longer exists.
37 e (6.5.a, c, d) Deleted reference to an Operations Supervisor since the position no longer exists.
40 * (6.7.a) Deleted reference to an Operations Supervisor since the position no longer exists.
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(6.8.a) Grammatical correction.
e (6.8.b.3) Deleted reporting requirement for changes in Operations Supervisor since position has been eliminated. Added reporting requirement for change in the Reactor Health Physicist.
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