ML19225C853
| ML19225C853 | |
| Person / Time | |
|---|---|
| Site: | Washington State University |
| Issue date: | 07/02/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19225C851 | List: |
| References | |
| NUDOCS 7908020603 | |
| Download: ML19225C853 (3) | |
Text
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UNITED STATES i
NUCLEAR REGULATORY COMMISSION y
y;j W ASWNGTON. D C. 20555 SAFETY EVALUATION BY THE OFFILE OF NUCLEAR REACTOR REGtJLATION SUPPORTING MENDMENT NO. 9 TO FACILITY LICENSE NO. R-76 WASHINGTON STATE UNIVERSITY DCCKET Mo 50-27 Introduction 15, 1978, supplemented by letter dated February 13, By letter dated August 1979, Washington State University (the licensee) recuested License No. R-76 be amended to allow possession and use of 25 kilograms (kg) of contained Uranium-235 (U-235). Currently, this license allows the possession of 13 9.g of U-235.
The request defines the proposed maximum total authorized special nuclear material (SNM) exempt and non exempt categorized according to the type of fuel and percent enrichment.
The request also would change the' Technical Spedification (TS) in the area of reactivity limitations.
Discussion The current TS authorizes the operation of the reactor with a core configuration ccmposed of standard TRIGA fuel, FLIP TRIGA fuel or conDination thereof (mixed The licensee has pro-core). The present configuration is w!tn a mixed core.
posed to add in the near future 5.6 kg of U-235 FLIP fuel (enricned at 70%),
5.5 kg of U-235 enricned below 20% at a later date, and 5 kg of U-235 enricned The present possession limits are inadequate to 20t or greater at a later date.
to cermit receipt of tne proposed additional fuel and to retain the fuel to ce replaced until it can be discosed of.
The licensee's proposed chance to the TS in the area of reactivity limitaticns would specify tne shutdown margin be 0.50 dollars or greater with the hichest wortn control element and the regulatory element (if not scramable) fully Tne current TS specify the shutdown margin be 0.50 dollars or creater witn the transient control element and the regulating element (if not wi tndr awn.
scrrrabie) fully u tncrawn.
Evaluaticn The reactor pool at ' Washington State University is 31 feet long by 15 feet wide The pool is divided into two sections by a concrete dam with and 25 feet oeep.
The rear section of the pool is used fcr fuel an integral aluminum gate.The storage racks are designed witn sufficient space available element storage.
4 ;0 013 7908020 60 3 p
.. - in the pool to acconcodate both the proposed FLIP fuel and any irradiated Storage space is provided in racks constructed fuel removed from the core.
in such a way as to assure the stored array will not exceed a k effective value of.8 and in the case of irradiated fuel to assure that the required convective cooling is alsc available.
Requirements to assure that these conditions are met are centained in the TS.
esed increase in total amount af U-2.5 at this facility wou'd not The prw invcive any change in core reactivity since excess core reactivity ir 1imited by the TS.
The receipt, storage and use of the proposed additional U-235 would not involve a safety consideration not previously addressed and does not reduce the margin of safety previously established in the TS for the use of nis fuel and for the k effectise of 0.8.
Af ter reviewing the factors involved in this request we conclude that the proposed additional SNM would not increase the safeguard risk asscciated with the facility and therefore, is ccceptable. We conclude that the proposed authorized SNM is within the level of protection afforded by the licensee's approved security plan.
We conclude that the proposed change, modified by discussions with the licensee, relating to the scecificity of the authorized SNM appropriately defines tne maximum tetal authorize ~d SNM, the maximum SNM exempt and the We conclude that this is acc':ptable to acccmmodate maximum SNM non exempt.
the proposed regulation 10 CFR Part 73.47 and t.he objee.tives of the Nonpro-liferation Act of March 10, 1978.
The proposed change to -the TS in the area of reactivity limitations is more conservative and changes the wording to be consistent witn actual practice.
We conclude this wculd not reduce the margin of safety and therefore is acceptacle.
In summary, the orcposed amencment (1) does not involve any reduction in tne level of safety of One facility, (2) does not increase the safegt ard risxs. associatec witn the facility, and (3) provides tne spec'ficity on maximum SNM authorized Oc accommcdate the prcoosed regulation 10 CFR Par:
73.47 and tie Ncncroliferation Act of Ma'ch 10, 1978, and, therefore, is acceptable.
Environmental Consideration We have detemined that this amencment will not result in any significant environmental imcact and that it does not constitute a major Ccmmission the human environment. We action significantly affecting the cuality 0 have also detemined that this action is not one cf those covered by 10 CFR s51.5(a) or (b). Having made :nese determinations, we have further pursuant to 10 CFR 551.5(d)(4), an environmental impac concluded tna t, statement or environmental impact aporaisal and negative declaration need not be prepared in connection witn issuance of this amencment.
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'n'e have concluded, based on the considerat: ens discussed above, that:
(1) because the amendment dces not involve a significant increase in tne probability or consecuences of accidents previcusly consicered and does nct involve a sicnificant decrease in a safety margin, the arendment does not involve a significant ha:ards consiceration, (2)
- nere is reasonable assurance that the health and safety of the public will not be endangered by operation in tne proccsed manner, and (3) such activities will be conducted in comoliance with the Commissien's regulations and the issuance of tnis amerdment will not be inimical to the common defense and security or to the health and safety of the public.
Catec: July 2, 1979 1
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