ML19325D285
| ML19325D285 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 10/06/1989 |
| From: | Swenson W Office of Nuclear Reactor Regulation |
| To: | Fay C WISCONSIN ELECTRIC POWER CO. |
| References | |
| TAC-68862, TAC-68863, NUDOCS 8910230011 | |
| Download: ML19325D285 (2) | |
Text
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octcber 6, 1989 l
Docket No. 50-266 Distribution I
and 50-301 5NETTffD' WSwenson
~
NRC & Local PDRs OGC Mr. C. W. Fay, Vice President GHolahan EJordan Nuclear Power Department JZwolinski BGrimes
)
Wisconsin Electric Power Company PKreutzer ACRS(10) 231 W. Michigan Street, Room 308 PDIII-3 r/f PDIII-3 Gray File Milwaukee, Wisconsin 53201
Dear Mr. Fay:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION CONCERNING NUCLEAR FUEL STORAGE ENRICHMENT AMENDMENT REQUEST (TAC NOS. 68862 AND t
68863)
The NRC staff has completed a preliminary review of your July 6,1988 amendment request concerning ftel storage enrichments for the Point Beach Nuclear Plant, Unit Nos. 1 and 2.
As a result of this preliminary review, we t
have determined that additional information is required in order to complete staff review of the amendment request. Specifically, the NRC staff requests that the licensee respond to staff concerns delineated below:
1.
Describe the corrective actions to be taken if degraded Boraflex specimens or absorber is found in the spent fuel pool. Certain types of corrective actions, e.g. use of poison rods or checkerboard l
loading patterns, could require revised criticality analysis.
l 2.
Do the Boraflex sheets extend to cover the full length of the active l
fuel zone, even after maximum shrinkage due to irradiation? If not, what effect does the resulting gaps have on the criticality analysis?
3.
The radiological consequences of a spent fuel handling accident need to be analyzed at the higher fuel burnup levels planned for the new higher enriched fuel. Provide the results of this analysis.
4.
It is the staff's understanding that your request to utilize an optional axial-zoned core-loading scheme refers to the use of a l
single enrichment throughout the active portion of the fuel assembly with axial blankets of natural (non-enriched) fuel above and below I
the active portion of the fuel assembly.
Please confirm our understanding or provide additional justification.
5.
The requirement:, of 10 CFR 51.52(b) for a detailed analysis of the l
environmental effects of transportation of fuel and wastes to and from the reactor must be satisfied. WEPC0 should either adopt the I
NRC staff statement developed for Shearon Harris (53 FR 30355 as l
corrected by 53 FR 32322) if applicable or WEPC0 should provide its own statement under 10 CFR 51.52(b).
l 89102300J1 891006 PDR ADOCK 05000266 P
i i
Mr. C. W. Fay j In order to maintain our current review schedule, your res)onse is requested prior to November 30, 1989. The information requested in t11s letter affects j
fewer than 10 respondents; therefore, OMB clearance is not required under Pub. L.96-511.
Sincerely,
/s/
i Warren H. Swenson, Project Manager Project Directorate III-3 J
Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation cc: See next page l
l DOCUMENT NAME: 68862/68863 RAI g
Office:
LA/PDIII-3 PMhyy. -
PD/PDIII-3 Surname: PKr utzer WMq'nson/tg JHanpon Date:
g g /89 Jeff/89
/o/4,/89 l
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