ML20155G354
| ML20155G354 | |
| Person / Time | |
|---|---|
| Site: | 07003018 |
| Issue date: | 10/07/1988 |
| From: | Bidinger G, Mccaughey D NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | |
| Shared Package | |
| ML20155G338 | List: |
| References | |
| NUDOCS 8810140216 | |
| Download: ML20155G354 (2) | |
Text
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OCT 7 1988 DOCKET NO:
70-3018 LICENSEE:
Houston Lighting A Power Company (HL&P)
FACILITY:
South Texas Projtct Electric Generating Station, Unit 2
SUBJECT:
SAFETY EVALUATION REPORT, RE AMENDMENT TO AUTHORIZE NEW FUEL i
STORAGE IN SPENT FUEL RACKS
Background
on August 30, 1988, HL&P was issued Materials License No. SNM-1983 which authorized the receipt, possession, inspection, and storage of uranium enrichd in the U-235 isotope contained in fuel assemblies. During our initial review, the Office of Nuclear Reactor Regulation (NRR) Frotect Manager reported that the structural review for the spent fuel racks was not completed.
Therefore, Condition 11 was added to the license specifying that, until the structural review was completed and NRR was satisfied with the structural integrity of the spent fuel racks, fuel assembly storage in the spent fuel racks was not authorized.
By letter dated October 5, 1988 (copy enclosed), NRR approved the structural design of the racks. The NRR analysis was for both wet and dry storage conditions.
Discussion The spent fuel pool is a stainless steel lined, reinforced concrete pool.
The saent fuel storage racks consist of square stainless steel cells of 0.085-inch t11ck Type 304 stainless steel. The cells have a 10.95-inch center-to-center r
spacing with locked renovable poison boxes between each cell. The poison boxes contain two sheets of Boraflex. This configuration allows each side of a fuel assembly to be covered by a poison sheet. The Boraflex sheets are 0.075-inches thick, 7.5-inches wide, and 173-inches long. The Boraflex is encased in thin stainless steel sheeting.
ThepoigonintheBoraflexis BaC particles with a boron-10 loading of 0.02 g/cm. The pool loading has a c3pacity of 1,969 fuel assemblies.
The licensee has stated that the fuel will i
be stored dry in a region of the pool consisting of 288 cells. The licensee reported that the k-effective of the array would be less than 0.95 under optimum water moderation conditions.
The calculations were performed using PDQ-7, a four group diffusien theory code. The cross-sections were generated using LEOPARD.
The staff confirmed the licensee's results by calculating the array using the 16 group Hansen-Roach cross-section set which is found in the SCALE program, along with KEN 0-Va, a Monte Carlo code.
The results are independent of the degree of water moderation within and between the assemblies or the degree of concrete reflection surrounding the arr e.
8810140216 es1007
{DR ADOCK 07003018 FDC
Houston Lighting & Power Comapny 2
Cor.clusion Based on the staff's analysis, it is recommended that HL&P be authorized to i
store new fuel in the spent fuel racks and that Coridition 11 to Materials License No. SNM-1983 be deleted. The staff finds that the 3roposed change in the license will have no adverse effect on the public healti and safety or on 4
the environment.
M l
)
David A. McCaughey 4
Uranium Fuel Section Fuel Cycle Safety Branch l
Division of Industrial and Medical Nuclear Safety, HMSS
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Approved by:
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George H. Bidinger, SectionT eader l
Enclosure:
As stated l
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i DATE:10/6/88 10/4/88 10/ 7 /88 i
0FFICIAL RECORD COPY l
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