ML19350A857

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Forwards Responses to NRC 801105 Questions Re Fuel Storage Facility Mod.Earlier Responses Were Forwarded 801121,810114 & 0203
ML19350A857
Person / Time
Site: Prairie Island  Xcel Energy icon.png
Issue date: 03/10/1981
From: Mayer L
NORTHERN STATES POWER CO.
To:
Office of Nuclear Reactor Regulation
References
NUDOCS 8103170158
Download: ML19350A857 (20)


Text

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March 10, 1981

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Director of Nuclear Reactor Regulation U S Nuclear Regulatory Commission d

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Prairie Island Nuclear Generating Plant 4

Docket No. 50-282 License No. DPR-42 50-306 DPR-60 Supplemental Information - License Amendment Request Dated January 31, 1980 Attached is the fourth set of responses to questions sent to L 0 Mayer from R A Clark on November 5, 1980, concerning the Prairie Island NGP Fuel Storage Facility modification. The first, second and third set of answers were sent on November 21, 1980, January 14,1981 and February 3, 1981 re spect ive ly.

Attached is the answer to Auxiliary Systems Branch (ASB) question 5 and a report titled " Prairie Island Spent Fuel Pool Modification -- Spent Fuel Pool Ccoling System Analysis" which will supplement the response to ASB-2 dated February 3,1981. This completes the answers to the November 3, 1980 questions.

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L 0 Mayer, PE l

Manager of Nuclear Support Services LOM/TMP/bd cc: J G Keppler l

C Charnoff MPCA Atta: J W Ferman NkC Resident Inspector i

8108170 M P

Attachment to March 10, 1981 Letter AUXILIARY SYSTEMS BRANCH (ASB)

QUESTION ASB 5:

In regard to section 3.4.4.6 of Exhibit C, describe, discuss and verify that all the handling tools, that are to be handled above the stored spent fuel assemblies will not result in unacceptable consequences when dropped from their maximum operational elevations.

RESPONSE ASB 5:

Spent fuel pool operations have been reviewed and the following restrictions will be adhered to following the installation of the new fuel racks:

Items weighing less than 1625 lbs (the weight of a fuel assembly,1275 lbs, and its tool, 350 lbs) shall be restricted when they are suspended by the Spent Fuel Pool Bridge Crane over a pool containing fuel. The height of such items shall be restricted such that their potential energy will not be greater than 3250 ft-lbs. (relative to the top of spent fuel assemblies in the racks).

Identification marks will be located on the shafts of the tools to indicace how high the tools may be raised.

Items weighing less than 1625 lbs carried by the Auxiliary Building Crane will not be restricted due to the large capacity of the crane relative to 1625 lbs, hign factors of safety of slings used, and the low frequency of moving the tools with the Auxiliary Building Crane.

In the review of this question the spent fuel pool canal gates were also investigated. AFthough the gates are not considered handling tools, they do weigh more than a fuel assembly and its handling tool. The Technical Specifications as originally issued and currently worded, prohibit the movement of " heavy loads" in the spent fuel pool. Although not specifically defined, this was meant to restrict shipping casks and heavy equipment and not gates.

However, recently issued NRC documents have defined " heavy loads" to be loads greater than a fuel assembly and its haniling tool. Therefore, a review of gate handling procedures was conducted. To reduce the likelihood i

of one failure causing the dropping of a gate, it will be handled by'both hoists on the Spent Fuel Pool Bridge Crane when being moved in a spent fuel pool containing fuel. The weight of a gate is approximately 2600 pounds and each hoist has a 6000 pound capacity.

In conclusion, the proposed method of handling the gates makes the possibility of dropping-a gate extremely low. With these precautions, the gates will not be considered

" heavy loads" as referred to in Technical Specifications 3.8.B.1.

4

Acccchment to March 10,19811.etter PRAIRIE ISLAND SPENT FUEL POOL MODIFICATION SPENT FUEL POOL COOLING SYSTEM ANALYSIS The analysis of the spent fuel pool cooling system (SFPCS) and resulting pool water temperatures for various conditions is described in Exhibit C.

Section 3.5 of the License Amendment Request dated January 31, 1980. The purpose of this report is to update the results presented in Section 3.5 to account for two changes. First, the application of the uncertainty factor in the heat generation computation is changed to confonn exactly with the method of Branch Technical Position ASB 9-2.

Second, the abnormal condition of Section 3.5 was based on the assumptions that a flow rate of 2200 gpm would be distributed evenly between the two heat exchangers. Recent calculations have shown that the system is capable of handling 2600 gpm (the maximum pump output), and that the flow can be distributed unequally between the heat exchangers.

Therefore, in response to NRC coments and including the above changes, new results are presented in this report. The following conditions have been analyzed:

I.

Normal condition, main heat exchanger and one pump at 1300 gpm II. Normal condition, backup heat exchanger and two pumps at 2600 gpm total III. Abnonnal condition, both heat exchangers (main 1600 gpm and backup 1000 gpm IV. Faulted condition, main heat exchanger and one pump at 1300 gpm V.

Faulted ccndition, backup heat exchanger and two pumps at 2600 gpm total The methods used are_ the same as described in Section 3.5, except for the uncertainty factor change. The results of the analyses are shown in Figures 1 through 15 anc in Table 1..

The peak pool temperatures and applicable ' figures for each condition are given below.

Peak Pool Applicable Condition Temperature- (CF)

Figures I

133 1, 2 & 3 II 137 4, 5 & 6 III 145 7, 8 & 9 IV 175 10, 11 & 12 V

183 13, 14 & 15 Table 1 lists the peak heat generation, and heat exchanger inlet and outlet temper &tures and flow rates.

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SFP CCll PEAK SPENT FUEL P0OL HATER C0lf0flENT COOLING HATER I

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FAULTED MAlfi 2 pumps 6

5 FAULTED BACVUP 2.509 X 10 178.5 159.1 1,301X10 95 i

123.04 9 X 10 TABLE 1 SPEllT FUEL P0OL COOLING DATA

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