ML19317F196
| ML19317F196 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/04/1975 |
| From: | Kreger E Office of Nuclear Reactor Regulation |
| To: | Purple R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8001080909 | |
| Download: ML19317F196 (2) | |
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G 5 Robert A. Purple, Chief, Operating Reactors Branch 1, RL DOSE ASSESSME2TI FROM OCONEE SP!Drf FUEL POOL EDIFICATION (TAR 1865-POLLOW-UP)
Plant Meme: Ononea173,and3 Docket Ntsaber: 50-25V Responsible BrancW ORB 1 Task Leader:
G. Zech Request Received by RAB: November 18, 1975 Requested Completion Date: December 4,1975 Description of Response Dose Assessment from spent fuel pool x
modifications Review Status: Complete (Follow-up of Oconee response to Question 7 of TAR 1865)
With respect to the Oconee spent fuel pool codifications, the following analysis is made to provide estimates of man-rem doses expected during fuel pool operations. The input for the analysis was supplied by Oconee based on a telephone conversation with Gary Zech.
A.
Critaria for handline spent fuel assemblies:
(1) Fuel Rods from Oconee 1 and 2 sent to Oconee 3 for clorage (2) 100 man-hrs. required to transporn each assembly (3) 150 assemblies to complete leading in ocacee 3 spent fuel pool (4) Dose rate at contact with transfer cask approxinate.~y = 25 mr/hr B.
Assumptions:
(Based on criteria developed by S, Block and G. Zech)
(1) F.alf of operation man-hrs-spent over fuel pool wh~ile_ Ioading assembly onto transfer cash (2) Asserse average dose rate 1 Mrea/hr at edge of pool (3) 50 man-hrs spent handling cask during transfer of ead; from Oconee 1/2 to Oconee 3.
(4) Average dose rate during the handling period is ~1 Mram/hr sinen-there is no reason to make close contact during hardling.
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Dcee Asseeement per transfer eperation:
50 man-hre I 1 ares /hr = 0.050 man-rem during ramtesi from pool 50 man-hrs 1 1 aren/hr = 0.050 maa-ren during transfer to ocames 3 pool
- = 0.100 man-ran 1
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CEC 4 55 R. A. Purple D. Dose Assessment _ for 150 assemblies:
0.100 x 150 = 15 man-ren E. Computation of Dose durina normal fuel pool operations:
(1) The Occupancy Factor during fuel transfer from the reactor to the
' spent fuel pool is equal to 5 days for a total of 240 man-hrs -
(From Oconee)
(2) Usina the source terne for resetor coolant from Reg Guide 1BB and j
correcting for oconee power (.66), dulution with the spent fuel j
pool water (.05), and consideration of spent fuel pool clean-up systems (0.10), the 155 source terms that would contribute to the highest dose to personnel in the operating area of the spent fuel pool, would be as follows:
l 137Cs = 6 x 10_,5 };eifeg 134Cs = 8 x 10 5 gegfee soco = 7 x 10 ~6 geifee 58Co = 5 x 10 ~3 Mei/cc From relevant exposures from Point Beach, La Crosse, and Indian Point 3 spent fuel pool dose rata calsulations and sneasurements using respective source terms, normally greater than those given above, have provided dose equivalent rates of -1.5 mrsm/hr at 3' sbove the fuel pool surface.
Using this value, as the most conservative estir. ate, and occupancy factor given in E(1), we get 1.5 mren/hr x 24n man-hrs = 0.360 man-rm as the maximum dose equivalent exposure to personnel occupying the spent fuel pool area during normal fuel handling operations.
This work was performed by S. Block, RPS.
William E. Kreger, Leader Radiation Protection Section Division of Technical Review cc:
R. Heinamman H. Denton K. Gollar G. Zech D. Scarletti S. Block
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