ML20210T089

Forwards Response to Round 2 Question & Positions Re Radiation Protection Design Aspects.Response to Question 331.4 Not Adequate & Will Require Analysis of Radiation Levels from Radioactivity in Fuel Pool

ML20210T089
Person / Time
Site:	Satsop
Issue date:	01/16/1975
From:	Harold Denton Office of Nuclear Reactor Regulation
To:	Deyoung R US ATOMIC ENERGY COMMISSION (AEC)
References
CON-WNP-1737 NUDOCS 8605290709
Download: ML20210T089 (3)

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JAN 161976 Richard DeYonage Assistant Director for Liglitt Water Emactors,. Groep 1, L

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Esquested Ceepletia Date 1/24/75 Description of Responess Ecuand 2 Questicas and Positions Revier Status: Ceeplete.-

1 Se Weehington Publia Famer Supply System's WPP55 Project 3 & 5 PSAE has been regissed through A= send===t 7 by the Eadiation

,, Frotaction Section. As a result of this review including discussions with the appliaast en January 9,1975, questions ad posit. ions o.

esamenise the Radiatism Freteetion design aspects of the project have been Emmerated med feeluded la the emelaeure.

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p) m WPPSS 3 & 5 Q-2 331.19 The response to question 331.1 is not adequate. Provide (Q331.1) an analysis including calculations and assumptions that the gap and the are length will in fact provide acceptable radiation levels in the auxilliary building during fuel transfer.

l 331.20 The response to question 331.4 is not adequate. We will (Q331.4) require the information requested, including the analysis of the radiation levels from'the radioactivity in the fuel pool. Justification of the capacity of the cle.an up system incl'uding ass'umptions and calculations is also' needed.

i 331.21 The responses to questions 331.8 and 331.15 are not adequate.

(Q331.8)

Provide justification for using ths 15 millirem per hour 4

(Q331.15) used in table 12.1-17a now that table 12.1-17 has removed all reference to radiation levels in plants. Give examples I

of the man-rem dose estimates you will perform simultaneously

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with plant design (p.12.1-20).. Provide a copy of i

reference 12.1-16 concerning actual. dose accur.alation.

Reference to man-rem analyses, if applicable, performed t

for other docketed reactors would be ' acceptable.

The analysis of section 12.1.6 is not clear concerning occupancy add radiation levels _to,iustify the 410 man-rem to which the plant is designed. (p.12-1.20).

331.22' To meet the criteria for location o'f area radiation (Q331.9) -

monitors, it is our position that monitors should also be located at:

a) The air cleaning units located on the 465' level of the auxilliary building b) the tool decontamination / hot maching shop" area 4

c) the spent resin valve area on the 330' level of the auxilliary building

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331.23 Provide the location of the airborne radioactivity monitors (9.4) on Figure 9.4.1 and 9.4.3.

Since the ventilation system (12.2.4) flow diagram has had extensive changes, the analysis (Q331.11) provided in section 12.2 is no longer valid or consistent with the figures.

331.24 The location of a 5 curie cobalt 60 or cesium 137 ' source (Q331.12) could possibly raise background radiation levels in the vicinity of the calibration facility to unacceptable levels (for low level counting or monitoring for personnel contasination). Provide what actions will be taken' to assure that radiation levels resulting from the use of the calibration source in its present location will not unacceptably interfere with the counting and monitoring

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functions in the adjacent facilities.

t 331.25 The ' arrangement drawings' of the administration building (Q331.14).

do not reflect the comments on the laundry design'on page'12.1-9.

These arrangement drawings should be corrected. Also provide the criteria and assumptions used for designing the. laundry, facilities with respect to volume.of clothing required during outages, laundry cycle, manpower, etc.

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