ML18081A771

Affidavit of RP Douglas on 791102 Re Relative Toxicity Index Resulting from Replacement of Present Spent Fuel Pool Racks W/Proposed Racks

ML18081A771
Person / Time
Site:	Salem
Issue date:	11/02/1979
From:	Douglas R Public Service Enterprise Group
To:
Shared Package
ML18081A770	List: ML18081A769 ML18081A771
References
NUDOCS 7912190092
Download: ML18081A771 (2)

Text

STATE OF NEW JERSEY )

) SS.

COUNTY OF ESSEX )

AFFIDAVIT OF ROBERT P. DOUGLAS ROBERT P. DOUGLAS, being first duly sworn accord-ing to law, deposes and states:

1. I am employed by Public Service Electric and Gas Company as Licensing Manager and Acting Environment Manager.

My professional qualifications, which I incorporate by reference herein, are contained in the transcript of this proceeding following Tr. 402.

2. I reviewed the submittal of the Nuclear Reg-ulatory Commission relating to the Atomic Safety and Licensing Board's question regarding the increase of the Relative Toxicity Index (RTI) for the proposed Salem Unit 1 spent fuel pool modification. The NRC staff, in their Assumption No. (5),

utilized a linear decay of radioactivity between one and ten years and between ten and twenty years. The NRC staff acknowledges that this linear assumption results in an overestimate of the total activity in the proposed spent fuel pool. This, of course, re-sults in an overestimate of the relative increase in the RTI for the expanded pool.

3. I have supervised independent calculations similar to those performed by the NRC staff to determine the increase in RTI for the *expanded fuel pool compared to the pre-sent pool design.

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Instead of using a linear interpolation of radioactive decay, however, actual decay calculations were performed for each batch of spent fuel that would be present in the expanded fuel pool.

Our calculations also differ from NRC Assumption No. (6) in that we assume that the full core off-load was decayed for seven days instead of the thirty days assumed by the NRC staff. This difference should not affect the final result significantly since the full core off-load is assumed both for the present fuel pool design and the proposed expansion. Instead of utilizing NUREG-0575 as was indicated in Assumption No. (3) by the NRC

.

staff, we performed our calculations for each year of decay using the ORIGEN computer code developed by Oak Ridge National Laboratory. This enabled us to calculate decay of radioactivity for each specific time period.

4. Our results indicate that the RTI increases by approximately 31% in expanding the fuel pool capacity. This compares with the approximately 50% calculated by the NRC staff using the linear interpolation model.

We concur with the NRC staff conclusion that the risk to the public health and safety from the activity in the modified spent fuel pool continues to be negligible.

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