ML20147D339

Supp Testimony Re Bd Question 2-3 Noted in the Order Ruling on Motions for Summary Disposition.Testimony Indicates That New Info Was Submitted on Allens Creek Docket W/Regard to a BWR/6 Calculation

ML20147D339
Person / Time
Site:	Black Fox
Issue date:	09/08/1978
From:	Frahm R, Sheron B AFFILIATION NOT ASSIGNED
To:
Shared Package
ML20147D176	List: ML20147D170 ML20147D339
References
NUDOCS 7810140026
Download: ML20147D339 (2)

Text

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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD In the Matter of PUBLIC SERVICE COMPANY OF Docket Nos. STN 50-556 OKLAHOMA, ASSOCIATED STN 50-557 FLECTRIC COOPERATIVE, INC. , - )

AND WESTERN FARMERS ELECTRIC )

COOPERATIVE (Black Fox Station, Units 1 and 2) )

SUPPLEMENTAL TESTIMONY OF BRIAN W. SHERON AND RONALD K. FRAHM ON BOARD QUESTION 2-3 We are the sponsors of the attached document entitled " Supplemental Testimony of Brian Sheron and Ronald Frahm on Board Question 2-3,"

and belie"e it to be accurate to the best of our knowledge and belief.

This attachment is an additional response to the question 2-3 noted in the " Order Ruling on Motions for Summary Disposition," by the Atonac Safety and Licensing Board, dated September 8, 1978.

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• Brian W. Sheron

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Supplemental Testimony on Board Question 2-3 The testimony of Brian Sheron and Ronald Frahm, in response to Board Question 2-3, indicated that new information was submitted on the Allens Creek docket (50-466) with regard to a BWR/6 calculation. We also indicated that we would report on this information in a supplement to our original testimony.

The Allens Creek calculation.was performed to provide additional information regarding the effect of automatically diverting two low pressure coolant injection (LPCI) pumps to wetwell spray 10 minutes followingaloss-of-coolantaccident(LOCA). The diversion of LPCI at 10 minutes has only a slight effect on ECCS performance for large breaks since the reactor core would be reflooded (core hot spot covered) prior to 10 minutes; however, for some small breaks the core is not reflooded prior to LPCI diversion. Reflood is delayed thereby yielding a higher peak cladding temperature (PCT).

Recent calculations submitted on the Allens Creek docket show a PCT higher than those submitted on the GESSAR docket referenced by the applicant.

The higher temperature is caused by assuming a different break location and single failure; and by model corrections made subsequent to the sensitivity study on LPCI diversion submitted on the GESSAR docket.

For a small break in the high pressure core spray line and assuming failure to start of a Division 1 diesel, the temperature reported on Allens Creek is-2085 F and is higher than the value reported for the large break design basis accident of 2038 F. However, the temperature criterion of 10 CFR 50.46 is not exceeded. The staff is in the process of requesting additional information from the applicant and will report an update of our review in a supplement to the Black Fox Station Safety Evaluation Report.

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