ML20151V788

Errata to NEDO-24081, LOCA Analysis for Peach Bottom Atomic Power Station,Unit 2, Replacing Page 4-14

ML20151V788
Person / Time
Site:	Peach Bottom
Issue date:	01/31/1988
From:	GENERAL ELECTRIC CO.
To:
Shared Package
ML19302D529	List: ML20151V773 ML20151V785 ML20151V788 ML20151V830
References
NEDO-24081-ERR, NUDOCS 8805030186
Download: ML20151V788 (2)

Text

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APPLICABLE TC:

NEDO-24081

PUeLICATION NO.

ERRATA And ADDEND A O T. i. e. NO.

LOCA Analysis for Peach SHEET

TITLE "0-Bottom Atomic Power Station January 1988 oats Unit 2 NOTE: Correct sit copies of the applicable tSSUE DATE December 1977 publicstion as specified below.

REFERENCES INST RUCTIONS ITEM (SECTION PAGt (CORREC7 TONS AND ADOtt#ONS)

PA R AG R APH, LIN g) 01 Page 4-14 Replace with new page 4-14,

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• 175 C.emer recue 725 8e0503o186 880421 PDRADOCK05g277

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(, . .. NEDO-24081 j l

hV. Table 4-3k _

MAPLHGR VERSUS AVERAGE PIANAR EXPOSURE o

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i Plant: 78-2 Puel Type: BD319A }

r Least Limiting Most Limiting Average Planar MAPLHCR MAPLHGR Exposure (GWd/St) (kW/ft) __ (kW/ft) 0.2 11.68 11.22 2.0 11.87 11.47 4'. 0 12.20 11.85 6.0 12.62 12.34 8.0 13.04 12.84 10.0 13.13 13.06 12.5 13.07 12.91 15.0 12.77 12.71 20.0 12.17 12.16 50.0 6.69 6.63 O Table 4-31 MAPLHGR VRSUS AVERAGE P1ANAR EXPOSURE Plant: PB-2 Fuel Typet BD32LA Least Limiting Most Liniting Average Planar MAPLHGR MAPLEGR Exposure (GWd/St) (kW/ft) (kW/ft) 0.2 11.51 11.05 2.0 11.75 11.33 4.0 12.04 11.67 6.0 12.27 11.95 8.0 12.70 12.47 10.0 13.13 12.73 12.5 13.05 12.98 15.0 12.76 12.74 20.0 12.18 12.16 l

50.0 6.68 6.62 4-14 i

r ATTACHMENT II NUCLEAR ENGINEERING SCIENCES DEPARTMENT Nuclear Reactor Facility ,

University of Florida

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April 11, 1988 *

% c,oo m w.wmsso Safety Channel #1 Circuit Failure - 3 Nuclear Regulatory Commission Suite 2900

- 101 Marietta Street, N.W.

Atlanta , GA 30323 Attention: J. Nelson Grace Regional Administrator, Region II Re: University of Florida Training Reactor Facility License: R-56, Docket No. 50-83 As per telephone conversation on 11 April 1988 with Mr. Paul Burnett, relative to failure of Safety Channel #1 Circuit for the UPTR, the event described in our letters of 15 and 16 March 1988 as well as our letter dated March 28 con-stituting our interim 14-dsy report on the failures occurring on 14 and 15 March 1988, has recurred during a power run conducted for a senior laboratory training operations laboratory. Although a special test procedure had been used to verif y proper operation of Safety Channel 1 by monitoring voltage and current levels on Safety Channel 1 components at power levels up to full power for nearly three (3) hours total time no specific root cause had been identi-fied for the second circuit failure. All results of the test procedure were successf ul with no specific fault noted; therefore, the UFTR was returned to normal operation per communication with Region II and Reactor Safety Review Subcommittee approval on April 1, 1988.

For this recurrence of an intermittent f ailure, the RSRS Executive Committee will meet later today but will certainly instruct NRC notification as per Sec-tion 6.6.2 of the UTTR Tech Specs though the event nay still not be required to be promptly reportable depending on interpretation of the Tech Specs.

Specific plans to address this recurrence prior to attempting restart include swapping amplifiers in the two Safety Channels, replacing the Safety 1 prea m-plifier and sevoral cable connectors. A complete test procedure is being pre-pared for review.

Further infornution will be supplied prior to restart.

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William G. Vef"ne tson' ~

Director of Nuclear Facilities 11 April 1988 WGV/ps cc: P.M. Whaley RSRS sw o6mimm,%w sw

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