ML18127A664

LER 1978-016-00 for St. Lucie Unit 1, on 05/26/78 Concerning Containment Pressure-High Trip Setpoint (Table 2.2-1) Appeared to Be in Error During the Refueling Outage

ML18127A664
Person / Time
Site:	Saint Lucie
Issue date:	06/09/1978
From:	Schmidt A Florida Power & Light Co
To:	O'Reilly J NRC/RGN-II, NRC/IE
References
PRN-LI-78-153 LER 1978-016-00
Download: ML18127A664 (5)

Text

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DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED

SUBJECT:

LTR 1 ENCL 1 LICENSEE EVENT REPT e78-016 ON 5/26/78 CONCERNING CONTAINMENT PRESSURE-HIGH TRIP SETPOINT (TABLE 2. 2-1> APPEARED TO BE IN ERROR DURING THE REFUELING OUTAGE.

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June 9 1978 PRN-LI-78 153 Mr. James P. O'Reilly, Director, Region II Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission 230 Peachtree Street., N.'W., Suite 1217 C Atlanta, Georgia 30303 '</>

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I ST. LUCIE UNIT 1 Al CJ CO DATE OF OCCURRENCE: MAY 26 1978 TECHNICAL SPECIFICATION 2.2.1 CONTAINMENT PRESSURE TRIP SETPOINT The attached Licensee Event Report is be'ing submitted in accordance with Technical Specification 6.9 to provide prompt notification of the subject occurrence.

Very truly yours, A. D. Schmidt Vice President Power Resources MAS/cpc Attachment cc: Robert Lowenstein, Esquire Director, Office of Inspection and Enforcement (40)

Director, Office of Management Information and Program Control (3) 7S1870322 PEOPLE... SERVING PEOPLE

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~lo an e was incor orated into the Final Safety but for unknown reasons resumabl ersonnel error it in r r d in the Technical S ecifications. A Technical S ecific-tion chan e re uest is bein re ared to correct Table 2.2-1.

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REPORTABLE OCCURRENCE 335-78-16 LICENSEE EVENT REPORT PAGE TWO Additional Event Descri tion Shortly after Cycle 1 shutdown, the NSSS vendor noted (in a letter regarding core Cycle 2 Specifications) that the reactor protective instrumentation trip setpoint for "containment pressure - high" (T. S. Table 2.2-1) appeared to be in error. During the refueling outage, records were reviewed and it was found that the vendor had recommended a setpoint change shortly before St.

Lucie Unit 1 was licensed, but the change had not been incorporated into the Technical Specifications. The setpoint in Table 2.2-1 is <3.9 psig, and the actual Cycle 1 operating setpoint was "conservatively" set at <3.5 psig. The vendor was requested to provide further information, and, .as a precaution before Cycle 2 reactor startup after refueling, the actual operating setpoint was reduced to <3.3 psig (as recommended by the vendor). On Nay 26, 1978, the vendor conf7rmed that the required setpoint is <3.3 psig.