ML19347C750

RO 2-80-106:on 801226,while Operating at Approx 56% Power, Reactor Scrammed Resulting in HPCI Trip & Isolation on High Exhaust Pressure.Caused by Low Level Auto Initiation Signal. Trip Reset.Damaged Snubbers Repaired

ML19347C750
Person / Time
Site:	Brunswick
Issue date:	12/29/1980
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
RO-2-80-106, NUDOCS 8101050401
Download: ML19347C750 (2)

Text

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Talcetpied to Mr. O'R: illy, 12/30/80 C@SL .

Carolina Power & Light Company Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461 December 29, 1980 FILE: B09-13516 SERIAL: BSEP/80-2125 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II, Suite 3100 101 Marietta Street N.W.

Atlanta, GA 30303

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BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. DPR-62 LICENSE No. 50-324 CONFIRMATION OF AN IMMEDIATELY REPORTABLE EVENT (2-80-106)

Dear Mr. O'Reilly:

This facsimile confirms the telephone conversation between Mr. A. C. Tollison, Jr., General Manager, and Mr. Austin Hardin of your office at 2030 on December 26, 1980. While operating at approxi=ately 56%, Unit No. 2 Reactor scracmed l due to low level at 1020 on December 26, 1980. HPCI and RCIC received an auto initiation signal at Low Level 2 (minus 38"); however, HPCI immediately l tripped and isolated on high exhaust pressure. The trip was immediately reset and the HPCI system ran satisfactorily. Later, while investigating the cause of the high exhaust pressure trip, 3 snubbers on the steam exhaust line were noted to be physically damaged. The remaining 9 snubbers on this line were functionally tested and 4 additional snubbers were determined to be inoperable. All 7 inoperable snubbers have been either repaired or I replaced and the HPCI system has been returned to normal operation.

l V ly yours, A. C. Tolli on, Jr., General Manager l

Brunswick Steam Electric Plant l RMP/ mew cc: Mr. R. A. Hartfield' Mr. V. Stello, Jr.

6101050 '

401 .

NRP F0F34 366 U. S. NUCLEAR REGULATORY COMMISSISN G787)

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