05000324/LER-1982-029, Forwards LER 82-029/03L-0.Detailed Event Analysis Encl

Forwards LER 82-029/03L-0.Detailed Event Analysis Encl

ML20041F844
Person / Time
Site:	Brunswick
Issue date:	03/01/1982
From:	Dietz C CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20041F845	List: 05000324/LER-1982-029, Forwards LER 82-029/03L-0.Detailed Event Analysis Encl 05000324/LER-1982-029-03, /03L-0:on 820203,discovered Suction Header Low Pressure Lockout Rendering Divs I & II RHR Svc Water Subsystem Inoperable.Caused by Loss of Operating Fluid Level in Diaphragm Housing of Suction Header Pressure Switch
References
BSEP-82-436, NUDOCS 8203170474
Download: ML20041F844 (3)

LER-1982-029, Forwards LER 82-029/03L-0.Detailed Event Analysis Encl

Event date:
Report date:
3241982029R00 - NRC Website

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Carolina Power & Light Company Brunswick Steam Electric Plant d

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P. O. Box 10429 Southport, NC 28461-0429 March 1, 1982 4

FILE:

B09-13516 SERIAL:

BSEP/82-436 e

OCEM/99 3

Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission mq p.,,.;..fbO2%Q~-

Region II, Suite 3100 F C mca 101 Marietta Street N.W.

it Atlanta, GA 30303

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BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 ' ' a g g p, DOCKET NO. 50-324

~L-LICENSE NO. DPR-62 LICENSEE EVENT REPORT 2-82-29

Dear Mr. O'Reilly:

In accordance with Section 6.9.1.9b of the Technical Specifications for Brunswick Steam Electric Plant, Unit No. 2, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-0161, July 1977.

l Very truly yours, C. R. Dietz, General Manager i

Brunswick Steam Electric Plant RMP/daj Enclosure cc:

Mr. V. Stello, Jr.

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LER ATTACHMENT - RO # 2-82-29 Facility: BSEP Unit No. 2 Event Date:

2-3-82 During plant operation, while investigating an annunciator problem with "A" RHRSW pump, an attempt to start the pump revealed the existence of a low suction header pressure lockout which makes the divison I RHRSW subsystem inoperable. At the time of this discovery, No. 4 diesel generator, which is the emergency power source to division II RHRSW subsystem pump 1B, was unavailabic due to planned maintenance. In accordance with Specification 3.0.5, the division II RHRSW subsystem was then declared inoperable due to its redundant subsystem, division I, being inoperable.

The investigation of the division I low pressure lockout determined that the actual pump suction pressure was normal. An inspection of the switch, Barksdale Model No. D2T-M150-SS, showed that a total loss of switch diaphragm operating fluid had occurred, causing the switch to erroneously sense a low pressure condition. This loss of fluid is attributed to minute perforations in the switch diaphragm material which had allowed the fluid to seep out.

To facilitste establishing operability of the division I RHRSW subsystem, the corresponding division II RHRSW subsystem pressure switch, SW-PS-1176, which was operable, was installed in place of the 1175 instrument on divison I.

Due to the lack of a replacement switch for the 1175 instrument, proper operating fluid level was reestablished in the switch and it was calibrated and returned to service on the division II RHRSW subsystem. A replacement switch for the 1175 switch is presently on order from the manufacturers. In addition,

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i LER ATTACHMENT - RO # 2-82-29 (Cont'd) until a replacement instrument is installed in place of the present 1175 instrument, a daily check of the switch will be performed to ensure its operability.

1 As a result of this event, the corresponding Unit No.1 RHRSW suction header pressure switches were checked for proper operation with no problems found.

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