ML19340B216

Ro:In Reviewing Containment Atmospheric Dilution Sys, Determined Relay in Logic Circuit Does Not Meet FSAR Requirements.Operating Procedures Revised to Include Jumpering of Contacts

ML19340B216
Person / Time
Site:	Brunswick
Issue date:	10/16/1980
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
BSEP-80-1731, NUDOCS 8010210667
Download: ML19340B216 (4)

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Telecopied to Mr. JamIs P. O'Railly October 16, 1980 Carolina Power & Light Company L

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[ Brunswick Steam Electric Plant P. O. Box 10429 4

I Southport, NC 28461 October 16, 1980

, FILE: B09-13516 SERIAL: BSEP/80-1731 Mr. James P. O'Reilly, Director l U. S. Nuclear Regulatory Commission l Region II, Suite 3100 101 Marietta Street N.W.

- Atlanta, CA 30303 ,

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BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 & 2 i LICENSE NOS. DPR-71 AND DPR-62 '

DOCKET NOS. 50-325 AND 50-324

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CONFIRMATION FACSIMILE FOR AN IMMEDIATELY REPORTABLE EVEh"r (2-80-79)

Dear Mr. O'Reilly:

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This facsimile confirms the conversation between Mr. A. C. Tollison, Jr.,

BSEP General Manager, and Mr. P. J. Kellog, of your office, at 0945 on October 15, 1980.

4 In reviewing the Containment Atmospheric Dilution (CAD) syst.am in response to item 2.1.Sa of NUREG-0578, Carolina Power & Light Cenpany has determined that a relay exists in the logic circuit for both Brunswick Units which does not meet the single active failure criteria of the CAD system as stated in the FSAR. A failure of this relay, located in the containment isolation override logic circuit, could prevent post-LOCA nitrogen injection due to the inability to remotely operate the injection valves CAC-VS, V6, V47,

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V48, V55, and V56.

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O Mr. J. P. O'Reilly October 15, 1980 The FSAR states that nitrogen injection will not be required until approxi-mately ten hours after a LOCA event with fuel damage to control the oxygen concentration. To ensure that nitrogen injection can be accomplished when required with this relay in the failed condition, the operating procedures describing injection are being revised to advise the operator to check the status of this relay should the injection valves fail to open. The pro-cedures will also include instructions for jumpering the relay _ contacts to

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their appropriate position for valve operability with available predesignated jumpers. A plant modification which is being prepared in response to NUREG-0578 and scheduled to be completed on both units by late 1981 will

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provide a permanent correction to this problem.

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Very truly,yours,

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A. C. To111 son, Jr., General Manager Brunswick Steen Electric Plant  !

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