ML20043C902

Responds to Violations Noted in Insp Repts 50-324/90-14 & 50-325/90-14.Corrective Actions:Box Cover Closed Following Notification of Discrepancy & Human Performance Evaluation Initiated to Ensure Proper Corrective Actions Initiated

ML20043C902
Person / Time
Site:	Brunswick
Issue date:	06/01/1990
From:	Harness J CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BSEP-90-0415, BSEP-90-415, NUDOCS 9006060324
Download: ML20043C902 (3)

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.e CD&L i Carolina Power & Light Company

'Br'unswic'k" Nuclear Troject s P. O. Box 10429 i Southport, N.C. 28461-0429 j June 1, 1990 FILE: B09 13510C 100FR2.201, ,

SERIAL: BSEP/90 0415 U.S. Nuclear Regulaton Commission .

ATTN: Document Control Desk l Washington, D. C. 20555 ,

BRUNSWICK STEAM ELECTRIC PLANT UNITS 1 AND 2 DOCKET NOS 50 325 AND 50 324 LICENSE NOS DPR 71 AND DPR 62 ESPLY TO A NOTICE OF VIOLATION Centlemen:

The Brunswick Steam Electric Plant (BSEP) has received NRC Inspection Report 50-325/90-14 and 50 324/90-14.and finds that it does not contain information of a proprietary nature.

This report included a NOTICE OF VIOLATION. Enclosed is Carolina Power & Light I Company's response to that NOTICE OF VIOLATION. j Very truly yours, i

d t. i J. L. Harness, General Manager ,

Brunswick Nuclear Project l

, TH/ 3 1  !

Enclosure cc: Mr. S. D. Ebneter

,. Mr. N. B. Le

! BSEP NRC Resident Office l

! bec: Mr. R. M. Coats Mr. L. I . Loflin Mr. D. C. Whitehead L Mr. C. W. Crawford Mr. A. M. Lucas INPO Mr. A. b. Cutter Mr. R. E. Morgan Onsite Licensing Mr. W. J. Dorman Mr. J . O'Sullivan File: BC/A-4 Ms. R. S. Gatewood Mr. W. W. Simpson SHEEC Training Mr. W. P. Guarino Mr. R. B. Starkey Jr. Reference Library Mr. M. D. Hill Mr. L. V. Wagoner Mr. M. A. Jones Ms. T. A. Ward 90060603.i4 900601 l PDR ADOCK 03000324 L Q PDC TEo/

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NRC Document Control Deck I. NOTICE OF VIDIATION -

10CFR50.49(d) requires that the licensee maintain a list of equipment important to safety required to be environmentally qualified and provide information in an auditable form which demonstrates that the equipment will perform its function under its design harsh environmental conditions.

Qualification Data Package (QDP)-71, . Revision 0, establishes the qualification of General Electric CR151D- terminal blocks for use in the Reacter Building. The file requires that the terminal block be installed in a NL% 3 or better enclosure so that the device is protected from the direct effects of steam and water impingement.

Contrary to che above, a General Electric CR151D terminal block installed in junction box ESS-PN2 on instrument rack ll21-P022 in Unit 1 was installed in a c e figuration not supported by existing documentation due to its junction box cover being open. This condition existed from approximately April 10, 1990 until April 12, 1990. and resulted in 1-B32-PS N018B and 1-CAC PT 1257 2B (instruments which are terminated on this block) being inoperable for the above time period.

II. Reolv to a Notice of Violation A. Admission or Denial of Violation CP6L admits that it violated provisions of QDP 71 by not reinstalling the junction box cover on box ESS-PN2, instrument rack ll21 P022, following completion of required testing.

B. Beason for Violation Investigation into this incident has revealed that the junction box cover was initially removed on April- 10, 1990, in order to perform Unit 1 Maintenance Surveillance Test (MST)-RilR27M. Following completion of the MST, the cover was net closed and fastened.

The cause for this event has been determined to'be personnel error by the technicians performing the MST. The individuals performing the MST failed to fulfill their responsibility of ensuring the equipment had been properly returned to service. Significantly contributing to this event was an inadequate procedure. The procedure states to install and remove the Voltage-Ohm meter from the terminals, but does not address the box cover, llad the procedure contained a step in the procedure to close the box, this event probably would not have occutn d.

C. Corrective Stens Which llave Been Taken and Results Achieved The box cover was closed following notification of this discrepancy.

Technicians verified other box covers on instrument racks in the -

17' elevation of the reactor building to be properly installed.

NCR S-90-027 was initiated to identify the root cause of this incident. A lluman Performance Evaluation (HPE) was initiated to ensure proper corrective actions would be initiated to avoid recurrence.

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NRC Document Control Desk 3-

- Upon reinstallation of the junction box cover, conformance to QDP 71 I requirements was restored.

D. Corrective Actions to be Taken to Avoid Purther Violations and Date '

of Full comoliance The response to NCR S 90 027 identified the following actions to

- prevent recurrence:

1. Counseling of the involved and instructed as to their responsibility of craftsmanship as described in Maintenance '

Procedure ( m ) 001.

2 NCR S 90 027 will be reviewed in the - Maintenance Second Quarter Real Time -Training Program. Thie action is to be i completed by 8 1 90.

3. procedures 1MST RHR27M and 2MST RHR27M have been revised to e'ininate the necessity of accessing the terminal box during ,

L tne 65Ts by using Control Room indications.  ;

CP&L feels that compliance- relative to this event was achieved .

following completion of the junction box cover reinstallation and  !

follow up checks of other box covers in the affected area.

Additional actions, as noted above, are considered necessary to i prevent recurrence of this type event. Expected completion dates r for each of these actions is as noted.

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