ML20206F979
| ML20206F979 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 04/08/1987 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8704140413 | |
| Download: ML20206F979 (2) | |
Text
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i DUEE POWER GOMPANY P.O. BOX 33180 CHARLOTTE, N.C. 28242 HAL B. TUCKER reurnown vice rammenant UM) 3MMI weca.saa renoverson e
April 8, 1987 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555
Subject:
RII:PKV/MSL Catawba Nuclear Station Docket No. 50-414 Violation 414/87-05-05
Dear Sir:
Please find attached our response to the subject Violation.
Very truly yours, Hal B. Tucker LTP/35/sbn Attachment xc:
Dr. J. Nelson Grace, Regional Administration U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. P. K. Van Doorn NRC Resident Inspector 4
Catawba Nuclear Station 8704140413 870408 PDR ADOCK 05000414 Ol G
PDR si N
DUKE POWER COMPANY RESPONSE TO VIOLATION 414/87-05-05 Technical Specification 3.6.3 requires the containment isolation valves specified in Table 3.6-2b to be operable with isolation times as shown.
The action statement requires an inoperable valve to be restored to operable status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or isolation of the affected penetration within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the reactor be in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
Contrary to the above, on February 4, 1987 with the unit in Operational Mode 1, valve 2BB-8A failed to close within the maximum isolation time and was not returned to operational status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, nor was the affected penetration isolated within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> nor was the reactor placed in Hot Standby within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
RESPONSE
(1) Admission or Denial of Violation Duke Power Company admits the violation.
(2) Reason for Violation The violation occurred because the Technical Specification Interpretation for Technical Specification 3.6.3 incorrectly utilized the ASME Code grace period j
of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> before declaring a value inoperable.
The basis for Technical l
Specification 3.6.3 was not adequately researched when the Interpretation was l
written.
(3) Corrective Action Taken and Results Achieved The Technical Specification Interpretation has been rescinded and all affected station groups notified.
(4) Corrective Action Taken to Avoid Further Violations Technical Specification Interpretations will no longer be written solely on the basis of review by one group.
Station Compliance will review proposed Technical Specification Interpretations along with other knowledgeable groups against the basis for the specification.
(5) Date of Full Compliance i
Duke Power Company is now in full compliance.
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