ML20070M533
| ML20070M533 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 12/22/1982 |
| From: | Baynard P FLORIDA POWER CORP. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML20070M503 | List: |
| References | |
| 3F-1282-20, NUDOCS 8301250234 | |
| Download: ML20070M533 (2) | |
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m.....e_ Pow r December 22,1982
//3F-1282-20 Mr. 3. P. O'Reilly Regional Administrator, Region II U. S. Nuclear Regulatory Commission Office of Inspection & Enforcement 101 Marietta Street, Suite 3100 Atlanta, Ga. 30303
SUBJECT:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 IE Inspection Report No. 82-22
Dear Mr. O'Reilly:
Please find enclosed Florida Power Corporation's response to Inspection Report 82-22, dated November 23,1982.
Very truly yours, Y
dbp ' '
Dr. P. Y. Baynard Assistant to Vice President Nuclear Operations PGH/ mig Enclosure cc:
Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C. 20555 r301250234 830105 l PDR ADOCK 05000302 PDR General Office 3201 Thirty-fourth street soutn. P O Box 14042, st. Petersburg. Florida 33733 e 813-866-5151
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d INSPECTION REPORT 82-22 VIOLATION Technical Specification 3.4.6.2.b requires that Reactor Coolant System unidentified leakage be no greater than I gallon per minute. If leakage is greater than 1 gallon per minute, the Technical Specification requires the leakage rate to be reduced to less than 1 gallon per minute within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or that plant shutdown commence.
Contrary to the above, at 1545 on September 10, 1982, a Reactor Coolant System leakage calculation indicated a leakage of 1.009 gallons per minute and no attempt was made to verify the calculated leakage, reduce the leakage to less than I gallon per minute within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, nor to commence plant shutdown.
This is a Severity Level IV Violation (Supplement 1).
RESPONSE
(1)
FLORIDA POWER CORPORATION'S POSITION: Florida Power Corporation agrees with the violation. Personnel did not verify the calculated leakage or reduce the leakage within four (4) hours, nor did they commence plant shutdown, as required by Technical Specification 3.4.6.2.
(2)
DESIGNATION OF APPARENT CAUSE: This violation was caused by personnel error because personnel failed to indicate they were taking action required by the Technical Specifications.
At 1545 on September 10, 1982, the Reactor Coolant System Leakage calculation indicated an unidentified leakage rate of 1.009 gpm. The Shift Supervisor recognized that carrying the calculations out to three decimal places was inconsistent with the accuracy of the instrumentation used to perform the calculation. The Shift Supervisor signed the data and transmittal sheet. On the transmittal sheet, he indicated that the leakage rate was not within specifications, and indicated a retest to verify the rate would be performed by the next shif t (1600-2400).
The Supervisor, however, failed to note these actions in the log book or on the shift turnover sheet.
Thus, when the following shift came on duty, the relieving shift supervisor was not informed that he needed to complete the calculation verification.
(3)
IMMEDIATE CORRECTIVE ACTIONS: The Nuclear Shift Supervisors were instructed l
in the importance of follow-up documentation of actions.
At 0238 on September 11, 1982, a second leak rate calculation indicated that the unidentified leakage rate had decreased to.676 gpm.
On October 1,1982, the leakage calculation procedure was revised to round off to one decimal place, consistent with the accuracy of the instrumentation used.
(4)
LONG TERM CORRECTIVE ACTIONS: Florida Power Corporation has determined that the immediate corrective actions are adequate to prevent a recurrence of this violation.
(5)
DATE OF FULL COMPLIANCE: On October 1,1982, Florida Power Corporation was m full compliance.