ML19341D046

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Responds to NRC 801112 Ltr Re Violations Noted in IE Insp Rept 50-302/80-36.Corrective Actions:Dome Survey Worksheets Investigated & All Recoverable Worksheets Filed W/Data Sheets.Personnel Admonished to Follow Procedure
ML19341D046
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 12/05/1980
From: Hancock J
FLORIDA POWER CORP.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19341D032 List:
References
CS-80-281, NUDOCS 8103040759
Download: ML19341D046 (2)


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  1. 3-120-20 Mr. J. P. O'Reilly, Director Docket No. 50-302 Office of Inspection & Enforcement Licensee No. OPR-72 U.S. Nuclear Regulatory Comission Ref: FII:JJL 101 Marietta St., Suite 3100 50-302/80-36 Atlanta, GA 30303

Dear Mr. O'Reilly:

We offer the following responses to the Items of Noncompliance in the referenced inspection report.

NOTICE OF VIOLATION A. As required by 10 CFR 50, Appendix B, Criterion V, " Activities affecting quality shall be prescribed by documented instructions, procedures, ...and drawings." FSAR Section 1.7.6.7.1.e states in part that Florida Power Corporation has established written pro-cedures in accordance with the requirement of 10 CFR 50, Appendix B, Criterion V, and that these written procedures will be strictly adhered to in all matters relating to nuclear safety. Surveillance Procedure SP-180 requires that a work sheet with the dome survey information for the survey locations be filed with the data sheets for each surveillance inspection. SP-180 also requires that any change in dome elevation which exceeds the acceptance limit given in Table 1 of SP-180 be reported to the Technical Support Engineer for evaluation and resolution.

Contrary to the above:

1. The worksheets with the survey information for the dome survey locations were not filed with the data sheets for the dome surveillance inspections, 2 The change in elevation of point 1 on the dome as surveyed in I the July 1980 surveillance exceeded the acceptance limit stated in Table 1 of SP-180. This was not reported to and was not evaluated by the Technical Support Engineer.

A. Response: The subject worhheets have been investigated and all recoverable worksheets hav. been obtained and filed with the data sheets. Some of the worksheets, however, were not recoverable. The change in AEL that was entered on the data sheet after the surveyors signed off the AEL values was found to be erroneous. The actual change in 8103 04 0 7 sq General Office 3201 Tnirty-fourtn street soutn . P O Box 14042. st Petersburg. Fionda 33733 e 813-866 5151

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9 Notice of Violation Response RI'I:JJL 50-302/80-36 Page 2 AEL is within the acceptance criteria and is verified by the work sheet.

All persons involved have been admonished to follow SP-180. In addition, SP-180 will be revised to require reporting any data which failed to meet the acceptance criteria to the Performance Engineering Supervisor for his evaluation and resolution.

Full compliance will be achieved 1 January 1981.

B. As required by 10 CFR 50, Appendix B, Criterion V, " Activities affecting quality shall be prescribed by documented instructions, procedures,...

and shall be accomplished in accordance with these instructions, procedures, or drawings." FSAR Section 1.7.6.7.1.e states in part that Florida Power Corporation has established written procedures in accordance with the re-quirements of 10 CFR 50, Appendix B, Criterion V, and that these written procedures will be strictly adhered to in all matters relating to nuclear safety.

Paragraphs 6.2.2.8, 6.2.2.9, and 6.3.ld of Surveillance Procedure SP-182 re-quires that, when the average value of the wire force to achieve tendon lift-off is less than the lower limit or greater than the upper limits shown on Figures 1 through 3 of SP-182, adjacent tendons on each side of the tendon in question be checked to determine their lift-off force.

Contrary to the above, the lift-off forces were not measured for tendons ad-jacent to those which had lift-off forces greater than predicted in Figures 1 through 3 of SP-182.

B. Response: An evaluation of Fiour:s ' through 3 of SP-182, in comparison with Technical Specifications shms the pred9:ted lift-off forces to be lower than allowed by Technical Specifications, making SP-182 very conservative. This problem occurred due to an expected Technical Specification change which, in fact, did not take place, but was taken into consideration during the formu-lation of Figures 1 through 3 of SP-182. Using Technical Specification 4.6.1.6, Amendment 29, enforced at the time of the survey, which is also enforced at present, none of the~ tendons tested exceeded any limits end, therefore, no additional testing of the area surveyed is planned.

SP-182 will be revised prior to the next surveillance to reflect actual Tech-nical Specifications concerning tendon surveillance in force at that time.

The next surveillance is scheduled for the fall of 1981. The reason for the delay is due to a possible change to the Technical Specification.concerning tendon surveillance between now and the next surveillance.

Should there be further questions, please contact us.

Very truly yours, FLORIDA POWER CORPORATION Ik Wb "T J. A. Hancock fvpNuclearPlantManager Assistant Vice President Nuclear Operations .

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