IR 05000269/1985025

Forwards Assessment of Denying Violations Noted in Insp Repts 50-269/85-25,50-270/85-25 & 50-287/85-25. Violation Remains as Stated.Supplemental Response Requested within 30 Days

ML20204K025
Person / Time
Site:	Oconee
Issue date:	07/31/1986
From:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:	Tucker H DUKE POWER CO.
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8608110263
Download: ML20204K025 (3)

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I July 31, 1986

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Cocket Nos. 50-269, 50-270, 50-287 License Nos. DPR-38, DPR-47, DPR-55 Duke Power Company ATTN: Mr. H. B. Tucker, Vice President Nuclear Production Department 422 South Church Street Charlotte, NC 28242 Gentlemen:

SUBJECT: INSPECTION REPORT NOS. 50-269/85-25, 50-270/85-25, AND 50-287/85-25 We have evaluated your response of October 14, 1985, to our Notice of Violation issued on September 19, 1985, concerning activities conducted at your Oconee facility under NRC Operating License Nos. DPR-38, DPR-47, and DPR-5 After careful review, we find you have presented no new information to change our findings regarding the violation. Our comments related to your response are enclosed. We have evaluated your response to the violation and found that it does not meet the requirements of 10 CFR 2.201; therefore, a supplemental'

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response is require This supplemental response should be submitted within 30 days of the date of this lette We appreciate your cooperation in this matte

Sincerely, ORIGML LEED On J. HELSON GRACE J. Nelson Grace Regional Administrator Enclosure:

Staff Assessment of Duke Power Company Denial of Violation for Oconee cc w/ encl:

M. S. Tuckman, Station Manager bcc (see page 2)

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Duke Power Company 2 July 31, 1986 bec w/ enc 1:

NRC Resident Inspector H. Nicolaras, NRR State of South Carolina Document Control Desk

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ENCLOSURE NRC STAFF ASSESSMENT OF DUKE POWER COMPANY DENIAL OF VIOLATION FOR OCONEE We have evaluated your response dated October 14, 1985, to the violation as stated in NRC Inspection Report Nos. 50-269/85-25, 50-270/85-25, and 50-287/85-25 concerning the inability to measure hydrogen concentrations in the containment structure. Our analysis and conclusions are as follows:

NRC agrees that,10 CFR 50.44(b) and NUREG-0737,. Item II.F.1.6, do not delineate specific surveillance requirements, nor do they delineate the limiting conditions i of operation (LCO) for the RB Hydrogen Monitoring Syste CFR 50.44(b) and -f NUREG-0737, Item II.F.1.6, however, do stipulate that operating reactors will have the capability to measure the hydrogen concentration in the containment structure. Oconee Nuclear Station was judged as having a syste.m capable of monitoring hydrogen concentrations based upon the information on instrument accuracy provided to the NRC by the Duke Power Company (DPC). Oconee Nuclear Station, therefore, meets the requirements of 10 CFR 50.44(b) and NUREG-0737, Item II.F.1.6 when, and only when, the system is in calibration according to the calibration standards provided by DPC and approved by the ' NRC. By DPC's admission, the subject equipment was not in calibration during the time period '

from March 6, 1985, to March 26, 1985, and therefore, not operable and capable of measuring the concentration of hydrogen in the containment structure during accident conditions to the required accuracy. This is a violation of 10 CFR 50.44(b). 1 In conclusion, your denial of this violation is not accepted and the violation remains as writte '

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