ML20207L834

Notice of Violation from Insp on 880629-0718,Violation Noted:Failure to Verify Adequacy of Design & Perform Design Analysis Utilizing Contractor Computer Program to Perform Setpoint Analysis for Cycle 11

ML20207L834
Person / Time
Site:	Fort Calhoun
Issue date:	10/12/1988
From:	Martin R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20207L829	List: IR 05000285/1988022 ML20207L834
References
50-285-88-22, NUDOCS 8810170485
Download: ML20207L834 (3)

Text

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NOTICE OF VIOLATION l

Omaha Public Power District Docket No. 50-285 Fort Calhoun Station License No. DPR-40 EA 88-201 During an NRC inspection conducted during the period June 29 through July 18, 1988, violations of NRC requirements were identified, in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2 Appendix C (1988), the violations are listed below:

A. 10 CFR Part 50, Appendix B, Criterien 111 states, in part, that measures shall be established to assure that applicable regulatory requirements and the design basis, as defined in Section 50.2, for those structures, systems and componer,ts to which Appendix B applies are correctly translated into specifications, drawings, procedures and instructions and that the design control measures shall provide for verifying or checking the adequacy of design.

The approved "Quality Assurance Program," Section A.4, "Design Control,"

of Appendix A to the updated Safety Analysis Report for the Fort Calhoun Station states, in part, that the verification of engineering and design adequacy of the contractors' design documents is performed in accordance with an OPPD approved quality program and procedures.

Paragraph 4.3.5 of Section :i.1 of the licensee's Quality Assurance Manual, "Control of Plant Design and Modifications," states, in part, that design analyses such as physics, stress, thermal, hydraulic, and accident analyses, shall be performed in a planned, controlled, and correct manner.

Contrary to the above, OPPD failed to verify the adequacy of design and failed to perform design analyses in a correct manner in that OPPD util' zed a computer program supplied by a contractor to perform setpoint analyses for Cycle 11 reactor operations without verifying the adequacy and correct use of the computer code. The licensee failed to determine all factors required to be used in computer-derived calculations of the setpoints for the thermal margin / low pressure rea: tor trip function of the Reactor Protection System, resulting in setpoints that reduced the margin of safety. This condition existed from June 7,1987, when Cycle 11 operations began, until June 29, 1988, when this condition was corrected.

This is a Severity Level !!! violation (Supplement I) (285/8822-01).

B. Section 50.9 of 10 CFR Part 50 states, in part, that information provided to the ConTnission by a licensee shall be complete and accurate in all material respects.

Contrary to the above, the licensee submitted a letter, dated July 1, 1988, that stated the shift supervisor had placed instructions in his log to reduce reactor power to 80 percent if the excore detectors were used to 8810170485 esgot; PDR ADocg ogoopg5 Q PDC

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, Notice of Violation measure linear heat rate. The NRC inspector noted following NRC's receipt of the July 1 letter that the shif t supervisor's log did not contain instructions to reduce reactor power to 80 percent.

This is a Severity Level IV violation. (Supplement 1) (285/8822-02)

Pursuant to the provisions of 10 CFR 2.201, Omaha Public Power District is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region IV, and a copy to the NRC Resident Inspector at Fort Calhoun Station within 30 days of the date of the letter transmitting this Notice. The reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation:

(1) the reason for the violation if admitted the corrective steps t1at will be havebeentakenandtheresultsachieved,)(3}(2)thecorrective taken to avoid further violations, and (4 the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COPFilSSION Y Y{fk Robert D. Martin Regional Administrator Dated at Arlington, Texas, ,

this 12th day of October 1988. '

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