ML20217D414

Interim Part 21 Rept Re Errors Noted During Preparation of ITS Surveillance Test Procedures Using GE Calculated Setpoints.Setpoint Calculations Will Be Reviewed,Corrected & Approved to Establish Significance of Errors

ML20217D414
Person / Time
Site:	Cooper
Issue date:	09/29/1997
From:	Graham P NEBRASKA PUBLIC POWER DISTRICT
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
REF-PT21-97 NLS970124, NUDOCS 9710030170
Download: ML20217D414 (5)

Text

. l P.O 00X W LL NES SKA 64321 Nebraska Public Power District

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gu NLS970124 September 29,1997 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555-0001 Gentlemen:

Subject:

Interim Report Pursuant to 10 CFR 21.21(a)(2)

Cooper Nuclear Station, NRC Docket 50-298, DPR-46 Under the notification requirements of 10 CFR 21.21(a)(2), an interim report must be prepared and submitted to the Commission within 60 days ofdiscovety of a deviation or failure to comply that has the potential to have created a substantial safety hazard. Accordingly, the Nebraska Public Power District (the District) is herein notifying the Commission of a condition where safety related calculations provided to the District by General Electric Nuclear Energy were found to contain nonconservative errors. While a preliminary review suggests a substantial safety hazard would not have been created, an in-depth evaluation has yet to be completed. Attachment I to this letter provides additional information concerning this condition.

Should you have any questions or require any additional information, please contact me.

Sincerely,

%9/AA-Philip D. Graham Vice President of Nuclear Energy

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USNRC - Region IV Senior Project Manager USNRC - NRR Project Directorate IV-1 9710030170 970929' ~

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NLS970124 September 29,1997 Page 2 0f 2 Senior Resident Inspector USNRC-- Tyrone Slayton GE Nuclear Energy NPG Distribution 1

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         - Attachment l-to NLS970124
         .Page1of2 Interim Report Pursuant to 10 CFR 21.21(a)(2) 4 Cooper Nuclear Station, NRC Docket 50-298, DPR-46 Under the notification requirements of 10 CFR 21.21(a)(2), an interim report must be prepared

+ and submitted to the Commission within 60 days of discovery of a deviation or failure to comply the has the potential to have created a substantial safety hazard. Accordingly, the Nebraska Public Power District (the District)is herein notifying the Commission of a condition where safety

         . related calculations provided to the District were found to contain nonconservative errors, The following prosides additional details associated with this condition.

DJckground f

General Electric Nuclear Energy (GE) was authorized by the District to provide setpoint calculations for analytical limits, allowable values, and nominal trip setpoints for the Cooper Nuclear Station (CNS) Improved Technical Specifications (ITS) project, The work was classified as Essential (Nuclear-Safety Related) and was performed under GE's quality assurance program in accordance with Senice Agreement Number 86A-MS2, Task Authorization Number 376 The calculated allowable values were subsequently submitted to the Commiesion as part of the ,

ITS submittall' Deviation or Failure to Comply

          - During the preparation ofITS sun >eillance test procedures using the GE calculated setpoints, it was discovered that several of the setpoint calculations contained errors. Specificahy, it was discovered that, in'some instances, the calculated setpoints would exceed the calculated allowable          ,

values when considering as-left tolerances. Further, a sample review of the setpoint calculations indicated that some setpoint calculations contained errors that affect the allowable values already provided to the Commission in the ITS submittal and the associated nominal setpoints. Substantial Safety Hazard Evaluatioil Since the setpoint calculations were performed in support ofITS which has yet to be approved and implemented, the errors have no impact to current plant operations. A preliminary review suggests a substantial safety hazard would not have been created; however, an in-depth evaluation

          . has yet to be completed.
                    '       Letter (NLS970002) to USNRC from G. R. Horn (NPPD) dated March 27,1997,
                            " Proposed Change to CNS Technical Specifications Conversion to Improved Standard Technical Specifications, Cooper Nuclear Station, NRC Docket No. 50-298, License No. DPR-46" m_

     ,                                                                                                           s Attachment I to NLS970124 Page 2 of 2 The Commission has been apprised of the errors with regard to the ITS submittal.

To establish the significance of the errors, the setpoint calculations will be reviewed, corrected

             . and approved, and the results compared to those supplied by GE. Discrepancies resulting from errors introduced by GE will then be evaluated to determine if a substantial safety hazard could have been created, assuming the original calculationis were implemented as supplied. This in.

depth evcluation will be completed by January 9,1998. u

_ _ _ _ _ _ _ _ . . _ _ .m.. _- __ _ _

         .           ATTACHMElJT 3 LIST or NRC COMMITMENTS                                                                                 l 4

Correspondence Not_NLS970124 The*following tabla identifies those actions committed to by the District in this document. Any other actions discussed in the submittal represent intended or planned actions by the District. They are described to the NRC for the NRC's inf or:..ation and are not regulatoly commitments. Please notify the Licensing Manapr at Cooper Nuclear Station of any questions regarding this document or any associa<;ed regulatory commitments. Colt 41TTED DATE COMMITMENT OR OUTAGE To establish the significance of the errors, the setpoint calculations will be reviewed, corrected and approved, and the results compared to those supplied by GE. Discrepancies resulting from errors introduced 'oy GE Will anuary 9, IW then be evaluated to determine if a substantial safety hazard could have been created, assuming the original calculations were implemented as supplied. { 1 l 1 1 l PROCEDURE NUMBER 0.42 l REVISION NUMBER 5 l PAGE 9 OF 13 l

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