ML20217M909

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Notice of Violation from Insp on 980209-27.Violation Noted:As of 980227,measures Were Not Established to Assure That Design Basis of safety-related MOVs Was Correctly Translated Into Specifications,Drawings & Instructions
ML20217M909
Person / Time
Site: Millstone Dominion icon.png
Issue date: 04/08/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20217M904 List:
References
50-423-98-82, NUDOCS 9804080253
Download: ML20217M909 (2)


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1 u NOTICE OF VIOLATION Northeast Nuclear Energy Company Docket No: 50-423 Millstone Unit 3 - License No: NPF-49 During an NRC inspection conducted from February 9 through 27,1998, a violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violation is listed below:

1. 10 CFR 50; Appendix B, Criterion 111, " Design Control," requires that measures shall be established to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions.

l Chapter 4, " Design inputs and Design Verification," of the Millstone Station Design Control Manual, Revision 6, states that " design inputs are those criteria, parameters, bases or other design requirements upon which the detailed f5al design is based." The Design Control Manual requires that "the accuracy and limitations of all design inputs must be determined and understood prior to their use in the design process."

Contrary to the above, as of February 27,1998, measures were not established to assure that the design basis of safety-related motor-operated valves (MOVs) was correctly translated into specifications, drawings, procedures,' and instructions in that certain MOV design basis thrust calculations were incorrect, as evidenced by.

the following types of errors:

' a. Thrust Calculation 89-094-1017ES," Millstone. Unit 3 Target Thrust / Torque -

Calculations for 3SIL*MV8801 A,3SIL*MV8801B,3SIL*MV8801C, and 3SIL*MV8801 D," Rev. 4, dated January 26,1998, for the safety injection accumulator outlet isolation valves was incorrect in evaluating the unwedging capability and the opening capability under maximum differential pressure conditions, in that the valve structural weak-link limit, in lieu of the actuator's open degraded voltage thrust capability, was used as an estimate of the motor-actuator output capability. Similar errors were noted in the thrust calculations for other MOVs.

b.- The database software tool called SMARTBOOKused to store and develop MOV thrust / torque calculations caused errors within the calculations by not selecting from specific indicated allowable torque and thrust limits. Such errors were present in Section 18 of Calculation 89-094-0900ES," Millstone Unit 3 Target Thrust / Torque Calculation for 3SIL*MV8804A and 3SIL*MV88048,"Rev. 5, dated February 9,1998, where an incorrect torque value was displayed in the comparison answer box. Also, in some cases -

SMARTBOOKtruncated the most significant digit of the torque value displayed in the comparison answer box. Such errors were present in Section 18 of Calculation 89-094-1017ES," Millstone Unit 3 Target Thrust / Torque Calculations for 3SIL*MV8801 A,3SIL*MV88018, 3SIL*MV8801C, and 3SIL*MV8801 D," Rev. 4, dated January 26,1998.

This is a Severity Level IV violation (Supplement 1).

9804000253 900327 PDR ADOCK 05000423

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Pursuant to the provisions of 10 CFR 2.201, Northeast Nuclear Energy Company 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 I, and a copy to the NRC Resident inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation (Notice). This 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, or, if contested, the basis for disputing the violation or severity level, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include pr'evious docketed correspondence, if the correspondence adequately addresses the required response. If an adequate reply is not

. received within the time specified in this Notice, an order or a Demand for Information may be issued as to why the license should not be modified,' suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

if you contest this enforcement action, you should also provide a copy of your response to the Director, Office of Enforcement, United States Nuclear Regulatory Commission, Washington, DC 20555-0001.

Under the authority of Section 182 of the'Act,42 U.S.C. 2232, this response shall be submitted under oath or affirmation.

Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information so that it can be placed in the PDR without redaction. If personal privacy or' proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of your response that identifies the information that should be protected and a redacted copy of your response that deletes such information. If you request withholding of such material, you mMal specifically identify the portions of your response that you seek to have withheld an'd provide in detail the bases for your claim of withhold-ing (e.g., explain why the disclosure of information will create an unwarranted invasion of personal privacy or provide the information required by 10 CFR 2.790(b) to support a request for withholding confidential commercial or financial information). If safeguards j information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

Dated at King of Prussia, Pennsylvania this 27th day of March,1998.

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