ML20151Y022

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Notice of Violation from Insp on 880207-0402.Violations Noted:Msiv B Tested While in Mode 2,resulting in Steam Generator Oscillations & Reactor Trip Due to Low Low Steam Generator Level
ML20151Y022
Person / Time
Site: Callaway Ameren icon.png
Issue date: 04/27/1988
From: Knop R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20151X990 List:
References
50-483-88-04, 50-483-88-4, NUDOCS 8805040311
Download: ML20151Y022 (2)


Text

. i NOTICE OF VIOLATION Union Electric Company Docket No. 50-483 As a result of the inspection contiucted on February 7 through April 2,1988, and in accordance with the "General Policy and Procedures for NRC Enforcement

' Action," 10 CFR Part 2, Appendix C (1985), the following violations were identified:

The Code of Federal Regulations; 10 CFR, Part 50, Appendix B, Criterion V. -

Instructions, Procedures, and Drawings requires that: Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances and shall be accomplished in accordance with these instructions, procedures, or drawings.

Union Electric Operating Quality Assurance Manual (0QAM) Section 5 Instructions, Procedures and Drawings, Paragraph 5.1 specifies that the activities affecting quality associated with the operating phase shall be accomplished in accordance with documented instructions, procedures, drawings or checklists which specify the methods for complying with 10 CFR 50, Appendix B and the Technical Specifications.

a. 0QAM, Paragraph 5.2 specifies that activities affecting quality shall be controlled by using approved drawings, procedures, instructions or checklists to accomplish an activity.

The initial conditions of retest procedure OSP-AB-V002 B for Testing of the Main Steam Isolation Valve (MSIV) "B" specified that the plant be in Mode 3.

Contrary to the above, while in Mode 2, on November 8,1987 at 2:52 AM CST, Valve MSIV "B" was tested, resulting in Steam Generator (S/G) oscillations and reactor trip due to Low Low S/G Level,

b. 0QAM, Paragraph 5.2 specifies that activities affecting quality shall be controlled by using approved drawings, procedures, instructions or checklists to accomplish an activity.

Contrary to the above, while in Mode 1, on January 4,1988 at 2:36 AM CST, applicable wiring Drawing AE-PSL-0039A was not used during trouble shooting activities associated with the Main Feedwater Isolation Valve AE-FV-39. The incorrect placement of a jumper resulted in a reactor trip on Low Low Steam Generator Level,

c. 0QAM, Paragraph 5.2 specifies that activities affecting quality shall be controlled by preparing procedures, instructions, specifications, drawings or checklists of a type appropriate to the activity and its importance to safety; including in these documents quantitative or qualitative acceptance criteria for verifying that an activity has been satisfactorily accomplished.

8805040311 G80427 PDR ADOCK 05000483 O DCD

Notice of Violation 2 Contrary to the above, Plant Emergency Procedure ES-0.1 (Reactor Trip Response) did not include appropriate instructions for the closing of main steam isolation valves (MSIVs). The failure to close MSIVs following a reactor trip on February 13, 1988, resulted in low steam line pressure and automatic initiation of safety injection.

Collectively,)the (Supplement 1 (483/88004-02(DRP)). above examples comprise a Severity Level IV violation The inspection showed that action had been taken to correct the identified violations and to prevent recurrence. Consequently, no reply to the violations is required and we have no further questions regarding this matter.

Dated

!APR 2 71988

[(

Richard C. Knop, Chief q

Reactor Projects Branch 3 s

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