ML20202B922

From kanterella
Jump to navigation Jump to search
Notice of Violation from Insp on 971130-980110.Violation Noted:On 971204,extension Cord Was Draped Across safety-related Cable Tray 1TX817B w/free-air Cables & Required one-foot Separation Was Not Maintained
ML20202B922
Person / Time
Site: River Bend Entergy icon.png
Issue date: 02/06/1998
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20202B904 List:
References
50-458-97-19, NUDOCS 9802120124
Download: ML20202B922 (3)


Text

i Et[QLOSURE__1 NOTICE OF VIOLATION Entergy Operations, Inc. Docket No.: 50-458 River Bend Station License No.: NPF-47 Durinp an NRC inspection conducted on November 30,1997, through January 10,1998, three violations of NRC requirements were identified, in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the violations are listed below:

A. 10 CFR Part 50, Appendix B, Criterion V, states, in part, " 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 .

Updated Final Safety Analysis Report Section 8.3.1.4.2 requires that safety related cables from different divisions and nonsafety-related cables be separated per the minimum allowable separation distances in Table 8.3.9, " Separation Criteria Allowable Versus Tested." Table 8.3-9 requires one foot of separation b% n a horizontal tray and a cable.

Procedure ADM-0073, " Temporary Installation Guidelines," Revision 2, Step 5.2, requires that temporary installations adhere to the design separation from divisional cable and that plant personnel be cognizant of the separation requirements of a temporary installation to divisional cabling as specified on Drawing EE-34ZE.

Drawing EE-34ZE, " Standard Details for Separation Requirements," Revision 7, identifies the separation requirements for free air cables to trays as orie foot.

Contrary to the above, on December 4,1997, an extension cord was draped across safety-related cable Tray 1TX8178, with free-air cables, and the required one-foot separation was not maintained.

This is a Severity Level IV violation (Supplemen I)(50-458/9719-01).

B. Technical Specification 5.5 states, in part, "the following programs and manuals shall be established, implemented, and maintained .

5.5.3 Post Accident Sampling . This program provides controls that ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The program shallinclude the following . Provisions for maintenance of sampling and analysis equipment."

9002120124 900206 PDR ADOCK 05000458 G PDR

t Contrary to the above, between March 3 and December 12,1997, provisions for maintenance of sampling and analysis equipment were inadequate to effectively ensure the capability to obtain and analyze reactor coolant, radioactive gases, and particulates in plant gaseous effluents and containment atmosphere samples under accident conditions. The postaccident sampling system was out of service for approximately 50 percent of the time during the subject period.

i This is a Severity Level IV violation (Supplement I)(50-458/9719-03).

C. 10 CFR Part 50, Appendix B, Criterion XVI, states, in part, " Measures shall be established to assure that conditions adverse to quality, such as . . . malfunctions . . . are promptly identified and corrected. In the case of significant conditions sdverse to quality, the measures shall assure that the cause of the condition is determined and corrective actions taken to preclude repetition . . "

Contrary to the above, on January 23,1997, a significant amount of air was found in reactor core isolation cooling flow instrument sensing lines (a significant condition adverse to quality) but established measures did not assure the cause of the air entrapment was identified, and actions were not taken to preclude repetition.

Consequently, the following problems were observed due to air entrapment in other system flow instrument lines: (1) on November 11,1997, the high pressure core spray ,

minimum flow valve malfunctioned; (2) on December 11,1997, the residual heat removal Train C minimum flow valve malfunctioned; and (3) on December 12,1997, the

residual heat removal Train B minimum flow valve malfunctioned.

This is a Severity Level IV violation (Supplement I)(50-458/9719-05).

Pursuant to the provisions of 10 CFR 2.201, Entergy Operations, Inc. is hereby required to submit a wntten 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,611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011,- and a copy to the NRC Resident inspector at the facility that is the subject of this Notice, within 30 days of the dati. f-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 previous 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 Demcnd 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.

l

._ )

If you contest this enfucement 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.

3 Under the authority of Section 182 of the Act 42 U.S.C. 2232, this response shall be submitted E 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 p3rsonal privacy or proprietary information is necessary to provide an acceptable response, then please provide a bracketed copy of ytur response that identifies the information that should be protected and a redacted copy of your ,

response that deletes such information. If you reques? withholding of such material, youjnust specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim of withholding (e.g., explain why the disclosure of information will c 9aie 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 information is nr - arv to provide an acceptable response, please provide the level of protection described in s 't i T3 21.

Dated at Arlington, Texas this 6th day of February 1998 s

_ _ _ _ _ _ _ _ _ _ _ ._