ML20248M134

Notice of Violation from Insp on 980329-0511.Violation Noted:Licensee Identified & Took Corrective Actions of Concerns W/Potential Effects of Flooding from Feedwater Line Break on Ability of Main Isolation Valves to Close

ML20248M134
Person / Time
Site:	Prairie Island
Issue date:	06/05/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20248M130	List: IR 05000282/1998007 ML20248M129 ML20248M134
References
50-282-98-07, 50-282-98-7, 50-306-98-07, 50-306-98-7, NUDOCS 9806150051
Download: ML20248M134 (3)

Text

I NUTICE OF VIOLATION Northem States Power Company Docket Nos.: 50-282; 50-306 Praine Island Nuclear Generating Plant Licenses Nos.: DPR-42; DPR-60 l

During an NRC inspection conducted from March 29 to May 11,1998, 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"

1. Criterion XVI, " Corrective Action," of Appendix B of 10 CFR Part 50 requires, in part, that l measures be established to assure that conditions adverse to quaiity are prnmptly l identified and corrected.

l Contrary to the above, on March 23 and 24,1998, the licensee identified and took corrective actions for concems with the potential effects of flooding from a feedwater line l break on the ability of the main steam isolation valves to close. However, the licensee i

failed to identify or take corrective actions for the potential effect of flooding on a main i steam isolation valve junction box in the room adjacent to the Unit 2 loop A main steam isolation valves, a condition adverse to quality, until the concem was identified by the NRC on April 22,1998.

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

2. Criterion V, " Instructions, Procedures, and Drawings," of Appendix B of 10 CFR Port 50 requires, in part, that activities affecting quality be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances.

Contrary to the above, on April 30,1998, Surveillance Procedure SP 1306, "D2 Diesel Generator Functional Test," Revision 3, a procedure for a Technical Specification-

. required test affecting quality, was not appropriate to the circumstances because it did not contain adequate isolation instructions to prevent an inadvertent start attempt of the diesel engine.

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

3. Criterion V, " Instructions, Procedures, and Drawings," of Appendix B of 10 CFR Part 50 requires, in part, that activities affecting quality be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances.

Contrary to the above, on February 9 and 10,1998, Work Orders 9800533 and 9800534 for the installation of auxiliary feedwater system flow element orifice plates, an activity affecting quality, were not appropriate to the circumstances because the work orders did not contain adequate instructions to ensure the proper orientation of the orifice plates. As a result, the orifice plates were installed backwards.

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

I 9806150051 980605 POR ADOCK 05000982 '

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r Notice of Violation 4. - Criterion XVI, " Corrective Action," of Appendix B of 10 CFR Part 50 requires, in past, that measures be established to assure that conditions adverse to quality are promptly identified and corrected.

Contrary to the above, inadequate acceptance criteria, conditions adverse to quality, were identified in May 1987 in Surveillance Procedures SP 2101, "21 Motor-Driven Auxiliary Feedwater Pump Once every Refuelir,g Shutdown," Revision 26, and SP 2103, "22 Turbine-Driven Auxiliary Feedwater Pump Once every Refueling Shutdown,"

ReviWo 29, and were still not corrected when the procedures were used on March 4 and 5.1998.

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

5. Criterion XI, " Test Control," of Appendix B of 10 CFR Part 50 requires, in part, that a test program be established to assure that all testing required to demonstrate that structures, systems, and components will pe23rm satisfactorily in service is identified and performed in accordance with writter test procedures which incorporate the requirements and acceptance limits contained in applicable design documents. The test program shall include, as appropriate, proof tests prior to installation, preoperational tests, and

. operational tests during nuclear power plant operation.

Contrary to the above,

s. on October 3,1995, preoperational testing of a safety-related backup air supply for the air-operated valves in the cooling water system .; trainers, installed per Temporary Modification 95PO47, did not include testing of the check valves which l would be required to isolate the backup system from the nonsafety-related instrument air system during a loss of instrument air pressure, and

b. as of May 11,1998, the test program for the safety-related backup air supply did L not include operational tests, and operational tests had not been conducted since the preoperational testing.

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

Pursuant to the provisions of 10 CFR 2.201, Northem States Power 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, l Region lil, 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 vio!stion, or,'if contested, the b& sis 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 viola *. ions, and (4) the date when full compliance will be achieved. Your response may reference or include previous dockoted

. correspondence, if the correspondence adequately addresses the required response if an

Notice of Violation 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, U.S. Nuclear Regulatory Commission, Washington, D.C.

20555-0001.

Because your response will be placed in the NRC Pubic Document Room (PDR), to the extent possible, it should not include any personal privacy, proprietary, or safeguards information to 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 ycur response that deletes such information. If you request withholding of such material, you mW.El specifically identify the portions of your response that you seek to have withheld and provide in detail the bases for your claim oi . withholding (e.g., explain why the disclosure of intanation 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 information is necessary to provide an acceptable response, please provide the level of protection described in 10 CFR 73.21.

Dated at Lisle, Illinois this day of June 1998 i

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