ML20217F649

Notice of Violation from Insp on 980223-0313 & 0330-0402. Violations Noted:On 980226,seismic Deficiency W/Containment Spray Heat Exchanger,That Had Been Identified in Late 1996 by Licensee,Had Not Been Adequately Corrected

ML20217F649
Person / Time
Site:	Oyster Creek
Issue date:	04/22/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20217F631	List: ML20217F627 ML20217F649 ML20217F664
References
50-219-98-80, NUDOCS 9804280221
Download: ML20217F649 (3)

Text

.

NOTICE OF VIOLATION GPU Nuclear incorporated Docket No. 50-219 Oyster Creek Nuclear Generating Station License No. DPR-16 1

During a NRC inspection conducted between February 23, and April 3,1998, for which exit meetings were held on March 20,1998, and via telephone on April 8,1998, four 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. Technical Specification (TS) 3.4.B.1 requires that: "Five electromatic relief valves of the automatic depressurization system shall be operable when the reactor water temperature is greater thea ;212*F and pressurized above 110 psig, except as specified in 3.4.B.2. Tlie automatic pressure relief function of these valves (but not the automatic depressurization function) may be inoperable or bypassed during {

reactor vessel pressure testing consistent with T.S.1.39 and 3.3.A.(l)." .

i TS Table 3.1.1, item G.1 requires High Drywell pressure instrumentation to be 1 operable to support ADS operability. TS 4.1.1, item 9 requires the High Drywell pressure instruments to be channel checked once per day. j Contrary to the above, on October 6,1996, when the automatic depressurization function was required during the Reactor Vessel Pressure Test, GPUN failed to perform the required High Drywell Pressure Channel Check in accordance with T.S.

4.1.1. Item 9, and therefore, failed to ensure ADS operability as required by TS , 3.4.B.1.

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

1 B. 10 CFR 50, Appendix B, Criterion V, instructions, Procedures, and Drawings, requires in part 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 l drawings."

Contrary to the above, GPUN personnel failed to follow established procedures for calculations and safety evaluations involving salety related activities in the following two instances:

(1) in early 1996, calculations to support the seismic adequacy of safety-related equipment (to address issues of NRC Generic Letter 87-02, Revision 1) were not verified as required by Procedure EP-06, Revision 3.03.  ;

9804280221 980422

~

l PDR G ADOCK 05000219 l PDR 1

~

( Notice cf Violation 2 (2) On February 26,1998, there were numerous examples of non-compliance with

Procedure EP-016, Nuclear Safety / Environmental Determination and Evaluation, which required a printed name and signature for engineer / originator, section i manager or project manager (for AEs), responsible technical reviewer, i

independent safety reviewer, and other reviews as applicable.

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

C. 10 CFR 50, Appendix B, Criterion XVI, Corrective Actions, requires, in part, that:

" Measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficienc;es, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.

Contrary to the above, on February 26,1998, a seismic deficiency with a containment spray heat exchanger, that had been identified in late 1996 by the licensee, had not been adequately corrected.

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

D. 10 CFR 50.59(b)(2) requires, in part, that licensees submit a report containing a brief description of any changes, tests and experiments (CTE), including a summary of the safety evaluation of each, annually or along with the UFSAR updates as required by 10 CFR 50.71(e) or at such shorter intervals as may be specified in the license.

Contrary to the above, as of March 12,1998, GPUN did not submit a CTE report for 1983 and 1986 for Oyster Creek Nuclear Generating Station, and the report submitted on February 16,1998, covered a period of April 1993 to March 1995.

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

Pursuant to the provisions of 10 CFR 2.201, GPU Nuclear incorporated is hereby required to submn 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 within 30 days of the l 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: (1) the reason for the violation, or, if contested, the basis for disputing the violation; (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 i correspondence adequately addresses the required response. If an adequate reply is not I l received within the time specified in this Notice, an order or a Demand for Information may l 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.

i

Notice of Violation 3 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 must 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 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 King of Prussia, PA this 22nd day of April,1998.

i l

\

l