ML14181A981

Notice of Violation from Insp on 980105-09.Violation Noted: as of 970407,licensee Failed to Correct Conditions Adverse to Quality Associated W/Instrument Sensing Line Slope Deficiencies Documented in Ltrs & 960221

ML14181A981
Person / Time
Site:	Robinson
Issue date:	02/06/1998
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML14181A980	List: ML14181A981
References
50-261-98-03, 50-261-98-3, EA-98-043, EA-98-43, NUDOCS 9802170036
Download: ML14181A981 (3)

Text

NOTICE OF VIOLATION Carolina Power and Light Company Docket No. 50-261 Robinson Nuclear Plant License No. DPR-23 EA 98-043 During an NRC inspection conducted on January 5-9, 1998, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedures for NRC Enforcement Actions," NUREG-1600, the violation is listed below:

A.

10 CFR 50, Appendix B. Criterion XVI requires that measures shall be established to assure that conditions adverse to quality, such as failures, malfunctions, deficiencies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected.

Contrary to the above, as of April 7, 1997, the licensee failed to correct conditions adverse to quality associated with instrument sensing line slope deficiencies documented in CP&L letters to NRC dated September 14, 1994, and February 21, 1996,

Subject:

Reply to a Notice of Violation for NRC Inspection Report numbers 50-261/94

)

17 and 95-30.

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

B.

10 CFR 50.46(a)(3)(ii) requires each significant change to or error discovered in an acceptable evaluation model or in the application of such a model that affect the peak cladding temperature calculation, be reported to NRC within 30 days.

Significant change or error is defined in 10 CFR 50.46(a)(3)(I) as one that results in a peak cladding temperature different by more than 500F from the temperature calculated for the limiting tran sient using the last acceptable model.

Contrary to the above; the licensee failed to report a significant change in peak cladding temperature from 2006 0F to 2064F, as calculated on April 24. 1996, to the Commission between May 24, 1996, and October 14, 1996.

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

C.

10 CFR 50.59, "Changes: Tests, and Experiments" provides in part, that the licensee may make changes in the facility or procedures as described in the safety analysis report (SAR) without prior Commission approval, unless the proposed changes involves an 9802170036 980206 PDR ADOCK 05000261 G

PDR

2 unreviewed safety question. The licensee shall maintain records of the changes to the extent that the changes constitute a change as described in the SAR. These.records must include a written safety evaluation which provides the basis for the determination that the change does not involve an unreviewed safety question.

Contrary to the above, as of April 7, 1997, the licensee failed to perform a safety evaluation which provided the basis for the determination that a change to the facility did not involve an unreviewed safety system. Specifically., the 50.59 Safety Evaluation Screen performed on March 7, 1996, to address replacement of motor pinions and worm shaft clutch gears for Valves RHR-744 A & B, under Engineering Service Request 9600012, was inadequate. The activity resulted in increasing the motor operator valve stroke times beyond the ten seconds specified in UFSAR Section 6.3.2.2.12 and thus resulted in a change to the facility described in the UFSAR and no safety evaluation was performed. The modifications to the valves which increased the stroke times beyond ten seconds were implemented in 1996.

This is a Severity Level IV violation (Supplement I)

D.

10 CFR 50.9 (a) requires, in part, that information required by statute or by the Commission's regulations, order, or license condition to be maintained by the licensee shall be complete and accurate in all material respects.

UFSAR Section 8.3.1.3 states that control cables are separated into two basic channels as required for redundant circuits. Cables assigned to these channels for separation are required to be in their respective channels from the beginning of the cable to the final termination.

Contrary to the above, as of May 25,-1997, safety injection pump C autostart cable C2239C and manual cable C2239D were in the same channel (cable tray) as the SI pump A autostart cable C2237D and the SI pump B (train A line up) autostart cable C2891C. The information the licensee provided to NRC in the UFSAR was not accurate.

This is a Severity Level IV violation (Supplement I)

Pursuant to the provisions of 10 CFR 2.201. Carolina Power and Light 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 II..and a copy to the NRC Resident Inspector at the Robinson facility, within 30 days of the date of

.the letter transmitting this Notice of Violation (Notice). This reply should

3 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 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, D.C. 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 must specifically identify the portions of your response that you week 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 Atlanta, Georgia this 6th day of February 1998