ML18012A491

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Notice of Violation from Insp on 961124-970104.Violations Noted:Inspector Identified Where Licensee Failed to Assure, Over Extended Period of Time
ML18012A491
Person / Time
Site: Harris Duke Energy icon.png
Issue date: 01/31/1997
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML18012A490 List:
References
50-400-96-11, NUDOCS 9702070452
Download: ML18012A491 (3)


Text

NOTICE OF VIOLATION Carolina Power 5 Light Company Shearon Harris Unit 1 Docket No. 50-400 License No.

NPF-63 During an NRC inspection conducted from November 24, 1996 through January 4, 1997, 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.

B.

Technical Specification 6.8.1.a.

requires written procedures to be established, implemented, and maintained covering the activities recommended in Appendix A of Regulatory Guide 1.33, Revision 2.

February 1978.

Regulatory Guide 1.33, Item 1.a references procedures for operator log-keeping.

Items 3.n and 5 reference procedures for the chemical and volume control system and for abnormal, offnormal or alarm conditions, respectively.

OHN-016, Revision 8, Operator

Logs, Paragraph 5.1.b, Operations Shift Records, requires operators, in part, zo check each

- operating recorder chart at least once per shift to assure that pens are marking properly and timing correctly. It further requires operators to mark each chart with the time the check is performed and initial.

Contrary to the above, on December 4,

1996, the inspector identified where the licensee failed to assure, over an extended period of time, that the steam generator "A" feed flow red pen was properly marking the chart recorder as required.

2.

APP-111, Revision 6, Freeze Protection and Temperature Haintenance, various sections, required operators to notify the main control room of heat trace trouble alarms.

Certain heat trace trouble alarms (in the radwaste control room) are associated with circuits which heat safety-related boric acid lines in the chemical and volume control system.

Contrary to the above, on December 12 and 13, 1996, operators failed to notify the main control room of several alarming conditions occurring locally at temperature maintenance panels affecting safety-related boric acid lines'he corresponding central alarm in the radwaste control room had been "locked in" for weeks such that operators were unaware of and therefore could not promptly respond to new local alarming conditions observed by the inspector.

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

Technical Specification 4.3.3.5.2 requires in part, that each Remote Shutdown System transfer switch, power and control circuit and control switch (required by the Shearon Harris Nuclear Power Plant Safe Shutdown Enclosure 1

9702070452 970i3f PDR ADOCK 05000400 8

PDR

CPSL Analysis to control Reactor Coolant System pressure) shall be demonstrated OPERABLE at least once per 18 months.

Contr ary to the above, between September 2,

1995, and December 18,
1996, the licensee failed to test the remote shutdown system control circuit for block valve 1RC-115 associated with a reactor coolant system power operated relief valve.

The valve had not been tested since the Spring 1994 refueling outage, approximately 32 months earlier This is a Severity Level IV Violation (Supplement 1)

C.

10 CFR 50, Appendix B, Criterion XVI, Corrective Action, requires that measures be established to assure that conditions adverse to quality such as deficiencies, deviations, and nonconformances are promptly identified and corrected.

These requirements are further delineated in Section 12 of the licensee's corporate Quality Assurance Program Hanual, Revision 18.

Contrary to the above, after September 1.

1996, when plant personnel identified that clearance tags had been improperly relied upon for nearly a year to implement design basis changes to the emergency service water
system, the licensee failed to correct the adverse condition and issue a temporary modification to reflect associated valve lineup changes.

No modification was issued until December 11, 1996, after the NRC inspectors questioned the practice of using valve clearance tags to implement design basis changes isolating emergency service water flow to two fan units, AH-86A and AH-86B, in order to ensure adequate flow to other safety-related parts of the system.

This is a Severity Level IV Violation (Supplement 1)

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 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 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 fur ther 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 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.

Enclosure 1

CPSL 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.

However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the

PDR, and provide the legal basis to support your request for withholding the information from the public.

Dated at Atlanta, Georgia this 31st day of January 1997 Enclosure 1