IR 05000400/2003006

IR 05000400-03-006, on 3/3-7/2003 and 4/7-10/200, Harris Nuclear Plant. Temporary Instruction (Ti) 2515/148, Verification of Compliance with Interim Compensatory Measures Order & Access Authorization/Behavioral Observation

ML031420553
Person / Time
Site:	Harris
Issue date:	05/22/2003
From:	Boland A Division of Reactor Safety II
To:	Scarola J Carolina Power & Light Co
References
IR-03-006
Download: ML031420553 (8)

Text

SUBJECT:

HARRIS NUCLEAR PLANT - NRC SAFEGUARDS INSPECTION REPORT 50-400/03-06

Dear Mr. Scarola:

On April 10, 2003, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Harris Nuclear Plant. The enclosed inspection report documents the inspection findings, which were discussed on April 10, 2003, with you and other members of your staff.

The inspection examined activities conducted under your license as they relate to safety and compliance with an Order issued on February 25, 2002, which required your site to implement specific measures related to security of your facility. The inspection used Temporary Instruction 2515/148, Inspection of Nuclear Reactor Safeguards Interim Compensatory Measures, to verify implementation of the Order as clarified in your responses dated March 18, 2002 and September 6, 2002. The inspection also reviewed other selected areas of the security program including performance indicators and behavioral observation/access authorization. Within these areas, the inspection consisted of selected examination of procedures and records, observation of activities, and interviews with personnel.

Based on the results of this inspection, the report documents an inspector-identified finding not related to the Interim Compensatory Measures, of very low safety significance (Green) which was determined to involve a violation of NRC requirements. However, because of the very low safety significance and because it has been entered into a corrective action process, the NRC is treating this finding as a non-cited violation (NCV) in accordance with Section VI.A of the NRCs Enforcement Policy. If you contest the NCV, you should provide a response within 30 days of the date of this inspection report, with a basis for your denial, to the U.S. Nuclear Regulatory Commission, ATTN.: Document Control Desk, Washington, DC 20555-0001; with DOCUMENT CONTAINS ENCLOSURE CONTAINS UPON SEPARATION THIS PAGE IS DECONTROLLED

CP&L 2 DOCUMENT CONTAINS copies to the Regional Administrator, Region II; the Director, Office of Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; and the NRC Resident Inspector at the Harris Facility.

In accordance with 10 CFR 2.790 of the NRCs "Rules of Practice," a copy of this letter, without the enclosed Safeguards Information, will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Should you have any questions concerning this letter, please contact us.

Sincerely,

/RA/

Anne T. Boland, Chief Plant Support Branch Division of Reactor Safety Docket No. 50-400 License Nos. NPF-63

Enclosure:

NRC Inspection Report 50-400/03-06

REGION II==

Docket No.: 50-400 License No.: NPF-63 Report No.: 50-400/03-06 Licensee: Carolina Power and Light Company Facility: Harris Nuclear Plant Location: New Hill, NC Dates: March 3-7 and April 7-10, 2003 Inspectors: Donald B. Forbes, Senior Physical Security Inspector Jerry D. Ennis, Physical Security Inspector Larry S. Mellen, Senior Emergency Preparedness Inspector James A. Canady, Acting Senior Resident Inspector Approved By: Anne T. Boland, Chief Plant Support Branch Division of Reactor Safety DOCUMENT CONTAINS ENCLOSURE CONTAINS UPON SEPARATION THIS PAGE IS DECONTROLLED SUMMARY OF FINDINGS IR 05000400/2003-006: Carolina Power and Light Company; 3/3-7/2003 and 4/7-10/2003; Harris Nuclear Plant, Unit 1; Temporary Instruction (TI) 2515/148, Verification of Compliance with Interim Compensatory Measures Order and Access Authorization/Behavioral Observation.

The report covered an announced inspection by two regional physical security inspectors, an emergency preparedness inspector, and a resident inspector. One Green non-cited violation (NCV) was identified. The significance of most findings is indicated by their color (Green, White, Yellow, Red) using Inspection Manual Chapter 0609, Significance Determination Process (SDP). Findings for which the SDP does not apply may be Green or assigned a Severity level after NRC management review. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.

A. Inspector-Identified and Self-Revealing Finding Cornerstone: Physical Security Green. Failure to remove a worker, whose fitness may have been questionable, from activities within the scope of 10 CFR Part 26.

An inspector identified non-cited violation of 10 CFR 26.27(4)(b)(1) was identified. The finding is greater than minor, because if left uncorrected, the issue could have become a more significant safety concern in that the trustworthiness and reliability of employees is an critical attribute of the Physical Protection Cornerstone objective. It was determined to be of very low safety significance because it involved a failure to meet regulatory requirements involving the access control/behavioral observation program; however, there was no malevolent action and there have not been greater than two similar findings in the previous four quarters. (Section VII.B)

B. Licensee-Identified Violations None DOCUMENT CONTAINS ENCLOSURE CONTAINS UPON SEPARATION THIS PAGE IS DECONTROLLED