IR 05000219/2002004

IR 05000219/2002-004; on March 26-29, 2002; Amergen Energy Company, LLC; Oyster Creek; Action on White Finding in the Area of Physical Protection; Safeguards

ML021260188
Person / Time
Site:	Oyster Creek
Issue date:	05/03/2002
From:	Lanning W Division of Reactor Safety I
To:	Skolds J Exelon Generation Co, Exelon Nuclear
References
IR-02-004
Download: ML021260188 (12)

Text

SUBJECT:

OYSTER CREEK GENERATING STATION - NRC SUPPLEMENTAL INSPECTION REPORT NO. 50-219/02-04

Dear Mr. Skolds:

On March 29, 2002, the NRC completed a supplemental inspection at your Oyster Creek reactor facility. During this inspection, the NRC reviewed evaluations and corrective actions completed by your staff in response to a White finding (i.e. a matter having low to moderate safety significance) involving a response strategy weakness identified during an Operational Safeguards Response Evaluation (OSRE) conducted May 7 - 10, 2001. The enclosed report documents the inspection findings which were discussed on March 29, 2002, with Mr. Ron DeGregorio and other members of your staff.

Based on the inspection results, we concluded that your evaluations were of adequate detail and commensurate with the significance of this performance issue. The inspector confirmed that your staff effectively identified the underlying causes of this matter, and implemented appropriate corrective actions.

Due to your acceptable performance in addressing this performance issue, consistent with the guidance contained in NRC Inspection Manual Chapter (IMC) 0305, Operating Reactor Assessment Program, this issue will only be considered in assessing plant performance for a total of four quarters from the date when the issue was identified on May 30, 2001. As specified in IMC 0305, a Regulatory Performance Meeting was conducted in a conference call on May 2, 2002, between your Security Manager, Mr. Rick Ewart, and Mr. John White of our staff. Previously, this matter was discussed in the Annual Public Meeting at Oyster Creek on April 11, 2002.

Mr. Jack Skolds -2-This report contains Safeguards Information (SGI) that must be protected against unauthorized disclosure in accordance with 10 CFR 73.21. In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter and the enclosed inspection report without the SGI enclosure 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).

Sincerely,

/RA/

Wayne D. Lanning, Director Division of Reactor Safety Docket No: 50-219 License No: DPR-16

Enclosure:

Inspection Report No. 50-219/02-04 (Contains Safeguards Information)

REGION I==

Docket No. 50-219 License No. DPR-16 Report No. 50-219/02-04 Licensee: AmerGen Energy Company, LLC Facility: Oyster Creek Generating Station Location: Forked River, New Jersey Dates: March 26-29, 2002 Inspector: Gregory C. Smith, Senior Physical Security Inspector Approved by: John R. White, Chief Radiation Safety and Safeguards Branch Division of Reactor Safety

SUMMARY OF FINDINGS

IR 05000219-02-04; on March 26-29, 2002; AmerGen Energy Company, LLC; Oyster Creek;

Action on White finding in the area of Physical Protection; Safeguards.

Cornerstone: Physical Protection

This supplemental inspection was performed by the NRC to assess AmerGens evaluations and corrective actions associated with a White finding involving a vulnerable protected strategy that resulted in the loss of a target set. This finding was identified during an Operational Safeguards Response Evaluation (OSRE) conducted May 7-10, 2001 and documented in inspection report 50-219/01-11 dated June 22, 2001. This current inspection was conducted in accordance with NRC Inspection Procedure 95001, Inspection for One or Two White Inputs in a Strategic Performance Area. The inspector determined that AmerGen effectively evaluated the finding, identified root and contributing causes, and established and implemented appropriate corrective actions. Consistent with the guidance contained in NRC Inspection Manual Chapter (IMC) 0305, Operating Reactor Assessment Program, this issue will only be considered in assessing plant performance for a total of four quarters from the date when the issue was identified on May 30, 2001.

ii 01

INSPECTION SCOPE

This supplemental inspection was performed to assess the licensees evaluations and corrective actions associated with a previously identified White finding involving the Physical Protection cornerstone of the Safeguards Strategic performance area.

Specifically, the White finding involved a vulnerability in the licensees protective strategy (i.e. the means and methods employed to protect against the design basis threat of radiological sabotage) that was identified as the result of an Operational Safeguard Response Evaluation (OSRE) conducted by the NRC on May 7-10, 2001.

Background The finding was preliminarily characterized as White (low to moderate risk significance)in NRC Inspection Report 50-219/01-11 dated June 22, 2001. Subsequently, this matter was discussed in a Regulatory Conference on August 3, 2001. Following the Regulatory Conference, the NRC considered the information provided by the licensee, made a final determination that issue constituted a White finding, and so informed the licensee in a letter dated August 28, 2001.

On September 12, 2001, the licensee appealed the NRCs final significance determination. On April 15, 2002, the NRC provided the results of the appeal and notified the licensee that the appeal panel concluded that the finding had been appropriately characterized as White, in accordance with NRC Manual Chapter 0609, Significance Determination Process.

EVALUATION OF INSPECTION REQUIREMENTS 02.01 THESE PARAGRAPHS CONTAIN AND IS NOT FOR PUBLIC DISCLOSURE - IT IS INTENTIONALLY LEFT BLANK.

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03 MANAGEMENT MEETINGS The inspector and the Radiation Safety and Safeguards Branch Chief met with licensee representatives on March 29, 2002. At that time, the purpose, scope, and findings were summarized.

KEY POINTS OF CONTACT Licensee E. Harkness Plant Manager J. Rogers Sr. Licensing Engineer R. Ewert Security Manager R. Pezzella Security Analyst M. Basti Security Analyst State of New Jersey D. Zannoni Dept. of Environmental Resources NRC L. Dudes Senior Resident Inspector, Oyster Creek J. White Chief, Radiation Safety and Safeguards Branch, DRS LIST OF ITEMS CLOSED Closed 50-219/01-11-01 FIN In an evaluated exercise (OSRE), the response strategy was insufficient to successfully interdict an adversary force. Based on this performance problem, the NRC OSRE team was unable to confirm that the design of the physical protection system was sufficient to protect against a design basis threat of radiological sabotage.

DOCUMENTS REVIEWED

Root Cause Report, CAP 02001-0796

Memo on OSRE, Lessons Learned, dated May 30, 2001

Oyster Creek Generating Station Procedure 307, Isolation Condenser System, Rev. 79, dated

January 18, 2002

Force-on-Force drill critiques for selected Force-on-Force drills conducted since May 2001

Oyster Creek Nuclear Generating Station NRC-Approved Physical Security Plan