IR 05000244/2002004

IR 05000244-02-004, on 05/19-06/29/2002, Rochester Gas & Electric; R. E. Ginna Nuclear Power Plant. Alert Notification System (ANS)

ML022070609
Person / Time
Site:	Ginna
Issue date:	07/25/2002
From:	Blough A Division Reactor Projects I
To:	Mecredy R Rochester Gas & Electric Corp
References
EA-02-141 IR-02-004
Download: ML022070609 (23)

Text

uly 25, 2002

SUBJECT:

R. E. GINNA - NRC INSPECTION REPORT NO. 50-244/02-04

Dear Dr. Mecredy:

On June 29, 2002, the NRC completed an inspection of your R. E. Ginna Facility. The enclosed report documents the inspection findings which were discussed with you and other members of your staff during an exit meeting on July 2, 2002.

The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your operating license. The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel.

Based on the results of this inspection, one preliminary finding of low to moderate safety significance (White) was identified. The finding is associated with a failure to ensure that the alert and notification system (ANS) was capable of performing its function. Specifically, long standing problems with the ANS siren feedback system prevented RG&E or the Counties from being able to identify which, if any, siren(s) activated and to conduct backup route alerting within 45 minutes for the populace covered by the failed siren(s). Using Manual Chapter 0609, Appendix B, section 5.0, "Failure to Meet a Risk Significant Planning Standard," and the Emergency Preparedness Risk determination flow chart to evaluate the finding, the finding screened to Yellow. However, the Emergency Preparedness Significance Determination Process (EP SDP) recognizes that a finding placed in context through the SDP can result in a color that exceeds the actual impact on public health and safety. We concluded that the problems with the ANS siren feedback system did not have a substantial impact on the EP Cornerstone Objective, and therefore, the finding does not rise to the level of substantial safety significance (Yellow) and is more appropriately characterized as low to moderate safety significance (White). The finding has low to moderate safety significance because there was a potential that the populace within the 10 mile emergency planning zone (EPZ) may not be promptly notified in the event of a radiological emergency at Ginna Station.

There is no immediate safety concern at this time due to the interim compensatory measures which are addressed in your June 14 and June 28, 2002, letters which are being reviewed by us with input from the Federal Emergency Management Agency.

Dr. Robert The finding is also an apparent violation of NRC requirements and is being considered for escalated enforcement action in accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600. The current Enforcement Policy is included on the NRCs website at www.nrc.gov/OE.

We believe that we have sufficient information to make a final significance determination.

However, before we make a final decision, you have the opportunity to request a Regulatory Conference, or provide a written position on your perspectives of the facts and assumptions applied by the NRC to determine this finding and its significance. If you choose to request a Regulatory Conference, you should be prepared to meet within 30 days of the receipt of this letter. In such case, we encourage you to provide supporting documentation at least one week prior to the conference in order to facilitate effectiveness and efficiency. A Regulatory Conference for a matter of this type would be open for public observation. If you decide to provide a written response, please send your submittal to the NRC within 30 days of the receipt of this letter.

Please contact Ms. Michele Evans, Chief, Reactor Projects Branch, at (610) 337-5224 within 10 business days of the date of receipt of this letter to notify the NRC of your intentions. If we have not heard from you within 10 days, we will continue with our significance determination and enforcement decision and you will be advised by separate correspondence of the results of our deliberations on this matter.

Since the NRC has not made a final determination in this matter, a Notice of Violation is not being issued for this inspection finding at this time. In addition, please be advised that the number and characterization of the apparent violation described in the enclosed inspection report may change as a result of further NRC review.

Immediately following the terrorist attacks on the World Trade Center and the Pentagon, the NRC issued an advisory recommending that nuclear power plant licensees go to the highest level of security, and all promptly did so . With continued uncertainty about the possibility of additional terrorist activities, the Nations nuclear power plants remain at the highest level of security and the NRC continues to monitor the situation. This advisory was followed by additional advisories, and although the specific actions are not releasable to the public, they generally include increased patrols, augmented security forces and capabilities, additional security posts, heightened coordination with law enforcement and military authorities, and more limited access of personnel and vehicles to the sites. The NRC has conducted various audits of your response to these advisories and your ability to respond to terrorist attacks with the capabilities of the current design basis threat (DBT). On February 25, 2002, the NRC issued an Order to all nuclear power plant licensees, requiring them to take certain additional interim compensatory measures to address the generalized high-level threat environment. With the issuance of the Order, we will evaluate Rochester Gas and Electric Corporations (RG&E)

compliance with these interim requirements.

Dr. Robert In accordance with 10 CFR 2.790 of the NRCs Rules of Practice, a copy of this letter and its 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 website at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

A. Randolph Blough, Director Division of Reactor Projects Docket No. 50-244 License No. DPR-18 Enclosure: Inspection Report 50-244/02-04 Attachment 1: Supplemental Information cc w/encl: P. Wilkens, President, Rochester Gas and Electric Corporation P. Eddy, Electric Division, Department of Public Service, State of New York C. Donaldson, Esquire, State of New York, Department of Law N. Reynolds, Esquire W. Flynn, President, New York State Energy Research and Development Authority J. Spath, Program Director, New York State Energy Research and Development Authority D. Stenger, Ballard Spahr Andrews and Ingersoll. LLP T. Wideman, Director, Wayne County Emergency Management Office M. Meisenzahl, Administrator, Monroe County, Office of Emergency Preparedness T. Judson, Central New York Citizens Awareness Network FEMA, Region II

Dr. Robert