IR 05000263/2005007

IR 05000263-05-007 (DRS) on 01/10/2005 - 01/12/2005 for Monticello Nuclear Generating Plant; Safety System Design and Performance Capability

ML050540545
Person / Time
Site:	Monticello
Issue date:	02/23/2005
From:	Kenneth Riemer Division of Reactor Safety III
To:	Thomas J. Palmisano Nuclear Management Co
References
IR-05-007
Download: ML050540545 (11)

Text

ary 23, 2005

SUBJECT:

MONTICELLO NUCLEAR GENERATING PLANT NRC INSPECTION REPORT 05000263/2005007(DRS)

Dear Mr. Palmisano:

On February 4, 2005, the U.S. Nuclear Regulatory Commission (NRC) completed an inspection at your Monticello Nuclear Generating Plant. The enclosed report documents the inspection findings which were discussed with your on-site staff on January 12, with you on January 14, and with your corporate staff on February 4.

The inspection examined activities conducted under your license as they relate to safety and to compliance with the Commissions rules and regulations and with the conditions of your license.

The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Specifically, this inspection focused on the Alert and Notification System (ANS)

performance indicator (PI).

On the basis of the results of this inspection, no findings of significance were identified.

An unresolved item (URI) was identified associated with the ANS PI data submitted by the licensee for the first calendar quarter of 2003. Specifically, your staff reported the subject PI as Green for the first calender quarter of 2003 based on counting the results of weekly and monthly siren tests. However, the inspectors calculated a lower ANS PI value using only the monthly siren test results which would have potentially resulted in a White PI. At the end of the inspection period, NRC headquarters and regional personnel were reviewing your actions and procedures to determine if your activities were consistent with station procedures in effect at the time data was gathered, and to determine whether your ANS PI calculations associated with the first quarter 2003 data were consistent with guidance provided in Nuclear Energy Institute (NEI)

Publication No. 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 2. In accordance with 10 CFR 2.390 of the NRC's "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 NRC's 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/

Kenneth R. Riemer, Chief Security and Preparedness Branch Division of Reactor Safety Docket No. 50-263 License No. DPR-22 Enclosure: Inspection Report 05000263/2005007(DRS)

cc w/encl: J. Cowan, Executive Vice President and Chief Nuclear Officer Manager, Regulatory Affairs J. Rogoff, Vice President, Counsel, and Secretary Nuclear Asset Manager, Xcel Energy, Inc.

Commissioner, Minnesota Department of Health R. Nelson, President Minnesota Environmental Control Citizens Association (MECCA)

Commissioner, Minnesota Pollution Control Agency D. Gruber, Auditor/Treasurer, Wright County Government Center Commissioner, Minnesota Department of Commerce Manager - Environmental Protection Division Minnesota Attorney Generals Office

SUMMARY OF FINDINGS

IR 05000263/2005007(DRS); 01/10/2005 - 01/12/2005; Monticello Nuclear Generating Plant;

Performance Indicator Verification.

The inspection was a three-day on-site inspection, supplemented by further in-office review of the Alert and Notification System (ANS) siren performance indicator. The inspection was conducted by a regional emergency preparedness inspector and an emergency preparedness specialist from the Emergency Preparedness Directorate, Office of Nuclear Security and Incident Response. 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 be assigned a severity level after NRC management review. The NRC's program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, "Reactor Oversight Process," Revision 3, dated July 2000.

No findings of significance were identified.

A. Inspector-Identified and Self-Revealed Findings

Cornerstone: Emergency Preparedness

• TBD. An unresolved item (URI) was identified associated with the ANS Performance Indicator (PI) data submitted by the licensee for the first calendar quarter of 2003.

Specifically, additional NRC review was required to determine if the Monticello staffs first quarter 2003 ANS PI results, as reported to the NRC, were consistent with procedures in effect at the time data was gathered. Also, additional NRC review was required to determine whether ANS PI calculations associated with the first quarter 2003 data were consistent with guidance provided in Nuclear Energy Institute (NEI)

Publication No. 99-02, Regulatory Assessment Performance Indicator Guideline,

Revision 2.

Licensee-Identified Violations

None.

REPORT DETAILS

4OA1 Performance Indicator (PI) Verification

a. Inspection Scope

The inspectors interviewed licensee personnel and reviewed the licensees records related to the Alert and Notification System (ANS) to determine if the licensees program was implemented consistent with the industry guidelines in Nuclear Energy Institute (NEI) Publication No. 99-02, Regulatory Assessment Performance Indicator Guideline, Revision 2, and related licensee procedures. Specifically, licensee personnel were interviewed and licensee records related to the performance of the ANS were reviewed to assess the accuracy and completeness of the data submitted to the NRC for the period of January through March 2003.

b. Findings

1) Description Revision 2 of EPWI-01.05, Public Alert Notification System (PANS) Maintenance and Testing, dated September 27, 2002, Section 4.6.2, identified Fixed sirens are tested on the following frequency: (A) Sherburne County - 1st Wednesday of the month at 1:00 p.m.; and (B) Wright County - 1st Wednesday of the month at 1:00 p.m.

Section 4.6.1 identified Fixed sirens are activated in accordance with the following procedures: (A) Test 1359 Weekly Cancel Test; and (B) Test 1409 Monthly and Quarterly Activation.

On November 10, 2002, Monticello Nuclear Generating Plant implemented Revision 1 to EPWI-01.06, Emergency Plan Performance Indicator Program. This procedure stated, in part, for the purposes of this indicator, the Monthly Siren Activation Test (Surveillance 1409) conducted on the first Wednesday of each month, will be the only test used in this calculation. The licensee had conducted weekly siren tests since the late 1980's. After the licensees siren upgrade, which was completed in the Fall of 2002, the licensee tracked the results of these weekly tests. However, the results of the weekly testing were not included in the calculation of the PI.

During the first monthly test conducted on January 1, 2003, 81 of 81 sirens were successfully tested. However, on February 5 and March 5, 2003, the monthly siren tests resulted in 47 of 81 and 50 of 81, respectively, successful siren tests.

On March 31, 2003, the licensee implemented Revision 2 to EPWI-01.06. Revision 2 changed the ANS PI calculation from utilizing only the monthly test data results, to calculating the PI indicator by also including the results from the weekly siren tests.

Specifically, Revision 2 to EPWI-01.06 stated ...for the purposes of this indicator, the monthly siren activation test conducted on the first Wednesday of each month and the weekly cancel signal test (beginning January 1, 2003) will be the only tests used in this calculation.

The licensees calculation for the first quarter 2003 ANS PI was based on the data from the monthly and weekly siren tests. On approximately April 21, 2003, the licensee submitted to the NRC the results of the first quarter of 2003 ANS PI data and reported the results as Green with a twelve month average of 96.2 percent which included 1008 successful siren tests out of 1073 siren tests for the first quarter. In comparison, the licensee reported the fourth quarter of 2002 ANS PI results as Green with a twelve month average of 99.5 percent which included 243 successful siren tests out of 243 siren tests for the fourth quarter of 2002.

The NRC endorsed guidance for licensees PI program, NEI 99-02, Revision 02, states that the periodic ANS tests that are to be counted in the PI calculation are the

...regularly scheduled tests (documented in the licensees test plan or guidelines)...

2) Analysis The NRC inspectors independently calculated Monticellos first quarter 2003 PIs, using only the monthly test results which resulted in a potentially White ANS PI. At the end of this inspection period, the inspectors, in consultation with NRC headquarters staff, were evaluating as to whether the licensees approach to calculate the first quarter 2003 ANS PI was consistent with station procedures in effect at the time. The NRC was also evaluating whether the licensees ANS PI results reported to the NRC for the first quarter 2003, were consistent with NEI guidance.

This issue was considered an unresolved item (URI) pending additional review by the NRC. Pending completion of this activity, the issue is considered an URI (URI 50-263/05-07-01). The licensee entered this issue into their corrective action program as CAP 036648, Potential Violation Discussed at EP Exit.

4OA6 Meetings, Including Exits

.1 Exit Meeting

The inspectors presented the inspection results to Mr. B. Sawatzke and other members of the licensees management and staff at the conclusion of the inspection on January 12, 2005. A telephone exit was held on January 14, 2004, with Mr. T. Palmisano, Site Vice President. A final telephone exit was conducted on February 4, 2005, with Mr. E. Weinkam, Corporate Regulatory Affairs Manager, and other members of the licensees corporate and station staff. No proprietary information was identified.

ATTACHMENT:

SUPPLEMENTAL INFORMATION

KEY POINTS OF CONTACT

Licensee

T. Palmisano, Site Vice President

R. Baumer, Compliance Engineer

J. Conway, Site Director of Operations

G. Holthaus, Senior Emergency Preparedness Coordinator

K. Jepson, Radiation Protection and Chemistry Manager

D. Miller, ECP Manager, Duane Arnold Energy Center

J. Mestad, ECP Manager, Monticello Nuclear Generating Plant

D. Neve, Regulatory Affairs Manager

D. Pedersen, Emergency Preparedness Manager

B. Sawatzke, Acting Plant Manager

E. Weinkam, Regulatory Affairs Manager, Corporate

A. Williams, Projects Manager

Nuclear Regulatory Commission

R. Orlikowski, Resident Inspector

ITEMS OPENED, CLOSED, AND DISCUSSED

Opened

05000263/2005007-01 URI NRC Review to Determine Whether Submittal of First Quarter 2003 ANS PI Data Was Consistent With Procedures, Guidance, and Requirements In Effect at the Time

Closed

None.

Discussed

None.

Attachment