ML081990534

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Errata for Final Significance Determination for a White Finding and Notice of Violation, NRC Inspection Report 05000298/2008008, Cooper Nuclear Station
ML081990534
Person / Time
Site: Cooper Entergy icon.png
Issue date: 07/14/2008
From: O'Keefe N
NRC/RGN-IV/DRS/EB2
To: Minahan S
Nebraska Public Power District (NPPD)
References
EA-07-204, IR-08-008
Download: ML081990534 (5)


See also: IR 05000298/2008008

Text

UNITED STATES

NU C LE AR RE G ULATO RY C O M M I S S I O N

R E GI ON I V

612 EAST LAMAR BLVD , SU ITE 400

AR LIN GTON , TEXAS 76011-4125

July 14, 2008

EA 07-204

Stewart B. Minahan

Vice President-Nuclear and CNO

Nebraska Public Power District

P.O. Box 98

Brownville, NE 68321

SUBJECT: ERRATA FOR FINAL SIGNIFICANCE DETERMINATION FOR A WHITE

FINDING AND NOTICE OF VIOLATION, NRC INSPECTION

REPORT 05000298/2008008, COOPER NUCLEAR STATION

Dear Mr. Minahan:

This Errata corrects the decision basis for the significance determination for the subject

violation. Table 4 in Enclosure 2 of our letter (ML081650090) (Caniano to Minahan, dated

June 13, 2008) erroneously provided data that had been used in a sensitivity study as opposed

to the probabilities calculated to support the final determination of significance. Please replace

Page E2-13 of Enclosure 2, Final Significance Determination Summary, with the enclosed

revised page. We regret any inconvenience this may have caused.

In accordance with 10 CFR 2.390 of the NRCs "Rules of Practice," a copy of this letter, its

enclosure, and your response (if any) will be made available electronically for public inspection

in the NRC Public Document Room or from the Publicly Available Records (PARS) component

of NRCs document system (ADAMS), accessible from the NRC Web site at

http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

Neil F. OKeefe, Chief

Engineering Branch 2

Division of Reactor Safety

Docket: 50-298

License: DPR-46

Nebraska Public Power District -2-

EA 07-204

cc w/enclosure: as stated

Gene Mace

Nuclear Asset Manager

Nebraska Public Power District

P.O. Box 98

Brownville, NE 68321

John C. McClure, Vice President

and General Counsel

Nebraska Public Power District

P.O. Box 499

Columbus, NE 68602-0499

David Van Der Kamp

Licensing Manager

Nebraska Public Power District

P.O. Box 98

Brownville, NE 68321

Michael J. Linder, Director

Nebraska Department of

Environmental Quality

P.O. Box 98922

Lincoln, NE 68509-8922

Chairman

Nemaha County Board of Commissioners

Nemaha County Courthouse

1824 N Street

Auburn, NE 68305

Julia Schmitt, Manager

Radiation Control Program

Nebraska Health & Human Services

Dept. of Regulation & Licensing

Division of Public Health Assurance

301 Centennial Mall, South

P.O. Box 95007

Lincoln, NE 68509-5007

H. Floyd Gilzow

Deputy Director for Policy

Missouri Department of Natural Resources

P. O. Box 176

Nebraska Public Power District -3-

EA 07-204

Jefferson City, MO 65102-0176

Director, Missouri State Emergency

Management Agency

P.O. Box 116

Jefferson City, MO 65102-0116

Chief, Radiation and Asbestos

Control Section

Kansas Department of Health

and Environment

Bureau of Air and Radiation

1000 SW Jackson, Suite 310

Topeka, KS 66612-1366

Melanie Rasmussen, State Liaison Officer/

Radiation Control Program Director

Bureau of Radiological Health

Iowa Department of Public Health

Lucas State Office Building, 5th Floor

321 East 12th Street

Des Moines, IA 50319

John F. McCann, Director, Licensing

Entergy Nuclear Northeast

Entergy Nuclear Operations, Inc.

440 Hamilton Avenue

White Plains, NY 10601-1813

Keith G. Henke, Planner

Division of Community and Public Health

Office of Emergency Coordination

930 Wildwood, P.O. Box 570

Jefferson City, MO 65102

Paul V. Fleming, Director of Nuclear

Safety Assurance

Nebraska Public Power District

P.O. Box 98

Brownville, NE 68321

Ronald L. McCabe, Chief

Technological Hazards Branch

National Preparedness Division

DHS/FEMA

9221 Ward Parkway

Suite 300

Kansas City, MO 64114-3372

Nebraska Public Power District -4-

EA 07-204

Daniel K. McGhee, State Liaison Officer

Bureau of Radiological Health

Iowa Department of Public Health

Lucas State Office Building, 5th Floor

321 East 12th Street

Des Moines, IA 50319

Ronald D. Asche, President

and Chief Executive Officer

Nebraska Public Power District

1414 15th Street

Columbus, NE 68601

Nebraska Public Power District -5-

EA 07-204

Electronic distribution by RIV:

Regional Administrator (Elmo.Collins@nrc.gov)

DRP Director (Dwight.Chamberlain@nrc.gov)

DRP Deputy Director (Anton.Vegel@nrc.gov)

DRS Director (Roy.Caniano@nrc.gov)

DRS Deputy Director (Troy.Pruett@nrc.gov)

Senior Resident Inspector (Nick.Taylor@nrc.gov)

Resident Inspector (Michael.Chambers@nrc.gov)

Branch Chief, DRP/C (Geoffrey.Miller@nrc.gov )

Senior Project Engineer, DRP/C (Wayne.Walker@nrc.gov)

Public Affairs Officer (Victor.Dricks@nrc.gov)

Team Leader, DRP/TSS (Chuck.Paulk@nrc.gov)

RITS Coordinator (Marisa.Herrera@nrc.gov)

DRS STA (Dale.Powers@nrc.gov)

OEDO RIV Coordinator (Patricia.Lougheed@nrc.gov )

ROPreports

CNS Site Secretary (Sue.Farmer@nrc.gov)

OEMail.Resource@nrc.gov

OEWeb.Resource@nrc.gov Mike.Franovich@nrc.gov

Doug.Starkey@nrc.gov Jeff.Circle@nrc.gov

Maryann.Ashley@nrc.gov Joseph.Anderson@nrc.gov

Michael.Vasquez@nrc.gov Tim.Kobetz@nrc.gov

Victor.Dricks@nrc.gov Thomas.Hiltz@nrc.gov

Bill.Maier@nrc.gov Carl.Lyon@nrc.gov

Linda.Smith@nrc.gov Undine.Shoop@nrc.gov

Neil.OKeefe@nrc.gov Richard.Borchardt@nrc.gov

John.Mateychick@nrc.gov Melissa.Wyatt@nrc.gov

Karla.Fuller@nrc.gov Paul.Lain@nrc.gov

Michael.Cheok@nrc.gov Bruce.Boger@nrc.gov

John.Grobe@nrc.gov Harold.Barrett@nrc.gov

Mark.Cunningham@nrc.gov Frederick.Brown@nrc.gov

Alexander.Klein@nrc.gov Christine.Tucci@nrc.gov

Christi.Maier@nrc.gov Amy.Powell@nrc.gov

SUNSI Review Completed: _TWP__ ADAMS: Yes Initials: _TWP__

Publicly Available Non-Sensitive ML081990534

C:EB2 DD:

Neil OKeefe Troy Pruett

M.Runyan for /RA/

7/14/08 7/14/08

OFFICIAL RECORD COPY T=Telephone E=E-mail F=Fax

The analyst used the main control room abandonment freql \encies documented in

Table 3. In addition, sensitivities were run using the Iicense~'s values.

Recovery Following Failure of Valve RHR-MO-25B

As documented in Assumption 5, the analyst calculated a combined non-recovery

probability using the event tree shown in Figure 2 in the Attachment.

Table 4 documents the 'final split fractions used in quantifying this event tree.

Table 4

Split Fractions for RECOVERY-PATH

Top Event How Assessed Failure Probability

LEVEL-DOWN SPAR-H Diagnosis Only) 8.8 x 10-4

SRV-STATUS Best Estimate of Fraction 1.0 x 10-1

CLOSE-SRVS SPAR-H Action Only) 5.7 x 10-4

RESTORE-HPCI SPAR-H Combined) 1.9 x 10-2

OPEN-MO-25B-3 SPAR-H Combined) 6.7 x 10-1

OPEN-MO-25B-5n SPAR-H Combined) 6.7 x 10-1

Using the event tree in Figure 2 and the split fractions in Table 4, the analyst calculated

a combined non-recovery probability of 7.9 x 10.2 . The licensee's combined non

3

recovery probability was 4.0 x 10- * The licensee used a similar approach to quantify this

value. However, the licensee assumed that operators would always shut the safety

relief valves upon determining that reactor pressure vessel water level was decreasing.

The analyst assumed that some percentage of operators would continue to follow the

procedure and attempt to recover from the failed RHR valve or try alternate methods of

low-pressure injection. In addition, the analyst identified the following issues that

impacted the licensee's analysis: .

  • The inspectors determined that it would require 112 ft-Ibs of force to manually

open Valve RHR-MO-25B. The analyst determined that this affected the

ergonomics of this recovery. Some operators may assume that the valve is on

the backseat when large forces are required to open it. Some operators might

be incapable of applying this force to a 2-foot diameter hand wheel.

  • The analyst noted that the following valves would be potential reasons for lack

of injection flow and/or may distract operators from diagnosing that

Valve RHR-MO-025B is closed:

RHR-81 B, RHR Loop B Injection Shutoff Valve, could be closed.

RHR-27CV, RHR Loop B Injection Line Testable Check Valve,

couid be stuck ciosed.

E2-13 Enclosure 2