ML12325A495

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Errata for Browns Ferry Nuclear Plant - NRC Integrated Inspection Report, 05000259-12-003, 05000260-12-003, 05000296-12-003, 05000259-12-502, 05000260-12-502, and 05000296-12-502
ML12325A495
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 11/19/2012
From: Eugene Guthrie
Division Reactor Projects II
To: James Shea
Tennessee Valley Authority
References
IR-12-003, IR-12-502
Download: ML12325A495 (6)


See also: IR 05000260/2012003

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION REGION II 245 PEACHTREE CENTER AVENUE NE, SUITE 1200 ATLANTA, GEORGIA 30303-1257

November 19, 2012

Mr. Joseph W. Shea

Vice President, Nuclear Licensing

Tennessee Valley Authority

1101 Market Street, LP 4B-C

Chattanooga, TN 37402-2801

SUBJECT: ERRATA FOR BROWNS FERRY NUCLEAR PLANT - NRC INTEGRATED INSPECTION REPORT 05000259/2012003, 05000260/2012003,

05000296/2012003, 05000259/2012502, 05000260/2012502, AND

05000296/2012502

Dear Mr. Shea:

It was identified that in NRC Integrated Inspection Report 05000259/2012003,

05000260/2012003, 05000296/2012003, 05000259/2012502, 05000260/2012502, and 05000296/2012502, (ADAMS ML12227A711) previously completed and reported inspection samples in section 4OA1.1 Performance Indicator (PI) Verification were erroneously reported for

RCS Activity for Units 2 and 3; and RCS Leakage for Units 2 and 3. These items were

completed and documented in NRC Integrated Inspection Report 05000259/2007002, 05000260/2007002, and 05000296/2007002 and should be removed from this report.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter, its enclosure, and your response (if any), will be available electronically for public inspection in the

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

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/ Eugene F. Guthrie, Chief Special Project, Browns Ferry Division of Reactor Projects

Docket Nos.: 50-259, 50-260, 50-296

License Nos.: DPR-33, DPR-52, DPR-68

Enclosure: Errata page 33 for NRC Integrated Inspection Report 05000259/2012003, 05000260/2012003, 05000296/2012003, 05000259/2012502,

05000260/2012502, AND 05000296/2012502

cc w/encl: (See page 2)

__

ML12325A495 __________________ X SUNSI REVIEW COMPLETE OFFICE RII:DRP RII:DRP SIGNATURE /RA/ /RA/ NAME CKontz EGuthrie DATE 11/16/2012 11/20/2012 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

J. Shea 2

cc w/encl: K. J. Polson Site Vice President

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

S. M. Bono

Plant Manager

Browns Ferry Nuclear Plant

Tennessee Valley Authority

Electronic Mail Distribution

James E. Emens

Manager, Licensing

Browns Ferry Nuclear Plant

Tennessee Valley Authority Electronic Mail Distribution

E. W. Cobey

Manager, Corporate Licensing

Browns Ferry Nuclear Plant

Tennessee Valley Authority Electronic Mail Distribution

T. A. Hess

Program Manager

Corporate Licensing Tennessee Valley Authority Electronic Mail Distribution

Edward J. Vigluicci

Associate General Counsel, Nuclear

Tennessee Valley Authority Electronic Mail Distribution

Chairman

Limestone County Commission

310 West Washington Street

Athens, AL 35611

State Health Officer

Alabama Dept. of Public Health

P.O. Box 303017

Montgomery, AL 36130-3017

J. Shea 3

Letter to Joseph W. Shea from Eugene Guthrie dated November 19, 2012

SUBJECT: ERRATA FOR BROWNS FERRY NUCLEAR PLANT - NRC INTEGRATED INSPECTION REPORT 05000259/2012003, 05000260/2012003,

05000296/2012003, 05000259/2012502, 05000260/2012502, AND

05000296/2012502

Distribution w/encl

J. Baptist, RII

L. Douglas, RII

OE Mail

RIDSNRRDIRS PUBLIC RidsNrrPMBrownsFerry Resource

33 * Unit 1 Mitigating Systems Performance Index - Reactor Core Isolation Cooling

4OA1 Performance Indicator (PI) Verification

Cornerstone: Barrier Integrity

a. Inspection Scope

The inspectors reviewed the licensee's procedures and methods for compiling and

reporting the Performance Indicators (PI) listed below, including procedure SPP-3.4, Performance Indicator for NRC Reactor Oversight Process for Compiling and Reporting

PIs to the NRC. The inspectors reviewed the raw data for the PITs listed below for the

1 st through 4

th quarters of 2006. The inspectors compared the licensee's raw data

against graphical representations and specif

ic values reported to the NRC in the 4

th quarter 2006 PI report to verify that the data was correctly reflected in the report. The

inspectors also reviewed the past history of

PERs for any that might be relevant to problems with the PI program. Furthermore, the inspectors met with responsible chemistry and engineering personnel to discuss and go over licensee records to verify

that the PI data was appropriately captured, calculated correctly, and discrepancies resolved. The inspectors reviewed Nuclear Energy Institute 99-02, Regulatory

Assessment Performance Indicator Guideline, to verify that industry reporting guidelines

were applied.

  • RCS Activity for Units 2 and 3
  • RCS Leakage for Units 2 and 3

b. Findings

No findings were identified.

Cornerstone: Emergency Preparedness

a. Inspection Scope

The inspectors sampled licensee submittals relative to the PIs listed below for the period

October 1, 2011, and March 31, 2012. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in NEI 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6, were used to confirm the

reporting basis for each data element.

  • Emergency Response Organization (ERO) Drill/Exercise Performance
  • ERO Drill Participation
  • Alert and Notification System Reliability

33 * Unit 1 Mitigating Systems Performance Index - Reactor Core Isolation Cooling

4OA1 Performance Indicator (PI) Verification

Cornerstone: Emergency Preparedness

a. Inspection Scope

The inspectors sampled licensee submittals relative to the PIs listed below for the period

October 1, 2011, and March 31, 2012. To verify the accuracy of the PI data reported during that period, PI definitions and guidance contained in NEI 99-02, "Regulatory Assessment Performance Indicator Guideline," Revision 6, were used to confirm the

reporting basis for each data element.

  • Emergency Response Organization (ERO) Drill/Exercise Performance
  • ERO Drill Participation
  • Alert and Notification System Reliability