IR 05000259/2005003

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Errata Letter for Browns Ferry NRC Integrated Inspection Report 05000259/2005003, 05000260/2005003, & 05000296/2005003
ML052170215
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 08/05/2005
From: Cahill S
Reactor Projects Region 2 Branch 6
To: Singer K
Tennessee Valley Authority
References
IR-05-003
Download: ML052170215 (5)
v • d • e


Text

ust 5, 2005

SUBJECT:

ERRATA LETTER FOR BROWNS FERRY NRC INTEGRATED INSPECTION REPORT 05000259/2005003, 05000260/2005003, AND 05000296/2005003

Dear Mr. Singer:

It has come to our attention that the Browns Ferry Integrated Inspection Report which was dated July 29, 2005, contains a footnote in Section 1R22 which incorrectly indicates that a listed procedure included testing of a containment isolation valve. It should have referenced RCS leakage detection testing. The ADAMS Accession Number for that document was ML052130484. Please substitute the enclosed amended page into all copies of the subject Integrated Inspection Report. We apologize for any inconvenience caused by this error.

Should you have any questions concerning this matter, please contact Stephen J. Cahill at (404) 562-4520.

Sincerely,

/RA/

Stephen J. Cahill, Chief Reactor Projects Branch 6 Division of Reactor Projects Docket Nos. 50-259, 50-260, 50-296 License No. DPR-33, DPR-52, DPR-68 Enclosures: 1. Errata Sheet 2. Integrated Inspection Report Amended Page cc w/encls: (See page 2)

TVA 2 cc w/encl: State Health Officer Ashok S. Bhatnagar Alabama Dept. of Public Health Senior Vice President RSA Tower - Administration Nuclear Operations Suite 700 Tennessee Valley Authority P. O. Box 303017 Electronic Mail Distribution Montgomery, AL 36130-3017 Larry S. Bryant, General Manager Chairman Nuclear Engineering Limestone County Commission Tennessee Valley Authority 310 West Washington Street Electronic Mail Distribution Athens, AL 35611 Brian O'Grady Jon R. Rupert, Vice President Site Vice President Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Browns Ferry Nuclear Plant Tennessee Valley Authority Tennessee Valley Authority Electronic Mail Distribution P. O. Box 2000 Decatur, AL 35609 Robert J. Beecken, Vice President Nuclear Support Robert G. Jones, Restart Manager Tennessee Valley Authority Browns Ferry Unit 1 Restart Electronic Mail Distribution Browns Ferry Nuclear Plant Tennessee Valley Authority General Counsel P. O. Box 2000 Tennessee Valley Authority Decatur, AL 35609 Electronic Mail Distribution Distribution w/encl: (See page 3)

John C. Fornicola, Manager Nuclear Assurance and Licensing Tennessee Valley Authority Electronic Mail Distribution Bruce M. Aukland, Plant Manager Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution Glenn W. Morris, Manager Corporate Nuclear Licensing and Industry Affairs Tennessee Valley Authority Electronic Mail Distribution William D. Crouch, Manager Licensing and Industry Affairs Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution

_________________________

OFFICE DRP:RII SIGNATURE SJC for NAME RCarrion DATE 08/05/2005 E-MAIL COPY? YES NO YES NO YES NO YES NO YES NO YES NO YES NO

The inspectors reviewed PERs generated during U2C13 to verify that initiation thresholds, priorities, mode holds, and significance levels were assigned as required.

Resolution and implementation of corrective actions of several PERs were also reviewed for completeness.

b. Findings No findings of significance were identified.

1R22 Surveillance Testing a. Inspection Scope The inspectors either witnessed portions of surveillance tests or reviewed test data for the seven risk-significant SSCs listed below to verify that the tests met TS surveillance requirements, UFSAR commitments, and in-service testing (IST) and licensee procedure requirements. The inspectors review was to confirm that the testing effectively demonstrated that the SSCs were operationally capable of performing their intended safety functions and fulfilled the intent of the associated surveillance requirement. Applicable IST data was compared against the requirements of licensee procedures 0-TI-362, Inservice Testing of Pumps and Valves; 0-TI-230, Vibration Monitoring and Diagnostics.

  • 1-2A EDG Monthly Surveillance Test per 0-SR-3.8.1.1(A)

a. Unit 3 HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure per 3-SR-3.5.1.7 *

  • Unit 2 RCIC Comprehensive Test per 2-SR-3.5.3.3
  • Unit 3 Drywell Floor Drain Sump Flow Integrator Calibration per 3-SR-3.4.5.3 **
  • Unit 3 Diesel Generator 24 Hour Run per 3-SR-3.8.1.7(3A)
  • This procedure included inservice testing requirements.
    • This procedure included testing of a containment isolation valve.

b. Findings No findings of significance were identified Enclosure 1

Correction Action Program The inspectors reviewed PERs generated during U2C13 to verify that initiation thresholds, priorities, mode holds, and significance levels were assigned as required.

Resolution and implementation of corrective actions of several PERs were also reviewed for completeness.

b. Findings No findings of significance were identified.

1R22 Surveillance Testing a. Inspection Scope The inspectors either witnessed portions of surveillance tests or reviewed test data for the seven risk-significant SSCs listed below to verify that the tests met TS surveillance requirements, UFSAR commitments, and in-service testing (IST) and licensee procedure requirements. The inspectors review was to confirm that the testing effectively demonstrated that the SSCs were operationally capable of performing their intended safety functions and fulfilled the intent of the associated surveillance requirement. Applicable IST data was compared against the requirements of licensee procedures 0-TI-362, Inservice Testing of Pumps and Valves; 0-TI-230, Vibration Monitoring and Diagnostics.

  • 1-2A EDG Monthly Surveillance Test per 0-SR-3.8.1.1(A)
  • Unit 3 HPCI Main and Booster Pump Set Developed Head and Flow Rate Test at Rated Reactor Pressure per 3-SR-3.5.1.7 *
  • Unit 2 RCIC Comprehensive Test per 2-SR-3.5.3.3
  • Unit 3 Drywell Floor Drain Sump Flow Integrator Calibration per 3-SR-3.4.5.3 **
  • Unit 3 Diesel Generator 24 Hour Run per 3-SR-3.8.1.7(3A)
  • This procedure included inservice testing requirements.
    • This procedure included RCS leakage detection testing.

b. Findings No findings of significance were identified Enclosure 2

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