IR 05000259/2005003
| ML052170215 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| 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) | |
Text
August 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)
cc w/encl:
Ashok S. Bhatnagar Senior Vice President Nuclear Operations Tennessee Valley Authority Electronic Mail Distribution Larry S. Bryant, General Manager Nuclear Engineering Tennessee Valley Authority Electronic Mail Distribution Brian O'Grady Site Vice President Browns Ferry Nuclear Plant Tennessee Valley Authority Electronic Mail Distribution Robert J. Beecken, Vice President Nuclear Support Tennessee Valley Authority Electronic Mail Distribution General Counsel Tennessee Valley Authority Electronic Mail Distribution 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 State Health Officer Alabama Dept. of Public Health RSA Tower - Administration Suite 700 P. O. Box 303017 Montgomery, AL 36130-3017 Chairman Limestone County Commission 310 West Washington Street Athens, AL 35611 Jon R. Rupert, Vice President Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35609 Robert G. Jones, Restart Manager Browns Ferry Unit 1 Restart Browns Ferry Nuclear Plant Tennessee Valley Authority P. O. Box 2000 Decatur, AL 35609 Distribution w/encl: (See page 3)
_________________________
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
Enclosure 1 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.
- Unit 2 Standby Liquid Control System Functional Test per 2-SR-3.1.7.7
1-2A EDG Monthly Surveillance Test per 0-SR-3.8.1.1(A)
Unit 2 Turbine Control Valve Fast Closure Test per 2-SR-3.3.1.1.8(9)
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 2 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.
- Unit 2 Standby Liquid Control System Functional Test per 2-SR-3.1.7.7
1-2A EDG Monthly Surveillance Test per 0-SR-3.8.1.1(A)
Unit 2 Turbine Control Valve Fast Closure Test per 2-SR-3.3.1.1.8(9)
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