ML18037A513
| ML18037A513 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/20/1993 |
| From: | Hebdon F Office of Nuclear Reactor Regulation |
| To: | Medford M Tennessee Valley Authority |
| Shared Package | |
| ML18037A514 | List: |
| References | |
| TAC-M83580, TAC-M83581, TAC-M83582 NUDOCS 9310250245 | |
| Download: ML18037A513 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 October 20, 1993 Docket Nos. 50-259, 50-260 and 50-296 Dr. Hark 0. Hedford, Vice President Technical Support Tennessee Valley Authority 38 Lookout Place 1101 Market Street Chattanooga, Tennessee 37402-2801
Dear Dr. Hedford:
SUBJECT'ECOND 10-YEAR INTERVAL INSERVICE INSPECTION PROGRAM PLAN AND ASSOCIATED REQUESTS FOR RELIEF BROMNS FERRY NUCLEAR PLANT, UNIT 2 (TAC NOS.
- H83580, M83581, AND H83582)
By letters dated Hay 22, 1992 and February 16, 1993, the Tennessee Valley Authority (TVA, the licensee) submitted its Second 10-Year Interval Inservice Inspection
- Program, Revision 0 and Revision 1, respectively, for the Browns Ferry Nuclear Plant (BFN), Unit 2. 'In these submittals, the licensee also requested relief from certain ASHE Boiler and Pressure Vessel Code requirements that were considered impractical to perform during the second 10-year inservice inspection (ISI) interval for BFN, Unit 2.
These requests for relief were identified as,ISI-2-1, SPT-l, SPT-2, and SPT-3.
s'y letters dated April 8, 1993, April 27,
- 1993, and May 16,
- 1993, TVA
, submitted additional requests for relief from the ASME Code requirements (i.e.,
SPT-4, SPT-5, and SPT-6, respectively).
Previous requests for relief SPT-I, SPT-2, and SPT-3 were subsequently withdrawn by TVA's letter dated May 12, 1993.
The NRC staff approved SPT-4, SPT-5, and SPT-6 by letter and safety evaluation (SE) dated Hay 21, 1993.
were imposed on BFN, Unit 2.
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The NRC staff, with tqchnical assistance from the Idaho National Engineering Laboratory (INEL), evaluated TVA's updated ISI Program (including the System Pressure Test program),
and request for code relief (ISI-2-1), for the second 10-year interval of BFN, Unit 2.
Based on TVA letters dated May 22,,1992 and February 16,
- 1993, and related supporting information (e.g.,
- diagrams, drawings, and component lists), the staff concluded that the Second 10-Year Interval ISI Program, through Revision 1, for BFN, Unit 2 is acceptable and complies with 10 CFR 50.55a(g)(4) and Technical Specification (TS) 4.6.G. 1.
The staff also concluded that the ASHE Section XI Code requirements associated with TVA's Request for Relief No. ISI-2-1 were impractical to perform and relief could be granted pursuant to 10 CFR 50.55a(a)(3)(ii) and (g)(6)(i).
In granting TVA relief from the specific code requirements related to ISI-2-1 the staff determined that relief was authorized by law and would not endanger life, property, or the common defense and security, and is otherwise in the public interest.
Furthermore, relief is hereby granted by giving due consideration to the burden upon TVA that could result, without a compensating increase in safety, if. the Code requirements
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Dr; Mark 0. Medford The staff's evaluation and conclusions are contained in the enclosed Safety Evaluation (SE).
,Attached to this SE'is the INEL Technical Evaluation Report.
In its Hay 22, 1992 letter, TVA also enclosed a copy of the first interval ISI program for BFN, Units 1 and 3.
Since. both units are currently in an extended shutdown condition, the ISI program was not updated to reflect a subsequent 120-month inspection interval pursuant to 10 CFR 50.55a(g),
nor were any additional or revised requests for code relief included.
By letter dated March 1,
- 1988, TVA notified the NRC of its intention to extend the first 10-year interval of the BFN ISI'and System Pressure Test Programs while Units 1, 2, and 3 were shut down.
As such, the second 10-year interval ISI programs for Units 1 and 3 will not begin until 1 year after each of their respective startup dates.
These second 10-year interval ISI programs will be based on the latest ASHE Code requirements referenced by 10 CFR 50.55a(b) at the time of startup.
The NRC staff considers this extension acceptable, assuming,all required ISI program examinations of the first 10-year interval are completed prior to initiating the second 10-year interval.
'Sincerelz, Origina s signed by Frederick J.
Hebdon, Director Project Directorate II-4 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/enclosure:
See next page Distribution
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Hebdon B. Clayton T.
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