ML19322A151
| ML19322A151 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/29/1978 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7901030057 | |
| Download: ML19322A151 (2) | |
Text
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7 TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 374o1 M0C Chestnut Street Tower II DEC 291978 Director of Nuclear Reactor Regulation Attention:
Mr. Thomas A. Ippolito, Chief Branch No. 3 Division of Operating Reactors U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Mr. Ippolito:
In the Matter of the
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Docket No. 50-296 Tennessee Valley Authority
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This is in response to A. Schwencer's letter of September 6, 1977, to Godwin Williams, Jr., which transmitted NUREG-0312.
Enclosed is a brief summary of the feedwater sparger and control rod drive nozzle inspection and repair program completed on Browns Ferry unit 3 during the recent refueling outage. A detailed description of this modifi-cation was submitted to you by my letter of July 11, 1978.
Very truly fours, i
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-.m vL bJ. E. Gilleland Assistant Manager of Power Enclosure i
7901030057 An Equal Opportunity Employer
r ENCLOSURE BROWNS FERRY NUCLEAR PLANT UNIT 3 - FEEDWATER/ CONTROL ROD DRIVE RETURN LINE N0ZZLE - INSPECTION PROGRAM RESULTS We offer the following response to NRC's NUREG-0312 Interim Technical Report on BWR Feedwater and Control Rod Drive Return Line Nozzle cracking for information concerning the feedwater sparger and control rod drive nozzle inspections accomplished during the fall 1978 Browns Ferry unit 3 refueling outage.
During the fall of 1978 Browns Ferry unit 3 refueling outage,.the reactor pressure vessel nozzles were inspected, and the control rod drive nozzles were modified as described in a TVA letter dated July 11, 1978, with the following comments:
- 1. -
Feedwater Nozzle and Feedwater Sparger Program A UT examination of the six feedwater nozzle safe ends, bores, and inside blend radii was performed and no indications were found. A cursory internal visual inspection was also performed, and all were found to be in an acceptable condition.
2.
Control Rod Drive Return Line Nozzle Program The CRD rerurn line was capped and rerouted. Cracks were detected in the blend radius and nozzle bore, and all relevant indications were removed by machining or grinding. This completed our response on CRD return line nozzles as inspections, repairs, and modifications are now complete on all three units.
3.
Dose Rate, Manpower, and Man-Rem Information for Invessel Work Total man-rem for CRD modification was 28.4 man-rem. Working field was 275 man-rem /hr (450 MR before shield). The number of personnel involved in the CRD was approximately 15 people, 4
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