IR 05000296/1978027
| ML20150D365 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/20/1978 |
| From: | Conlon T, Economos N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20150D355 | List: |
| References | |
| 50-296-78-27, NUDOCS 7812050172 | |
| Download: ML20150D365 (4) | |
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UNITED STATES
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gd #8209 NUCLEAR REGULATORY COMMISSION
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Report No.: 50~296/78-27 Docket No.: 50-296 License No.: DPR-68 Category: C Licensee: Tennessee Valley Authority 830 Power Building l
Chattanooga, Tennessee 37401 l
Facility Name: Browns Ferry Nuclear Plant, Unit 3 l
Inspection at: Browns Ferry Site Inspection conducted: October 17, 1978 Inspectors:
N. Economos T. E. Conlon
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Approved
'Date T. E. Conlon, Chief Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch Inspection Summary 17,'1978 (Report No. 50-296/78-27)
Inspection on October Ultrasonic examination of Browns Ferry (Unit 3) recircula-
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Areas Inspected:
tion nozzles.
Of the one area inspected, no apparent items of noncompliance or Results:
deviations were identified.
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RII Report No. 50-296/78-27 I-1 DETAILS I Prepared b-
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/Date Engineering,7 1etallurgical Engineer Support Section No. 2 Reactor Construction and Engineering Support Branch Dates of Inspection: October 17, 1978
/cfeh Reviewed by; -
Ja. 2 W
T. E. Conlon, Chief
/Date'
Engineering Support Section No. 2 Reactor Construction and Engineering Support Branch 1.
Persons Contacted a.
Tennessee Valley Authority (TVA)
- R. H. Daniel, Mechanical Engineer, Power Plant Maintenance Branch b.
Contractor Organization Lambert, MacGill and Thomas, Incorporated (LMT)
E. L. Inomas, Level III Inspector / Supervisor
- Denotes those present at exit interview.
2.
Scope Announced inspection to observe the ultrasonic examination of recircu-lation nozzle safe ends.
3.
Recirculction Nozzle Safe End Examination In response to a RII request, TVA agreed to ultrasonically examine five of the ten recirculation nozzle safe ends in Unit 3 during this outage. This examination was requested in order to ascertain whether any indication, subject to question, existed around the area of the attachment weld - made to attach the thermal sleeve to the internal surface of the safe end.
The licensee's representative stated the nozzle thermal sleeve arrange-ment was the type 3 design and unlike the Brunswick safe ends which were made of forged, sensitized incennel material, the safe ends on this vessel were made of annealed, type 316, stainless steel material.
The examination was conducted using the same technique and equipment
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RII Report No. 50-296/78-27 I-2 similar to that used on the Brunswick safe ends. The inspector wit-nessed the ultrasonic examination of three nozzles, 3NCA, 3NCC, and 3NCE. Equipment failure precluded the examination of nozzles 3NCG and 3NCJ at that time.
The examination was conducted by a Level III, UT examiner who scanned the entire OD surface of the safe end axially and circumferentially in two directions. Particular emphasis was placed around the aforemen-tioned area of the weld.
Inspection results showed no indications of a suspicious nature.
On October 18, 1978 the licensee advised RII that nozzles 3NCG and 3NCJ were examined with the same results as above.
Finally, the licensee is considering the examination of five (5)
recirculation nozzles in Unit I to be performed during the next scheduled outage sometime in November, 1978.
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