ML20100P058
| ML20100P058 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 11/29/1984 |
| From: | Hufham J TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-84-550-000 PT21-84-550, PT21-84-550-000, NUDOCS 8412130611 | |
| Download: ML20100P058 (2) | |
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.D TENNESSEE VALLEY AUTHORITY "simcpATT4@pQ). TENNESSEE 374ot A I L AN T A00 Chelit:AlA Street Tower II November 29, 1984 5
r3 P I: 22 BLRD-50-438/82 35 BLRD-59-439/82-32 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900
- Atlanta, Georgia 30323
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2
.0PERATIONAL DEFECTS IN HIGH-PRESSURE INJECTION N0ZZLES AND THERMAL SLEEVES - BLRD-50-438/82-35, BLRD-50-439/82 SEVENTH INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector Don Quick on April 29, 1982 in accordance with 10 CFR 50.55(e) as NCR BLN NEB 8206. This was followed by our interim reports dated June 1 and
_. July 28,1982; March 1, April 11, and November 1,1983; and May 16, 1984.-
Enclosed is our seventh interim report. We expect to submit our next report on er about June 3,1985. We consider 10 CFR Part 21 applicable to this deficiency.
If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.
Very truly yours, TENNESSEE VALLEY AUTHORITY M
$cI. W. Hufham, Manager Licensing and Regulations Enclosure oc (Enclosure):
Mr. Richard C. DeYoung, Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, Georgia 30339 H. B. Barkley 205 Plant Project Services P.O. Box 10935 0FFICIAL COPY Lynchburg, Virginia 24506-0935 8412130611'841129 gDRADOCK05000
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An Equal Opportunity Employer
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ENCLOSURE BELLEFONTE NUCLEAR PLANT UNITS 1 AND 2 OPERATIONAL DEFECTS IN HIGH-PRESSURE INJECTION N0ZZLES AND THERMAL SLEEVES NCR BLN NEB 8206 BLRD-50-438/82-35, BLRD-50-439/82-32 10 CFR 50.55(e)
SEVENTH INTERIM REPORT Description of Deficiency Recent inspections at several B&W operating plants revealed defects in the makeup /High Pressure Injection (HPI) nozzles and their thermal sleeves and in the makeup piping upstream of these nozzles. The nozzles are located on each reactor coolant cold leg between the reactor coolant pump and reactor vessel.
The nozzles and sleeves are supplied by B&W under the Nuclear Steam Supply System (NSSS) contract. The defects include:
. through-wall circumferential crack at the welded joint between the nozzle safe end and the first check valve upstream of the safe end
. loose thermal sleeves
. missing or worn thermal sleeve retaining buttons The loose thermal sleeves and missing or worn retaining buttons remove the mechanical restraints which were designed to avoid exposing the nozzle and pipe to a thermal shock condition by preventing sleeve movement in the upstream direction.
s Although the degraded components at the affected plants were the same,. the resulting damage was not identical. Accordingly, B&W is investigating this 4
concern to determine its cause and to determine if it has galeric implications for other B&W plants, including Bellefonte. The Bellefonte nozzle configuration is similar to that at the affected plants except that it is a one-piece construction while the nozzles for the affected plants have a welded safe end. B&W has notified TVA of no similar potential deficiencies in the past for other Bellefonte NSSS nozzles. There are no l
implications for other TVA plants.
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Interim Progress Interim report No. 6 outlined TVA's remaining concern about the adequacy of the sleeve recolling for the life of the plant. Specifically, TVA requested B&W to provide a quantitative evaluation supporting maintenance of the rolled interface l
(thermal sleeve / nozzle interface) stress field for the design life thermal
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In response to this concern, B&W indicated that the rolled interface design will l
be verified through periodic inspection of operating units before the time BLN l
units go into service. TVA has questioned how a near-term inspection program l
for the HPI cozzle thermal sleeves will verify the 40-year design life.
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