ML20236N631
| ML20236N631 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 08/07/1987 |
| From: | Rooney V Office of Nuclear Reactor Regulation |
| To: | Capstick R VERMONT YANKEE NUCLEAR POWER CORP. |
| Shared Package | |
| ML20236N634 | List: |
| References | |
| TAC-64524, NUDOCS 8708120040 | |
| Download: ML20236N631 (2) | |
Text
- _ _ - _ _ _ _ _ _ _ _ _ _
'd
,. 4 (
August 7, 1937
}
-'?
Docket No.:
50-271 Mr R. W. Capstick Licensing Engineer Vermont Yankee Nuclear Power Corporation 1671 Worcester Road Framingham, Massachusetts 01701
Dear Mr. Capstick:
SUBJECT:
ELIMINATION OF PENETRANT EXAMINATION OF FEE 0 WATER N0ZZLES (TAC NO. 64524)
Re:
Vermont Yankee Nuclear Power Station By letter dated January 5,1987, Vennont Yankee Nuclear Power Corporation requested permanent elimination of the liquid penetrant (PT) examination of the feedwater nozzles at the Vermont Yankee Nuclear Station. The PT examination of the feedwater nozzles is a part of the requirements that stem from the staff's resolution of the BWR feedwater nozzle cracking issue.
Vermont Yankee's feedwater nozzles are required to have a PT examination every 2 fuel cycles, and an ultrasonic (UT) examination every fuel cycle.
In addition, the feedwater sparger is required to have a visual examination every two cycles. The licensee re examination as adequate, (2) quested the change because (1) VYNPC regards UT no cracks have been found in the nozzles in the past ten years of examinations; and (3) the leakage monitoring system has not recorded any leakage at the nozzles.
Based on our evaluation, we believe that the permanent elimination of the PT examination is inappropriate because we do not have reasonable assurance and confidence that the UT examination can totally replace the PT examination. However, based on the licensee's modifications to the feedwater nozzles, we find that the PT examination may be lengthened from the existing 2 fuel-cycle interval to a 6 fuel-cycle interval.
I 4
8708120040 970007 j
PDR ADOCK 0500 1
P
{
l
- o
J $.
-2 The new examination interval will begin at the current fuel cycle so that the first outage of the 6 fuel-cycle interval is the August 1o87 refueling outage.
Should cracks be detected in the future the licensee is required to revert to the original 2 fuel-cycle interval for PT examination.
A copy of our Safety Evaluation is enclosed.
Sincerely,
/S/
Vernon L. Rooney, Project Manager Project Directorate I-3 Division of Reactor Projects I/II
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page DISTRIBUTION: ;
'Dockett E11e.,50-271' NRC PDR Local PDR PDI-3 r/f S. Varga B. Boger M. Rushbrook V. Rooney D. Hagen E. Jordan J. Partlow T. Barnhart (4)
Wanda Jones E. Butcher Tech. Review Branch - J. Tsao, MEB ACRS (10) 3PA/PA ARM /L MB J
.v OFC :PDI-3 /
D -JT
- ACT [LREDI-3:
y- ----:-. ----.---:------------::----------- :-: --------
:..-- l.
NAME:VRoondy m :MRus bro k :VNe es
- 08/l/87
- 08/1 /87 f
DATE :08//
87
/
\\
0FFICIAL RECORD COPY
_.. _ _ _ _ _