ML19339A055
| ML19339A055 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 03/27/1973 |
| From: | Autio H YANKEE ATOMIC ELECTRIC CO. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| NUDOCS 8010310691 | |
| Download: ML19339A055 (3) | |
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i Attention: Directorate of Licensing
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Reference:
License No. DPR-3 (Docket 50-29)
Dear Sirs:
In accordance with Section D (1) (b) of the plant license we are reporting the following variance in the pressurizer code safety valve set pressures.
The pressurizer safety valves are provided to prevent system The two pressurizer code safety pressure from exceeding design limits.
valves are Dresser 2" x 3" Model 1719 WA valves with a capacity of 92,000 pcunds/ hour / valve. The safety valve designations and set points are:
f PR-SV-181 2485 psig PR-SV-182 2560 psig i
i These safety valves are removed and tested on a test stand with nitrogen at refueling intervals for pressure settings and spring load data.
I Both have had a past history of confomance with the ASME Code require-However during the Core 9-10 refueling in March 1972, the "as ments.
found" set point pressures were out of tolerance.
PR.-SV-181 Was 175 pounds above the code set point limit.
PR-SV-182 Was 174 pounds above the code set point limit.
4 The valves were disassembled and thoroughly inspected. No abnormal conditions were noted during this inspection. The valves were reset on the test stand to the correct set points.
These same safety valves were removed and retested in November 1972 i
j under the direction of a Dresser Industries representative. Again a variance l
was noted in the "as found" pressure set points with both valves lifting i
j above the required settings.
l
he Dresser representative disassembled and inspected both safety j
valves. The spindles were found to be bent between.012"
.014".
Subsequent investigation by the service engineer concluded that one phase of the existing j
1 In test procedure could have a detrimental effect on the valve spindles.
i his opinion, measuring the safety valve spring loading during deflection could result in spindle distortion. This test was 3mally performed with the valve fully assembled, and warned of possible spri.t tension loss.
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!8010s 10 g p
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The pressurizer safety valve test procedure was revised to eliminate this problem.- S"bsequent testr confirmed repeated lifts within code tolerances.
The pressurizer code safety valves will be removed and retested during the next major plant outage. This time interval to be no earlier than six months and no later than the Core 10-11, refueling outage. The valve vendor will be consulted before and during this next test.
A safety evaluation has been completed of the effects of the 175 psi overpressure on_ system compcnent: and transient conditions. The evaluation indicates that no system or transient safety problem would have resulted if the overpressure condition had occurred.
Very truly yours, i h s)
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Herbert A. Autio Plant Superintendent flu
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AEC DISTR 71 TION FOR PART 50 DOCIET MATERIAL (TEMPORARY FOR'4)
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COiiTROL NO:
2100-777,
7303:
DATE OF DOC:
DATE REC'D LTR EMO RPf OIHER Yankee Atocic Electric Company 01367 n,. d Massachuse,tts 3-27-73 _
3-30-73.
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$ 0F INFO INPUT NO CYS REC'D D0';l:ET NO:
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ENCLOSURES:
Ltr reporting an variance in the pressuiizer code safety valve set pressures......
NOTE: *PLEASE CIRCUIAT3-INSUFFICIENT COIIES 00 f\\'Of R8m0Ve RECEIVED FcR FutL DISTRIBurION QElW MCn
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cc: Mr. Donald G. Allen, President Yankee Atomic Electric Company
= 21 20 Turnpike Road Westboro, Massachusetts 01581
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Greenfield Public Library.
402 Main Street Greenfield, Massachusetts 01581 o
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