ML20064C916
| ML20064C916 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 12/27/1982 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| REF-PT21-82 10CFR-050.55E, 10CFR-50.55E, NCR-2086, NCR-2087, NCR-2088, NUDOCS 8301040513 | |
| Download: ML20064C916 (2) | |
Text
N TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ol 400 Chestnut Street Tower II December 27, 1982 BLRD-50-438/82-80 U.S. Nuclear Regulatory Commission Region II Attn:
Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
BELLEFONTE NUCLEAR PLANT UNIT 1 - RAW COOLING WATER CHILLER UNIT FLOW CONTROL VALVE DEFICIENCIES - BLRD-50-438/82 FIRST INTERIM REPORT The subject deficiency was initially reported to NRC-0IE Inspector G. A. Belisle on November 26, 1982 in accordance with 10 CFR 50.55(e) as J NCR's 2086, 2087, and 2088.
Enclosed is our first interim report. We d expect to submit our next report on or about March 21, 1983 Weconsideg 10 CPR Part 21 to be applicable to this deficiency.
g If you have any questions concerning this matter, please get in touch with R. H. Shell at FTS 858-2688.
'/
Very truly yours, ct TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Enclosure oc:
Mr. Richard C. DeYoung, Director (Enclosure)
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 fr y tr.,; r
~
X
- f. 8301040513 821227
/-- tb d-i PDR ADOCK 05000438 S
PDR An Equai opportoruty Employer
' t 4r i
ENCLOSURE BELLEFONTE NUCLEAR PLANT UNIT 1 RAW COOLING WATER CHILLER UNIT FLOW CONTROL VALVE DEFICIENCIES 10 CFR 50.55(e)
BLRD-50-438/82-80 NCR's 2086, 208h 2088 FIRST INTERIM REPORT E
Description of Deficiency Two six-inch freon-activated raw cooling water (RCW) flow control valves (serial Nos. 24867 and 24865) failed to operate upon activation.
This resulted in a high-pressure trip of the HVAC water chillers which are used to remove heat generated by components of the engineered safety features (ESP) system.
Investigation revealed that the failures were because of two separate conditions. One valve (serial No. 24867) failed because of a buildup of rust and scale on the valve's pilot seat contact surfaces. This inhibited the movement of the valve stem. On both valves, the valve stem nut was completely detached. This allowed the valve diaphragm to operate independently of the valve stem. These conditions degraded the valves' ability to perform their intended function.
In addition, the internal configuration of the valves supplied do not conform to the vendor's drawings. The drawings depict a two-way valve but the valves supplied are three-way valves with one lower port blocked to make it a two-way valve. In addition, the drawings show a lower diaphragm, diaphragm spar:er, and diaphragm plate which are not on the valves j
supplied.
l The valves in question were manufactured by Metrex Valve Corporation, l
Glendora, California, and supplied as components on the water chillers fabricated by Dunham-Bush, West Hartford, Connecticut.
Interim Progress TVA is in the process of contacting the valve vendor to determine the cause of the failures and request a recommendation for corrective actions.
t i
i l
-.