ML20100K677
| ML20100K677 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 11/27/1984 |
| From: | Edelman M CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| (RDC-77(83)), NUDOCS 8412110243 | |
| Download: ML20100K677 (2) | |
Text
_
pmn f THE CLEVELAND ELECTRIC ILLUM W ATING COMPANY P.o. box 5000 - CLEVELAND. oHlo 44101 - TELEPHONE (216) 622-9800 - lLLUMINATING BLDO. - 55 PUOLICSOUARE Serving The Best Location in the Nation MURRAY R. EDBJAAN VICE PRESIDENT NUCUAR Mr. James G. Keppler Regional Administrator, Region III Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 RE: Perry Nuclear Power Plant Docket Nos. 50-440; 50-441 Main Steam Isolation Valves Supplied By The General Electric Company [RDC 77(83)]
Dear Mr. Keppler:
This letter serves as the final report pursuant to 10CFR50.55(e) on the potential significant deficiency concerning the actuators on the Main Steam Isolation Valves (MSIV) supplied by the General Electric Company (CE) to the Perry Nuclear Power Plant.
Mr. E. Riley of The Cleveland Electric Illuminating Company notified Mr. J. Konklin of your office of the potential significant deficiency on July 8, 1983. Previous correspondence on this subject was submitted July 29, 1983, and May 15, 1984.
This report contains a description of the potential deficiency, an analysis of safety implications, and the corrective action being taken. As a result of our analysis of safety implications, it has been determined that this condition is not reportable pursuant to 10CFR50.55(e).
Description of Deficiency The MSIV actuator, Biller /Sheffer SA-A034 supplied by GE, failed qualification testing to NUREG 0588. The MSIV was tested as a normal qualification function to evaluate the ability of the actuator to perform its safety-related function for the PWPPs environments. The actuator was exposed to high levels of gamma radiation and temperatures which may exceed these to which the actuator would actually be subjected. This resulted in hardening of the lubricant which inhibited mechanical motion of the actuator and in the deterioration of various Viton seals and o-rings causing hydraulic and pneumatic leakage.
t Analysis of Safety Implication l
The identified failure mode restricts actuator operation, however, such a failure would not inhibit closure of the MSIVs. The MSIVs are designed to close in the event of loss of electrical power or loss of pneumatic pressure.
I Failure of the actuator will cause the MSIV to close. By closing, the MSIV performs its intended safety function of sealing the primary containment and isolating the reactor coolant pressure boundary. Therefore, the identified l
deficiency is not considered to be reportable.
NOV 3 01984 8412110243 841127 PDR ADOCK 05000440 S
PDR y y/
a.
Mr. James G. Kappler Nsvembar 27, 1984 Submittal of the analysis of safety implications for the MSIVs was not made previously pending the results of the qualification testing. This was to ensure that no test failures occurred which affected the ability of the valves
'to perform their intended safety functions.
Corrective Actions As a result of the test failure, the seals on the actuators being tested were changed to EPDM material and the lubrication was changed to Super-0-Lube after which the actuators were aged and successfully tested to the requirements of NUREG 0588. The MSIVs were then qualified with these modifications.
Project Organization issued Nonconformance Reports (NR) TAS 45 and TAS 80 to track the nonconforming condition for Unit I and NRs TAS 46 and TAS 81 for Unit 2.
All MSIV actuators on site will be reworked to replace the existing 4
lubricants and seals with qualified materials. GE issued FDI 134-82411 to implement this change for Unit I rework which will be completed by January 31, 1985. Completion of the Unit 2 rework will be consistent with the Unit 2 construction schedule prior to turnover of the affected systems.
Sincerely,
[
W j
Murray R. Edelman Vice President l
Nuclear Group MRE:pab cc: Mr. J. A. Grobe l
NRC Site Office i
Director j
Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.
20555 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, D.C.
20555
' Records Center, SEE-IN Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 Atlanta, Georgia. 30339 i
,--+-.--..v...m...-.,#
,,__.m__
,..,.,..,_,r,.._,,_....m.,
,_,m_r-my._-m.,,,,.,..,_,,v.~w,
,