ML20072T254
| ML20072T254 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 02/08/1991 |
| From: | Stols R COMMONWEALTH EDISON CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 9104180047 | |
| Download: ML20072T254 (3) | |
Text
Commonwealth Edison e
'gi 1400 Opus Place gigin m.ig, Downers nrove, Hunois 00516 g
y P; MF i W x February 8, 1991
'g'Q{
,4-Mr. A. Dert Davis Regional Administrator U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137
Subject:
Quad Cities Nuclear Power Station Unit i High Pressure Coolant Injection (HPCI)
Steam Exhaust Chect Valve NRCJott etJiou50-25L_
Reference:
(a) H.J. Hiller to Cordell Reed letter dated June 15, 1990 transmitting Inspection Report 50-254/89024 and 50-265/89024.
(b) 1.J. I:ovach to A.B. Davis letter dated August 17, 1990 transmitting response to Notice of Violation.
Mr. Davis:
A Notice of Violation (NOV) was issued as a result of an NRC Inspection of the Quad Cities containment testing program (Reference (a)).
The NOV cited that ineffective corrective actions were implemented for 10 CFR 50 Appendix J test failures.
Reference (b) provided our response to the HOV.
In that response, Commonwealth Edison committed to replace the Unit i HPCI steam exhaust valve during the current Unit 1 Refueling Outage; however, we have determined that valve replacement, at this time, is not prudent.
The basis for that determination is provided in the attachment. Commonwealth Edison will continue to test the valve on an accelerated schedule to assure its integrity as a containment boundary and to assess the effectiveness of other actions implemented to correct repetitive valve failures.
Our reviscd plan not replace the HPCI steam exhaust check valve was discussed with F. Maura of your staff on January 17, 1991.
During that meeting, Mr. Maura was briefed on the results most recent Quad Cities test campaign and the corrective attions implemented.
\\V 9104180047 910208 DR ADOCK 0500 2i4 g
Mr. A.B. Davis February 8, 1991 If there are any questions or comments concerning this submittal, please contact me at 708/515-7283.
Very truly yours, N
h Rita Stols Nuclear Licensing Administrator cc:
L.H. 01shan, NRR Project hanager D.L. Burgess, Section Chief, Region 111 H.P. Phillips Section Chiif, Region 111 F.A. Maura, Regional Inspertor, Region 111 T.E. Taylor, Senior Resideitt inspector RS:Imw ZHLD744/4
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MTACHMENI BASIS FOR THE REVISED COMMITTMENT B6cLgrov0d HRC Inspection Report 50-254/89024 and 50-265/89024 issued a Notice of Violation which cited that ineffective correction actions were implemented in response to repetitive failures of 10 CFR 50 Appendix J tests. One of the valves specifically discussed in the Inspection Report was the High Pressure Coolantinjection(HPCI) steam exhaust check valve.
In response to the Notice of Violation, Commonwealth Edison committed to replace the Unit 1 HPCI steam exhaust check valve during the current Refueling Outage.
In addition, Commonwealth Edison committed to perform diagnostic testing of the HPCI steam exhaust check valve.
This testing was performed in response to a General Electric finding which indicated that low speed operation of the turbine may have a detrimental effect on the valve and piping.
Quad Cities has conducted the testing and has revised the HPCI survelliance procedure to restrict the time period for operation of the
- turbine, Dn11 dor _theley11edlemmitment On August 30, 1990, the HPCI surveillance test was revised such that the HPCI turbine speed is allowed to operate at 2000 RPM to accommodate valve line-up changes.
Previously, the turbine remained at 2000 RPM for approximately three (3) minutes to allow for turbine warming.
The revision to the surveillance procedure was implemented to reduce the " chattering" of the HPCI steam exhaust valve (2301-45) which occurs during low speed operation.
The 1-2301-45 valve was replaced in September, 1990 following the failure of a test of the valve which was performed on an accelerated schedule.
1he valve has been in-service under the revised surveillance procedure.
On November 19, 1990, Unit 1 began its Refueling Outage.
The
(.ocal Leak Rate Test which was performed on 1-2301-45 was successful with a leakage of "0" scfh.
It is therefore essential that the current valve remain in the system to assess the effectiveness of the revised survelliance methodology.
A local leak rate test of the 1-2301-45 valve will be conducted approximately three (3) months after the completion of Unit 1 Refueling Outage.
Additional testing of the existing valve would provide additional data points which are essential for the determination of the cause for the repetitive valve failure.
In the event that the 1-2301-45 valve fails during this test, the valve will be replaced.
If the valve passes the test, the testing frequency will be evaluated to assure valve integrity and to assist in the determination of the effectiveness of the revised HPCI surveillance test.
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