NRC-91-0033, Revises 891020 Commitment to Perform Monthly stroke-time Testing for Four Jamesbury Valves W/Carbon Steel Internals at End of Second Refueling Outage,Per Violations Noted in Insp Rept 50-341/87-22
| ML20073B967 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 04/17/1991 |
| From: | Orser W DETROIT EDISON CO. |
| To: | Davis A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| CON-NRC-91-0033, CON-NRC-91-33 NUDOCS 9104250037 | |
| Download: ML20073B967 (3) | |
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NRC-91-0033 Mr. A. B. Davis Region *III Administrator Region III Office 799 Roosevelt Road Glen Ellyn, IL 60137
Reference:
1)
Fermi 2 HRC Docket No. 50-341 NRC License No. NPF-43 2)
HRC Inspection Report No. 50-341/87022, dated July 23, 1987 3)
Detroit Edison Letter, NRC-87-0140, dated August 21, 1987 4)
Detroit Edison Letter. NRC-89-0219, dated October 20, 1989
Subject:
Removal of Jamesbury Valves from Increased Frequency of Stroke-Time Testine In 1987, Detroit Edison received a violation for inadequate corrective action to prevent failures of Jamesbury butterfly valves (Reference 2).
The corrective action to prevent reoccurrence stated in the response to the violation (Reference 3) was that:
The remaining carbon steel shaf ts and wafers in safety-related Jamesbury valves vill be replaced with stainless steel shafts and vafers. Twenty-three of the thirty-three safety-related Jamesbury butterfly valves already have stainless steel components. The remaining ten valves vill be modified by replacing their carbon steel shafts and vafers with corresponding stainless steel components prior to startup following the first refueling outage....In the interim, the ten Jamesbury valves with carbon steel internals vill be monitored by stroke-time testing monthly until they have been modified as described above.
In 1989, the commitment to replace all safety-related Jamesbury butterfly valves carbon steel internals was changed (Reference 4), and stated that:
Ins,tead, for the remaining five valves, monthly stroke-time testing vill be conducted to monitor for potential degradation until the stems and wafers are replaced with stainless steel components.
[}I,1)}' I 9104250037 910417 PDR ADOCK 05000341 U
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U. S. Nucloar Rsgulatory Co :ission April 17, 1991 i
NRC-91-0033 Page 2 The remaining five valves containing a carbon steel shaft and/or vafer are:
Shaft Vafer Material Material Location T4600F402 CS CS/ Nickel Plated Reactor Bldg. 3rd Floor T4600F407 SS CS/ Nickel Plated Reactor Bldg. 3rd Floor T4600F408 SS CS/ Nickel Plat,ed Reactor Bldg. 5th Floor 74800F407 CS CS/ Nickel Plated Top of Torus T4803F601 CS CS/ Nickel Plated Dryvell - Approx. Elev.
584 ft.
From Reference 4, the use of stroke-time trending to indicate valve degradation due to corrosion at the valve shaft and bearing (bushing) surface interface is appropriate. As discussed in recent telephone conversations with R. DeFayette and R. Huber of HRC Region III staff, and based on satisfactory valve performance trends, Detroit Edison will be discontinuing the monthly stroke-time testing for the above valves, and instead vill be performing quarterly stroke-time testing per the Inservice Test Program fa; the following reasons:
Valve T4600F402, since January 1985, has been stroked over sixty times with stroke-times in the closed direction from 1.3 to 2.6 seconds, except for a single errant stroke-time of 3.8 seconds in l
August 1990.. Valve T4600F408, since January 1989, has been stroked over twenty-five times'with stroke-times in the closed direction from 22.0 to 25.5 seconds, except for two errant stroke-times of 17.7 seconds in July 1989 and 9.8 seconds in December 1989.
Also, since July 1989, valve T4600F408 has been i
stroked over twenty times in the open direction from 9.0 to.11.5 seconds, except for a single errant stroke-time of 2.5 seconds in-March 1990.
Furthermore, these valves are located in a similar non-corrosive environment as valve T4600F409 (Reactor Bldg. 5th floor) which was inspected and appeared to be in 'like nev' l
' condition (Reference 4).
Based on consistent stroke-times and l
non-corrosive environments, these valves will be removed from an
-increased frequency. testing schedule.
L Valve T4800F407, since April 1985, has been stroked over fifty-five times with stroke-times in the closed direction from l
2.0 to 4.6 seconds without an errant stroke-time. Also, this j.
valve.is located in a less corrosive environment than valve l
T4800F405 (Torus H Inert.), which was inspected and appeared to 2
be in " good' condition (Reference 4).
Valve T4803F601, since January 1989, has been stroked over twenty-five times with stroke-times in the closed direction from 3.4 to 4.0 seconds l
vithout an errant stroke-time.
Based on consistent stroke-times, l:
these' valves will be removed from an increased frequency testing schedule.
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U. S. Nuclear Regulatory Cormission April 17, 1991 HRC-91-0033 Page 3 Valve T4600F407 is being worked during the current refueling outage (RF02) and having its internals removed and replaced with stainless steel.
After this work is performed, and following successful completion of the Post Maintenance test, this valve vill be removed from an increased frequency testing schedule.
For these reasons, Detroit Edison is revising the commitment to perform monthly stroke-time testing for the four Jamesbury valves which will have carbon steel internals at the end of the second refueling outage. Instead, quarterly stroke-time testing per the Inservice Test program vill be conducted to monitor for potential valve degradation. The internals of these valves vill be replaced with stainless steel componenta at a later time when maintenance requiring disassembly of these valves is needed.
In addition, if future stroke-time trends show valve degradation, then replacement of internals vill be performed as needed.
The change in this commitment was confirmed per telecon with Mr. Mark Huber, NRC Region III, on April 1, 1991.
If you have any questions please contact Mr. Peter J.
Rashid at (313) 586-1495.
Sincerely,
/
cc R. V. DeFayette V. G. Rogers J. F. Stang R. Huber USNRC Document Control Desk
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