ML20077S425
| ML20077S425 | |
| Person / Time | |
|---|---|
| Site: | 05000000, Crane |
| Issue date: | 10/23/1981 |
| From: | Haverkamp D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Keimig R NRC |
| Shared Package | |
| ML20077S281 | List: |
| References | |
| FOIA-83-349 NUDOCS 8309220077 | |
| Download: ML20077S425 (3) | |
Text
[ **lg UNITED STATES
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-*k NUC:. EAR REGULATORY COMMisslON Yl R E
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OCT 2 31987 s31 ARK AVcNUE nina or paussia,'ecussvi.vania i,4os g
Docket No. 50-289 MEMORANDUM FOR:
R. R. Keimig, Chief, Projects Branch #2 THRU:
A. N. Fasano, Chief fy/Sw Three Mile Island Residhnt Section FROM:
D. R. Haverkamp, Senior Resident Inspector (TMI-l)
Three Mile Island Resident Section
SUBJECT:
TEMPORARY REPAIR OF VALVE DH-V-1 USING FURMANITE
Reference:
September.1981 Monthly Operating Report for TMI-1, This memorandum is sent to ' document my understanding of the licensee'h recent, temporary repair of valve DH-V-1, as discussed.in our telephone conversation on October 21, 1981.
The Major Safety Related Maintenance section of the above referenced licensee report stated; "While operating at 2155 psi, 532*F, Decay Heat Valve, DH-V-1, developed a small seal ring leak.
Repair to the valve was performed by reinjecting furmanite into the seal ring area.
The leakage from the seal ring area was reduced.
1 The leakage was stopped when the system was placed in-service."
i Your review of the above information and your recollection of similar problems with valve DH-V-1 identified a need to obtain certain additional information regarding the most recent repair.
My followup to your questions included discussions with Mr. R. Barley, Lead Mechanical Engineer and Mr. R. Troutman, Supervisor of Management Control.
Information
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obtained during those discussions is summarized below.
The valve was repaired initially in November 1976 using furmanite.
Minor leakage developed subsequent to that repair, which resulted in additional injection of furmanite during 1977 or 1978.
Those problems and repairs are described in several 4
Region I inspection reports and various internal memoranda.
During the preliminary hot functional testing which occured in
~
August and September 1981, the licensee noted additional minor leakage past the seal ring of DH-V-1.
Attempts were made to stop that leakage by drilling and removing existing furmanite from the installed injection adapters and reinjecting furmanite in those areas.
One of the injection adapters was bent and thus furmanite could not be removed and reinjected in that area.
Due to that problem, the leak was not able to be fully ll B309220077 830728 PDR FOIA PETCHEB3-349 PDR
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OCT 2 319g1 R. R. Keimig j2-stopped in September 1981.
However, with the plant in the current cold shutdown condition using the Decay Heat System at essentially no differential pressure, there is no leakage from DH-V _1 to the reactor building.
The recurring leakage appears to be minor in nature and is described by the licensee representatives' as a weep or vapor puffs.
There may be minor deterioration of the sealihg properties of the furmanite compound over a period of time.
For that reason -the licensee had initiated monthly inspections of the valve DH-V-1 while the reactor was in operation.
During that mode df operation the valve is shut and the valve seat provides a pressure. breakdown which reduces the leakage if any should occur.
The only time the furmanited area is directly subjected to RCS pressure is when DH-V-1 is open.
That occurs when-the reactor is being cooled by'the Decay Heat System and during transitions between RCS cooling using -
reactor coolant pumps and normal Decay Heat System cooling.
The maximum RCS pressure is about 400'psig during the' transition periods which are generally of short duration.
The licensee's plans for short term corrective action include the removal of the bent injection adapter and. replacement with an-adapter which is on hand.
Furmanite will then be reinjected.
These actions are to occur during the next heatup which may be in January 1982.
The licensee's plans for long term corrective action include-permanent repair or replacement of the entire valve if necessary.
Either maintenance action must be accomplished with the reactor core defueled, as the Decay Heat Cooling System is out of service during the time the repairs are in 'progres's.
The licensee plans to accomplish this repair during the first outage which requires a total core defueling.
At this time that type of defueling is next required for the 10 year inservice inspection of the reactor vessel currently scheduled to occur about 1987 or 1988.
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OCT 2 31981 R. R. Keimig _
I am not aware of any technical problems or inadequacies associated with the licensee's past or future actions concerning the repair of DH-V-1.
However, the above information has been sent to document my understanding of the licensee's actions and to. inform you and those inspectors in the regional office having more technical expertise in this area than myself.
Should you or others require additional information regarding the DH-V-1 repairs, please do not hesitate to contact me.
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D. R. Haverkamp Senior Resident Inspector (TMI-1)
Three Mile Island Resident Section cc:
S. Ebneter, Acting Cnief, Engineering Inspection Branch L. Tripp,. Chief, Materials and Processes Section, EIB S. Reynolds, Reactor Inspector,' MAPS, EIB 4
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