ML19309H257
| ML19309H257 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/05/1980 |
| From: | Finfrock I GENERAL PUBLIC UTILITIES CORP., JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TASK-06-07.C1, TASK-07-03, TASK-08-03.B, TASK-RR NUDOCS 8005090446 | |
| Download: ML19309H257 (2) | |
Text
8005090 Wlog Jersey Central Power & Light Company
_lfMkl EDH uaa, son ^ venue at eunen so~i noaa Mornstown, New Jersey 07960 (201)455-8200 May 5, 1380 Director, Nuclear Reactor Regulation United States Nuclear Regulatory Commission Washington, D. C.
20555
Dear Sir:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 Modification Schedule Due to delivery and receipt inspection problems of certain com-ponents, the plant modification to the 125 VDC system that was to be completed during the present refueling outage will not be fully implemented until the next scheduled plant outage which is presently planned for the Fall of 1980.
A modification of the station's 125 VDC system is physically complete and operable; however, four components in the system are not Class IE components. As stated in my letter to you dated April 4,
- 1978, the 125 VDC modification was installed during the 1978 refueling outage.
At that time, eleven components were not IE components; and tw'
- her components lacked documentation of certification.
Since that time, work has continued to upgrade the system to make it a completely qualified IE system.
The present status is that four components will not be certified IE components when the plant starts up from the present refueling outage. These components include two distribution panels and two breakers. The presently installed non-IE components are essentially the same as the IE components that will replace them, but they lack traceability of materials and quality certifications.
Also, in my letter of April 10, 1980 to Mr. D. G. Eisenhut, a description of the high range stack gas monitors was provided. Prior 1
to startup from the present refueling outage, the system, as described in our original submittal, will be installed and fully operational except that the indication and recorder will be located locally rather than 1
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\\t V Jersey Central Power & Light Comcany 's a Member of the General Pubhc Uti!.t:es System i
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Director, Nuclear Reactor Regulation Page 2 in the Control Room as originally stated. The local location selected will be in an area where post-accident dose rates will permit readings to be taken every fifteen minutes and relayed to the Control Room and/or Technical Support Center. Control Room readout for this system will be provided by January 1, 1981 as required by NUREG 0578.
If you should have any questions concerning these modifications, please contact Jim Knubel (201-455-8753) of my staff.
Very truly yours, o
Ivan R. Finf ck, r.
Vice Presid t 1r 1
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