ML19309E942
| ML19309E942 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/18/1980 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| TLL-176, NUDOCS 8004250360 | |
| Download: ML19309E942 (3) | |
Text
3 Metropolitan Edison Company Post Office Box 480
=
Middletown, Pennsylvania 17057 717 944-4041 Writer's Direct Dial Number April 18, 1980 TLL 176 Office of Nuclear Reactor Regulation Attn: Harold Denton, Director U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit II (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 Exemption from the Requirements of 10 CFR 50.55a This letter is written to formally request relief from the requirements of 10 CFR 50.55a concerning the Inservice Inspection Program. As a result of the accident which o curred on March 28, 1979, the unit will be shutdown for an extended period of time (at least until 1984). In lieu of the requirements of 10 CFR 50.55a, testing /surveillances will be performed in accordance with the Recovery Technical Specifications / Recovery Operations Plan as addressed in the February 11, 1980 Order. The enclosed justification provides the basis for this request.
Sincerel,
R. C.
rnold Sr. Vice President RCA:LWH:SDC: hah Enclosure ec:
J. T. Collins B. Crier V. Stello Aco!
sE
///
8004250360 Metropohtan Ecison Company is a Memeer of the General Puche Utihties System
's -
Encloaurs 1 TLL 176 This facility is required by 10 CFR 50.55a Section G, Paragraphs 1 and 4 to meet the inservice inspection requirements of Section XI of the ASME Boiler and Pressure Vessel Code and its addenda. The edition to which this facility ascribes is the 1974 edition with the summer of 75 addenda.
As a result of the March 28, 1979 accident, the Unit II facility has been, and continues to be out of service. The out of service term has already exceeded one year and will continue until at least 1984.
According to article IWA-2400, Inspection Intervals, paragraph (a) the inspection interval for Class I, II and III components may be extended for a period equivalent to the length of the shutdown provided that it is equal to or greater than one year. As of the end of March,1980, we have met this criteria and are therefore requesting the extension of the inspection interval for articles IWB, IWC and IWD _ of Section XI of the ASME code.
Article IWP-3400, Frequency of Inservice Tests, paragraph (a) allows for discontinuing the inservice tests of pumps during shutdown periods.
It is our intention to discontinue testing pumps which are no longer safety related.
Those pumps that are safety related, in the facilities present condition, will be tested in accordance with the Recovery Technical Specifications and the Recovery Operations Plan.
Article IWV-3000 deals with inservice inspection of safety related valves.
Section IWV-3410, Valve Exercising Tests, paragraph (f), allows an exemption to the exercising requirements of category A and B valves in systems out of-service while paragraph (b)(1), allows for exercising category A valves only as far as practical, if at all, during_ plant operation.
In this facility, I
category A valves are exclusively containment isolation valves. While many of the systems which these valves are a part, are out of service, the valves 7
remain in service to maintain containment isolation.
These valves will not be tested as allowed for in section IWV-3410(f) and (b)(1). These valves will be maintained as required by the Recovery Technical Specifications and the Recovery Operations Plan.
t
' TLL 176 Category B valves in systems out of service will not be tested as allowed for in section IWV-3410(f). The remaining safety related category B valves will be tested in accoraance with the Recovery Technical Specifications and the Recovery Operations Plan.
Category C valves in systems out of service will not be tested while the systems remain out of service. These category C valves will be tested at system restart.
Safety related category C valves will be tested in accordance with-the Recovery I
Technical Specifications and the Recovery Operations Plan.
I
.