ML19341B100
| ML19341B100 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 01/06/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML19341B097 | List: |
| References | |
| NUDOCS 8101300212 | |
| Download: ML19341B100 (1) | |
Text
[
p
- 0, V
e UNITED STATES j
,g NUCLEAR REGULATORY COMMISSION a
wAsMimoTON. o. c. 20sss
\\...../
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION o
TO FACILITY OPERATING LICENSE NO. OPR-50 METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER AND LIGHT COMPANY PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT N0. 1
/
DOCKET N0. 50-289 Introduction By letter dated December 30, 1976 (GQL 1729) Metropolitan Edison Company (the licensee) requested a change to the Three Mile Island Nuclear Station Unit 1 (TMI-1) Technical Specification (TS). This change revises the bases for the reactor coolant leakage requirements.
Discussion & Evaluation The licensee is required by the TS to assure that any reactor coolant leakage does not compromise the the safe operation of the TMI-l facili ty. The bases of this TS, discusses the methodology for accom-plishing this requirement which includes a paragraph as follows:
"When the source and location of leakage has been identified, the situction can be evaluated to determine if operation can safely continue. This evaluation will be performed by the Three Mile Island Operations Group according to routine established in Section 12.1.1 of the FSAR. Under these conditions, an allowable leakage rate of 30 gpm has been established."
The licensee has proposed to eliminate the second sentence in the above quoted paragraph dealing with evaluation being performed by the Three Mile Island operations group according to the established section 12.1.1 of the FSAR. The basis for deleting this statement is that the section 12.1.1 of the FSAR describes the general administrative function of the licensee and this is covered in more detail under section 6 of Appendix A of the TS which is applicable to the evaluation g
of source and location of any reactor coolant leakage. Furthermore the-statement is in error in that other groups besides the operation group perform such an evaluation.
We agree with the licensee that the second sentence in the above quoted paragraph is not necessary and its -
deletion will in no way endanger the public health and safety. On this basis we find the deletion of the sentence dealing with evaluation of the source and location of the reactor coolant leakage is acceptable.
Date: January 6, 1981 6101 ; O 0${3--
.-