ML20032B241
| ML20032B241 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/27/1981 |
| From: | Hukill H METROPOLITAN EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20032B238 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-2.F.2, TASK-TM L1L-312, NUDOCS 8111050338 | |
| Download: ML20032B241 (1) | |
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Metropolitan Edison Company Post Office Box 480 e
Middletown, Pennsylvania 17057 Writer's Direct Dial Number October 27,1981 LlL 312 Office of Nuclear Reactor Regulations Attn:
John t.
.,Mlz, Chief Operating Reactor; Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-239 Modifications to NUREG 0737 Item, Completion Dates In our letters of January 23, 1981 (TLL 680) and February 6, 1981 (L1L 033) we identified anticipated completion dates for both short term (Restart) and long term ar.tivities required by NUREG 0737. This letter constitutes preliminary notification that we intend to request that,with respect to certain items listed below, the NRC exercise the flexibility, discussed in Commission Order CLI-81-3 (March 23, 1981), to amend the previously established dates for the completion of these items. The request with justification information will be provided within two weeks of the date of this letter.
It will include appropriate details regarding material delivery problems, plant controlling construction lead times, plant controlling test requirements, any other controlling item, or compensat-ing interim capabilitics to the extent necessary to justify the newly proposed dates.
The identified items which we currently project require this consideration are:
NUREG 0737 Item Description II.B.3 Post Accident RCS Sampling - Pressurized San,l'. Capability i
Post Accident Containment Sampling II.F.1 Post Accident Containment Pressure - Safety Grade Post Accident Containment Hydrogen Monitoring Reactor Building Sump Water Level - Safety Grade II.F.2 Backup Incore Thermocouples If there is any other information that you require, please let us know.
Sincerely, 1050338 g11030 o
ADOCK 0S000289 PDR n.
D.
lukill Dtrector, TMI-l cc:
R. Jacobs T. Novak rocchtan Edison Company is a Memoer of the General Fuchc Utities System t
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