ML20058D044
| ML20058D044 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/21/1982 |
| From: | J. J. Barton GENERAL PUBLIC UTILITIES CORP. |
| To: | Barrett L Office of Nuclear Reactor Regulation |
| References | |
| 4400-82-L-0119, 4400-82-L-119, NUDOCS 8207270016 | |
| Download: ML20058D044 (1) | |
Text
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GPU Ouclear P.O. Box 480 g{
/
Middletown, Pennsylvania 17057 717-944-7621 Writer's Direct Dial Number:
f July 21, 1982 4400-82-L-0119 4
i TMI Program Office Attn:
Mr. L. H. Barrett, Deputy Program Director US Nuclear Regulatory Commission
- /o Three Mile Island Nuclear Staticn Washington, DC 20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 2 (TMI-2)
Operating License No. DPR-73 Docket No. 50-320 CRDM Leadscrew Uncoupling The purpose of this letter is to inform you of our intent to uncouple all CRDM leadscrews immediately following the Quick Look Project.
It is our intent to only attempt uncoupling the leadscrews.
Parking the leadscrews will not be attempted. The uncoupling activitfes,will be Q
Technical Specification 6.8.2.
The proposed activities will cover a h.
)N accomplished utilizing procedures.previously developed and approved to period of approximately three to four weeks.
Based on the results of g
the Quick Look, an assessment will be made to determine if t:te RCS g3 i
heatup rate will allow the RCS to remain unpressurized and drained for g
N the extra time period. As discussed in the Quick Look Safety Evaluation, A
g contingency plans and emergency procedures are available, should the RCS temperature approach the limit. The proposed activities are bounded by the safety evaluation reports previously submitted to the NRC for the APSR Insertion and for the Quick Look Project.
p Both Safety Evaluationshave been reviewed and accepted by the staff.
There will be no additional criticality, boron dilution, or other safety concerns above those addressed in the referenced Safety Evaluations.
The uncoupling of the leadscrews can be accomplished without undue risk DO O to the health and safety of the public, and does not constitute an unreviewed safety question. Therefore, GPU proposes to uncouple the CRDM leadscrews as described above.
E h
l Sincerely, c_
M(
h
/s/ J. J. Barton h
m M
N 8207270016 820721 SE PDR ADOCK 05000320 J. J. Barton m
P PDR Acting Director, TMI-2 E
JJB/RBS/jep N
l O
l CC:
B. J. Snyder, Program Director - TMI Program Office GPU Nuclear is a part of the General Public Utilities System lJ