ML20076K776
| ML20076K776 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/12/1983 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737 5211-83-197, GL-82-33, NUDOCS 8307180098 | |
| Download: ML20076K776 (2) | |
Text
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i GPU Nuclear
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P.O. Box 480 g
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Middletown, Pennsylvania 17057 717-944-7621 s Nect Dal WmW July 12, 1983 5211-83-197 Office of Nuclear Reactor Regulation Attn: Darrel G. Eisenhut, Director Division of Licensing 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. 50-289 Emergency Response Capabilities Supplement 1 to NUREG 0737 This letter further documents our response to the information requested in Generic Letter S'_-33 and provides a clarification to the TMI-1 Integrated Implementation Schedule as shown on page 1-3 of our April 15 letter. At the request of our Project Manager, Mr. James Van Vliet, we have identified items in the schedule that are not dependent on the fuel cycle. Depending on our actual restart date, we will complete those items as sta'.ed in our April 15 letter (i.e., a number of months aftcr restart), but no later than the calendar date specified in this letter.
For those items that are dependent on the fuel cycle, we have assumed (for the purpose of this letter) a September 20, 1983 start for Cycle 5.
For these items we have provided estimated dates that can slip on a day for day basis if restart is delayed beyond September 20, 1983.
If restart is before September 20, 1983, our completion of these items will be earlier.
.Our schedule to complete the items in NUREG 0737 - Supplement 1, which reflects the above considerations, is attached.
HDH:PJD:CWS:j rg Sincerely, Attachment cc:
J. Van Vliet R. Conte H. D. Hu ill Director, TMI-l d$
Sworn and Subscribed to before me this 12th oo day of July, 1983.
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m-TMI-1 Integrated.Impicmentation Schedule Emergency Response Capabilities NUREG 0737 - Supplement 1 ltem Schedule I.
SPDS Safety Analysis 4 months after restart but no later than April 30, 1984.
SPDS Implementation Plan.
The date for submittal of SPDS Implementation Plan is dependent on a timely review by the NRC of our Safety Analysis and therefore, remains at 2 months af ter accep-tance of the Safety Analysis by the NRC.
Basic SPDS Operational, with existing data points, prior to Cycle 6. (implementation during refueling shutdown est. date 1/31/85)*
Upgrades to Basic SPDS Installed and operational prior to Cycle 7. (implementation during refueling shutdown est. date 8/31/86)*
II.
Detailed Control Room Design Review (DCRDR)
Program Plan (on incomplete 2 months after restart but no later items) and Summary DCRDR Report than February 15, 1984.
Final Report (Supplement)
Within 2 months after startup from Cycle 6. (est. date 3/30/85)*
Ill.
Reg. Guide 1.97 Prior to ead of' Cycle 5 but no Implementation Schedule later than September 30, 1984.
And Final Report (Note:.The Reg. Guide 1.97 effort involves CPUN's participation in and subsequent review of the B&W Owner's Group final report.)
IV.
Upgrade of Emergency Operating Procedures Procedures Generation Package 6 months after restart but no later than
" June 30, 1984.
Implementation of E0P's Prior to Cycle 6 Startup. (implementation during refueling shutdown est.' date 1/31/85)*
V.
, Emergency Response Facilities Techncial Support Center -
6 months after. restart but no Upgrade later than June-30, 1984.
Emergency Operations, Facility Operational November 1, 1983.
- Assumes Restart for Cycle 5 by 9/20/83.
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