ML20035A617
| ML20035A617 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/19/1993 |
| From: | Broughton T GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20035A618 | List: |
| References | |
| C311-93-2032, NUDOCS 9303290084 | |
| Download: ML20035A617 (2) | |
Text
f GPU Nuclear Corporation S d Nuclear re:'r Middletown, Pennsykania 17057-0480 (717) 944-7621 Wnter's Direct Dial Number.
i (717) 948-8005 March 19 1993 C311-93-$032 U. S. Nuclear Regulatory Commission Attention: Document Control Desk f:i Washington, DC 20555
Dear Sir:
Subject:
Three Mile Island Nuclear Station, Unit 1, (THI-1)
Operating License No. DPR-50 t
Docket No. 50-289 Technical Specification Change Request (TSCR) No. 207 RPV Pressure and Temperature (PT) Limits In accordance with 10 CFR 50.4(b)(1), enclosed is' Technical Specification Change Request No. 207.
Also enclosed is the Certificate of Service for this request certifying service to the chief executives of the township and county in which the facility is located, as well as the designated official of the Commonwealth of Pennsylvania, Bureau of Radiation Protection.
The purpose of this TSCR is to request that the THI-1 Technical Specifications l
Section 3.1.2, regarding reactor vessel pressurization heatup and cooldown limitations, and Sections 3.1.12.1 through 3, and 4.5.2.1.c.1, regarding PORV operability and HPI testing as they relate to low temperature overpressurization (LTOP) protection, be revised to extend the period of applicability from 10 EFPY to 32 EFPY, which is beyond the present licensed expiration date based on 90% availability.
i In anticipation of your request we have enclosed Technical Specification Section 3.1.2 Reference No. 6 (Topical Report TR 095, Rev. 0).
Pursuant to 10 CFR 50.91(a)(1), enclosed is our analysis, applying the standards in 10 CFR 50.92 to make a determination of no significant hazards considerations. As stated, above, pursuant to 10 CFR 50.91(a), we have provided a copy of this letter, the' proposed change in Technical Specifications, and our analyses of significant hazards considerations to
' Richard R. Janati, the designated representative of the Commonwealth of '
r 9303290084 930319 260061 P" ^" "#8!'
.R GPU Nuclear Corporation is a subsidiary of General Public Utihties Corporation b[
6
F Document Control Desk.
C311-93-2032 Page 2 i
The existing TMI-l Technical Specification heatup and cooldown limits are applicable for plant operation to ten (10) EFPY. GPU Nuclear requests issuance of this amendment by August 1,1993 to allow sufficient time for implementation prior to the plant exceeding 10 EFPY.
Sincerely h%
T. G. Broughton 3
Vice President and Director, THI-l l
YN\\ pip
Enclosures:
(1) Technical Specification Change Request No. 207 (2) Certificate of Service for Technical Specification i
Change Request No. 207 i
(3) Technical Specification Section 3.1.2 Reference No. 6 Topical Report TR 095, Rev. 0
-t cc: Administrator Region I TMI Senior Resident Inspector THI-l Senior Project Manager 5
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i t
5
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