ML20247M293: Difference between revisions
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+i GPU Nuclear Corporation | |||
GPU Nuclear Corporation | < E Nuclear | ||
=ersgra o | |||
Middletown, Pennsylvania 17057-0191 717 044-7621 TELEX 84-2386 Writer's Direct Dial Number: | Middletown, Pennsylvania 17057-0191 717 044-7621 TELEX 84-2386 Writer's Direct Dial Number: | ||
September 15, 1989 C311-89-2087 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC | September 15, 1989 C311-89-2087 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 | ||
==Dear Sir:== | ==Dear Sir:== | ||
Three Mile Island Nuclear Station, Unit 1 (TMI-1) | Three Mile Island Nuclear Station, Unit 1 (TMI-1) | ||
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.193 In accordance with 10 CFR 50.4 (b)(1), enclosed is one (1) original, and in addition ten (10) conformed copies of Technical Specification Change Request No. 193. | Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.193 In accordance with 10 CFR 50.4 (b)(1), enclosed is one (1) original, and in addition ten (10) conformed copies of Technical Specification Change Request No. 193. | ||
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Pursuant to 10 CFR 50.91(a)(1), we enclose our analyses, using the standards in 10 CFR 50.92 of significant hazards considerations. As stated above, pursuant to 10:CFR 50.91(a) of the regulations, we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant ha;tards considerations to Thomas Gerusky, the designated representative of the Commonwealth of Pennsylvania. | Pursuant to 10 CFR 50.91(a)(1), we enclose our analyses, using the standards in 10 CFR 50.92 of significant hazards considerations. As stated above, pursuant to 10:CFR 50.91(a) of the regulations, we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant ha;tards considerations to Thomas Gerusky, the designated representative of the Commonwealth of Pennsylvania. | ||
NRC approval is requested by December 1,1989 so that the TSCR may be implemented during the plant refueling cycle BR beginning in January,1990, otherw he implementation will begin in plant refueling cycle 9R. | NRC approval is requested by December 1,1989 so that the TSCR may be implemented during the plant refueling cycle BR beginning in January,1990, otherw he implementation will begin in plant refueling cycle 9R. | ||
Sincerely, | Sincerely, g | ||
i i | |||
. D. | |||
ukill Vice President & Director, TMI-1 HDH/EP/cjg | |||
==Enclosures:== | ==Enclosures:== | ||
: 1) Technical Specification Change Request No.193 | : 1) Technical Specification Change Request No.193 | ||
: 2) Certificate of Service for Technical Specification Change Request No. 193 cc: | : 2) Certificate of Service for Technical Specification Change Request No. 193 cc: | ||
u___ _ ___ _ _ _ __ _ [_ _ _ | J. Stolz, R. Hernan, W. Russell, F. Young i | ||
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation G909250175 890915 PDR ADOCK 05000289 u___ _ ___ _ _ _ __ _ [_ _ _ | |||
PDC 1}} | |||
Latest revision as of 19:44, 1 December 2024
| ML20247M293 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/15/1989 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| Shared Package | |
| ML20247M294 | List: |
| References | |
| C311-89-2087, NUDOCS 8909250175 | |
| Download: ML20247M293 (1) | |
Text
.
e
+i GPU Nuclear Corporation
< E Nuclear
=ersgra o
Middletown, Pennsylvania 17057-0191 717 044-7621 TELEX 84-2386 Writer's Direct Dial Number:
September 15, 1989 C311-89-2087 US Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No.193 In accordance with 10 CFR 50.4 (b)(1), enclosed is one (1) original, and in addition ten (10) conformed copies of Technical Specification Change Request No. 193.
Also enclosed is one signed copy of the Certificate of Service for this request to the chief ~ executives of the township and county in which the facility is located,.as well as the Bureau of Radiation Protection.
Pursuant to 10 CFR 50.91(a)(1), we enclose our analyses, using the standards in 10 CFR 50.92 of significant hazards considerations. As stated above, pursuant to 10:CFR 50.91(a) of the regulations, we have provided a copy of this letter, the proposed change in Technical Specifications, and our analyses of significant ha;tards considerations to Thomas Gerusky, the designated representative of the Commonwealth of Pennsylvania.
NRC approval is requested by December 1,1989 so that the TSCR may be implemented during the plant refueling cycle BR beginning in January,1990, otherw he implementation will begin in plant refueling cycle 9R.
Sincerely, g
i i
. D.
ukill Vice President & Director, TMI-1 HDH/EP/cjg
Enclosures:
- 1) Technical Specification Change Request No.193
- 2) Certificate of Service for Technical Specification Change Request No. 193 cc:
J. Stolz, R. Hernan, W. Russell, F. Young i
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation G909250175 890915 PDR ADOCK 05000289 u___ _ ___ _ _ _ __ _ [_ _ _
PDC 1