ML20133C556
| ML20133C556 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 10/02/1985 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20133C560 | List: |
| References | |
| 5211-85-2154, NUDOCS 8510070426 | |
| Download: ML20133C556 (4) | |
Text
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GPU Nuclear Corporation g
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Post Office Box 480 Route 441 South Middletown, Pennsylvania 17057 0191 717 944 7621 TELEX 84 2386 Writer's Direct Dial Number 5211-85-2154 October 2, 1985 Office of Nuclear Reactor Regulation Attn: John F. Stolz, Chief Operating Reactors Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Stolz:
Three Mile Island Nuclear Station, Unit I, (TMI-1)
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 104, Rev. 3 Enclosed are three originals and forty conformed copies of Technical Specification Change Request No. 104, Rev. 3.
Also enclosed is one signed copy of the Certificate of Service for this t
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 hazards considerations to Thomas Gerusky, the designated representative of the Commonwealth of Pennsylvania.
Pursuant to the provisicns of 10 CFR 170.21, a check for $1,200.00 was sent as payment of the fee associated with Technical Specification Change Request No. 104, Rev. O on June 5, 1981.
1 Sincerely, 8510070426 851002 DR ADOCK O 289 p
. D.
u ill Director, TMI-1 HDH/SM0/spb
Enclosures:
- 1) Technical Specification Change Request No. 104, Rev. 3
- 2) Certificate of Service for Technical Specification Change Request No. 104, Rev. 3
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J. Thoma h0 R. Conte Q4 S
GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
a UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET N0. 50-289 LICENSE N0. DPR-50 GPU NUCLEAR CORPORATION This is to certify that a copy of Technical Specification Change Request No.104, Rev. 3 to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with executives of Londonderry Township, Dauphin County, Pennsylvania; Dauphin County, Pennsylvania; and the Pennsylvania Department of Environmental Resources, Bureau of Radiation Protection, by deposit in the United States mail, addressed as follows:
Mr. Jay H. Kopp, Chairman Mr. Fred Rice, Chairman Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Courthouse Middletown, PA 17057 Harrisburg, PA 17120 Mr. Thomas Gerusky, Director PA. Dept. of Environrrental Resources Bureau of Radiation Pro +.ection P.O. Box 2063 Harrisburg, PA 17120 GPU NUCLEAR CORPORATION BY DirectoY, TMI-1 DATE: October 2,1985
4 METROPOLITAN EDIS0N COMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PENNSYLVANIA ELECTRIC COMPANY THREE MILE ISLAND NUCLEAR STATION, UNIT 1 t
Operating License No. DPR-50 Docket No. 50-289 Technical Specification Change Request No. 104, Rev. 3 This Technical Specification Change Request is submitted in support of-Licensee's request to change Apper. dix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station, Unit 1.
As a part of this request,
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proposed replacement pages for Appendix A are also included.
GPU NUCLEAR CORPORATION BY DirectbN, TMI-l Sworn and Subscribed to beforp me This J/'b day of d> Mhth,1985.
(tLLbY k blik
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Notary P,dblic
$HARON P. BROWN, NOTARY PUBLIC c!G3LETOWN EORO, CAUPHIM COUfi1Y MY COMMIS$10N EXPl2C3 JUEE 12,1989 Member. Pennsylvania Association of Notaries
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,u LIST OF TABLES TABLE TITLE PAGE 1.2-
. Frequency Notation 1-8 2.3-1 Reactor Protection System Trip Setting Limits 2-9 3.1.6.1 Pressure Isolation Check Valves Between the Primary 3-15a Coolant System and LPIS 4
3.5-1 Instruments Operating Conditions 3-29 3.5-2 Accident Monitoring Instruments 3-40c 3.5-3 Post Accident Monitoring Instrumentation 3-40d 3.18-1 Fire-Detection Instruments 3-87 4
3.21-1.
-Radioactive Liquid Effluent Monitoring Instrumentation 3-97 4
3.21-2 Radioactive Liquid Effluent Monitoring Instrumentation 3-101 3.23-1 Radiological Environmental Monitoring Program 3-122 3.23-2 Reporting Levels for Radioactivity Concentration 3-126 in Environmental Samples 4.1-1 Instrument Surveillances Requirements 4-3 4.1-2 Minimum Equipment Test Frequency 4-8 4.1-3 Minimum Sampling Frequency 4-9 4.1-4 Post Accident Monitoring Instrumentation 4-10a I
4.19-1 Minimum Number of Steam Generators to be 4-84 Inspected During Inservice Inspection 4.19-2 Steam Generator Tube Inspection 4-85 4.21-1 Radioactive Liquid Effluent Monitoring 4-88 Instrumentation Surveillance Requirements k-91 4.21-2 Radioactive Gaseous Effluent Monitoring Instrumentation Surveillance Requirements 4.22-l' Radioactive Liquid Waste Sampling & Analysis Program 4-98 4.22-2 Radioactive Gaseous Waste Sampling & Analysis Program 4-106 4.23-1 Maximum Valves for the Lower Limits of Dectection (LLD) 4-118 I
vi
. Amendment No. 59,.72, 100, 106
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