ML19260A053
| ML19260A053 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 02/03/1977 |
| From: | Arnold R METROPOLITAN EDISON CO. |
| To: | |
| Shared Package | |
| ML19260A047 | List: |
| References | |
| NUDOCS 7910290682 | |
| Download: ML19260A053 (4) | |
Text
4 IETROPOLITAN EDISON CCMPANY JERSEY CENTRAL POWER & LIGHT COMPANY AND PE'INSYLVANIA ELECTRIC COMPANY Th"REE MILE ISLAND NUCLEAR STATION UNIT 1 Operating License No. DPR-50 Docket No. 50-289 Technical Seecification Chance Recuest No. 39, A=.
1 This Technical Specification Change Request is submitted in support of request to change Appendix A to Operating License No. DPR-50 for Three Mile Island Nuclear Station Unit 1.
As a part of this request,
proposed replacement pages for Appendix A are also included.
METROPOLITAN EDISON COMPANY k.
By f
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Vice.FMsident Sworn and subscribed to me this 3rd day cf Februar7 1977 u_
Notary Publi V I
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y, 1479 073
- 7910290 p
UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION IN THE MATTER OF DOCKET NO. 50-289 LICENSE NO. DPR-50 METROPOLITAN EDISON COMPANY This is to certify that a copy of Technical Specification Change Request No. 39, Amendment 1, to Appendix A of the Operating License for Three Mile Island Nuclear Station Unit 1, has, on the date given below, been filed with the U. S. Nuclear Regulatory Commission and been served on the chief executives of Londonderry Township, Dauphin Count /, Pennsylvania and Dauphin County, Pennsylvania by deposit in the United States mail, addressed as follows:
Mr. Weldon B. Arehart Mr. Harr-/ B. Reese, Jr.
Board of Supervisors of Board of County Commissioners Londonderry Township of Dauphin County R. D. #1, Geyers Church Road Dauphin County Court House Middletown, Pennsylvania 17057 Harrisburg, Pennsylvania 17120 METRCPOLITAH EDISON COMPANY n
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ViceL7 resident Dated: February 3, 1977 1479 074
Three Mile Island Nuclear Station, Unit 1 (TMI-1)
Operating License No. DPR-50 Docs.et No. 50-289 Technical Scecification Chanste Request No. 39, Amendment 1 The licensee requests that the,ttrched revised page replace page 2-4 of the existing Technical Specifications, Appendix A.
Reason for Proposed Change This change is requested in order to make the bases of Technical Specifica-tion 2.2.1 consistent with the changes proposed in Technical Specification Change Request No. 39 submitted on October 21, 1976.
Safety Anaylsis Justifying Change This proposed change does not involve any unreviewed safety questions in that it only serves to revise Technical Specification 2.2.1 according to the changes proposed by Technical Specification Change Request No. 39 1479 075
2.2 SAFETY LIMITS - REACTOR SYSTEM PRESSURE Atulicability Applies to the limit on reactor coolant system pressure.
Objective To maintain the integrity of the reactor coolant system and to prevent the release of significant amounts of fission product activity.
Scecificatien 2.2.1 The reactor coolant system pressure shall not exceed 2750 psig when there are fuel asser.blies in the reactor vessel.
Bases The reactor coolant system (1) serves as a barrier to prevent radienuclides in the reactor coolant from reaching the atmosphere. In the event of a fuel cladding failure, the reactor coolant system is a barrier against the release of fission products. Establishing a system pressure linit helps to assure the integrity of the reactor coolant system. The maximum transient pressure allovable in the reactor coolant system pressure vessel under the ASME Code,Section III, is 110%
of design pressure.(2)
The maximum transient pressure allowable in the reactor coolant system piping, valves, and fittings under ANSI Section B31.7 is 110% of design pressure. Thus, the safety limit of 2750 psig (110% of the 2500 psig design pressure) has been established.(2) The maxi =um settings for the reactor high pressure trip (2h05 psig) and the pressurizer code safety valves (2500 psig)
(3) have been established in accordance with ASME Boiler and Pressurizer Vessel Code,Section III, Article 9, Winter, 1968 to assure that the reactor coolant system pressure safety limit is not exceeded. The initial hydrostatic test was conducted at 3125 psig (125% of design pressure) to verify the integrity of the reactor coolant system. Additional assurance that the reactor coolant system pressure does not exceed the safety limit is provided by setting the pressurizer electromatic relief valve at 2255 psig.(h)
References (1)
FSAR, Section h (2)
FSAR, Section h.3.10.1 (3)
FSAR, Section h.2.h (k)
FSAR, Table L-1 2k 1479 076