ML17158C130
| ML17158C130 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/25/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Allegheny Electric Cooperative, Pennsylvania Power & Light Co |
| Shared Package | |
| ML17158C131 | List: |
| References | |
| NPF-22-A-138 NUDOCS 9705060419 | |
| Download: ML17158C130 (5) | |
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UNITED STATES NUCLEAR REGULATORY COMMiSSiON WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER
& LIGHT COMPANY LLEGHENY ELECTRIC COOPERATIVE INC.
DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDM NT 0 FACILITY OPERATING LICENS Amendment No. 138 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by the Pennsylvania Power 8
Light Company, dated April 16,
- 1997, and as supplemented by a letter dated April 18,
- 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance:
(i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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'DR ADOCK 05000388 P
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2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.
NPF-22 is hereby amended to read as follows:
(2) Technical.
S ecifications and Environmental Protection lan The Technical Specifications contained in Appendix A, as revised through Amendment No. 138, and the Environmental Protection Plan con-tained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of issuance and is to be implemented upon receipt.
FOR THE NUCLEAR REGULATORY COMMISSION Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 25, 1997
ATTACHMENT TO LICENSE AMENDMENT NO.>38 FACILITY OPERATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 Replace the following page of the Appendix A Technical Specifications with enclosed page.
The revised page is identified by Amendment number and contains vertical lines indicating the area of change.
INSERT 5-6 5-6
DESIGN FEATURES 5.3.1 The reactor core shall contain 764 fuel assemblies.
Each assembly consists of a matrix of Zircaloy clad fuel rods with an initial composition of non-enriched or slightly enriched uranium dioxide as fuel material and water rods or water channels.
Limited substitutions of Zirconium alloy filler rods for fuel rods, in accordance with NRC-approved applications of fuel rod configurations, may be used.
Fuel assemblies shall be limited to those fuel designs that have been analyzed with applicable NRC staff-approved codes and methods, and shown by test or analyses to comply with all fuel safety design bases.
A limited number of lead use assemblies that have not completed representative testing may be placed in non-limiting core regions.
Reload fuel shall have a maximum lattice average enrichment of 4.5 weight percent U-235.
5.3.2 The reactor core shall contain 185 cruciform shaped control rod assemblies.
The control material shall be boron carbide powder (B4C), and/or Hafnium metal.
The control rod shall have a nominal axial absorber length of 143 inches.
Control rod assemblies shall be limited to those control rod designs approved by the NRC for use in BWRs.
5.4.1 The reactor coolant system is designed and shall be maintained:
a.
In accordance with the code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of:
1.
1250 psig on the suction side of the recirculation pumps.
2.
1500 psig from the recirculation pump discharge to the jet pumps.
c.
For a temperature of 575'F.
5A.2 The total water and steam volume of the reactor vessel and recirculation system is approximately 22,400 cubic feet at a nominal T,, of 532'F.
ATRIUM -10 fuel is only allowed in the reactor core in OPERATIONAL CONDITIONS 3, 4, and 5.
The design bases applicable to ATRIUM -'IO fuel are those which are applicable to OPERATIONAL CONDITIONS 3, 4, and 5.
1N, SUSQUEHANNA - UNIT 2 5-6 Amendment No. 138
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