ML17158C079
| ML17158C079 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/09/1997 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Allegheny Electric Cooperative, Pennsylvania Power & Light Co |
| Shared Package | |
| ML17158C080 | List: |
| References | |
| NPF-22-A-136 NUDOCS 9704220236 | |
| Download: ML17158C079 (6) | |
Text
~R AE0(
+~
~o 1
'J Cy
~C J
0O C
O VJ
~O
"++*++
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 205554001 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
~ DOCKET NO. '50-388 SUS UEHANNA STEAM ELECTRIC STATION UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 136 License No.
NPF-22 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 March 17, 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'his 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 requi rements have been satisfied; 9704220236 970409 PDR ADOCK 05000388 PDR 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 Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.136, 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 its date of'ssuance and is to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION F. Stolz, Direct P
ject Directorate I-2 Division of Reactor Projects
- I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications.
Date of Issuance:
April 9, 1997
ATTACHMENT TO LICENSE AMENDMENT NO. 136 l
FACILITY OPERATING LICENSE NO.
NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the area of change.
REMOVE 5-6 6-20b INSERT 5-6 6-20b
5E
3 DESIGN FEATURES 5.3.t Tha reactor core shall contain 76rt 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.
5.4.2 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.
5-6 ATRIUM'-10fuel is only allowed in the reactor core in OPERATIONAL CONDITION 5.
The design bases applicable to ATRIUM -10 fuel are those which are applicable to OPERATIONAL CONDITION 5.
SUSQUEHANNA - UNIT 2 Amendment No. ~36
ADMINISTRATIVECONTROLS I
(Continued) 14.
ANF-1125(P)(A) and ANF-1125(P)(A), Supplement 1, "ANFB Critical Power Correlation," April 1990.
15.
NEDC-32071P, "SAFER/GESTR-LOCA Loss of Coolant Accident Analysis,"
GE Nuclear Energy, May 1992.
16.
NE-092-001A, Revision 1, "Licensing Topical Report for Power Uprate With Increased Core Flow," Pennsylvania Power 5 Light Company, December 1992.
17.
NRC SER on PPSL Power Uprate LTR (November 30, 1993).
18.
PL-NF-90-001, Supplement 1-A, "Application of Reactor Analysis Methods for BWR Design and Analysis: Loss of Feedwater Heating Changes and Use of RETRAN MOD 5.1," September 1994.
19.
PL-NF-94-005-P-A, "Technical Basis for SPC 9x9-2 Extended Fuel Exposure at Susquehanna SES," January 1995.
20.
NEDE-24011-P-A-10, "General Electric Standard Application for Reactor Fuel," February 1991.
21.
PL-NF-90-001, Supplement 2, "Application of Reactor Analysis Methods to BWR Design and Analysis:
CASMO-3G Code and ANFB Critical Power Correlation."
22.
ANF-89-98(P)(A)
Revision 1
and Revision 1
Supplement 1,
"Generic Mechanical Design Criteria for BWR Fuel Designs" Advanced Nuclear Fuels Corporation, May 1995.
6.9,3.3 The core operating limits shall be determined such that all applicable limits (e.g.,
fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, transient analysis limits and accident analysis limits) of the safety analysis are met
~
In addition to the applicable record retention requirements of Title 10, Code of Federal Regulations, the following records shall be retained for at least the minimum period indicated.
6.10.1 The following records shall be retained for at least 5 years:
a.
Records and logs of unit operation covering time interval at each power level.
SUSQUEHANNA - UNIT 2 6-20b Amendment No. i3~