ML17158B065
| ML17158B065 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/03/1996 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Allegheny Electric Cooperative, Pennsylvania Power & Light Co |
| Shared Package | |
| ML17158B060 | List: |
| References | |
| NPF-22-A-128 NUDOCS 9601160277 | |
| Download: ML17158B065 (4) | |
Text
r RE0I P0 0O I
0
+
~0
++*++
~
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 PENNSYLVANIA POWER
& LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE INC.
.DOCKET NO. 50-388 SUS UEHANNA STEAM ELECTRIC STAT ON UNIT AMENDMENT TO FACILITY OP RATING LICENSE Amendment No.i28 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 5 Light Company, dated August ll, 1995, 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'ctivities 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.
960iih0277 960i03 PDR ADOCK 05000388 P,
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. 128, 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 issuance and is to be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION John F. Stolz, irector Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
January 3
ig96
ATTACHMENT TO LICENSE AMENDMENT NO. 128 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.
REMOVE 3/4 3-71 INSERT 3/4 3-71
TABLE3.3.7.5-1 ACCIDENT MONITORING INSTRUMENTATION 0Cmz zz z
INSTRUMENT 1.
Reactor Vessel Steam Dome Pressure 2.
Suppression Chamber Water Level REQUIRED NUMBER OF CHANNELS MINIMUMCHANNELS OPERABLE ACTION 80 80 80 APPLICABLE OPERATIONAL CONDITIONS 1,2 1,2 1.2
~
~
4.
Suppression Chamber Water Temperature 5.
Suppression Chamber Air Temperature 6.
Primary Containment Pressure 7.
Drywell Temperature 8,6 locations 2/range 6,1/location 1/range 80 80 80 80 1.2 1,2 1,2 1,2 8.
Drywell Gaseous Analyzer a.
Oxygen b.
Hydrogen 9.
Safety/Relief Valve Position Indicators
- 10. Containment High Radiation 1/valve",
1/valve",
80 82 80 81 1,
2 1.2 1.2
- 11. Noble gas monitors a.
Reactor Bldg. Vent b.
SGTS Vent c.
Turbine Bldg. Vent
- 12. Primary Containment Isolation Valve Position
- 13. Neutron Flux 1/valve 1
1 1
1/valve 81 81 81 80 80 1,2 and 1,2 and 1,2 1,2 1.2 ga z0 s
Acoustic monitor.
~ 0 Mid-range and high-range channels.
~ 0%
When moving irradiated fuel in the secondary containment.
See Special Test Exception 3.10.1.
Compliance with these requirements for the S
SRV acoustic monitor is not required for the period beginning January 21, 1994, until the next unit shutdown of sufficient duration to allow for containment entry, not to exceed the sixth refueling and inspection outage.