ML20129A546
| ML20129A546 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 07/02/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20129A552 | List: |
| References | |
| NUDOCS 8507150328 | |
| Download: ML20129A546 (5) | |
Text
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o UNITED STATES E,o NUCLE R REGULATORY COMMISSION
!} [fs-q]l/,f dl WASHINGTON, D. C. 20555 gw l PENNSYLVANIA POWER & LIGHT COMPANY ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY CPERATING LICENSE Amendment No.13 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for an amendment filed by the Pennsylvania Power
& Light Company, dated February 7, 1985 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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.
2.
Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.13, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
PP&L shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
B P
P P
J
I 3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION d
-r Walter R. Butler, Chief Licen:ing Branch No. 2 Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: 3 0 3 gg
ATTACHMENT TO LICENSE AMENDMENT NO.13 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 INSERT 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18
,e p
O iABLE 3.3.2-2 y
3 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS Eg ALLOWABLE g
TRIP FUNCTION TRIP SETPOINT VALUE I
1.
PRIMARY CONTAINMENT ISOLATION g
a.
1)
Low, Level 3 113.0 inches
- 1.11.5 inches 2)
Low Low, Level 2 1 -38.0 inches
- 1 -45.0 inches y
3)
Low Low Low, Level 1 2 -129 inches
- 2 -136 inches b.
Drywell Pressure - High 5 1.72 psig 5 1.88 psig c.
Manual Initiation NA NA d.
SGTS Exhaust Radiation - High 5 23.0 mR/hr 5 31.0 mR/hr Main Steam Line Radiation - High 5 3 X full power background 5 3.6 X full power background e.
2.
SECONDARY CONTAINMENT ISOLATION a.
Low Low, Level 2 1 -38.0 inches
- 2 -45.0 inches y
b.
Drywell Pressure - High 5 1.72 psig 5 1.88 psig c.
Refuel Floor High Exhaust Duct Radiation - High 5 2.5 mR/hr**
$ 4.0 mR/hr**
d.
Railroad Access Shaft Exhaust Duct Radiation - High 5 2.5 mR/hr**
5 4.0 mR/hr**
e.
Refuel Floor Wall Exhaust Duct Radiation - High 5 2.5 mR/hr**
$ 4.0 mR/hr**
f.
Manual Initiation NA NA 3.
MAIN STEAM LINE ISOLATION a.
Reactor Vessel Water Level - Low Low, Level 2 1 -38 inches
- 1 -45.0 inches b.
Main Steam Line Radiation - High 5 3 X full power background 5 3.6 X full power background c.
Main Steam Line. Pressure - Low 1 861 psig 2 841 psig d.
Main Steam Line Flow - High 5 107 psid 5 110 psid
TABLE 3.3.2-2 (Continued) h ISOLATION ACTUATION INSTRUMENTATION SETPOINTS E
E ALLOWABLE g
TRIP FUNCTION TRIP SETPOINT VALUE 2
MAIN STEAM LINE ISOLATION (Continued)
- e.
Condenser Vacuum - Low 1 9.0 inches Hg vacuum
> 8.8 inches Hg vacuum f.
Reactor Building Main Steam Line N
Tunnel Temperature - High 5 177*F 5 184*F g.
Reactor Building Main Steam Line Tunnel A Temperature - High 5 99*F
< 108*F h.
Manual Initiation NA IIA i.
Turbine Building Main Steam Line Tunnel Temperature - High 5 177 F
$ 184 F 4.
REACTOR WATER CLEANUP SYSTEM ISOLATION p
a.
RWCU A Flow - High 5 60 gpm 5 80 gpm w
h; b.
RWCU Area Temperature - High 5 147 F or 118.3*F#
$ 154*F or 125.3 F#
c.
RWCU/ Area Ventilation A Temperature - High 1 69 F or 35.3 F#
~< 78 F or 44.3 F#
d.
SLCS Initiation NA NA e.
Low Low, Level 2 1 -38 inches
- 1 -45 inches f.
RWCU Flow - High
$ 426 gpm 1 436 gpm g.
Manual Initiation NA NA 5.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION g
a.
RCIC Steam Line A Pressure - High 5 153" H 0**
5 165" H 0**
l 2
2 k
b.
RCIC Steam Supply Pressure - Low 1 60 psig 2 53 psig 5
c.
RCIC Turbine Exhaust Diaphragm p
Pressure - High 5 10.0 psig
$ 20.0 psig a