ML17146A335
| ML17146A335 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/15/1986 |
| From: | Adensam E Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17146A336 | List: |
| References | |
| NUDOCS 8604210010 | |
| Download: ML17146A335 (7) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 PENNSYLVANIA POWER 8t LIGHT COMPANY ALLEGHENy ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-387 SUSQUEHANNA STEAN ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 58 License No.
NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
The application for the amendment filed by the Pennsylvania Power 8
Light Company (the licensee),
dated Jul.y 22,
- 1983, as supplemented on July 26, August 2, November 22, 1983, June 21 and November 13,
- 1984, complies with the standards and requirements of the Atomic Enerqv 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 witliout 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 aoplicable requirements have been satisfied.
2.
Accordinqly, the license is amended by changes to the Technical Specifica-tions as indicated in the attachment to this license amendment and paragraoh 2.C.(2) of the Facility Operatinq License No. NPF-14 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. 58, and the Environmental Protection Plan con-tained in Appendix B are hereby incorporated in the license.
PPSL shall operate the facility in accordance with the Technical Specifica-tions and the Environmental Protection Plan.
86042i0010 8504i5 PDR ADOCK 05000387 P
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3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Enclosure:
Changes to the Technical Specifications Date of Issuance:
April 15, 1986 Elinor G. Adensam, Director BWR Prospect Directorate No.
3 Division of BWR Licensing
ATTACHMENT TO LICENSE AMENDMENT NO.
58 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 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.
The corresponding overleaf,pages are also provided to maintain document completeness.
RENDVE 2-3 2-4 3/4 3-17 3/4 3-18 INSERT 2-3 (overleaf) 2-4 3/4 3-17 3/4 3-18 (overleaf)
SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS
- 2. 2 LIMITING SAFETY. SYSTEM SETTINGS REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2.2. 1 The reactor protection system instrumentation setpoints shall be set consistent with the Trip Setpoint values shown in Table 2.2. 1-1.
APPLICABILITY:
As shown in Table 3.3.1-1.
ACTION:
kith a reactor protection system instrumentation setpoint less conservative than the value shown in the Allowable Values column of Table 2.2. 1-1, declare the channel inoperable and apply the applicable ACTION statement requirement of Specification 3.3. 1 until the channel is restored to OPERABLE status with its setpoint adjusted consistent with the Trip Setpoint value.
SUS(UEHANNA - UNIT 1 2-3
TABLE 2.2.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS 2.
Average Power Range Monitor:
a.
Neutron Flux'-Upscale, Setdown b.
Flow Biased Simulated Thermal Power-Upscale:
1)
Flow Biased 2)
High Flow Clamped c.
Neutron Flux-Upscale d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure
- High 4.
Reactor Vessel Mater Level - Low, Level 3
5.
Main Steam Line Isolation Valve - Closure 6.
Main Steam Line Radiation High
'7.
8.
Drywell Pressure - High Scram Discharge Volume Water Level High a.-
Level Transmitter b.
Float Switch 9.
Turbine Stop Valve - Closure 10.
Turbine Control Valve Fast Closure, Trip Oil Pressure - Low ll.
Reactor Mode Switch Shutdown Position 12.
Manual Scram FUNCTIONAL UNIT l.
Intermediate Range Monitor, Neutron Flux-High TRIP SETPOINT
< 120/125 divisions
.of full scale
< 15K of RATED THERMAL POWER
< 0.58 M+59K, with a maximum of
< 113.5X of RATED THERMAL POWER
< 118'f RATED THERMAL POWER
< 1037 psig
> 13.0 sncht;s above Tnstrument zero*
< 10K closed
< 7.0 x full power background
< 1.72 psig
< 88 gallons
< 88 gallons
< 5.5X closed
. > 500 psig NA ALLOWABLE VALUES
< 122/125 divisions of full scale
< 20X of RATED THERMAL POWER
< 0.58 M+62K, with a maximum of
< 115.5X of RATED THERMAL POWER
< 120K of RATED THERMAL POWER
< 1057 psig
> 11.5 inches above Tnstrument zero
< llew closed
< 8.4 x fu11 power background
< 1.88 psig
< 88 gallons
< 88 gallons
< 7X closed
> 460 psig NA "See Bases Figure B 3/4 3-1.
See Specification 3.4.1.1.2.a for single loop operation requirement.
TRIP FUNCTION TABLE 3. 3. 2-2 ISOLATION ACTUATION INSTRUMENTATION SETPOINTS TRIP SETPOINT ALLOWABLE VALUE 1.
PRIMARY CONTAINMENT ISOLATION a.
Low, Level 3
2)
Low Low, Level 2
3)
Low Low Low, Level 1
b.
Drywell Pressure
- High c.
Manual Initiation d.
SGTS Exhaust Radiation - High e.
Main Steam Line Radiation - High SECONDARY CONTAINMENT ISOLATION
> 13.0 inches"
> -38.0 inches*
> -129 inches*
< 1 72 psig NA
<23.0 mR/hr
< 3 x full power background
> 11. 5 inches
> -45.0 inches
> -136 inches
< 1.88 psig NA
<31.0 mR/Hr
<3.6 x full power background a ~
b.
C.
d.
e.
Reactor Vessel Water Level-Low Low, Level 2
Drywell Pressure
- High Refuel Floor High Exhaust Duct
~ Radiation - High Railroad Access Shaft Exhaust Duct Radiation - High Refuel Floor Wall Exhaust Duct Radiation - High Manual Initiation
> -38.0 inches"
< 1.72 psig
< 2.5 mR/hr.""
< 2.5 mR/hr."*
< 2.5 R/hr.""
NA
> -45.0 inches
< 1.88 psig
< 4.0 mR/hr."*
< 4.0 mR/hr.**
< 4.0 mR/hr.""
NA a ~
C.
Reactor Vessel Water Level - Low Low, Level 2
Main Steam Line Radiation - High Main Steam Line Pressure - Low d.
Main Steam Line Flow " High 3.
MAIN STEAM LINE ISOLATION
> -129 inches*.
< 7 '
X full power background
> 861 psig
< 107 psid
> -136 inches
< 8.4 X full power background
> 841 psig
< 110 psid
C/l m
I TRIP FUNCTION HAIN STEAN LINE ISOLATION (Continued)
~ I
~
~ e.
Condenser Vacuum - Low TRIP SETPOiNT
> 9.0 inches Hg vacuum TABLE 3.3.2-2 (Continued)
ISOLATION ACTUATION INSTRUHENTATION SETPOINTS ALLOWABLE VALUE
> 8.8 inches.Hg vacuum g.
h.
Reactor Building Hain Steam Line Tunnel Temperature - High Reactor Building Hain Steam Line Tunnel h Temperature - High Manual Initiation Turbine Building Hain Steam Line Tunnel Temperature-High 177oF 99oF NA
<177 F
< 184 F
< 108 F
NA
<184'F 4P telI 00 4.
REACTOR MATER CLEANUP SYSTEM ISOLATION 5.
< 60 gpm
< l47'F or 118.3'F8 69oF or 35 3oF NA
> -38 inches"
< 426 gpm NA a.
RWCU d Flow - High b.
RWCU Area Temperature - High c.
RWCU/Area Ventilation h Temperature - High d.'LCS Initiation e.
Reactor Vessel Water Level-Low Low, Level 2 f.
RWCU Flow - High g.
Hanual Initiation REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION
< 80 gpm
< 154'F or 125.3'F8
< 78 F or 44.3 FH NA
> -45 inches
< 436 gpm NA O
Ch aO b.
C.
RCIC Steam Line h Pressure - High RCIC Steam Supply Pressure - Low RCIC Turbine Exhaust Oiaphragm Pressure - High
< 177" H>0""
> 60 psig
< 10.0 psig
]89ll H 0*4
> 53 psig
< 20.0 psig