ML17278A264
| ML17278A264 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/25/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278A265 | List: |
| References | |
| TAC-56945, NUDOCS 8507100417 | |
| Download: ML17278A264 (12) | |
Text
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0 UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 hAhhlhGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT NO.
2 ANENDIIENT TO FACILITY OPERATING LICENSE License No. NPF-21 Amendment No.
13 1.
The Nuclear Regulatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washington Public Power Supply System (the Supply System, also the licensee) dated February 27, 1985, 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 as
- amended, 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 the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the CoraIission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, Facility Operating License No. NPF-21 is amended to revise the Technical Specifications as indicated in the attachments to this amendment and paragraph 2.C.(2) of Facility Operating License NPF-21 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. 13, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
8507100417 850625 PDR ADOCK 05000397 P
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3.
This atvendrrent
'.s effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COHHISSIOH Halter R. Butler, Chief Licensing Branch No.
2 Division of Licensing
Enclosure:
Changes to Technical Specifications Date of Issuance:
""N ~ ~ ~
ATTACHMENT TO LICENSE AMENDMENT NO.
13 N.
-1 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 areas of change.
REMOVE 3/4 3-28 3/4 3-32 3/4 3-36 INSERT 3/4 3-28 3/4 3-'32 3/4 3-36
TRIP FUNCTION TABLE 3.3.3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE CHANNELS PER TRIP SYSTEM a APPLICABLE OPERATIONAL CONDITIONS ACTION C.
DIVISION 3 TRIP SYSTEM 1.
HPCS SYSTEM a.
b.
C.
d.
e.f.
g.
Reactor Vessel Water Level Low, Low, Level 2
Drywell Pressure High Reactor Vessel Water Level-High, Level 8 Condensate Storage Tanks Level-Low Suppression Pool Water Level-High HPCS System Flow Rate-Low (Minimum Flow)
Manual Initiation 2(b) 2(b) 2(c) 2(d) 2(d) 1 1/division 1
2 3
1 2
3 1
2 3
1, 2, 3, 1
.2.3 1, 2, 3, 5*
4A'A 5*
4IAl 5
4A'IIC 5A 30 30 32 36 36 31 34 TOTAL NO.
CHANNELS OF CHANNELS TO TRIP MINIMUM CHANNELS OPERABLE APPLICABLE OPERATIONAL CONDITIONS ACTION D.
LOSS OF POWER l.
4.16 kV Emergency Bus Under-voltage (Loss of Voltage) 2.
4.16 kV Emergency Bus Under-voltage (Degraded Voltage) 2/bus 3/bus 1/bus 2/bus 2/bus 1, 2, 3, 4"*, 5""
37 2/bus 1, 2, 3, 4*", 5"~
38 TABLE NOTATIONS (a)
A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during periods of required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.
(b)
Also activates the associated division diesel generator.
(c)
Provides signal to close HPCS pump discharge valve only on 2-out-of-2 logic.
(d)
Provides signal to HPCS pump suction valves only.
When the system is required to be OPERABLE per Specification 3. 5. 2 or 3. 5. 3.
Required when ESF equipment is required to be OPERABLE.
Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 128 psig.
N
TABLE 3.3.3-2 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION C.
DIVISION 3 TRIP SYSTEM 1.
HPCS SYSTEM a.
Reactor Vessel Water Level - Low Low, Level 2
b.
Drywell Pressure - High c.
Reactor Vessel Water Level - High, Level 8 d.
Condensate Storage Tank Level - Low e.
Suppression Pool Water Level - High f.
HPCS System Flow Rate - Low (Minimum Flow) g.
Manual Intiation D.
LOSS OF POWER TRIP SETPOINT
> -50 inches"
< 1.65 psig
< 54.5 inches"
> 448 ft 3 in.
elevation
< 466 ft 8 in.
elevation
> 1250 gpm N.A.
ALLOWABLE VALUE
> -57 inches
< 1.85 psig
< 56 0 inches
> 448 ft 0 in. elevation
< 466 ft 10 in. elevation
> 1200 gpm N. A.
l.
- 4. 16 kV Emergency Bus Undervoltage Loss of Voltage ¹¹ a.
Divisions 1 and 2
b.
Division 3 2.
- 4. 16 kV Emergency Bus Undervoltage Degraded Voltage (Divisions 1, 2, and 3 a.
4.16 kV Basis - 2870 t 86 volts b.
120 V Basis 82 + 2.5 volts a.
4.16 kV Basis - 3016 + 90 volts b.
120 V Basis - 87 e 2.5 volts a.
- 4. 16 kV Basis - 3632 + 108 volts b.
120 V Basis - 104.0 t 3.0 volts c.
8 + 0.04 sec time delay 2870 a 172 volts 82 + 5 volts
'016
+ 180 volts 87 2 5 volts 3632 + 216 volts 103.8 a 6.0 volts 8 ~ 0.8 sec time delay TABLE NOTATIONS "See Bases Figure B 3/4 3-1.
¹¹These are inverse time delay voltage relays or instantaneous voltage relays with a time delay.
The voltages shown are the maximum that will not result in a trip.
Lower voltage conditions will result in decreased trip times.
TABLE 4.3.3.1-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION C.
DIVISION 3 TRIP SYSTEM 1.
HPCS SYSTEM CHANNEL CHECK CHANNEL OPERATIONAL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TEST CALIBRATION SURVEILLANCE RE UIRED a.
Reactor Vessel Water Level-Low Low, Level 2
b.
Drywell Pressure-High c.
Reactor Vessel Water Level-High Level 8 d.
Condensate Storage Tank Level-Low e.
Suppression Pool Mater Level - High f.
HPCS System Flow Rate-Low (Minimum Flow) g.
Manual Initiation D.
LOSS OF POWER 1.
- 4. 16 kV Emergency'us Undervoltage (Loss of Voltage)
S N.A.
S N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
R N.A.
1, 2, 3, 4*, 5" 1
2 3
1, 2, 3, 4", 5" 1, 2, 3, 4*, 5*
1, 2, 3, 4", 5" 3
4*
5A 3
4'AA 5'A*
2.
- 4. 16 kV Emergency Bus Undervoltage (Degraded Voltage)
N.A M
TABLE NOTATIONS 3
4*%')hA
¹Not required to be OPERABLE when reactor steam dome pressure is less than or equal to 128 psig.
When the system is required to be OPERABLE per Specification 3.5.2.
""Required when ESF equipment is required to be OPERABLE.
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