ML17278A254
| ML17278A254 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/25/1985 |
| From: | Butler W Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17278A255 | List: |
| References | |
| TAC-57685, NUDOCS 8507030042 | |
| Download: ML17278A254 (9) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Ii'ASliIHGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 WPPSS NUCLEAR PROJECT HO.
2 AMENDMENT TO FACILITY OPERATING LICENSE License No. NPF-21 Amendment Ho.
11 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 May 16, 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 COIImission;.
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 Commission'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. 11, 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.
soo7osooi2 soosio PDR ADOCK 05000397
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This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Walter R. Butler, Chief Licensing Branch No.
2 Division of Licensing
Enclosure:
Changes to Technical Specifications Date of Issuance:
JUN 2 5 QS
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ATTACHMENT TO LICENSE AMENDMENT NO.
11 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 3-26 3/4 3-27 3/4 3-30 3/4 3-31 3/4 3-34 3/4 3-35 INSERT 3/4 3-26 3/4 3-27 3/4 3-30 3/4 3-31 3/4 3-34 3/4 3-35
TABLE 3.3.3-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION TRIP A.
FUNCTION DIVISION I TRIP SYSTEM 1.
RHR-A LPCI MODE L LPCS SYSTEM MINIMUM OPERABLE APPLICABLE CHANNELS Pff)
OPERATIONAL TRIP SYSTEMS CONDITIONS ACTION a.
b.
C.
d.
Low Low Low, Level 1
Drywell'ressure - High LPCS Pump Discharge Flow-Low (Minimum Flow)
Reactor Vessel Pressure-Low (LPCS Permissive) e.
Reactor Vessel Pressure-Low (LPCI Permissive) f.
LPCI Pump A Start Time Delay Relay g.
LPCI Pump A Discharge Flow-Low (Minimum Flow) h.
Manual Initiation 2.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "A"0 1
11/division 1, 2, 3, 1
2 3
1, 2, 3, 1, 2, 3, 4)k 5A 1
2 3.
4)h 5A 1, 2, 3, 1
2 3
1, 2, 3, 5'4 3O 30 4* 5A'2 33 32 33 4*, 5" 32 4A'A 31 5)h 34 aO b.
C.
d.
e.f.
g.
Reactor Vessel Water Level - Low Low Low, Level 1
ADS Timer Reactor Vessel Water Level - Low, Level 3 (Permissive)
LPCS Pump Discharge Pressure-High (Pump Running)
LPCI Pump A Discharge Pressure-High (Pump Running)
Manual Initiation Inhibit Switch 2
1 1
2 2
2/division 1/division 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1 2
3 1, 2, 3
1, 2, 3
30 32 32 32 32 35 35 O
C7 I
C)
TRIP FUNCTION TABLE 3.3. 3-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION MINIMUM OPERABLE APPLICABLE CHANNELS Pg))
OPERATIONAL TRIP SYSTEMS CONDITIONS ACTION n
m m
B.
DIVISION 2 TRIP SYSTEM 1.
Reactor Vessel Water Level - Low Low Low, Level 1
b.
Drywell Pressure High c.
Reactor Vessel Pressure-Low (LPCI Permissive) d.
LPCI Pump B Start Time Delay Relay e.
LPCI Pump Discharge Flow-Low (Minimum Flaw) f.
Manual Initiation 2.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "B"¹ 2
2 1/val ve 1
1/pump 1/division 1, 2, 3, 1, 2, 3
1 2
3 5A 1
.2 3.
1 2
3 1
2 3
4A 5A 3O 30 32 33 4*
5A 32 4", 5" 31 4A4 34 a.
b.
C.
d.
e.f.
Reactor Vessel Water Level - Low Low Low, Level 1
ADS Timer Reactor Vessel Water Level - Low, Level 3 (Permissive)
LPCI Pump 8 and C Discharge Pressur e-High (Pump Running)
Manual Initiation Inhibit Switch 2/pump 2/division 1/division 1
2 3
1 2
3 1
2 3
1.2 3
1 2
3 1
2 3
30 32 32 32 35 35
TABLE 3.3.3-2 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION A.
DIVISION 1 TRIP SYSTEM 1.
RHR-A LPCI MODE AND LPCS SYSTEM TRIP SETPOINT ALLOWABLE VALUE a.
b.
C.
d.
e.
f.
g.
h.
Reactor Vessel Water Level - Low Low Low, Level 1
Drywell Pressure
- High LPCS Pump Discharge Flow-Low (Minimum Flow)
Reactor Vessel Pressure-Low (LPCS Permissive)
Reactor Vessel Pressure-Low (LPCI Permissive)
LPCI Pump A Start Time Delay Relay LPCI Pump A Discharge Flow-Low (Minimum Flow)
Manual Initiation
> -129 inches*
< 1.65 psig
> 770 gpm
> 470 psig, decreasing
> 470 psig, decreasing
< 5 seconds
> 800 gpm N.A.
> -136 inches
< 185 psig
< 900 gpm
> 450 psig, decreasing
> 450 psig, decreasing
< 6 seconds
> 650
- gpm, N.A.
2.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "A" a.
b.
C.
d.
e.
f.
g.
Reactor Vessel Water Level - Low Low Low, Level 1
ADS Timer Reactor Vessel Water Level-Low, Level 3
(Permissive)
LPCS Pump Discharge Pressure-High (Pump Running)
LPCI Pump A Discharge Pressure-High (Pump Running)
Manual Initiation Inhibit Switch
> -129 inches"
< 105 seconds
> 13.0 inches*
> 145 psig, increasing
> 125 psig, increasing N.A.
N.A.
> -136 inches
< 117 seconds
> ll inches
> 125 psig, increasing
> 115 pssg, sncreaszng N.A.
N.A.
TABLE 3.3.3-2 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPOINTS TRIP FUNCTION B.
DIVISION 2 TRIP SYSTEM 1.
b.
C.
Reactor Vessel Mater Level - Low Low Low, Level 1 Drywell Pressure
- High Reactor Vessel Pressure-Low (LPCI Permissive) d.
LPCI Pump B Start Time Delay Relay e.
LPCI Pump Discharge Flow-Low (Minimum Flow) f.
Manual Initiation 2.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "B" TRIP SETPOINT
> -129 inches"
< 1.65 psig
> 470 psig, decreasing
< 5 seconds
> 800 gpm N.A.
ALLOMABLE VALUE
> -136 inches
< 1.85 psig
> 450 psig, decreasing
< 6 seconds
> 650 gpm
. N.A.
aO b.
C.
d.
e.f.
Reactor Vessel Water Level - Low Low Low, Level 1
ADS Timer Reactor Vessel Mater Level-Low, Level 3
(Permissive)
LPCI Pump B and C Discharge Pressure-High (Pump Running)
Manual Initiation Inhibit Switch
> -129 inches"
< 105 seconds
> 13.0 inches"
> 125 psig, increasing N.A.
N.A.
> -136 inches
< 117 seconds
> ll inches
> 115 psig, increasing N.A.
N.A.
TABLE 4.3.3.1-1 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION CHANNEL CHECK CHANNEL FUNCTIONAL TEST OPERATIONAL CHAN/EL CONDITIONS FOR WHICH CALIBRATION SURVEILLANCE RE UIREQ 2.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "A"8 a.
Reactor Vessel Water Level-Low Low Low, Level 1 ADS Timer Reactor Vessel Water Level-Low, Level 3 (Permissive) d.
LPCS Pump Discharge Pressure-High (Pump Running) e.
LPCI Pump A Discharge Pressure-High (Pump Running)
Manual Initiation Inhibit Switch f.
g.
A.
DIVISION I TRIP SYSTEM 1.
RHR-A LPC MODE AND LPCS SYSTEM a.
Reactor Vessel Water Level-Low Low Low, Level 1
b.
Drywell Pressure - High c.
LPCS Pump Discharge Flow-Low (Minimum Flow) d.
Reactor Vessel Pressure-Low (LPCS Permissive) e.
Reactor Vessel Pressure-Low (LPCI Permissive) f.
LPCI Pump A Start Time Delay Relay g.
LPCI Pump A Flow-Low (Minimum Flow) h.
Manual Initiation S
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
S N.A.
N.A.
N.A.
N.A.
N.A.
R N.A.
R N.A.
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" 1, 2, 3, 4", 5*
1, 2, 3, 4", 5*.
1, 2, 3
1 2
3 1
2 3
1 2
3 1, 2, 3
1 2
3 1, 2, 3
TABLE 4. 3. 3. 1-1 (Continued)
EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS C)
C:
M TRIP FUNCTION B.
DIVISION 2 TRIP SYSTEM 1.
Reactor Vessel Water Level-Low Low Low, Level 1
b.
Drywell Pressure - High
.c.
Reactor Vessel Pressure-Low (LPCI Permissive) d.
LPCI Pump 8 Start Time Delay Relay e.
LPCI Pump Discharge Flow-Low (Minimum Flow) f.
Manual Initiation 2.
AUTOMATIC DEPRESSURIZATION SYSTEM TRIP SYSTEM "B"0 CHANNEL CHECK S
N.A.
N.A.
N.A.
N.A.
N.A.
CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION R
N.A.
OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 3
4*
5A 1
2 3
1, 2, 3, 4", 5" 1, 2, 3, 4", 5" 1, 2, 3, 4", 5~
(D A.
B lD 0
a.
b.
C.
d.
e.f.
Reactor Vessel Watet Level-
.Low Low Low, Level 1
ADS Timer Reactor Vessel Water Level-Low, Level 3 (Permissive)
LPCI Pump 8 and C Discharge Pressure-High (Pump Running)
Manual Initiation Inhibit Switch S
N.A.
N.A.
N.A.
N.A.
R N.A.
N.A.
1 2
3 1
2 3
1.2 3
1, 2, 3
1, 2, 3
1, 2, 3