ML17279A987
| ML17279A987 | |
| Person / Time | |
|---|---|
| Site: | Columbia  (NPF-21-A-055, NPF-21-A-55) |
| Issue date: | 04/13/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A988 | List: |
| References | |
| NUDOCS 8804210347 | |
| Download: ML17279A987 (9) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 5G-397 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 55 License No.
NPF-21 1.
The Nuclear Regulatory Commission (the Coomission 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 June 1,
1987 complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the CoIImission'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 coranon 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 CoIImIission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as indicated in the enclosure to this license amendment and paragraph 2.C.(2) of the Facility Operating License No.
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. 55, 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.
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3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION George
. Knighto
, Director Project Directorate V
Division of Reactor Projects III, IV, V and Special Projects Office of Nuclear Reactor Regulation
Enclosure:
Changes to the Technical Specifications Date of Issuance:
April 13, 1988
April 13, 1988 ENCLOSURE TO LICENSE AMENDMENT NO. 55 FACILITY OPERATING LICENSE NO. NPF-2i DOCKET NO. 50-397 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.
The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.
REMOVE INSERT 3/4 3-22 3/4 3-23 3/4 3-22 3/4 3-23 Pages 3/4 3-21 and 3/4 3-24 are provided for document completeness.
TABLE 3.3.2-3 (Continued)
ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME TABLE NOTATIONS (a)The isolation system instrumentation response time shall be measured and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME.
Isolation system instrumentation response time specified includes the diesel generator starting and sequence loading delays assumed in the accident analysis.
(b)Radiation detectors are exempt from response time testing.
Response
time shall be measured from detector output or the input of the first electronic component in the channel.
"Isolation system instrumentation response time for MSIVs only.
No diesel generator delays assumed.
""Isolation system instrumentation response time for associated valves except MSIVs.
¹Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Table 3.6.3-1 and 3.6.5.2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.
¹¹This response time does not include the 45-second time delay.
MASHINGTON NUCLEAR - UNIT 2 3/4 3"21
TABLE 4.3.2.1-1 ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION 1.
PRIMARY CONTAINMENT ISOLATION a.
Reactor Vessel Water Level-1)
Low, Level 3
2)
Low Low, Level 2 b.
Drywell Pressure - High c.
Radiation - High 2)
Pressure Low 3)
Flow High d.
Main Steam Line Tunnel Temperature - High e.
Main Steam Line Tunnel 6 Temperature
- High f.
Condenser Vacuum - Low g.
Manual Initiation 2.
SECONDARY CONTAINMENT ISOLATION CHANNEL CHECK S
N ~ A.
N.A.
S N.A.
S S
N.A.
N.A.
CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION R
R N.A.
OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 1
2 3
1 2
3 1
2 3
1 2
3 1
1 2
3 1
2 3
1 2.3 1, 2", 3" 1
2 3
ao b.
C.
d.
Reactor Building Vent Exhaust Plenum Radiation - High Drywell Pressure - High Reactor Vessel Water Level - Low Low, Level 2
Manual Initiation S
N.A.
N.A.
N.A.
R N.A.
1, 2, 1, 2, 1.
2 1, 2, 3, and *"
3 3, and¹ 3
O
M CD CHANNEL TRIP FUNCTION CHECK 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED a.
b.
C.
d.
e.
f.
g.
h.
3 ~
6 Flow - High Heat Exchanger Area Temperature - High Heat Exchanger Area Ventilation h Temperature-High Pump Area Temperature - High Pump Room A Pump Room B
Pump Area Ventilation h, Temp. - High Pump Room A Pump Room B
SLCS Initiation Reactor Vessel Water Level - Low Low, Level 2 RWCU/RCIC Line Routing Area Temperature - High RWCU Line Routing Area Temperature - High Manual Initiation S
S N.A.
N.A.
S N.A.
R R
N.A.
R N.A.
1, 2, 3
1, 2, 3
1, 2, 3
1 2
3 1
2 3
1 2
3 1
2 3
1, 2, 3
1 y 2/3 1, 2, 3
1 2
3 1, 2, 3
4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION O
tgsVl ao b.
C.
d.
e.
RCIC Steam Line Flow - High RCIC/RHR Steam Line Flow - High RCIC Steam Supply Pressure-Low RCIC Turbine Exhaust Diaphragm Pressure - High RCIC Equipment Room Temperature - High RCIC Equipment Room 6 Temperature - High N.A.
N.A.
1 2.3 1,2,3 1, 2, 3
1 g 2 $ 3 1>>
2.
3 1, 2, 3
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS TRIP FUNCTION CHANNEL CHECK CHANNEL FUNCTIONAL TEST CHANNEL CALIBRATION OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued) g.
h.
RWCU/RCIC Steam Line Routing Area Temperature - High Orywe11 Pressure - High Manual Initiation N.A.
N.A.
N.A.
1, 2, 3
1, 2, 3
1 2
3 5.
RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION a0 b.
Reactor Vessel Water Level-Low, Level 3 Reactor Vessel (RHR Cut-in Permissive)
Pressure - High N.A.
1,2,3 1, 2, 3
c.
Equipment Area Temperature-High d.
Equipment Area Ventilation h Temp. - High e.
Shutdown Cooling Return Flow Rate - High f.
RHR Heat Exchanger Area Temperature - High g.
. Manual Initiation N.A.
N.A.
TABLE NOTATIONS N.A.
1,2,3 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
When reactor.
steam pressure
> 1037 psig and/or any turbine stop valve is open.
When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.
¹ During CORE ALTERATION and operations with a potential for draining the reactor vessel.