ML17285A551
| ML17285A551 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/06/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17285A552 | List: |
| References | |
| NUDOCS 8906150085 | |
| Download: ML17285A551 (11) | |
Text
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UNITEDSTATES LEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON.PUBLIC. POWER. SUPPLY-SYSTEM DOCKET N0.-50-397 NUCLEAR.PROJECT N0.-2 AIIENDMENT.TO. FACILITY-OPERATING LICENSE Amendment No.
70 License No.
NPF-21 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 licensee),
dated March 8, 1989 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, 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.
88061:50085 390606 PDR 'DOCK 0500035'7 P
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of 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.
7O, 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.
3.
This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 6, 1989
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eorge W. Knighton, Director Project Directorate V
Division of Reactor Projects - III, IV, V and Special Projects
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I CHANNEL TRIP FUNCTION CHECK 3.
REACTOR WATER CLEANUP SYSTEM ISOLATION a.
b.
C.
d.
e.
f.
g.
b, Flow - High S
Heat Exchanger Area Temperature - High Heat Exchanger Area Ventilation h Temperature-High N.A Pump Area Temperature
- High Pump Room A Pump Room 8 Pump Area Ventilation 6 Temp. - High Pump Room A
Pump Room 8 SLCS Initiation Reactor Vessel Water Level - Low Low, Level 2
RWCU/RCIC Line Routing Area Temperature - High N.A.
RWCU Line Routing Area Temperature - High Manual Initiation N.A.
N.A N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION CHANNEL FUNCTIONAL TEST SA SA SA SA SA SA R
SA SA R
1 2
3 1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
R R
N.A.
R N.A.
1,2,3 1 2.3 1, 2, 3
1 2
3 1, 2, 3
12 3.
1, 2, 3
OPERATIONAL CHANNEL CONDITIONS FOR WHICH CALIBRATION SURVEILLANCE RE UIRED O
CD a@
b.
C.
d.
e.
RCIC Steam Line Flow - High S
RCIC/RHR Steam Line Flow - High S
RCIC Steam Supply Pressure-Low N.A.
RCIC Turbine Exhaust Diaphragm Pressure
- High N.A.
RCIC Equipment Room Temperature - High N.A.
RCIC Equipment Room 6 Temperature - High N.A.
SA SA R
R R
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
1, 2, 3
h
TABLE 4.3.2.1-1 (Continued)
ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL FUNCTIONAL TEST CHANNEL CHECK SA M
R N.A.
N.A.
5.
RHR SYSTEM SHUTDOWN COOLING MODE ISOLATION TRIP FUNCTION 4.
REACTOR CORE ISOLATION COOLING SYSTEM ISOLATION (Continued) g.
RWCU/RCIC Steam Line Routing Area Temperature - High N.A.
h.
Drywell Pressure - High i.
Manual Initiation CHANNEL CALIBRATION N.A.
OPERATIONAL CONDITIONS FOR WHICH SURVEILLANCE RE UIRED 1, 2, 3
1 j 2 $
3 1, 2, 3
b.
C.
d.
e.
Reactor Vessel Water Level-Low, Level 3
Reactor Vessel (RHR Cut-in Permissive)
Pressure
- High Equipment Area Temperature-High Equipment Area Ventilation h, Temp. - High Shutdown Cooling Return Flow Rate - High RHR Heat Exchanger Area Temperature - High Manual Initiation N.A.
N.A.
N.A.
N.A.
N.A.
N.A.
TABLE NOTATIONS R
R N.A.
1 2
3 1,2,3 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.
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