ML17285A726
| ML17285A726 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/08/1989 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17285A728 | List: |
| References | |
| NUDOCS 8909210093 | |
| Download: ML17285A726 (10) | |
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UNITEDSTATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
73 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 September 6, 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.
89092i0093 8909'08 PDR ADOCK 05000397 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 Faci lity 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. 73, 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 George Knighton+Director Project Directorate V
Division'f Reactor Projects - III, IV, V and Special Projects
Attachment:
Changes to the Technical Specifications Date of Issuance:
September 8, 1989
ENCLOSURE TO LICENSE AMENDMENT NO. 73 FACILITY OPERATING LICENSE NO. NPF-21 DOCKET NO. 50-397 Replace the following page of the Appendix "A" Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains a vertical line indicating the areas of change.
Also to be replaced is the following overleaf page.
AMENDMENT PAGE 3/4 3-6 OVERLEAF PAGE 3/4 3-5
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TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRUMENTATION 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 /> for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.
(b)
The "shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn" and shutdown margin demonstrations are being performed per Specification 3. 10.3.
(c)
An APRM channel is inoperable if there are less than 2
LPRM inputs per level or less than 14 LPRM inputs to an APRM channel.
(d)
This function shall be automatically bypassed when the reactor mode switch is not in the Run position and reactor pressure
< 1037 psig.
(e)
This function is not required to be OPERABLE when the reactor pressure vessel head is removed per Specification 3.10.1.
(f)
This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(g)
Also actuates the standby gas treatment system.
(h)
With any control rod withdrawn.
Not applicable to control rods removed per Specification 3.9. 10. 1 or 3.9. 10.2.
(i)
This function shall be automatically bypassed when turbine first stage pressure is
< 165 psig, equivalent to THERMAL POWER less than 30K of RATED THERMAL POWER.
(j)
Also actuates the EOC-RPT system.
"Not required for control rods removed per Specification 3.9. 10. 1 or 3.9. 10.2.
WASHINGTON NUCLEAR - UNIT 2 3/4 3-5
TABLE 3.3.1"2 REACTOR PROTECTION SYSTEM RESPONSE TIMES C)
Cn IT)
I FUNCTIONAL UNIT 1.
2.
a.
Neutron Flux - High b.
Inoperative Reactor Vessel Steam Dome Pressure
- High Reactor Vessel Mater Level - Low, Level 3
Main Steam Line Isolation Valve - Closure Main Steam Line Radiation - High Primary Containment Pressure - High Scram Discharge Volume Mater Level - High a.
Level Transmitter b.
Float Switch 9.
Turbine Throttle Valve - Closure 10.
Turbine Governor Valve Fast Closure, Trip Oil Pressure - Low ll.
Reactor Mode Switch Shutdown Position 12.
Manual Scram 3.
5.
6.
7.
8.
Average Power Range Monitor":
a.
Neutron Flux - Upscale, Setdown b.
Flow Biased Simulated Thermal Power - Upscale c.
Fixed Neutron Flux - Upscale d.
Inoperative
RESPONSE
TIME Seconds N.A.
N.A.
N.A.
6+j4*
< 0.09 N.A.
< 0.55
< 1.05
< 0.06 H.A.
N.A.
N.A.
N.A.
< 0.06
< 0.08¹ N.A.
N.A.
m CD m
"Neutron detectors are exempt from response time testing.
Response
time shall be measured from the detector output or from the input of the first electronic component in the channel.
""Including simulated thermal power time constant.
¹Measured from start of turbine control valve fast closure.
TABLE 3.3.1-2 REACTOR PROTECTION SYSTEM RESPONSE TIMES FUNCTIONAL UNIT l.
2.
a.
Neutron Flux - High b.
Inoperative Reactor Vessel Steam Dome Pressure - High Reactor Vessel Water Level - Low, Level 3
Main Steam Line Isolation Valve - Closure Main Steam Line Radiation - High Primary Containment Pressure - High Scram Discharge Volume Water Level - High a.
Level Transmitter b.
Float Switch 9.
Turbine Throttle Valve - Closure 10.
Turbine Governor Valve Fast Closure, Trip Oil Pressure - Low ll.
Reactor Mode Switch Shutdown Position 12.
Manual Scram 3.
5.
6.
7.
8.
Average Power Range Monitor":
a.
Neutron Flux - Upscale, Setdown b.
Flow Biased Simulated Thermal Power - Upscale c.
Fixed Neutron Flux - Upscale d.
Inoperative
RESPONSE
TIME Seconds N.A.
N.A.
N.A.
6+1""
< 0.09 H.A.
< 0.55
< 1.05
< 0.06 H.A.
N.A.
N.A.
N.A.
< 0.06
< 0.08¹ H.A.
N.A.
"Neutron detectors are exempt from response time testing.
Response
time shal,l be measured from the detector output or from the input of the first electronic component in the channel.
""Including simulated thermal power time constant.
¹Measured from start of turbine control valve fast closure.
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