ML17279A945
| ML17279A945 | |
| Person / Time | |
|---|---|
| Site: | Columbia  (NPF-21-A-053, NPF-21-A-53) |
| Issue date: | 04/04/1988 |
| From: | Knighton G Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17279A946 | List: |
| References | |
| TAC-64697, NUDOCS 8804120197 | |
| Download: ML17279A945 (8) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
53 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 Supply System, also the licensee),
dated February 9, 1987 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.
2.
Accordingly, the license is amended by changes to the Technical Specifica-tions as~ipdicated 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. 53, 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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This amendment is effective as of the date of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION (J,)
C.
George W. Knighton, 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 4, 1988
~
April 4, 1988 ENCLOSURE TO LICENSE AMENDMENT NO.
53 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 area of change.
RENOVE INSERT 3/4 1-10 3/4 1-10 The following overleaf page is also provided for convenience:
3/4 1-9.
4(V
REACTIVITY CONTROL SYSTEMS CONTROL ROD SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION
- 3. 1.3.5 All control rod scram accumulators shall be OPERABLE.
APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 5".
ACTION:
In OPERATIONAL CONDITIONS 1 or 2:
2.
With one control rod scram accumulator inoperable, within 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />s:
a)
Restore the inoperable accumulator to OPERABLE status, or b)
Declare the control rod associated with the inoperable accumulator inoperable.
Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
With more than one control rod scram accumulator inoperable, declare the associated control rods inoperable and:
a)
If the control rod associated with any inoperable scram accumulator is withdrawn, immediately verify that at least one control rod drive pump is operating by inserting at least one withdrawn control rod at least one notch or place the reactor mode switch in the Shutdown position.
b)
Insert the inoperable control rods and disarm the associated control valves either:
b.
1)
Electrically, or 2)
Hydraulically by closing the drive water and exhaust water isolation valves.
Otherwise, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
In OPERATIONAL CONDITION 5":
With one withdrawn control rod with its associated scram accumu-lator inoperable, insert the affected control rod and disarm the associated directional control valves within one hour, either:
a)
Electrically, or b)
Hydraulically by closing the drive water and exhaust water isolation valves.
2.
c.
The With more than one withdrawn control rod with the associated
. scram accumulator inoperable or no control rod drive pump operating, immediately place the reactor mode switch in the Shutdown position.
provisions of Specification 3.0.4 are not applicable.
"At least the accumulator associated with each withdrawn control rod.
Not applicable to control rods removed per Specification 3.9. 10. 1 or 3.9. 10.2.
WASHINGTON NUCLEAR - UNIT 2 3/4 1-9
REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE UIREMENTS 4.1.3.5 Each control rod scram accumulator shall be determined OPERABLE:
a.
At least once per 7 days by verifying that the indicated pressure is greater than 940 psig unless the control rod is inserted and disarmed or scrammed.
b.
At least once per 18 months by:
1.
Performance of a:
a)
CHANNEL FUNCTIONAL TEST of the leak detectors, and b)
CHANNEL CALIBRATION of the pressure detectors, and verify-ing an alarm setpoint of equal to or greater than 940 psig on decreasing pressure.
Measuring and recording the time for up to 10 minutes that each individual accumulator check valve maintains the associated accumulator pressure above the alarm setpoint with no control rod drive pump operating.
WASHINGTON NUCLEAR - UNIT 2 3/4 1-10 Amendment No.