ML17285B095
| ML17285B095 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/07/1990 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17285B096 | List: |
| References | |
| NUDOCS 9003190075 | |
| Download: ML17285B095 (12) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO. 2 AMENDYiENT TO FACILITY OPERATING LICENSE Amendment No. 78 License No.
NPF-21 1.
The Nuclear Requlatory Commission (the Commission or the NRC) has found that:
A.
The application for amendment filed by the Washinqton Public Power Supply System (the licensee),
dated Parch 2, 1990 complies with the standards and requirements of the Atomic Eneroy Act of 1954, as amended (the Act), and the Commission's requlations set forth in 10 CFR Chapter-I; B.
The facility will operate in conformity with the applica-tion, the provisions of the Act, and the requlations of the Commission; C.
There is reasonable assurance (i) that the activities author-ized by this amendment can be conducted without endanqerinq the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's requla-tions 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 requlations and all applicable require-ments have been satisfied..
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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. 78, 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 REGULA ORY COMMISSION 3.4z John A
Zwolinski, Acting Assistant Director for R gion V
Division of Reactor Projects - III IV, V and Special Projects Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
March 7, 1990
tl
ENCLOSURE TO LICENSE AMENDMENT NO. 78 FACILITY OPERATING LICENSE NO. NPF-21 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.
Also to be replaced are the following overleaf pages.
AMENDMENT PAGE 3/4 3-71 3/4 3-74 3/4 4-7 OVERLEAF PAGE 3/4 3-72 3/4 3-73 3/4 4-8'
f' pl I
l h
'f r
INSTRUMENT l.
2.
3.
Reactor Vessel Pressure Reactor Vessel Mater Level Suppression Chamber Mater Level TABLE 3. 3. 7. 5-1 ACCIDENT MONITORING INSTRUMENTATION REQUIRED NUMBER OF CHANNELS MINIMUM CHANNELS OPERABLE APPLICABLE OPERATIONAL CONDITIONS 1
2 1 $
2 1,
2 ACTION 80 80 80 Suppression Chamber Mater Temperature 5.
Suppression Chamber Air Temperature 6.
Drywell Pressure 7.
Drywell Air Temperature 8.
Drywell Oxygen Concentration 9.
Drywell Hydrogen Concentration 10.
Safety/Relief Valve Position Indicators ll.
Suppression Chamber Pressure 2/sector 2/valve" 1/sector 1/val ve 1,
2 1,
2 1
2 1 $ 2 1
2 1,
2 80 80 80 80 80 80 80 80 12.
Condensate Storage Tank Level 2
1 1
2 13.
Main Steam Line Isolation Valve Leakage Control System Pressure 2
1 1
2 "NOTE - The acoustic monitors may be inoperable until the fifth Refueling Outage scheduled for No Later Than May 15, 1990 without applying the shutdown requirement of Action 80. a.
80 80
III
M C) m I
M INSTRUMENT 1.
Reactor Vessel Pressure 2.
Suppression Chamber Water Level 4.
Suppression Chamber Water Temperature 5.
Suppression Chamber Air Temperature 6.
Primary Containment Pressure CHANNEL CHECK CHANNEL CALIBRATION c
7.
Drywell Air Temperature 8.
Drywell Oxygen Concentration 9.
Drywell Hydrogen Concentration
'C 10.
Safety/Relief Valve Position Indicators TABLE 4. 3. 7. 5"1 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE RE UIREMENTS APPLICABLE >>
OPERATIONAL CONDITIONS 1,
2 1,
2 1,
2 1
2 1,
2 1
2 1 j 2 1
2 1
2 1 j 2 m
C7 fTl CO
'V CO 15.
16.
17.
RCIC Flow HPCS Flow LPCS Flow 11.
Suppression Chamber Pressure 12.
Condensate Storage Tank Level 13.
Main Steam Line Isolation Valve Leakage Control System Pressure 14.
Neutron Flux:
2 1
2 1,
2 1,
2 1,
2 1,
2 1
2 1,
2 1 j 2 "Surveillance of the OPERABLE Tailpipe Temperature instrument channels will be performed daily until the acoustic monitors are declared OPERABLE.
4 l
'EACTOR COOLANT SYSTEM 3/4.4.2~
SAFETY/RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.2 The safety valve function of at least 12 of the following reactor coolant system safety/relief valves shall be OPERABLE with the specified code safety valve function liftsettings:"
2 safety/relief valves 9 1150 psig +3%/-3X 4
safety/relief valves 9 1175 psig +IX/-3X 4
safety/relief valves ta 1185 psig +1%/-3X 4
safety/relief valves 9 1195 psig +3%/-3X 4
safety/relief valves 9 1205 psig +EX/-3X APPLICABILITY:
OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
a 0 b.
C.
With the safety valve function of one or more of the above required safety/relief valves inoperable, 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 /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
With one or more safety/relief valves stuck open, provided that suppression pool average water temperature is less than 90 F, close the stuck open safety/relief valve(s); if unable to close the open valve(s) within 2 minutes or if suppression pool average water tempera-ture is 110'F or greater, place the reactor mode switch in the Shut-down position.
With one or more safety/relief valve acoustic monitors inoperable, restore the inoperable monitor(s) to OPERABLE status within 7 days or 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 /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />."""
SURVEILLANCE RE UIREMENTS 4.4.2 The acoustic monitor for each safety/relief valve shall be demonstrated OPERABLE by performance of a:
a.
CHANNEL CHECK at least once per 31 days, and a
b.
CHANNEL CALIBRATION at least once per 18 months."*
"The liftsetting pressure shall correspond to ambient conditions of the valves at nominal operating temperatures and pressures.
""The provisions of Specification 4.0.4 are, not applicable provided the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reactor steam pressure is adequate to perform the test.
""~The acoustic monitors may be inoperable until the fifth Refueling Outage scheduled for No Later Than May 15, 1990 without applying the shutdown requirement.
WASHINGTON NUCLEAR - UNIT 2 3/4 4-7 Amendment No. 78
II