ML17289A633
| ML17289A633 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 06/15/1992 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17289A634 | List: |
| References | |
| NUDOCS 9206230182 | |
| Download: ML17289A633 (11) | |
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UNITED STATES NUCLEAR REGULATORY COMIVIISSION WASHINGTON, D.C. 20555 WASHINGTON PUBLIC POWER SUPPLY SYSTEM DOCKET NO. 50-397 NUCLEAR PROJECT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE 2.
Amendment No. 107 License No. NPF-21 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Washington Public Power Supply System (licensee) dated April 10,
- 1992, 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 rules and 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; 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.
Accordingly, the license is amended by changes to the Technical Speci-fications 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:
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(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. i07 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 This amendment is effective as of the date of issuance and must be fully implemented within 30 days of the date of issuance FOR THE NUCLEAR REGULATORY COMMISSION Theodore R. quay, Director Project Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June i5, )992
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ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO. 107 TO 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.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE xxiv 3/4 4-19 3/4 4-22 INSERT xxiv 3/4 4-19 3/4 4-22
INDEX LIST OF TABLES Continued l
I TABLE 3.3.7.5-1 4.3.7. 5-1 3.3.7.12-1 4.3.7. 12-1 3.3. 9-1 3.3. 9-2 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREHENTS...................
3/4 3-74 EXPLOSIVE GAS HONITORING INSTRUMENTATION.............
3/4 3-80 EXPLOSIVE GAS MONITORING INSTRUMENTATION SURVEILLANCE REQUIREHENTS...-"""----""-.---"-"
FEEDMATER SYSTEM/HAIN TURBINE TRIP SYSTEH ACTUATION INSTRUHENTATION......""-. - -. -. -. - -"-. - --
FEEDWATER SYSTEM/MAIN TURBINE TRIP SYSTEM ACTUATION INSTRUMENTATION SETPOINTS..................
3/4 3-81 3/4 3-85 3/4 3-86 PAGE ACCIDENT HONITORING INSTRUMENTATION..................
3/4 3-71 4.3.9. 1-1 FEEDWATER SYSTEH/MAIN TURBINE TRIP SYSTEH ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREHENTS...................................'......
3/4 3-87 I
3.4.3.2-1 3.4.3.2-2 3.4.4-1 4.4.5-1 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS.........................-..........
3/4 4-11 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS..............
3/4 4-14 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM.....................................
3/4 4-17 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES.....
3/4 4-11 WASHINGTON NUCLEAR - UNIT 2 Amendment No. SlB 98
INOEX LIST OF TABLES Continued TABLE 4.4.6.1.3-1 3.6. 3-1
- 3. 6.5. 2-1 3.7. 8"1 4.8. 1. l.2-1
- 4. 8. 2. 1-1 3.8.4. 2-1 3.8.4. 3-1 B3/4.4. 6-1 5.7. 1"1 6.2. 2-1 ELETED o
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D PRIMARY CONTAINMENT ISOLATION VALVES..............
SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION VALVES.......................
AREA TEMPERATURE MONITORING......................
DIESEL GENERATOR TEST SCHEDULE........;..........
BATTERY SURVEILLANCE REQUIREMENTS................
PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES...................
MOTOR-OPERATED VALVES THERMAL OVERLOAD PROTECTION.......................................
REACTOR VESSEL TOUGHNESS.........................
COMPONENT CYCLIC OR TRANSIENT LIMITS.............
MINIMUM SHIFT CREW COMPOSITION-SINGLE UNIT FACILITY............................
PAGE 3/4 4-22 3/4 6-21 3/4 6-39 3/4 7"31 3/4 8-9 3/4 8-14 3/4 8-23 3/4 8-26 B 3/4 4-6 5-7 6"6 WASHINGTON NUCLEAR " UNIT 2 XxiV Amendment No. 87, 98, 107
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REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued 4.4.6.1.2 The reactor coolant system temperature and pressure shall be deter-mined to be to the right of the criticality limit line of Figure 3.4.6. 1 curve C within 15 minutes prior to the withdrawal of control rods to bring the reactor to criticality and at least once per 30 minutes during system heatup.
4.4.6.1.3 The reactor vessel material surveillance specimens shall be removed and examined, to determine changes in reactor pressure vessel material properties as required by 10 CFR Part 50, Appendix H in accordance with the NRC approved schedule.
The results of these examinations shall be used to update the curves of Figure 3.4.6.1.
4.4.6. 1.4 The reactor vessel flange and head flange temperature shall be verified to be greater than or equal to 80'F:
a.
In OPERATIONAL CONDITION 4 when reactor coolant system temperature is:
1.
< 100'F, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
2.
< 90'F, at least once per 30 minutes.
b.
Within 30 minutes prior to and at least once per 30 minutes during tensioning of the reactor vessel head bolting studs.
WASHINGTON NUCLEAR - UNIT 2 3/4 4-19 Amendment No. 87, 107
A B
CORE BELTLINE LIMITS
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GN A, B) C, - ABC LIMITS AFTER AN'SSUMEP 76 F CORE BELTLINE TEMP SHIFT FROM AN INITIAL RTNPT OF 28 F 110 F
312 PSIG 180 F
312 PSIG 140 F
312 PSIG BOLTUP LIMIT 80 F 0
50 100 50 200 250 XO 350 400 450 500 MINIHUM REACTOR VESSEL METAL TEMPERATURE Temperature F
FIGURE 3.4.6.1 MINIHUM REACTOR VESSEL METAL TEMPERATURE VERSUS REACTOR VESSEL PRESSURE WASHINGTON NUCLEAR - UNIT 2 3/4 4-20 Amendment No.
87
THIS PAGE IS BLANK INTENTIONALLY WASHINGTON NUCLEAR - UNIT 2 3/4 4-21 Amendment No.
THIS PAGE IS BLANK INTENTIONALLY MASHINGTON NUCLEAR - UNIT 2 3/4 4-22 Amendment No.
107