ML20059D774
| ML20059D774 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 10/27/1993 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20059D766 | List: |
| References | |
| NUDOCS 9311020399 | |
| Download: ML20059D774 (3) | |
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. Att'achment IV to IIA 93-0203
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l ATTACIDdENT IV PROPOSED TECIINICAL SPECIFICATION CHANGES i
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. Attachment IV to NA 93-0203 Page 2 of 3 l
TABLE 4 3-1 (Continued)
TABLE NOTATIONS
- Only if the Reactor Trip System breakers happen to be closed and the control rod dove system is capable of rod withdrawal.
- Below P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.
- Below P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.
(1) If not performed in previous 31 days.
(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER Adjust excore channel gains consistent with calorimetric power if absoiute difference is greater than 2%. The provisions of Specification 4.0.4 are not applicable for entry Into MODE 2 or 1.
(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above l'
15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equalto 3% The provisions of Specification 4.0.4 are not apphcable for entry into MODE 2 or 1.
(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5) Detectorplateau4urves4 hall beobtainedrevaluatedandcompared-to INSERT A
---rnanufacturefs-data. For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER. The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.
(9) Quarterly surveillance in MODES 3*,4* and 5* shall also include venfication that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window. Quarterly surveillance shallinclude veiification of the Boron Dilution Alarm Setpoint of less than or equal to an increase of twice the count rate within a 10-minute period.
(10) Setpoint venfication is not required.
"(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shallindependently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Tnp Function. The test shall also venfy the OPERABILITY of the Bypass Breaker trip circuit (s).
J (12) At least once per 18 months during shutdown, verify that on a simulated Boron Dilution-Doubling test signal the normal CVCS discharge valves Will close and the centnfugal charging pumps suction valves from the i
RWST will open within 30 seconds.
" Complete venfication of OPERABILITY of the manual reactor trip switch circuitry shall be performed pnor to startup from the first shutdown to Mode 3 occurring after August 14,1992.
WOLF CREEK - UNIT I 3/4 3-12 Amendment No. 42,26,55 1
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J Att'achment IV to NA 93-02u3 ~
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For Source Range detectors, integral bias curves are obtained, evaluated,-
j and compared to manufacturer's data, For Intermediate Range and Power.
Range channels, detector plateau curves shall be obtained, evaluated, and compared to manufacturer's data.
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