ML20114A851
| ML20114A851 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/17/1992 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20114A849 | List: |
| References | |
| NUDOCS 9208240011 | |
| Download: ML20114A851 (3) | |
Text
Attachment IV to 110 92-0247-Page 1 of 3 I
ATTAC11 MENT IV
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PROPOSED TECIINICAL SPECIFICATION C11ANGES 1
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t Iv208240011 920817 PDR ADOCK 05000482 P
Attachment IV to N0 92-0247 Page 2 of 3 4
TABLE 4.3-1 (Continued)
TABLE NOTATIONS "Only if the Reactor Trio System breakers happen to be closed and the control rod drive systern is capable of rod withdrawal.
- Below 9-6 (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) Coroarisca af cal eimetric to excore power indication above 15% of RATED THERMAL PiswER.
Ad:'
.t excore channt.1 gains consistent with 7 1orimetric power if aosolute oif ference is greater than 2%.
The provisions of Speci-fication 4.0.4 are not applicable for entry into MODE 2 w 1.
(3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15%
of RATED THERMAL POWER.
Recalibrate if the absolute difference is greater l
than or equal to 3%.
The provisions of Specification 4.0.4 are not applic-able for entry. into MODE 2 or 1.
i (4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5) Detector plateau curves shall be obtained, evaluated and compared to manu-facturer's 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 provi-sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(7) Eacn~ train shall be tested at leas'. evey 62 days on a STAGGERED TEST BASIS.
(9) Quarterly surveillance in MODES 3", 48 and 5* shall also include verifica-tion that permissives P 6 and P-10 are in their required c. tate for
-existing plant conditions by observation of the permissive annunciator window.
Quarterly surveillance shall include verification of the Boron Dijution Alara Setpoint of less than or equal to an increase of twice, the count rate within a 10-minute period.
(10) Setpoint verification is not required.
(11EThe TRIP ACT'JATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undarvoltage and shunt trip circuits for the Manual Reactor _ Trip Function.
The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).
(12) At least once per 18 months during shutdown, verify that on a simulpted Boren Dilution Doubling test signal the nortaal CVCS discharge valves will close and the centrifugal charging pumps suction valves free the RWST will open within 30 seconds.
- Inse,. A WOLF CREEK - UNIT 1 3/4 3-12 Amendment No. Z2,26
Attachment'IV to NO S2-0247
-Page 3 of 3 4
INSERT A
- Complete verification of OPERA 7'LITY of the manual reactor trip switch circuitry shall be performed prior to startup-from the first shutdown to
' Mode 3 occurring after August 14, 1992.
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