ML20101S614
| ML20101S614 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 01/29/1985 |
| From: | UNION ELECTRIC CO. |
| To: | |
| Shared Package | |
| ML20101S605 | List: |
| References | |
| NUDOCS 8502050542 | |
| Download: ML20101S614 (4) | |
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Enclosure C
- o PROPOSED TECH!!ICAL SPECIFICATI0!1 CHANGES 8502050542 850129 PDR ADOCK 05000483 P
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TABLE 4.3-1 (Continued)
REVISION 1 TABLE NOTATIONS
- 0nly if_the Reactor Trip System breakers happen to be closed and the Con-
' trol Rod Drive System is capable of rod withdrawal.
- Below P-6.(Intermediate Range Neutron Flux interlock) Setpoint.
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- Below P-10 (Low Setpoint Power Range Neutron Flux interlock) Setpoint.
'(1) 'If not. performed in previous 7 days.
(2) Comparison of calorimetric'to excore power. indication above 15% of RATED THERMAL POWER.
Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.
The rrovisions 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 x4 15% of RATED THERMAL POWER.
Recalibrate if the absolute difference is greater than or equal to 3%..The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.
(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.
(5) Detector plateau curves'shall be obtained, evaluated and compared to i
. manufacturer's data.
For-.the Intermediate Range and Power Range Neutron 4
Flux channels the provisions of 5)ecification 4.0.4 are not applicable 4 if for entry into M00E 2 or 1.
i Incore"- Excore Calibratic.1, above 75% of RATED THERMAL POWER.
The
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'(6). provisions of Specification 4.0.4 are not applicable for entry into
. MODE 7. or-1.
D) Each train shall'be tested at leaTt every 62 days on a STAGGERED TEST BASIS. Insert A
'(8)_ With power greater than'or equal to the interlock Setpoint the required f
ANALOG CHANNEL OPERATIONAL TEST shall consist of ' verifying that the inter-lock is in the required state by observing the permissiv'e annunciator window, (9) Monthly surveillance in MODES 3*, 4*,- and 5* shall also include verification v
that permissives P_-6 and P-10 are in their required state for existing
.' plant conditions by observation of the permissive' annunciator window.
. Monthly. surveillance shall include verification of the Boron Oilution Alarm Setpoint of less than or equal to an increase of twice the count
- rate within a 10-minute period.
(10) Setpoint verification is not ired.
-(11) $t least once Der 18 months fni)following maintenance or adjustment of the Reactor trip breakers,-the TRIP ACTUATING OEVICE OPERATIONAL TEST shall include independent verification of the Undervoltage and Shunt trips. "I~nsert 6
-(12) At least once per 18 months durihg shutdown, verify that on a simulater
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Boron Dilution Doubling test signal the normal-CVCS discharge valves 'ill close and the centrifugal charging pumps suction valves from the RWS' will-open within 30 seconds.
(13) CHANNEL CALIBRATION shall include the RTO bypass loops flow rate.
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'Favdem - MV n 1/4 D-12
Enclosuro C Insert A - Enclosure C The TRIP ACTUATIllG DEVICE OPERATIO!!AL TEST shall include independent verification of the Undervoltage and Shunt trips.
Insert B - Enclosure C Operability testing of the Undervoltage Trip Attachments on the bypaas breakers shall be conducted at least once per 18 months.
Operability testing of the Shunt Trip Attachments on the bypass breakers shall be conducted with the breaker in the test position prior to racking in and closing of the bypass breakers for reactor trip breaker testing.
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bcct' 3456-0021.6 Nuclear Date DFS/ Chrono D. F. Schnell J. F. McLaughlin
~J. E. Birk W. H. Weber F. D. Field R. J. Schukai M. A. Stiller S. E. Miltenberger J. J. Beisman-Missouri Public Service Commission D. W. Capone 4
A. C. Passwater T. H. McFarland R. P. Wendling D. E. Shafer D. J. Walker G56.37 (CA-460).
Compliance (J. E. Davis)
NSRB.(Laura Robertson) i I
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