ML20216E486

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Proposed Tech Specs Re APRM Setpoints,Reactivity Anomalies & RPS Instrumentation
ML20216E486
Person / Time
Site: River Bend Entergy icon.png
Issue date: 09/05/1997
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20216E483 List:
References
NUDOCS 9709100204
Download: ML20216E486 (5)
v • d • e


Text

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Attachment C to RBG-44133 i Administrative Technical Specifications Changes t

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9709100204 970905 .

PDR ADOCK 05000458-P PDR .:..

.SURVEILUsNCE REQUIREMENTS

..................................... NOTES ---- - - - -- --- - ----

1. Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.
2. When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR -3.3.1.1.2 - ~~ -- --

NOTE- -. -- ----- - -

Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER 8 25% RTP.

Verify the absolute difference between the 7 days average power range monitor (APRM) channels and the calculated power E 22 RTP f r : y ;M -

idjr'--t ;Med by '_C011' * ^ r ::: "- --

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SR 3.3.1.1.3 Adjust the channel to conform to a calibrated 7 days flow signal.

SR 3.3.1.1,4 ---.--.--- -- --NOTE. ..---- - ------

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

7 days (continued) t-l

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,a 5.6 Reporting Requirements 5.6.2 -

Annual Radiological Environmental Operating Report (continued) results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report The Radioactive Effluent Release Report covering the operation of the unit during the previous calendar year shall be submitted by May 1 of each year, The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM t.nd process control program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix 1.Section IV.B.1.

5.6.4 Monthly Operating Reports Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam safety / relief valves, shall be submitted on a monthly basis no later than the 15th of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating 1 mits shall be established prior to each relaad cycle, or prior to any emaining portion of a reload cycle, and shi.ll be dacumented in the COLR for the following:
1) LCO 3.2.1. Average Dianar Linear Heat Generation Rate (APLHGR).
2) LCO 3.2.2. Minimum Critical Power Ratio (MCPR).
3) LCO 3.2.3. Linear Heat Generation Rate (LHGR) and
4) ' C 0 ' ' *-'"'~":'"~t"'*"""'""""p":
b. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC. specifically those described in the following documents.

D

. o Attachment D to RUG-44133 Additional Teeginical Specgr;C8tions Hases Changes i

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, 3 SURVEllLANCE SR 3.3.1.1.2

, REQUjREMENTS (continuct To ensure that the APRMs are accurately indicating the true core average power the APRMs are calibrated to the reactor power calculated from a heat balance. LCO 2.2.' "^:^r ;^ "~ c- P: ;r "cr"^r "?""' C:t :-d e^t-^!-it . " ! h:: th^ ^?"": te he r:dfr; ;rette- t':. ::tu:1 ER"^1 "9 te -^ t ::t- f^-

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&u' md "r' "D . The Frequency of once per 7 days is based on minor changes in LPRM sensitivity, which could affect the APRM reading between performances of SR 3.3.1.1.8.

A restriction to satisfying this SR w% < 25% RTP is provided that requires the SR to be met only at 8 25% RTP because it is difficult to accurately maintain APRM indication of core THERMAL POWER consistent with a heat balance when < 25% RTP. At low j

power levels, a high degree of accuracy is unnecessary because of the large inherent margin to thermal limits (MCPR and APLHGR).

At 8 25% RTP, the Surveillance is required to have been satisfactorily performed within the last 7 days in accordance with SR 3.0.2. A Note is provided which allows an increase in THERMAL POWER above 25% if the 7 day Frequency is not met per SR 3.0.2. In this event the SR must be performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reaching or exceeding 25% RTP. Twelve hours is based on operating experience and in consideration of providing a reasonable time in which to complete the SR.

SR 3.3.1.1.3 The Average Power Range Monitor Flow Biased Simulated Thermal Power-High Function uses the recirculation loop drive flows to vary the trip setpoint. This SR ensures that the APRM Function accurately reflects the required setpoint as a function of flow.

A variable calibrated flow signal is applied to each APRM flow biased simulated thermal power channel, and the trip setpoint is verified to be acceptable by application of a variable power signal to the channel.

The Frequency of 7 days is based on engineering judgment, operating experience, and the reliability of this instrumentation.

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