ML20092F320
| ML20092F320 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 02/10/1992 |
| From: | NORTHEAST NUCLEAR ENERGY CO. |
| To: | |
| Shared Package | |
| ML20092F313 | List: |
| References | |
| NUDOCS 9202190251 | |
| Download: ML20092F320 (12) | |
Text
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Dpeket No. S E!?)
luiQl2 Millstone Nuclear Power Station, Unit No. 3 Proposed Revision to Technical Specifications Reactor Trip System and Engineered Safety features Actuation System Instrumentation Response Times February 1992 9202190251 920210 ADOCK0500{ly3 DR
J1(DIX LIB 111RG CONDIT10RLLOR_DE(JM110N AND SURVElllANCLELQL!!REMENTS E110B MGE Position Indiction System -
Shutdown.....................
3/4 1-24 Rod Drop Time............................................
3/4 1 25 Shutdown Rod Insertion Limits............................
3/4 1 26 Control Rod Insertion lmits..............................
3/4 1-27 MLLEQRER DislRIBUTION LIM 115 3/4.2.1 AX1AL FLUX DIFFERENCE....................................
3/4 2-1 four Loops 0porating.....................................
3/4 2-1 1hree Loops 0peration....................................
3/4 2-3 3/4.2.2 IIEAT FLUX 110T CilANNEL FACTOR F
(Z).....................
3/4 2 5 four Loops 0perating............g 3/4 2 5 Three Loops Operating....................................
3/4 2-12 3/4.2.3 RCS FLOW RATE AND NUCLEAR ENillALPY RISE 110T CilANNEL FAC10R...................................................
3/4 2-19 four Loops 0perating.....................................
3/4 2-19 Three Loops 0perating....................................
3/4 2 22 3/4.2,4 QUA0 RANT POWER TILT RAT 10................................
3/4 2-24 3/4.2.5 DNB PARAMETERS...........................................
3/4 2-27 TABLE 3.2-1 DNB PARAMETERS........................................
3/4 2-28 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION......................
3/4 3-1 TABLE 3.3-1 REACTOR T RI P SYST EM INSTRUMENT AT ION...................
3/4 3-2 TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS.............................................
3/4 3-10 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION..........................................
3/4 3-15 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM I N ST RUM E NT AT I ON..........................................
3/4 3-17 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENT ATION T RI P SET P0lNTS...........................
3/4 3-26 MILLSTONE - UNIT 3 v
Amendment No. EP, 60 0042
1BDIl LIMITING CONDITIONS _ FOR OPERATID1 LAND SURVEILLMCI,_REQlllRDiUllS SLCllDil MGI.
TABLE 4.3 2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS................
3/4 3 36 3/4.3.3 MONITORING INSTRUMENTATION Radiation Monitoring for Plant Operations................
3/4 3 42 TABLE 3.3 6 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERAT10HS.....................................
3/4 3-43 TABLE 4.3 3 RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS.....................
3/4 3-45 Movable incore Detectors.................................
3/4 3-46 Seismic Instrumentation..................................
3/4 3-47 TABLE 3.3-7 SEISMIC MONITORING INSTRUMENTATION....................
3/4 3 48 TABLE 4.3 4 SEISMIC MONITORING INSTRUMENTATION SVRVEILLANCE REQUIREMENTS.............................................
3/4 3 49 Meteorological Instrumentation...........................
3/4 3-50 TABLE 3.3 8 METEOROLOGICAL MONITORING INSTRUMENTATION.............
3/4 3-51 TABLE 4.3-5 METEOROLOGICAL MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS............................................
3/4 3 52 Remote Shutdown Instrumentation..........................
3/4 3-53 TABLE 3.3-9 REMOTE SHUTDOWN INSTRUMENTATION.......................
3/4 3-54 TABLE 4.3 6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................................
3/4 3 58 Accident Monitoring Instrumentation......................
3/4 3 59 TABLE 3.3 10 ACCIDENT MONITORING INSTRUMENTATION..................
3/4 3-60 TABLE 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENIS.............................................
3/4 3 62 fire Detection Instrumentation...........................
3/4 3-64 TABLE 3.3-11 flRE DETECTION INSTRUMENTATION.......................
3/4 3 65 Loose-Part Detection System..............................
3/4 3 68 Radioactive Liquid Effluent Monitoring Instrumentation...
3/4 3 69 TABLE 3.3-12 RADI0 ACTIVE LIQUID EffLVENT MONITORING INSTRUMENTATION 3/4 3-70 TABLE 4.3 8 RADIDACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS................
3/4 3-72 Radioactive Gaseous Effluent Monitoring Instrumentation..
3/4 3-74 I
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3/4.3 IH11EWHIAUDR
}/4.3.1 REAC1OR 1R1P SYSTUi_lNSIRWi[l!IA110B LUil1111010f01110!4 FOR OPERAT10ft 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.
6EELKAllLllt:
As shown in Table 3.3 1.
6011D11:
As shown in Table 3.3-1.
S1!RRILLAf1CE REQMJREMEf1TS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1, 4.3.1.2 The REACTOR TRIP SYSTEM RESP 0!1SE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel (to include input relays to both trains) per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific Reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.
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INSTRUMENTATION 3/4.3.2 ENGINEfRED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety features Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3 3 shall be OPERABLE with their Trip Setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.
APPLICABILITY: As shown in Table 3.3-3.
ACTION:
a.
With an ESFAS Instrumentation or Interlock Trip Setpoint trip less conservative than the value shown in the Trip Setpoint column but more conservative than the value shown in the Allowable Value column of Table 3.3 4, adjust the Setpoint consistent with the Trip Setpoint value, b.
With an ESFAS Instrumentation or Interlock Trip Setpoint less conservative than the value shown in the Allowable Value column of Table 3.3-4, either:
1.
Adjust the Setpoint consistent with the Trip Setpoint value of Table 3.3-4, and determine within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> that Equation 2.2-1 was satisfied for the affected channel, or 2.
Declare the channel inoperable and apply the applicable ACTION statement requirements of Table 3.3-3 until the channel is restored to OPERABLE status with its Set consistent with the Trip Setpoint value. point adjusted Equation 2.2-1 Z + R + S s TA Where:
I - The value from Column Z of Table 3.3-4 for the affected
- channel, R - The "as measured" value (in percent span) of rack error for the affected channel, S - Either the "as measured" value (in percent span) of the sensor error, or the value from Column S (Sensor Error) of Table 3.3 4 for the affected channel, and TA - lne value from Column TA-(Total Allowance) of Table 3.3 4 for the affected channel, c.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
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INSTRUMENTATION BASES BBCTOR 1 RIP SYSTEM INSlRUMENTATION and ENGINEERED SAFETY FEATURES ACTVATION SYSTEM MSTRUMENTATION (Continued) the sensor from its calibration point or the value specified in Table 3.3-4, in percent span, from the analysis assumptions.
Use of Equation 3.3-1 allows for a sensor drift factor, an increased rack drift factor, and provides a threshold value for REPORTABLE EVENTS.
The methodology to derive the Trip Setpoints is based upon combining all of the uncertainties in the channels.
Inherent to the determination of the Trip Setpoints are the magnitudes of these channel uncertainties.
Sensor and rack instrumentation utilized in these channels are expected to be capable of operating within the allowances of these uncertainty magnitudes.
Rack drift in excess of the Allowable Value exhibits the behavior that the rack has not met its allowance.
Being that there is a small statistical chance that this will happen, an infrequent excessive drift is expected.
Rack or sensor drift, in excess of the allowance that is more than occasional, may be indicative of more serious problems and should warrant further investigation.
The measurement of response time at the specified frequencies provides assurance that the Reactor trip and the Engineered Safety Features actuation associated with each channel is completed within the time limit assumed in the safety analyses. The RTS and ESF response times are included in the Operating Procedure OP-3273 " Technical Requirements--Supplementary Technical Specifications." No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be demonstrated by any series of sequential, overlapping, or total channel test measurements provided that such tests demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either:
(1) in place, onsite, or offsite test measurements, or (2) utilizing replacement sensors with certified response time. Detector response times may be measured by the in situ on line noise analysis-response time degradation method described in the Westinghouse Topical Report, "The Use of Process Noise Measurements To Determine Response Characteristics of Protection Sensors in U.S. Plants,"
August 1983.
MILLSTONE - UNIT 3 B 3/4 3-2 Amendment No. J 0071
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