ML20091K792
| ML20091K792 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 08/22/1995 |
| From: | WOLF CREEK NUCLEAR OPERATING CORP. |
| To: | |
| Shared Package | |
| ML20091K788 | List: |
| References | |
| NUDOCS 9508280153 | |
| Download: ML20091K792 (12) | |
Text
_ _.
Att chm:nt IV to ET 95-0052 Page 2.
of 13 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL FLUX DIFFERENCE.(AFD) 3/42-1 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - Fo(X,Y,Z) 3/4 2-4 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR - F s(X,Y) 3/4 2-9 3
3/4.2.4 OUADRANT POWER TILT RATIO..
3/4 2-11 3/4.2.5 DNB PARAMETERS.,
3/4 2-14 TABLE 3.2-1 DNB PARAMETERS..
3/4 2-16 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION...
3/4 3-1 TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION..
3/4 3-2 LE 3.3-2 DELETEDREACTOP TPm SYSTE" 'NSTRU"5NTAT!ON RESPONSE "ES..
3!' 3 ' l TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-9 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...
3/4 3-13 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION.
3/4 3-14 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS..
3/4 3-22 m
ABLE 3.3-5 LETED NGINEERED S.^FE" FEATURES RESPONSE "ES 3/4 3-2 l
TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM
(
INSTRUMENTATION SURVEILLANCE REQUIREMENTS 3/4 3-34 t
WOLF CREEK-UNIT 1 V
Amendment No.44 l
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Attachm nt IV to ET 95-0052 Page 3 of 13 3/3.3 INSTRUMENTATION 3[4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION I
3.3.1 As a minimum, the Reactor Trip System i t menta i n channels and Table 3.3-1 shall be OPERABLE we. E_. ONS_ T!M__ ec c.me-M
.2533_
i APPLICABILITY: As shown in Table 3.3-1.
ACIlON:
As shown in Table 3.3-1, SURVEILLANCE REQUIREMENTS 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 RESPONSE TIME of each Reactor trip function to_be withiD t6 li_mit at_least once per 18 months. Neutro Msh Il e i
n at (detec o are exempt from response tiise tesfrnp a test s aIIinclude at least one train such that both trains are tested at least once per 36 months and one channel 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, WOLF CREEK - UNIT 1 3/4 3-1 l
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WOLF CREEK - UNIT 1 3/4 3-8
Attachmtnt IV to ET 95-0052 Page 6 of 13 INSTRUMENTATION i
i 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety lleatures Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their Trip I
Setpoints set c is ent with the values shown in the Trio Setooint column of Table 3.3-4 -andwe E.PON. T!BE5TGSE6T99 3g l
APPLICABILITY: As shown in Table 3.3-3.
ACTION
- a. With an ESFAS Instrumentation or Interlock Trip Setpoint less conserva-1 tive than the value shown in the Trip Setpoint column but more conser-vative than the value shown in the Allowable Value column of Table 3.3-4 adjust the Setpoint cansistent with the Trip Setpoint value.
- b. With an ESFAS Instrumentation or interlock Trip Setpoint less conserva-tive than the value shown in the Allowable Values column of Table 3.34, 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 channelis restored to OPERABLE status with its Setpoint adjusted consistent with the Trip Setpoint value.
Equation 2.2-1 Z + R + S 5 TA Where:
l Z = 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 l
1 TA = The value from Column TA (Total Allowance) of Table 3.3-4 for the affected channel.
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- c. With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
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l WOLF CREEK - UNIT 1
-3/4 3-13 Amendment No.-84 '
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l WOLF CREEK - tJNIT 1 3/4 3-30 Amendment No. 9 l
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Attachmtnt IV to ET 95-0052 Page 126 of 13 l
l l
. 3/4 3 INSTRUMENTATION i
BASES i
3/4.3.1 and 3/4 3.2 REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION l
The OPERABILITY of the Reactor Trip System and the Engineered Safety i
Features Actuation System instrumentation and interlocks ensure that: (1) the i
associated ACTION and/or Reactor trip will be initiated when the parameter monitored by each channel or combination thereof reaches its Setpoint, (2) the specified coincidence logic is maintained, (3) sufficient redundancy is main-tained to pormit a channel to be out-of-service for testing or maintenance, i
and (4) sufficient system functional capability is available from diverse parameters.
I i
The OPERABILITY of these systems is required to provide the overall reliability, redundancy, and diversity assumed available in the facility j
design for the protection and mitigation of accident and transient conditions.
The integrated operation of each of these systems is consistent with the assurnptions used in the safety analyses. The Surveillance Requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic i
surveillance tests performed at the minimum frequencies are sufficient to
[
1 demonstrate this capability.
j r
When determining compliance with action statement requirements, addition to the RCS of borated water with a concentration greater than or equal to the i
minimum required RWST concentration shall not be considered to be a positive reactivity change.
The Engineered Safety Features Actuation System Instrumentation Trip i
Setpoints specified in Table 3.3-4 are the nominal values at which the bistables I
are set for each functional unit. A Setpoint is considered to be adjusted consistent with the nominal value when the "as measured" Setpoint is within the band allowed for calibration accuracy. Specified surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, and Supplement 1. " Evaluation of Surveillance Frequencies and i
Out of Service times for the Reactor Protection Instrumentation System," sup-J plements to that report, and the NRC's Safety Evaluation dated February 21,
)
1985, WCAP-10271 Supplement 2 and WCAP-10271-P-A Supplement 2, Revision 1,
" Evaluation of Surveillance Frequencies and Out of Service Times for the Engineered Safety Features nctuation System," the NRC's Safety Evaluation dated February 22,1989, and the NRC's Supplemental Safety Evaluation dated April 30, i
]
1990. Surveillance intervals and out of service times were determined based on i
maintaining and an appropriate level of reliability of the Reactor Protection System and Engineered Safety Features instrumentation.
l 4
ESF repener M.:: Op-^&d != T6'e 3.3 5 et!$ 'nc'ede re rr-t!:! epe :
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WOLF CREEK - UNIT 1 B 3/4 3-1 Amendment No. 9,42,-43 N ;:m br22,1993 I
i 4
4 Attachment IV to ET 95-0052 Page 13' of 13 INSTRUMENTATION BASES REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION (Continued)
^- en"he VCT eerg!ng pump re-* e= v !re: are c!^ ed fe!!c#ng ep--!ng of the Pu!ST charging pump ercC^a v:!= '%en the regent!:! eper?!!cn of'he RWST end VCT v:'r:: !: net L c'eed !- 'he re pence t:me: @!cte ?),the v 'rer
- ---fed e' b :rd ^^ !% LOCA ent!yre The LOCA ene!y :: t:Er ~ed!! fer inl^^4n "r. re; -d'er: ef 'he :ceree Vermcet:^^ ef 'he :: pence !:me rper*ed - T b'e 3.3 5 "A!! : ure that the : ump!!cn er^d fer the LOCA :nd nen LOCA ne!ytet r* re:-^rt te ^per:tien Of'he VCT nd RWST v:!re: 2re ve!!d.
e o ccommo a e the instrument drift assumed to occur between operational tests and the accuracy to which Setpoints can be measured and calibrated, Allow-able Values for the Setpoints have been specified in Table 3.3-4. Operation with Setpoints less conservative than the Trip Setpoint but within the Allowable Value is acceptable since an allowance has been made in the safety analysis to accommodate this error. An optional provision has been included for determining the OPERABILITY of a channel when its Trip Setpoint is found to exceed the Allowable Value. The methodology of this option utilizes the "as measured" deviation from the specified calibration point for rack and sensor components in conjunction with a statistical combination of the other uncertainties of the instrumentation to measure the process variable and the uncertainties in calibrating the instrumentation. In Equation 3.3-1, Z + R + S 5 TA, the interactive effects of the errors in the rack and the sensor, and the as measured" values of the errors are considered. Z, as specified in Table 3.3-4, in percent span, is the statistical summation of errors assumed in the analysis excluding those associated with the sensor and rack drift and the accuracy of their measurement. TA or Total Allowance is the difference, in percent span, between the Trip Setpoint and the value used in the analysis for the actuation.
R or Rack Error is the "as measured" deviation, in percent span, for the affected channel from the specified Trip Setpoint. S or Sensor Error is either the "as measured" deviation of the sensor from its calibration point or the value specified in Table 3 3-4, in percent span, from the analysis assumptions.
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 i
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 WOLF CREEK - UNIT 1 B 3/4 3-2 Amendment No.-43 Nevember 22,1993
-