ML20072F348
| ML20072F348 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 08/17/1994 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML19304C524 | List: |
| References | |
| NUDOCS 9408230303 | |
| Download: ML20072F348 (19) | |
Text
,
j FNP Unit 1 Technical Specifications Changed Pages MniL1 Revision Page 3/43-1 Replace Page 3/4 3-15 Replace Page B 3/4 3-2 Replace Page B 3/4 3-2a Add 9408230303 940817 PDR ADOCK 05000348 P
PDR j
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION s.
LIMITING CON 0! TION FOR OPERATION 3.3.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.
l APPLICABILITY: As shown in Table 3.3-1.
ACTION:
' As shown' in Table 3.3-1 SURVEILLANCE RE0VIREMENTS 4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECX, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.2 The logic for the interlocks shall be demonstrated OPERA 8LE prior to each reactor startup unless performed during the preceding 92 days.
The total interlock function shall be demonstrated OPERABLE at least once per 18 months.
4.3.1.3 The R shall bh=.:EACTOR TRIP SYSTEM RESPONSE TINE of each reactor trip function verd.l E tr:t:d to be within its limit at least once per 18 months."
yefi%Mo acTite* shall include at least one logic train such that both logic trains l
t G J, s ite,utad at least once per 36 months and one channel per function such that nannels ar total number o%;st;d at least once every N times 18 months where N is the veu, d f redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.
Neutron detectors are exempt from response time testing.
l l
FARLEY-UNIT 1 3/4 3-1 AMENOMENT NO. 26.105
INSTRUMENTATTON 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INST l!MITING CON 0! TION FOR OPERATION 3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERA 8LE with their tr setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.
i l
ApptICABitITY: As shown in Table 3.3-3, ACTION:
1 With an ESFAS instrumentation channel or interlock trip setpoint less a.
3.3-4, declare the channel inoperable and apply the a requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint
- value, b.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REOUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHAN TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.2 the automatic actuation logic test.The logic for the interlocks shall be de demonstrated OPERA 8LE at least once per 18 months,The total interlock functi Ar3rha The ENGINEERED SAFETY FEATURES RESPONSE TINE Mg g
vtA h m W be.in..t;;.tr.4 to be within the limit at least once per 18 months.
s shall include at least one logic train such that both logic trains j.pg are at least once per 36 months and one channel per function such that M channels artWat least once per N times 18 months where N is the
~
verW.
total number of redundant channels in a specific ESFAS function as shown in the ' Total No. of Channels
- column of Table 3.3-3.
FARLEY-UNIT 1 3/4 3-15 AMENONENT NO. 26.105 9
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rNstnewnerAffeN BAsrs REic'f0R tR f e sYstDi AND InstatmewrAttoM ENd f NrfRED siFE'?Y FEA'F3RF Ac'f9]Af fdM sys?Dr continued) fbLO The, p - J t
assurance that the reactor trip and RSF actuation associated is completed within the time limit assumed in the accid channel time limite for the Reactor Trip system and EngLneered saf t ent analysee. Response Actuation system are maintained in Tables 7.2-5 and 7 3-16 of th e y Features respectively.
with response times indicatedNo credit was taken in the analyses for those channelsePa a_not a 1Lcable.
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3 /a.1.1.1 RAnf Atfew MoMITOR fNS I
TWRtRtMFwfATfoM The OPERASILITT of the-radiation monitoring channele ensures that radiation levels are continually measured in the areas served by the indivi
- 1) the channels and 2) level trip setpoint is encoeded.the alarm or automatic action is initiated when the radia ual o
Alare/ trip setpointe for the containment purge have been establi h d purge rate of 5,000 ocfm in all MODES and for purge rates of 25 000 ects a d se for 50,000 eefe in Mocas 4, 5, and 6.
n release in which Ze-133 and Kr-45 are the predoniaant isotopes, o values equal to or less than the effluent concentration limite stated in 10 on 20, Appendia 3 (to paragraphe 20.10g1 - 20 2401), Table 2 fR lootopes, and on a X/Q of 5.6 m 10 3
, Column 1 for these sec/m at the site boundary.
The alare/ trip setpoint for the fuel storage pool area has been based on a flow rate of 13,000 eefes a release in which ze-133 and E established prod-inant isotopes, os concentration values equal to or less than the effl r-45 are the
- n 20.k)iration limite stated in 10 CFR 20, Appendia [to paragraphe uent at the site boundary., Table 2, column 1 ve& wee 9er these isotopee, ese/m 3 /a. 3. 3. 2 newaar e fraso La wium e The OFERAs!LITY of -the movable Lacere deteeters with the specified system amourately represent the spatial neutron flua minimum s
core.
detector used and determining the acceptabtLity of its volt eactor For the purpose of measuring F II'*
is used.
O AM, and F a full incore fluz map Quarter-core flus maps, as detined in b-8648, June 1976, may be used in recalibration of the escore neutron flua detection system.
incore flux maps or syne.etric incere thimbles may be used for monit Full QU4DRANT POWER TILT RATIC when one Power Range Channel is inoperab oring the FAALIT-trNIT a 3/4 3-2 AMENDMENT No.
1 Unit 1 Page B 3/4 3 2 I
INSEllT A l
l Ilesponse time may be verified by actual tests in any series of sequential, overlapping or total-channel measurements, or by summation of allocated sensor response times with actual tests on the remainder of the channelin any series of sequential or overlapping measurements.
Allocations for specific pressure and differential pressure sensor response times may be
-obtained from: (1) historical records based on acceptable response time tests (hydraulic, noise, or power interrupt tests), (2) in place, onsite, or offsite (e.g. vendor) test measurements, or (3) utilizing vendor engineering specifications. WCAP-13632, Revision 1,
" Elimination of Pressure Sensor Response Time Testing Requirements," provides the basis and methodology for using allocated sensor response times in the overall verification of the channel response time for specific sensors identified in the WCAP. The allocations for these sensor response times must be verified prior to placing the sensor in operational service and re verified following maintenance that may adversely affect response time. In general, i
electrical repair work does not impact response time provided the parts used for repair are of the same type and value. One example where time response could be affected is replacing the sensing assembly of a transmitter. Ilesponse time verification for other sensor types must j
be demonstrated by test.
]
1 i
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i l
3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION i
LIMITING CONDITION FOR OPERATION
]
3.3.1 As a minimum, the reactor trip system instrumentation channels and j
interlocks of Table 3.3-1 shall be OPERABLE.
APPLICABILITY:
As shown in Table 3.3-1.
ECTION:
As shown in Table 3.3-1.
SURVEILLANCE REOUIREMENTS 4.53.1.1 Each reactor trip system instrumentation channel shall be demonstrated OFERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days.
The total interlock function shall be demonstrated OPERABLE at least once per 18 months.
4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function whall be verified to be within its limit at least once per 18 months.*
Each verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified 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.
1 l
i Neutron detectors are exempt from response time testing.
l 1
I I
FARLEY-UNIT 1 3/4 3-1 AMENDMENT NO.
INSTRUMENTATION 2/4.3.2 ENGINEEPED SAFETY FEATURE ACTUATION JySTI'M INSTRUMENTATION LIM (TING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Feature Actuation System (EOFAS) 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.
bf PLICAB RIII:
As shown in Table 3.3-3.
Mllolls a.
With an ESFAS instrumentation channel or interlock trip setpoint less conservative than the value shown in the Allowable values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value, b.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE PEOUIPEMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.
The total interlock function shall be demonstrated OPERABLE at least once per 18 months.
4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be verified to be within the limit at least once per 18 months.
Each verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified at least once per N timem 1G months where N is the total number of redundant caannels in a specific ESFAS function as shown in the
" Total No. of Channels" Coltmn of Table 3.3-3.
FARLEY-UNIT 1 3/4 3-15 AMENDMENT NO.
INSTRUMENTATION BASFS REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION (Continued)
The verification of response time at the specified frequencies provides l
assurance that the reactor trip and ESF actuation associated with each channel is completed within the time limit assumed in the accident analyses.
Response
time limits for the Reactor Trip System and Engineered Safety Features Actuation System are maintained in Tables 7.2-5 and 7.3-16 of the Parley FSAR, respectively. No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be verified by actual tests in any series of sequential, overlapping or total channel measurements, or by summation of allocated sensor response times with actual tests on the remainder of the channel in any series of sequential or overlapping measurements.
Allocations for specific pressure and differential pressure sensor response times may be obtained from:
(1) historical records based on acceptable response time tests (hydraulic, noise, or power interrupt tests), (2) in place, onsite, or offsite (e.g. vendor) test measurements, or (3) utilizing vendor engineering specifications.
WCAP-13632, Revision 1,
" Elimination of Pressure Sensor Response Time Testing Requirements," provides the basis and methodology for using allocated sensor response times in the overall verificatio: of the channel response time for specific sensors identified in the WCAP.
The allocations for these sensor response times must be verified prior to placing the sensor in operational service and re-verified following maintenance that may adversely affect response time.
In general, electrical repair work does not impact response time provided the parts used for repair are of the same type and value.
One example where time response could be affected is replacing the sensing assembly of a transmitter.
Response time verification for other sensor types must be demonstrated by test.
3/4.3.3 MONITORING INSTRUMENTATION 3 /4. 3. 3.1 RADI ATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
Alarm / trip setpoints for the containment purge have been established for a purge rate of 5,000 scfm in all MODES and for purge rates of 25,000 scfm and 50,000 scfm in MODES 4, 5,
and 6.
The containment purge setpoints are based on a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.1001-20.2j01), Table 2, 6
Column 1 for these isotopes, and on a X/Q of 5.6 x 10 sec/m at the site boundary.
FARLEY-UNIT 1 B 3/4 3-2 AMENDMENT NO.
INSTRUMENTATION DASES RADIATION MONITORING INSTRUMENTATION (Continued)
The alarm / trip setpoint for the fuel storage pool area has been established based on a flow rate of 13,000 scfm; a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.g001-30.2401), Table 2, Column 1 for these isotopes, and on a X/Q of 5.6 x 10 sec/m at the site boundary.
3/4.3.3.2 MOVABLE INCORE DETECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
For the purpose of measuring F9(Z), FfH, and F a full incore flux map is used.
Quarter-core flux maps, as defined inWCA[-8648, June 1976, may be used in recalibration of the excore neutron flux detection system.
Full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
i FARLEY-UNIT 1 B 3/4 3-2a AMENDMENT NO.
FNP Unit 2 Technical Specifications Changed Pages
_UIliL2 Revision Page 3/43-1 Replace Page 3/4 3-15 Replace l
Page B 3/4 3-2 Replace Page B 3/4/3-2a Add i
)
i I
I l
i
l 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION 4
LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERA 8LE.
{
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1 i
SURVEILLANCE REOUTREMENTS 4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERA 8LE by the performance of the CHANNEL CHECK, CHANNEL Call 8 RATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies show in Table 4.3-1.
4.3.1.2 The logic for the interlocks shall be demonstrated OPERA 8LE prior to each reactor startup unless performed during the preceding 92 days.
The total-interlock function shall be demonstrated OPERA 8LE at least once per 18 months.
4 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip funct 11 be t;-.r.;treted-to be within its limit at least once per 18 months.jon s
Ved ica so" Each shall include at least one logic train such that both logic trains veng-are at least once per 36 months and one channel per function such that eWatueTiTrht;;ted at least once every N times 18 months where N is the ver; g 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, 1
Neutron detectors are exempt from response time testing.
FARLEY-UNIT 2 3/4 3-1 AMENDMENT No. 98 e
~
p ti INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATIO LIMITING CONDITION FOR OPERATION i
3.3.2 The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERA 8LE with their trip
~
setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.
j' APPLICABILITY: As shown in Table 3.3-3 1
f ACTION:
With an ESFAS instrumentation channel or interlock trip setpoint a.
i less conservative than the value shown in the Allowable Values i
column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERA 8LE status with the trip setpoint adjusted consistent with the Trip Setpoint value, b.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
i SURVEILLANCE RE0UIREMENTS 4.3.2.1 Each ESFAS instrumentation' channel shall be demonstrated OPERA 8tE by -
the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNC TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
i 4.3.2.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.
demonstrated OPERA 8LE at least once per 18 months.The total interlock funct YEfipg 444The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ES l be.j- :2;tr;t:I to be Within the limit at least once per 18 months.
verMo(n Each shall include at least one logic train such that both logic trains n Lleast once per 38 months and one channel per function such that Y6#ifoid are noels a Wre at least once per N times 18 months Where N is the vedbed total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels' column of Table 3.3-3.
FARLEY-UNIT 2 3/4 3-15 ANENONENT NO. 97,98 5
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REA m n *nfp sys*pr ann rNemrrore sArr*Y FEATRE AmA???N fNetatwntfAtteM sys+rw (Continued)
)
The _::_.- -: of response time at the specified frequencies provides is completed within the time Limit assumed in the accident a time limite for the Reactor Trip system and Engineered Safety Featur
Response
Actuation system are maintained in Tables 7.2-5 and 7.3-16 of the Farl es respectively.
with response times indicatedNo credit was taken in the analysee for those channels ey[FS o et a liceale.
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3/4.3.3 Mc N T*dR 7Mt1 fMc*ntDO3r*AttCM 3/4.3.3 1 RAMfA?TSM MOMTTeaf*a YMcTatMnrf'1TTau The CPERASILITY of the radiation monitoring channels ensures that 1) radiation levels are continually measured in the areas served by the Ladividual the channele and 2) level trip setpoint is escoeded.the alarm or automatic action is Laitiated when the radiation Alare/ trip setpointe for the conta1 ament purge have been estahliehad for purge rate of 5,000 scia in all MODES and for purge rates of 25,000 ocfm and.
50,000 ocfm in NODES 4, 5, and 4.
release in.which Ze-133 and Er-45 are the pr=d==tamat Leetopee, on values equal to or less than the effluent concentration limite stated in 10 CFR 20,Appendia3(toparagraphe20.1g1-202401), Table 2,Columa1forthese isotopes, and on a X/g of 5.6 m 10 3
ses/n at the ette boundary.
The alare/ trip setpoint based on a flow rate of 13,000 octapfor the fuel storage pool area has been established a release La which Xe-133 and Er-SS are the predominant Leotopee, os concentration values equal to or less than the effluent congyntreties limite stated la 1,0,CFR 20, Appendia % f(to paragraphe 0
- 20. Fj), table 2, Colume 1 erir x for these isotopee, and on a X/g of 5.6 x 10,
20.1001 -
sec/m at the site hemedary.
3 / 4. 3. 3,2 wnrant a flamme -
Iue et
,m The OPERASILITY of the movable inoere detectors with the specified minimum complement of equipment ensures that the measuremente obtained from use of this system accurately represent the spatial neutros flua distribution of the reactor detector used and determining the acceptability of its voltage cu core.
For the purpose of measuring F i8le 8Is,andF a full incere flua map is used.
Q used in recalibration of the encore neutron flum detection system.
Lacore flua maps or symmetric incore thimbles may be used for monitoring the Full gaanRANT POWER TILT RATIO when one Power Range Chamael is inoperable.
rARLaT-Uw!T 2 a 3/6 3-2 AMENOMWFF NO. N e98 i
Unit 2 Page B 3/4 3-2 INSERT A Response time may be verified by actual tests in any series of sequential, overlapping or total channel measurements, or by summation of allocated sensor response times with actual tests on the remainder of the channel in any series of sequential or overlapping measurements.
Allocations for specific pressure and differential pressure sensor response times may be obtained from: (1) historical records based on acceptable response time tests (hydraulic, noise, or power interrupt tests), (2) in place, onsite, or offsite (e.g. vendor) test measurements, or (3) utilizing vendor engineering specifications. WCAP-13632, Revision 1,
" Elimination of Pressure Sensor Response Time Testing Requirements," provides the basis and methodology for using allocated sensor response times in the overall verification of the channel response time for specific sensors identified in the WCAP. The allocations for these sensor response times must be verified prior to placing the sensor in operational service and re-verified following maintenance that may adversely affect response time. In general, electrical repair work does not impact response time provided the parts used for repair are of the same type and value. One example where time response could be affected is replacing the sensing assembly of a transmitter. Response time verification for other sensor types must be demonstrated by test.
I l
3/4.3 INSTRUMENTATION l
3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITTON FOR OPERATION 3.3.1 As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.
APPLICABILITY: As shown in Table 3.3-1.
ACTION:
As shown in Table 3.3-1.
SURVETLT,ANCE REOUIREMENTS 4.3.1.1 Each reactor trip system instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-1.
4.3.1.2 The logic for the interlocks shall be demonstrated OPERABLE prior to each reactor startup unless performed during the preceding 92 days.
The total interlock function shall be demonstrated OPERABLE at least once per 18 months.
4.3.1.3 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be verified to be within its limit at least once per 18 months.*
Each verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified 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.
I l
[
- Neutron detectors are exempt from response time testing.
FARLEY-UNIT 2 3/4 3-1 AMENDMENT NO.
Il
INSTRUMRFTATION 2/1 3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The Engineered Safety Feature 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 channel or interlock trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.
b.
With an ESFAS instrumentation channel or interlock inoperable, take the ACTION shown in Table 3.3-3.
SURVEILLANCE REOUIREMENTS 4.3.2.1 Each ESFAS instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations for the MODES and at the frequencies shown in Table 4.3-2.
4.3.2.2 The logic for the interlocks shall be demonstrated OPERABLE during the automatic actuation logic test.
The total interlock function shall be demonstrated OPERABLE at least once per 18 months.
4.3.2.3 The ENGINEERED SAFETY FEATURES RESPONSE TIME of each ESFAS function shall be verified to be within the limit at least once per 18 months.
Each verification shall include at least one logic train such that both logic trains are verified at least once per 36 months and one channel per function such that all channels are verified at least once per N times 18_ months where N is the total number of redundant channels in a specific ESFAS function as shown in the
" Total No. of Channels" Column of Table 3.3-3.
FARLEY-UNIT 2 3/4 3-15 AMENDMENT NO.
INSTRUMENTATION BASES REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEH INSTRUMENTATION (Continued)
The verification of response time at the specified frequencien provides l
assurance that the reactor trip and ESF actuation associated with each channel is completed within the time limit assumed in the accident analyses.
Response
time limits for the Reactor Trip System and Engineered Safety Features Actuation System are maintained in Tables 7.2-5 and 7.3-16 of the Farley FSAR, respectively.
No credit was taken in the analyses for those channels with response times indicated as not applicable.
Response time may be verified by actual tests in any series of sequential, overlapping or total channel measurements, or by summation of allocated sensor response times with actual tests on the remainder of the channel in any series of sequential or overlapping measurements.
Allocations for specific pressure and differential pressure sensor response times may be obtained from:
(1) historical records based on acceptable response time tests (hydraulic, noise, or power interrupt tests), (2) in place, onsite, or offsite (e.g. vendor) test measurements, or (3) utilizing vendor engineering specifications.
WCAP-13632, Revision 1,
" Elimination of Pressure Sensor Response Time Testing Requirements," provides the basis and methodology for using allocated sensor response times in the overall verification of the channel response time for specific sensors identified in the WCAP.
The allocations for these sensor response times must be verified prior to placing the sensor in operational service and re-verified following maintenance that may adversely affect response time.
In general, electrical repair work does not impact response time provided the parts used for repair are of the same type and value.
One example where time response could be affected is replacing the sensing assembly of a transmitter.
Response time verification for other sensor types must be demonstrated by test.
3/4.3.3 MONITORING INSTRUMENTATION 3 /4. 3. 3.1 RADI ATION MONITORING INSTRUMENTATION e
The OPERABILITY of the radiation monitoring channels ensures that 1) the tadiation levels are continually measured in the areas served by the individual j
channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.
Alarm / trip setpoints for the containment purge have been established for a purge rate of 5,000 scfm in all MODES and for purge rates of 25,000 scfm and 50,000 scfm in MODES 4, 5,
and 6.
The containment purge setpoints are based on a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.100}6~sec/m$
I' Column 1 for these isotopes, and on a X/Q of 5.6 x 10 at the site boundary.
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FARLEY-UNIT 2 B 3/4 3-2 AMENDMENT NO.
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1 INSTPUMENTATION BASES RADIATION MONITOP1NG INSTRUMENTATION Continued) 2 The alarm / trip netpoint for the fuel storage pool area has been established based on a flow rate of 13,000 scfm; a release in which Xe-133 and Kr-85 are the predominant isotopes, on concentration values equal to or less than the affluent concentration limits stated in 10 CFR 20, Appendix B (to paragraphs 20.g001-30.2401), Table 2, Column 1 for these isotopes, and on a X/Q of 5.6 x 10 sec/m at the site boundary.
3/4.3.3.2 MOVABLE INCORE QFTECTORS The OPERABILITY of the movable incore detectors with the specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core.
The OPERABILITY of this system is demonstrated by irradiating each detector used and determining the acceptability of its voltage curve.
For the purpose of measuring F9(Z), Ffg, and F, a full incore flux map is used.
Quarter-core flux maps, asdefinedinWCA[-8648, June 1976, may be used in recalibration of the excore neutron flux detection system.
Full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.
FARLEY-UNIT 2 B 3/4 3-2a AMENDMENT NO.
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.l ATTACIIMENT II Westinghouse letter CAW-94-565, dated January 11,1994, " Application For Withholding Proprietary Information From Public Disclosure," with the following enclosures: Affidavit, Proprietary Information Notice, and Copyright Notice.
WCAP-13632, Proprietary Class 2," Elimination of Pressure Sensor Response Time Testing Requirements," WOG Program MUllP-3040, Revision 1.
WCAP-13787, Proprietary Class 3, " Elimination of Pressure Sensor Response Time Testing
' Requirements," WOG Program MUIIP-3040, Revision 1.
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