ML20067B977

Proposed Tech Specs Associated W/Relocation of Reactor Trip & ESFAS Response Time Limits

ML20067B977
Person / Time
Site:	Farley
Issue date:	02/15/1994
From:	SOUTHERN NUCLEAR OPERATING CO.
To:
Shared Package
ML20067B970	List: ML20067B968 ML20067B977
References
NUDOCS 9402250223
Download: ML20067B977 (5)

Text

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Joseph M.

Parley IJuclear Plant - Unita 1 and 2 Technical Specification Changes Associated with Relocation of Reactor Trip and Engineered Safety Feature Actuation System Bonponso Timo 1,lmite i

Ed20 ChanDff._.131L(IMC112DE Unit 1 RemoW_Page Inacrl__Enge 3/4 3-1 3/4 3-1 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-11 3/4 3-15 3/4 3-15 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 j

3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32 U 3/4 3-2 D 3/4 3-2 l

Unit 2 ReRQVu_Enge InteLLtn29 3/4 3-1 3/4 3-1 3/4 3-10 3/4 3-10 3/4 3-11 3/4 3-11 3/4 3-15 3/4 3-15 3/4 3-29 3/4 3-29 3/4 3-30 3/4 3-30 3/4 3-31 3/4 3-31 3/4 3-32 3/4 3-32 D 3/4 3-2 B 3/4 3-2 l

• (Revised February 1994)

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JM. 3 IH2TEGEUTATION PASES EEACTOR TRIP SYSTEM AND ENGINEEPED SAFETY FEATUBE ACTU EION SYSTEM IHETEUlEUTATION (Continued)

The measurement of response time at the specified frequencies provides 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 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 times.

2LLL.3 112 ult 9Rl!Ki INETEUliEUTATl.QU ad. 3. 3.1 Pl>RIATl91LMQHI.IRRIFG INSTitVHERTMICU The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual l

channels and 2) the alarm or automatic action is initiated when the radiation l

level trip setpoint is exceeded.

Alarm / trip setpoints for the containment purge have been established for 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 (toparagraphs20.10gl-20)2401), Table 2, Column 1 for these isotopes, and on a X/Q of 5.6 x 10 sec/m at the site boundary.

The alarm / trip setpoint for the fuel storage pool area has been established based on a flow rate of 13,000 ccfm; 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 ;6 20.203), Table 2, Column 1 values for these isotopes, and on a X/Q of 5.6 x 10 sec/m at the site boundary.

ALLLL2_MQYAELE IRCOEE_IITECIDED i

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 P un. @g, and F a full incore flux map g

yy is used.

Quarter-core flux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system.

Full incore flux maps or symm=Lilo lacore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.

FARLEY-UNIT 1 B 3/4 3-2 AMENDMENT NO.

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llL 3 IHSTRUMENTAT1011 BASES t

REACTRE TRIP SYSTEM AND_.EUGINEERED SAFETY FEhTURE ACTUATION SYSTEM 11GTP,UMENTAIlQU (Continued)

The measurement of response time at the specified frequencies provides 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 i

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 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 times.

3dJ. 3 MQ11LTORING IDATMBEUTAIlQM 3 / 4. 3. 3. LEbD1hTlQ1LEQUITRER!Q_llsIRUMEUTATI GU 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 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 w Tch Xo-133 and Kr-85 are the predominant isotopes, on concentration values equ,1 to or less than the effluent concentration limits stated in 10 CFR 20, AppendixB(toparagraphs20.10g1-202401), Table 2, Column 1 for these 3

isotopes, and on a X/Q of 5.6 x 10 sec/m at the site boundary.

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

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predominant isotopes, on concentration values equal to or less than the effluent concentration limits stated in in CFR 20, Appendix B, (to paragraphs 20.1001 6 20.203), Table 2, Column 1 values for these isotopes, and on a X/Q of 5.6 x 10 sec/m at the site boundary.

3/4.3.3.2 MOX5 ELE INCORE DETECTORE The OPERABILITY of the movable incere 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 r no, @n, and F a full incore flux map g

xy is used.

Quarter-core flux maps, as defined in WCAP-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 3-2 AMENDMENT NO.

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INSTRUMENTATION g Gin ec1 to Tables 'T.2.-6 oncl 'l.3-lb BASES of 4-he Rrk

...............................y FS A %....ve s p e ch,Ne ly.

REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTJATION SYSTE INSTRUMENTATION continued) s The measurement of response time at the specified frequencies provides assurance that the reactor trip and ESF actuation associated with each channel is completed within the time limit assumed in the accident analyses.arseAT No credit was taken in the analyses for those channels with response times "N

indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total enannel 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 times.

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 - 20.2401), Table 2.

Column 1 for these isotopes, and on a X/Q of 5.6 X 10-6 sec/m3 at the site boundary.

i The alarm / trip setpoint for the fuel storage pool area has been established l 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 8 (to paragraphs 20.1001 - 20.2401), Table 2, Column 1 for these isotopes, and on a X/Q of 5.6 X 10-6 sec/ M at the site boundary.

3/4.3.3.2 MOVABLE INCORE DETECTOR 1 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 Fn(Z), F g, and Fry a full incore flux map N

is used.

3 Quarter-core flux maps, as defined in WCAP-8648. June 1976, may be used in recalibration of the excore neutron flux detection system.

Full incore flux maps or symetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.

FARLEY-UNIT 1 8 3/4 3 2 AMENDMENT NO. 26, 100

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i ys INSTRUMENTATION g p p tathed ;n n h}es, 7, y Q -7,3 g MSES tof arley FSAR 7 <cs pecMely.

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1 REACTOR TRIP SYSTEM AND ENGINEERED SAFETY FEATURE ACTUATION 5, TEM f

INSTRUMENTATION (Continued)

The measurement of response time at the specified frequencies provides {

assurance that the reactor trip and ESF actuation associated _with each channel is completed within the time limit assumed in the accident analyses.gsgi 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 times.

3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION

)

l The OPERABILITY of the radiation monitoring channels ensures that 1) the i

radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiate 6 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 - 20.2401), Table 2, Column I for these isotopes, and on a X/Q of 5.6 X 10-6 sec/m3 at the site boundary.

Thealarm/tripsetpointforthefuelstoragepoolareahasbeenestablishedI 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 20.1001 - 20.2401), Table 2, Column 1 for these isotopes, and on a X/Q of 5.6 X 10-6 sec/m3 at the site boundary.

3/4.3.3.2 MOVABLE INCORE DETECTORS I

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 demon %trated by irradiating each detector used and determining the acceptability of its voltage curve.

For the purpose of measuring F (Z), FfH, and Fx5 a full incore flux map Q

is used.

Quarter-core flux maps, as defined in WCAP 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.

rapi rY-UNIT ?

B 3/4 3-2 AMENOMENT NO.

92

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