ML20095L023

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Proposed Improved TS & Bases,Allowing Flexibility to Install Main Stack Rms (Mod 5386) W/O Need for Addl Licensing Actions & Addressing Annotations to Reflect pre- & post-mod Scenarios,Respectively
ML20095L023
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 12/22/1995
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20095L015 List:
References
NUDOCS 9512290389
Download: ML20095L023 (15)
v • d • e


Text

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Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS

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

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation 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 primary containment isolation capability.

SURVEILLANCE FREQUENCY SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days SR 3.3.6.1.3 ------------------NOTE-------------------

For Function 1.d, radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 18 months i=

i

+

1-SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. 24 months SR 3.3.6.1.6 Calibrate each radiation detector. 24 months 1

SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months

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! PBAPS UNIT 2 %W- Amendment No. 210 9512290389 951222 PDR ADOCK 05000277 P PDR

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Primary Contairunent Isolation Instrumentation l

I APPLICASLE CONDITIONS McBES OR REGUIRED REFERENCED OTNER CHA MELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

1. Main Steam Line isolation
a. Reactor vessel Water 1,2,3 2 0 SR 3.3.6.1.1 2 160.0 l Level -Low Low Low SR 3.3.6.1.2 inches (Levet 1) SR 3.3.6.1.5 SR 3.3.6.1.7 )
b. Main Steam Line 1 2 E SR 3.3.6.1.3 t 850.0 psig  !

Pressure -Low SR 3.3.6.1.7 )

I

c. Main Steam Line 1,2,3 2 per D SR 3.3.6.1.1 5 123.3 paid ,

SR 3.3.6.1.2 F low -H i gh MSL SR 3.3.6.1.5 SR 3.3.6.1.7

d. Main Steam Line -High 1,2,3 2 D SR 3.3.6.1.1 5 15 x Fult i Radiation SR 3.3.6.1.3 Power  !

SR 3.3.6.1.6 Backgroimd SR 3.3.6.1.7

e. Main Steam tunnel 1,2,3 8 0 SR 3.3.6.1.1 5 200.0*F teaperature -High SR 3.3.6.1.2 l SR 3.3.6.1.5 1 SR 3.3.6.1.7
2. Primary Containment isolation
4. Reactor Vessel Water 1,2,3 2 G SR 3.3.6.1.1 t 1.0 inches )

Level -Low (Level 3) SR 3.3.6.1.2 l SR 3.3.6.1.5 SR 3.3.6.1.7

b. Drywell Pressure -High 1,2,3 2 C SR 3.3.6.1.1 s 2.0 psig I SR 3.3.6.1.2 l SR 3.3.6.1.5 4 sa 3.3.6.1.7

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c. Main Stack Monitor 1,2,3 1 F SR 3.3.6.1.1 s 2 x 10 4 I Radiation -High SR 3.3.6.1.2 gCl/cc l SR 3.3.6.1.4 j SR 3.3.6.1.7 j
d. Reactor Building 1,2,3 2 c SR 3.3.6.1.1 s 16.0 sit /hr i Ventitation Exhaust SR 3.3.6.1.3 ,

Radiation -High SR 3.3.6.1.7 '

e. Refueling Floor 1,2,3 2 G SR 3.3.6.1.1 s 16.0 udt/hr l Ventilation Exhaust SR 3.3.6.1.3 .

Radiation -High SR 3.3.6.1.7  !

(continued)

PBAPS UNIT 2 3.3-52 Amendment No. 210 l l

1

Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1 1 (page 3 of 3)

Primary Contalrunent Isolation Instrunentation APPLICABLE CONDIT!0Ns MODES OR REQUIRED REFERENCED OTNER CHAMELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWASLE FUNCTION C0mlTIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

5. Reactor Water Cleanup (RWCU) system Isolation
a. RWCU Ftou -Nigh 1,2,3 1 F SR 3.3.6.1.1 5 1251 rated SR 3.3.6.1.3 flew (23.0 SR 3.3.6.1.7 in-wc)
b. SLC System initiation 1,2 1 M SR 3.3.6.1.7 NA
c. Reactor vessel Water 1,2,3 2 F SR 3.3.6.1.1 a 1.0 inches Level -Low (Level 3) $4 3.3.6.1.2 SR 3.3.6.1.5 st 3.3.6.1.7
6. RHR shutdown Cooling System Isolation
s. Reactor Pressure -Nigh 1,2,3 1 F SR 3.3.6.1.3 s 70.0 pois SR 3.3.6.1.7
b. Reactor vessel Water 3,4,5 2(a) I st 3.3.6.1.1 t 1.0 inches Level -Low (Level 3) SR 3.3.6.1.2 st 3.3.6.1.5 SR 3.3.6.1.7
7. Feedwater Recirculation Isolation
a. Reactor Pressure -High 1,2,3 2 F SR 3.3.6.1.1 5 600 pels sa 3.3.6.1.2 SR 3.3.6.1.5 i st 3.3.6.1.7 i (a) In MODES 4 and 5, provided RHR shutdown Cooling system integrity is maintained, only one channel per trip system with an isolation signal available to one shutdown cooling pum suction isolation valve is required.

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(b) por ,oc % +He insMo1w S IM 5%,

AllmWe value 09 6vectm 2, c is 6 #10 cf-j.. . v v-i a

1 PBAPS UNIT 2 3.3-54 Amendment No. 210

E Primary Containment Isolation Instrumentation 3.3.6.1 l SURVEILLANCE REQUIREMENTS 1

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

1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation Function.
2. When a channel is placed in an inoperable status solely for performance of j required Surveillances, entry into associated Conditions and Required l 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 primary containment isolation capability.

[ .

I SURVEILLANCE FREQUENCY 4

l SR 3.3.6.1.1 Perform CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST. 92 days 1

SR 3.3.6.1.3 ------------------NOTE-------------------

For Function 1.d, radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days

,.. --4:s SR 3.3.6.1.4 Perform CHANNEL CALIBRATION. 18 months

/

/

/ SR 3.3.6.1.5 Perform CHANNEL CALIBRATION. 24 months

/

(

SR 3.3.6.1.6 Calibrate each radiation detector. 24 months SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months

-  % .~ % ~ . . . . - ~ - . - -

- NOTE R

_f-f%or-40-snstk t)de ci Md S'5%, Cl!MNEL CALutATk'N

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PBAPS UNIT 3 *- Amendment No. 214

Primary Containment Isolation instrumentation 3.3.6.1 Table 3.3.6.1 1 (page 1 of 3)

Primary Contairment !aolation Instrumentation APPLICABLE CONDIT!0Ns MODES OR REQUIRED REFERENCE 0 OTHER CHANNELS FROM sPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS sYsfEM ACTION C.1 REQUIREMENTS VALUE

1. Main steam Line Isolation
a. Reactor vessel Water 1,2,3 2 0 st 3.3.6.1.1 2 160.0 Level --Low Low Low st 3.3.6.1.2 inches (Level 1) sa 3.3.6.1.5 SR 3.3.6.1.7
b. Main steam Line 1 2 E SR 3.3.6.1.3 t 850.0 psig Pressure --Low st 3.3.6.1.7
c. Main steam Line 1,2,3 2 per D st 3.3.6.1.1 5 123.3 psid Flow digh Msl sa 3.3.6.1.2 st 3.3.6.1.5 sR 3.3.6.1.7
d. Main steam Line -.High 1,2,3 2 D sa 3.3.6.1.1 5 15 x Fult Radiation SR 3.3.6.1.3 Power i st 3.3.6.1.6 Backgrowuf SR 3.3.6.1.7
e. Main steam Tweet 1,2,3 8 0 sa 3.3.6.1.1 5 200.0*F Teeperature --Nigh SR 3.3.6.1.2 st 3.3.6.1.5 st 3.3.6.1.7 l
2. Primary Contalruent isolation
a. Reactor Vesset Water 1,2,3 2 G st 3.3.6.1.1 1 1.0 inches Level .-Low (Level 3) st 3.3.6.1.2 SR 3.3.6.1.5

$R 3.3.6.1.7

b. Drywell Pressure --Nigh 1,2,3 2 G st 3.3.6.1.1 s 2.0 psig SR 3.3.6.1.2 sa 3.3.6.1.5 I st 3.3.6.1.7 I
c. Main Stack Monitor 1,2,3 1 F sR 3.3.6.1.1 5 2 x 10'8 b Radiation a lgh sR 3.3.6.1.2 gCi/cc sR 3.3.6.1.4 SR 3.3.6.1.7
d. Reactor sullding 1,2,3 2 G st 3.3.6.1.1 s 16.0 aft /hr Ventilation Exhaust st 3.3.6.1.3 Rediation -Nigh SR 3.3.6.1.7
e. Refueling Floor 1,2,3 2 G sa 3.3.6.1.1 s 16.0 aft /hr Ventitation Exhaust sa 3.3.6.1.3 Radiation 4 1gh sa 3.3.6.1.7 (continued) l l

PBAPS UNIT 3 3.3-52 Amendment No. 214

Primary Containment Isolation Instrumentation 3.3.6.1 Toble 3.3.6.1 1 (page 3 of 3)

Primary Contairment isolation Instrumentation APPLICABLE CONDITIONS MODES OR REGulRED REFERENCED OTHER CHANNELS FROM i SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWASLE i COW ITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE j FUNCTION i

5. Reactor Water Cleane (RWCU) System isolation
a. RWCU Flow - Migh 1,2,3 i F SR 3.3.6.1.1 5 1251 rated SR 3.3.6.1.3 flow (23.0 SR 3.3.6.1.7 in we)
b. SLC System initiation 1,2 1 N SR 3.3.6.1.7 NA
c. Reactor vessel Water 1,2,3 2 F SR 3.3.6.1.1 e 1.0 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7
6. RHR Shutdown Cooling System isolation
a. Reactor Pressure -.4tish 1,2,3 1 F SR 3.3.6.1.3 5 70.0 psig SR 3.3.6.1.7
b. Reactor vessel Water 3,4,5 2(a)  ! SR 3.3.6.1.1 t 1.0 inches  ;

Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7

7. Feedwater Recirculation Isolation
a. Reactor Pressure -High 1,2,3 2 F SR 3.3.6.1.1 5 600 psig SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 (a) In MODES 4 and 5, provided RNR Shutdown Cooling System integrity is maintained, only one channel per trip system with an isolation signal available to one shutdown cooling puup suction isolation valve is

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requirg. _ _ . . _ . _ . , _ , , ,

([ gy 9 g e instoHohrn of Mod 53% , the Anotaable blue 09 Suntr> 2 C is N IX IC'cfs.

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PBAPS UNIT 3 3.3-54 Amendment No. 214

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Primary Containment Isolation Instrumentation B 3.3.6.1

BASES APPLICABLE 2.b. Drywell Pressure-Hiah (continued)

SAFETY ANALYSES, LCO, and The Allowable Value was selected to be the same as the ECCS

]. APPLICABILITY Drywell Pressure-High Allowable Value (LC0 3.3.5.1), since

~

this may be indicative of a LOCA inside primary containment.

, This Function isolates the Group II(B) valves listed in l Reference 1.

i 2.c. Main Stack Monitor Radiation--Hiah Main stack monitor radiation is an indication that the release of radioactive material may exceed established limits. Therefore, when Main Stack Monitor Radiation-High j

is detected when there is flow through the Standby Gas l

Treatment System, an isolation of primary containment purge supply and exhaust penetrations is initiated to limit the

< release of fission products. However, this Function is not  :

assumed in any accident or transient analysis in the UFSAR because other leakage paths (e.g., MSIVs) are.more limiting.

1 J

The drywell radiation signals are initiated from radiation detectors that isokinetically sample the main stack i

utilizing sample pumps. Two channels of Main Stack

- Radiation-High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

he Allowable Value is set below the maximum allowable release limit in accordance with the Offsite Dose

! Calculation Manual (ODCM).

This Function isolates the containment vent and purge valves

and other Group III(E) valves listed in Reference 1.

2.d. 2.e. Reactor Buildina Ventilation and Refuelina Floor i Ventilation Exhaust Radiation--Hiah 1

- High secondary containment exhaust radiation is an indication of possible gross failure of the fuel cladding.

The release may have originated from the primary containment due to a break in the RCPB. When Reactor Building or Refueling Floor Ventilation Exhaust Radiation-High is detected, the affected ventilation pathway and primary (continued)

PBAPS UNIT 2 8 3.3-151 Revision No. 0

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'$ The Allowable Value includes both the' pre and post modificat ion (5386) allowable value. Modification 5386 is being installed post ITS implementation due to an installation schedule change.

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Primary Containment Isolation Instrumentation B 3.3.6.1 BASES

} 59RVEILLANCE SR 3.3.6.1.2 REQUIREMENTS (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment.shall be consistent with the assumptions of the current plant specific setpoint methodology.

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The 92 day Frequency of SR 3.3.6.1.2 is based on the reliability analysis described in Reference 7.

(

SR 3.3.6.1.3,SR 'i . 3. 6.1. 4. SR 3.3.6.1.5. and SR 3.3.6.1.6 s

' A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the channel i

responds to the measured parameter within the necessary I range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive i calibrations, consistent with the assumptions of the current setpoint methodology. SR 3.3.6.1.6, however, is only a i calibration of the radiation detectors using a standard

radiation source.

1 y

As noted for SR 3.3.6.1.3, the main steam line radiation ,

i

< detectors (Function 1.d) are excluded from CHANNEL CALIBRATION due to ALARA reasons (when the plant is

  • operating, the radiation detectors are generally in a high radiation area; the steam tunnel). This exclusion is
acceptable because the radiation detectors are passive devices, with minimal drift. The radiation detectors are

- calibrated in accordance with SR 3.3.6.1.6 on a 24 month Frequency.

The 92 day Frequency of SR 3.3.6.1.3 is conservative with a

respect to the magnitude of equipment drift assumed in the setpoint analysis. The Frequency of SR 3.3.6.1.4 is based on the assumption of an 18 month calibration interval in the determination of the magnitude of equipment drift in the

, by setpoint analysis.1The Frequencies of SR 3.3.6.1.5 and SR

  1. i 3.3.6.1.6 are based on the assumption of a 24 month a

calibration intervai in the determination of the magnitude of equipment drift in the setpoint analysis.

(continued)

PBAPS UNIT 2 8 3.3-166 Revision No. 0 l i

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i N I SR 3.3.6.1.4 includes _a Note that prior to the installation of modification 5386, the calibration frequency is 12 months for each radiation monitor.

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Primary Containment Isolation Instrumentation B 3.3.6.1 BASES APPLICABLE 2.b. Drywell Pressure-Hiah (continued)

SAFETY ANALYSES, LCO, and The Allowable Value was selected to be the same as the ECCS APPLICABILITY Drywell Pressure-High Allowable Value (LC0 3.3.5.1), since this may be indicative of a LOCA inside primary containment.

This Function isolates the Group II(B) valves listed in Reference 1.

2.c. Main Stack Monitor Radiation-Hiah Main stack monitor radiation is an indication that the release of radioactive material may exceed established limits. Therefore, when Main Stack Monitor Radiation-High is detected when there is flow through the Standby Gas Treatment System, an isolation of primary containment purge supply and exhaust penetrations is initiated to limit the release of fission products. However, this Function is not assumed in any accident or transient analysis in the UFSAR because other leakage paths (e.g., MSIVs) are more limiting.

The drywell radiation signals are initiated from radiation detectors that isokinetically sample the main stack utilizing sample pumps. Two channels of Main Stack Radiation-High Function are available and are required to be OPERABLE to ensure that no single instrument failure can preclude the isolation function.

. The Allowable Value is set below the maximum allowable release limit in accordance with the Offsite Dose f4678 Calculation Manual (00CM).

This Function isolates the containment vent and purge valves and other Group III(E) valves listed in Reference 1.

2.d. 2.e. Reactor Buildino Ventilation and Refuelino Floor Ventilation Exhaust Radiation-Hiah High secondary containment exhaust radiation is an indication of possible gross failure of the fuel cladding.

The release may have originated from the primary containment due to a break in the RCPB. When Reactor Building or Refueling Floor Ventilation Exhaust Radiation-High is detected, the affected ventilation pathway and primary (continued)

PBAPS UNIT 3 8 3.3-151 Revision No. 0

t 4

1.

4.

^ .

$'(The Allowable value includes both the- pre and post m

/

ITS implementation due to an installation schedule change. ..

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Primary Containment-Isolation Instrumentation B 3.3.6.1 i

n . BASES

. SURVEILLANCE SR 3.3.6.1.R 4

. REQUIREMENTS j (continued) A CHANNEL FUNCTIONAL TEST is performed on each required channel to ensure that the entire channel will perform the intended function. Any setpoint adjustment shall be

consistent with the assumptions of the current plant .

i i specific setpoint methodology.

The 92 day Frequency of SR 3.3.6.1.2 is based on the reliability analysis described in Reference 7.

i SR 3.3.6.1.3. SR 3.3.6.1.4. SR 3.3.6.1.5 and 1 SR 3.3.6.1.6 A CHANNEL CALIBRATION is a complete check of the instrument l

loop and the sensor. This test verifies the channel responds to the measured parameter within the necessary range and accuracy. CHANNEL CALIBRATION leaves the channel adjusted to account for instrument drifts between successive calibrations, consistent with the assumptions of the current setpoint methodology. SR 3.3.6.1.6, however, is only a calibration of the radiation detectors using a standard l radiation source.

As noted for SR 3.3.6.1.3, the main steam line radiation detectors (Function 1.d) are excluded from CHANNEL CALIBRATION due to ALARA reasons (when the plant is operating, the radiation detectors are generally in a high radiation area; the steam tunnel). This exclusion is acceptable because the radiation detectors are passive devices, with minimal drift. The radiation detectors are

~ calibrated in accordance with SR 3.3.6.1.6 on a 24 month Frequency.

The 92 day Frequency of SR 3.3.6.1.3 is conservative with respect to the magnitude of equipment drift assumed in the 4

j setpoint analysis. The Frequency of SR 3.3.6.1.4 is based on the assumption of an 18 month calibration interval in the T determination of the magnitude of equipment drift in the

'TN$6ffTf,3 )_ setpoint analysis.+The Frequencies of SR 3.3.6.1.5 and SR

~

3.3.e.1.0 are based on the assumption of a 24 month

' calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

4 (continued)

PBAPS UNIT 3 8 3.3-166 Revision No O l

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SR 3.3.6.1.4 includes a Note that prior to the installation of modification 5386, the calibration frequency is 12 months for each

-radiation monitor.

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