ML20096F148

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Proposed Tech Specs Base Changes Re Implementation of Main Stack & Vent Stack Radiation Monitoring Sytems
ML20096F148
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 01/16/1996
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20096F146 List:
References
NUDOCS 9601230235
Download: ML20096F148 (11)
v • d • e


Text

. _ _ . _ . . _ . . _ _ . _ . _ _ _ _ . . . _ -___. . _ _ . _ _.. ....- ._ _ . _ _ _ . .

Primary Containment Isolation Instrumentation >

3.3.6.1 i

SURVEILLANCE REQUIREMENTS

NOTES------------------------------------ ,

i 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 -

i 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.

l 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 1 excluded.

Perform CHANNEL CALIBRATION. 92 days l

SR 3.3.6.1.4 ------------------NOTE-------------------

Prior to installation of Modification 5386, CHANNEL CALIBRATION frequency for Function 2.c is 12 months.

l 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 9601230235 DR 960116 ADOCK 05000277 PDR PBAPS UNIT 2 3.3-51 Amendment No. 210 w w.w--m-ew ,+c ! myi*w . e.u-- Tg - g ,m- 4 y., -g.r9,,

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

Primary Containment Isolation Instrunentation l APPLICABLE CONDITIONS l MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM

$PECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

1. Main Steam Line Isolation
s. Reactor vessel Water 1,2,3 2 D SR 3.3.6.1.1 a -160.0 Level - Low Low Low SR 3.3.6.1.2 inches (Level 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 a 850.0 psig Pres gre - Low SR 3.3.6.1.7
c. Main Steam Line 1,2,3 2 per D SR 3.3.6.1.1 s 123.3 psid F low - High MSL S.E 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7
d. Main Steam Line- High 1,2,3 2 0 SR 3.3.6.1.1 s 15 x Futt Radiation SR 3.3.6.1.3 Power SR 3.3.6.1.6 tackground SR 3.3.6.1.7
e. Main Steam Tunnel 1,2,3 8 0 SR 3.3.6.1.1 s 200.0*F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7
2. Primary Containment Isolation
a. Reactor vessel Water 1,2,3 2 G SR 3.3.6.1.1 a 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
b. Drywell Pressure - High 1,2,3 2 G SR 3.3.6.1.1 s 2.0 psig SR 3.3.6.1.2 l

SR 3.3.6.1.5 l SR 3.3.6.1.7 l

l c. Main Stack Monitor 1,2,3 1 F SR 3.3.6.1.1 s2XjHo*

l Radiation - High SR 3.3.6.1.2 pcl/cc SR 3.3.6.1.4 l

SR 3.3.6.1.7 1 d. Reactor Building 1,2,3 2 G SR 3.3.6.1.1 s 16.0 mR/hr I ventitation Exhaust SR 3.3.6.1.3 Radiation - Migh 3.3.6.1.7 l SR

e. Refueling Floor 1,2,3 2 G SR 3.3.6.1.1 s 16.0 mR/hr ventilation Exhaust SR 3.3.6.1.3 Radiation - High SR 3.3.6.1.7 (continued)

PBAPS UNIT 2 3.3-52 Amer.dment No. 210 1

- - - - - - - - - - - - - - 1

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

Primary Containment Isolation Instrumentation APPL 1CASLE COND!TIONS MODES OR REGUIRED REFERENCED OTHER CHANNELS FR(pl SPECIFIED PER TRIP REQUIRED SURVE!LLANCE ALLOWASLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE

5. Reactor Water clearve (RWCU) System Isolation
a. RWCU Flow - High ' 1,2,3 1 F SR 3.3.6.1.1 s 1253 rated SR 3.3.6.1.3 flaw (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 a 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 - High ' '1,2,3 1 F SR Z.3.6.1.3 s 70.J pelg SR 3.3.6.1.7
b. Reactor vessel Water 3,4,5 2(*) l SR 3.3.6.1.1 a 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-
7. Feedwater Recirculation  ;

Isolation l

)

a. Reactor Pressure- High 1,2,3 2 F SR 3.3.6.1.1 s 600 pois 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 RHR Shutdown Cooling System integrity is maintained, only one channel per trip system with an isolation signal available to one shutdown cooling pump suction isolation valve is required.

(b) Prior to the installation of Modification 5386, the Allowable value of Function 2.c is s 1X10' cps.

PBAPS UNIT 2 3.3-54 Amendment No. 210

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 CHA.iNEL 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 3.3.6.2.3 ------------------NOTE-------------------

For Function 1.d, radiation detectors are excluded.

Perform CHANNEL CALIBRATION. 92 days SR 3.3.6.1.4 ------------------NOTE-------------------

Prior to installation of Modification 5386, CHANNEL CALIBRATION frequency for Function 2.c is 12 months.

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 l l

SR 3.3.6.1.7 Perform LOGIC SYSTEM FUNCTIONAL TEST. 24 months I

PBAPS UNIT 3 3.3-51 Amendment No. 214

Primary Containment Isolation Instrumentation  !

3.3.6.1 l

i Table 3.3.6.1 1 (page 1 of 3) . ,

Primary Containment Isolation Instrunentation

=[

)

CONDITIONS APPLICABLE . REQUIRED MODES OR REFERENCED OTHER CHANNELS FROM . i SPECIFIED PER TRIP REQUIRED SURVE!LLANCE ALLOW 48LE ,

FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE i

1. Main Steam Line Isolation
a. Reactor Vessel Water 1,2,3 2 0- SR 3.3.6.1.1 a +160.0

SR 3.3.6.1.7

b. Main Steam Line 1 2 E SR 3.3.6.1.3 a 850.0 psis Pressure - Low SR 3.3.6.1.7 >
c. Main Steam Line 1,2,3 2 per D SR 3.3.6.1.1 s 123.3 paid ,

F L ow - High MSL SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7 j

d. Main Steam Line-High 1,2,3 2 D SR 3.3.6.1.1 s 15 X Futt j Radiation SR 3.3.6.1.3 Power SR 3.3.6.1.6 Background i SR 3.3.6.1.7
e. Main Steam Tunnel 1,2,3 8 D SR 3.3.6.1.1 s 200.0 *F i Tenperature - High SR 3.3.6.1.2  !

SR 3.3.6.1.5 l-SR 3.3.6.1.7 l

2. Primary containment F Isolation >
a. Reactor vessel Water. 1,2,3 2 G SR 3.3.6.1.1 a 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 b.' Drywel1 Pressure - High 1,2,3 2 G SR 3.3.6.1.1 s 2.0 psig SR 3.3.6.1.2 SR 3.3.6.1.5 l SR 3.3.6.1.7

c. Main Stack Monitor 1,2,3 1 F SR 3.3.6.1.1 s2Xj0-*

Radiation - High SR 3.3.6.1.2 pCl/cc "I SR 3.3.6.1.4 SR 3.3.6.1.7

d. Reactor Building 1,2,3 2 G SR 3.3.6.1.1 s 16.0 mR/hr Ventilation 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 mR/hr Ventilation Exhaust SR 3.3.6.1.3 Radiation - High SR 3.3.6.1.7 (continued)

PBAPS UNIT 3 3.3-52 Amendment No. 214

. Primary Containment Isolation Instrumentation 3.3.6.1 1

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

APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED l 0THER CHANNELS FROM l SPECIFIED PER TRIP REQUIRED ' SURVEILLANCE ALLOWABLE .

FUNCTION CONDITIONS SYSTEM ACTION C.1 REeulREMENTS VALUE

5. Reactor Water cleanup i (RWCU) System Isolation
a. RWCU Flow-High 1,2,3 1 F SR 3.3.6.1.1 s 125% rsted ' l SR 3.3.6.1.3 flow (23.0 i SR 3.3.6.1.7 . in-we)  :
b. SLC System Initiation 1,2 1 N SR 3.3.6.1.7 NA i
c. Reactor Vessel Water 1,2,3 2 F SR 3.3.6.1.1 a 1.0 inches Level -Low (Level 3) SR 3.3.6.1.2 SR 3.3.6.1.5 i SR 3.3.6.1.7
6. RHR Shutdown Cooling System Isolation
a. Reactor Pressure-High 1,2,3 1 F SR 3.3.6.1.3 s 70.0 pois SR 3.3.6.1.7 l
b. Reactor Vessel Water 3,4,5 2(a)  ! SR 3.3.6.1.1 a 1.0 inches Level-Low (Level 3) SR 3.3.6.1.2 i SR 3.3.6.1.5 l SR 3.3.6.1.7
7. Feedwater Recirculation Isolation j i
a. Reactor Pressure - High 1,2,3 2 F SR 3.3.6.1.1 s 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 RHR Shutdown Cooling System integrity is maintained, only one channel per trip system with an isolation signal available to one shutdown cooling pump suction isolation valve is required.

(b) Prior to the inst;..lation of Modification 5386, the Allowable Value of Function 2.c is s 1X10' cps. .

PBAPS UNIT 3 3.3-54 . Amendment No. 214

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ATTACHMENT 2

. Pritary Containment Isolation Instrumentation B 3.3.6.1 BASES l 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 1 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 includes both the pre and post modification (5386) Allowable Values. Modification 5386 is being installed post ITS implementation due to an installation schedule change. The Allowable Value is set below the maximum allowable release limit in accordance with the Offsite Dose Calculation Manual (0DCM).

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 Refuelino Floor Ventilation Exhaust Radiation-Hiah l

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 i Refueling Floor Ventilation Exhaust Radiation-High is detected, the affected ventilation pathway and primary ,

1 (continued) l PBAPS UNIT 2 B 3.3-151 Revision No. 2

Pritary Ccntainment Isolation Instrumentation B 3.3.6.1 BASES SURVEILLANCE SR 3.3.6.1.3. SR 3.3.6.1.4. SR 3.3.6.1.5. and REQUIREMENTS SR 3.3.6.1.6 (continued) .

The 92 day Frequency of SR 3.3.6.1.3 is conservative with 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 setpoint analysis. 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. The Frequencies of SR 3.3.6.1.5 and SR 3.3.6.1.6 are based on the assumption of a 24 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

SR 3.3.6.1.7 The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific channel. The system functional testing performed on PCIVs in LC0 3.6.1.3 overlaps this Surveillance to provide complete testing of the assumed safety function. ,

While this Surveillance can be performed with the reactor at power for some of the Functions, operating experience has shown these components will pass the Surveillance when performed at the 24 month Frequency. Therefore, the Frequency was found to be acceptable from a reliability standpoint.  ;

i l

REFERENCES 1. UFSAR, Section 7.3. l

2. NRC Safety Evaluation Report for Amendment Numbers 156 and 158 to Facility Operating License Numbers DPR-44 and DPR-56, Peach Bottom Atomic Power Station, Unit Nos. 2 and 3, September 7, 1990.
3. UFSAR, Chapter 14.
4. NED0-31466, " Technical Specification Screening Criteria Application and Risk Assessment,"

November 1987.

5. UFSAR, Section 4.9.3.

l (continued)

PBAPS UNIT 2 B 3.3-167 Revision No. 2

Pricary 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 (LCO 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 instrumen! 4ihre can preclude the isolation function.

The Allowable Value includes both the pre and post modification (5386) Allowable Values. Modification 5385 is being installed post ITS implementation due to an installation schedule change. The Allowable Value is set below the maximum allowable release limit in acccNance with the Offsite Dose Calculation Manual (0DCM).

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 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 B 3.3-151 Revision No. 2

Primary Containment Isolation Instrumentaticn B 3.3.6.1 ,

1 BASES SURVEILLANCE 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.

The 92 day Frequency of SR 3.3.6.1.2 is based on the '

reliability analysis described in Reference 7.

i 3.3.6.1.3. SR 3.3.6.1.4. SR 3.3.6.1.5. and SR SR 3.3.6.1.6 A CHANNEL CALIBRATION is a complete check of the instrument loop and the sensor. This test verifies the chanr.el responds to the measured parameter within the necessary j range and accuracy. CHANNEL CALIBRATION leaves the channel i adjusted to account for instrument drifts between successive calibrations, consistent with the a::umptions of the current setpoint methodology. SR 3.3.6.1.6, however, is only a calibration of the radiation detectors using a standard 4 radiation source. l As noted for SR 3.3.6.1.3, the main steam line radiation ,

detectors (Function 1.d) are excluded from CHANNEL l 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 setpoint analysis. The Frequency of SR 3.3.6.1.4 is based on the assumption of an 18 month calibration interval in the l determination of the magnitude of equipment drift in the setpoint analysis. 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. The Frequencies of SR 3.3.6.1.5 and SR 3.3.6.1.6 are based on the assumption of a 24 month calibration interval in the determination of the magnitude of equipment drift in the setpoint analysis.

(continued)

PBAPS UNIT 3 B 3.3-166 Revision No. 2

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