ML20063D096

Proposed Tech Specs Re Main Control Room Intake Air Radiation Monitors & Administrative Change to Seismic Monitoring Instrumentation Section

ML20063D096
Person / Time
Site:	Peach Bottom
Issue date:	01/26/1994
From:	PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20063D091	List: ML20063D088 ML20063D096
References
NUDOCS 9402070331
Download: ML20063D096 (8)

Text

.

Unit 2 PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS  ;

3.2.D. Radiation Monitorina 4.2.D. Ecdiation Monitorina Systems-Isolation and Systems-Isolation and Initiation Functions Initiation Functions ,

12 Reactor Buildino Ipolation 1. Reactor Buildind Isolation and Standby Gas Treatment and Standby Gas Treatment gyptem System The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-Table 3.2.D. brated and checked as indi-cated in Table 4.2.D. _.

2. Main Control Roo.E System logic shall be The limiting conditions for functionally tested as operation are given in indicated in Table 4.2.D.

Table 3.2.D.

2. Main Control Room '

E. Drvwell Leak Detection Instrumentation shall be The limiting conditions of functionally tested, operation for the instru- calibrated and checked as mentation that monitors indicated in Table 4.2.D.

drywell leak detection are ,

given in Section 3.6.C, E. Drvwell Leak Detection

" Coolant Leakage".

Instrumentation shall be calibrated and checked as indicated in table 4.2.E.

-)

i l

- i j

9402070331-940126 I PDR ADOCK 05000277 +l

.p. PDR L

, . _ . . ~ - . =. .. . ... . . . . -

I

. 1

Unit'3  !

. PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.2.D. Badiation Monitorina 4.2.D. Radiation Monitorina Systems-Isolation and Systems-Isolation and ,

Initiation Functions Initiation Functions I i

1. Reactor Buildina Isolation 1. Reactor Buildina Isolation and Standby Gas Treatment and Standby Gas Treatment System System l The limiting conditions Instrumentation shall be for operation are given in functionally tested, cali-Table 3.2.D. brated and checked as indi- U cated'in Table 4.2.D. I

2. Main Control Room System logic shall be  ;

The limiting conditions for functionally tested as j operation are given in indicated in Table 4.2.D.

Table 3.2.0.  ;

2. Main Control Room E. Drvwell Leak Detection Instrumentation shall be -

The limiting conditions of functionally tested, operation for the instru- calibrated and' checked as mentation that monitors indicated in Table 4.2.D.

drywell leak detection are '

given in Section 3.6.C, E. Drvwell Leak Detection

" Coolant Leakage".

Instrumentation shall be -

calibrated and checked as indicated in table 4.2.E.

Y t

h

. :i 5

l

^

k 2

- Unit 2.

- .~

PBAPS TABLE 4.2.D -

MINIMUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS .

Instrument Functional Instrument-Instrument Channels Test Calibration Check (2)

1) Refuel Area Exhaust (1) Once/3 months - once/ day-  ;

Monitors - Upscale

2) Reactor Building Area (1) Once/3 months Once/ day

3) Main Stack Monitor Once/3 months Once/12 months. Once/ day

-k as described in f* 4.8.C.4.a

4) Main Control Room Once/3 months Once/18 months once/ day as described in 4.11.A.5 Locric System Functional Test (4) (6) Freauency

1) Reactor Building Isolation Once/ Operating Cycle

2) Standby Gas Treatment Once/ Operating Cycle System Actuation 1

J 3

• i b

- g ->r, . ....,-.,.._o,-.._ s. m..m-4 . , . , . . . . . , ,,r... , , ..m, ., . .---e .. . . . - . . - , , _ , , . . ...s, . , , , , . , _ . , , . . _ _ . . , -

Unit 3 PBAPS ' *

~

TABLE 4.2.D .. '

[

MINIMUM TEST & CALIBRATION FREOUENCY FOR RADIATION MONITORING SYSTEMS ,

Inctrument Functional Instrument' -

Instrument Channels Test Calibration Check (21 -

1) Refuel Area Exhaust (1) Once/3 months Once/ day Monitors - Upscale

2) Reactor Building Area (1) Once/3' months once/ day e

- 3) Main Stack Monitor Once/3 months Once/12.nonths . Once/ day E3 as described in

- i' 4.8.C.4.a 4)- Main Control Room Once/3 months Once/18 months Once/ day i as described in ,

4.11.A.5 Y

Lonic System Func!:ional Test (4) (6) Frecuency

1) Reactor Building Isolation Once/ Operating Cycle

2) Standby Gas Treatment- Once/ Operating Cycle System-Actuation i

. :i 8

m, 3e - . - . - - , . - ~ . , -<,-,.--e

- e+ . --, ...- . - , . . . - . -

-~. - - . - , - - . . . . . . . . . - - , , . . , - - . . - . - ..e,,.~-- w., r+<. - ~, - ~ - . + ~ . , __

- - ..- .- . - . - ~ . - - . . - - - _

.s Unit 2- 1

. PBAPS.

j Ll!ETJEg_Q_Q@ITIONS FOR OPERAT1011 SURVETLTANCE REOUIREMENTS f

b. The results of laboratory d. A dry gas purge shall .

I carbon sample analysis be provided to the filters  !

shall sh w 90i_ radioactive to insure that the methyl. iodide removal at relative humidity in'the ,

a velocity within 20% filter systems does not  !

of syctem design, 0.05 exceed 70% during idle .I to 0.15 mg/m3 inlet periods. l methyl iodide concentra- 'i tion, 2 95% relative e. A sample of the charcoal- >

humidity and 2 125 degrees F, filter shall be analyzed once ,

or that filter train shall per year to assure halogen-not be considered operable. removal efficiency of at-least 99.5 percent.

c.-Fans shall be shown to .

operate at approximately 3. Once every 18 months automatic l 3,000 CFM 300 CFM initiation of control room j (design flow for the emergency ventilation, from filter train). all designed initiation  :

signals shall be demonstrated. l

5. The main control toom ventilation radiation 4. Operability of the main -:

r~'itors, which monitor main control room ventilation  !

- cs .t ol room ventilation radiation monitors and flow .i radiation levels, shall switches shall be functionally i be operable at all times tested every 3 months. l when secondary containment is required. 5. The main control room I radiation monitore shall be .j

a. One radiation monitoring calibrated electronically and j

. channel may be inoperable for "ith a known radioactive j 7 days, as long as the 3rce positioned in a  !

remaining radiation monitoring ... producible geometry with channel maintains the respect to the sensor every 18 capability of initiating months.  ;

emergency ventilation on any designed trip functions. 6. The main control room 1 ventilation supply flow

b. A trip system is operable when switches shall be calibrated  !

1 of 2 channels is available to every 18 months. i provide its trip function and i the inoperable channe: is -l placed in its tripped  !

condition. If a cuannel is ~ j inoperable or placed in its -j ^

tripped condition in both ,

l trip systems, then emergency ventilation must be initiated l 6 and maintained.

r

)

.i

-233a-

f t

WE -

k s. . - - ~ - , - - - - -,c, - - - a n , - .-

. .. ~ . - . . . - _ . , -- - . .

r

- Unit 3  ;

. PBAPS ,

. -E I

LIMITIh1G-CONDITIONSFOROPERATION SURVEILLANCE REOUIREMENTS

b. The results of laboratory .d. A dry gas purge shall ,

carbon sample analysis be provided to the filters i shall show 90% radioactive to insure that the .

L methyl iodide removal at relative humidity in the a velocity within 20% filter systems does not of system design, 0.05 exceed 70% during idle l to 0.15 mg/m3 inlet periods.

methyl iodide concentra- i tion, 2 95% relative e. A sample of the charcoal humidity and 2 125 degrees F, filter shall be analyzed once ,

or that filter train shall per year to assure halogen .l not be considered operable. removal efficiency of at least 99.5 percent.  !

c. Fans shall be shown to  !

operate at approximately 3. Once every 18 months automatic.

3,000 CFM 300 CFM initiation of control roon (design flow for the emergency ventilation, from filter train). all designed initiation j sf ~nals shall be demonstrated. 3

5. The main control room ventilation radiation 4. Operability of the main .;

monitors, which monitor main control room ventilation i control room ventilation radiation monitors-and flow I radiation levels shall switches shall be functionally. j be operable at all times tested every 3Lmonths. ';

when secondary cantainment is  :

required. 5. The main control room radiation monitors shall be

a. One radiation monitoring calibrated electronically.and channel may be inoperable for- with a known radioactive' 7 days, hs long as the source positioned in a remaining radiation monitoring reproduciale geometry with channel maintains Se respect to the sensor every 18 capability of iniv - ing months.

emergency ventilat. a, on any designed trip functions. 6. The main control room ventilation supply flow j

b. A trip system is operable when switches shall be calibrated 1 of 2 channels is available to every 18 months.

provide its trip function and the inoperable channel is placed in its tripped

condition. If a channel is j inoperable or placed in its tripped condition in both j

trip systems, then emergency ventilation must be initiated and maintained.

j i

)

-233a- ]

i

..J Unit 2 l J

PBAPS 3.11 EMU l I

A. liain Control Room Emerrency Ventilation System The control room emerEency ventilation system (CREV) is designed to filter the  ;

control room intake air during control room isolation conditions. The CREV system -l is designed to automatically start upon receipt of control room isolation signalc ;

and to maintain the control room at a positive pressure so that all leakage should be out-leakage.

High efficiency particulate absoluto (HEPA) filters are installed before the  ;

charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal  !

adsorbers are installed to reduce the potential intake of radiciodine to the l control room. The in-place test results should indicate a system leak tightness of less than 1 percent bypass leakage for the charcoal adsorbers and a HEPA efficiency of at least 99 percent removal of DOP particulates. The laboratory carbon sample test results should indicate a radioactive methyl iodide removal j efficiency of at least 90 percent for expected accident conditions. If the ef ficiencies of the HEPA filters and charcoal adsorbers are as specified, the resulting doses will be less than the allowable levels stated in Criterion 19 ,

of the Gener11 Design Criteria for Nuclear Power Plants, Appendix A to 10.CFR l Part 50. j One main control room emergency ventilation air supply fan provides adequate ventilation flow under accident conditions. Should one emergency ventilation air supply fan and/or fresh air filter train be out of service during reactor operation, the allowable repair time for 7 days is justified.

At least 1 of 2 channels per trip system in the Control Room Ventilation Radiation Monitoring System for indication and alarm of radioactive air being drawn into the main control room is considered adequate, provided that 3 of the 4 channels are available. With one channel of control room radiation monitoring inoperable _

the capability of automatically initiating emergency ventilation on receipt of  ;

any trip signal is still maintained and a > time is the ability to manually initiate emergency ventilarion lost. Therefore, the allowable time for repair of 7 days is justified. When one (1) radiation monitoring channel in both trip systems are inoperabic, then emergency ventilation shall be initiated and maintained. Main control room emergency ventilation ir .* tiated when a trip signal from the radiation detectors is given via high radt. tion or ,

downscale/ failure signal (one out of two twice logic) or loss of divisional power -

to local radiation monitoring system panel. Main control room emergency ventilation is also initiated on a low flow signal from one of two flow switches in the main control roon normal supply af ter a time delay.

-235-

a. , . _ _ _.

3 3

Unit 3  !

.\

2

. PBAPS

'3.11 BASES. l l

A. Hpin Control Room Emerrenev Ventilation Svsteg  !

l t

The control-room emergency ventilation system (CREV) is designed to filter thi  !

control room intake air during control room isolation conditions. The CREV system ,

is designed to automatically start upon receipt of control room isolation signals sud to maintain the control room at a positive pressure so that all Icakage j should be out-leakage. j t

High efficiency particulate absolute (HEPA) filters are' installed before the charcoal adsorbers to prevent clogging of the iodine adsorbers. The charcoal adsorbers are installed to reduce the potential intake of radioiodine to.the  ;

control room. The in-place test results should indicate a system leak tightness  !

of less than 1 percent bypass Icakage for the charcoal adsorbers and a HEPA .!

efficiency of at Icast 99 percent removal of DOP particulates. The laboratory .l carbon sample test results should indicate a radioactive methyl iodide removal {

efficiency of at least 90 percent for expected accident conditions. If the [

efficiencies of the HEPA filters and charcoal adsorbers are as specified, the  !

resulting doses will be less than the allowable levels stated in Criterion 19 l of the Cencral Design Criteria for Nuclear Power Plants, Appendix A to 10 CFR l Part 50.

One main control room emergency ventilation air supply fan provides adequate  !

ventilation flow under accident conditions. Should one emergency ventilation ,

air supply fan and/or fresh air filter train be out of service during reactor ,

operation, the allowabic repair time for 7 days is justified. [

i At least 1 of 2 channels per trip system in the Control Room Ventilation Radiation  ;

Monitoring System for indication and alarm of radioactive air being drawn into the main control room is considered adequate, provided that 3 of the 4 channels are available, With one channel of control room radiation moaitorint inoperable the capability of automatically initiating emergency ventilation on receipt of any trip signal is still maintained and at no time is the ability to manua13y t

initiate emergency ventilation lost. Therefore, che allowable time for repair of 7 days is justified. When one (1) radiation monitoring channel in both trip ,

systems are inoperable, then emergency ventilation shall be initiated and  ;

maintained. Main control room emergency ventilation is initiated when a trip signal from the radiation detectors is given via high radiation or downscale/ failure signal (one out of two twice logic) or loss of divisional power -

I to local radiation monitorin- vstem panel. Main control room emergency 'l ventilation is also initiated un a low flow signal from one of two flow switches in the main control room normal supply after a time delay. ,

l

-235- i

, - , - . . r.., n, - w -. .,

r ,e., ., - ,