ML20040H543

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Proposed Changes to Tech Specs 3.8.E,4.8.E & Tables 3.2.B, 3.2.F,4.2.B,4.2.F & 3.7.1,in Response to NUREG-0737 Items II.F.1,II.B.3,II.F.2,II.K.3.15,II.K.3.22,II.K.3.28 & II.K.3.13
ML20040H543
Person / Time
Site: Peach Bottom  Constellation icon.png
Issue date: 02/09/1982
From:
PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:
Shared Package
ML20040H527 List:
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.3, TASK-2.F.1, TASK-2.F.2, TASK-2.K.3.13, TASK-2.K.3.15, TASK-2.K.3.22, TASK-2.K.3.28, TASK-TM NUDOCS 8202180365
Download: ML20040H543 (15)
v • d • e


Text

._ - - ___ __.

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, ,g TABLE 3.2.B (CONTINUED) .

gm -s MO INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS .

3 07 80 o00 Minimum No.

E 7 Of Operable Number of Instru-Remarks Instrument Trip Function Trip Level Setting ment Channels Pro -

Channels Per vided by Design Trip System (1) l 1 Core Spray Sparger 5 (11.5) psid 2 Inst. Channels Alarm to detect core-to Reactor Pressure spray sparger pipe Vessel d/p break. /

2 Condensate Storage 15'above tank 2 Inst. Channels Provides interlock to Tank Low Level bottom HPCI pump suction l

valves.

i m

l  %

' Suppression Chamber 2 Inst. Channels Transfers HPCI pump 2 15"above normal suction to High Level water level '

suppression chamber.  ;

Transfer RCIC pump 2 Condensate Storage 15' above tank 2 Inst. Channels suction to suppression Tank Low Level bottom chamber b

1 a

TABLE 3.2.B (CONTINUED) .

INSTRUMENTATION THAT INITIATES OR CONTROLS THE CORE AND CONTAINMENT COOLING SYSTEMS .

Minimum No.

Of Operable Number of Instru-Instrument Trip Function Trip Level Setting ment Channels Pro- Remarks Channels Per vided by Design Trip System (1) 1 RCIC Turbine Higl, 1450" H O(2) 2 Inst. Channels Flow 2 1 RCIC Turbine High 3 1 1 seconds 2 Inst. Channels Flow Time Delay 2 RCIC Turbine Com- 1200 deg. F (2) 4 Inst. 3 o partment Wall ]16 Inst.

i )

6 RCIC Steam Line 1200 deg. F (2) 12 Inst. ]

Area Temp.

2 RCIC Steam Line 100> p> 50 psig (2) 4 Inst.

Low Pressure ,

1 HPCI Turbine Steam 1225" H O (3) 2 Inst. Channels Line High Flow 1 HPCI Turbine High 3 i I seconds 2 Inst. Channels Flow Time Delay

4 TABLE 3.2.F SURVEILLANCE INSTRUMENTATION -

Minimum No.

of Operable Type Instrument Indication Channels Instrument and Range Action 2 Reactor Water Level Recorder 0-60" (6) (7)

(narrow range) Indicator 0-60" 1 Reactor Water Level Recorder -165" to +50" (8)

(wide range) 1 Reactor Water Level Recorder -325" to 0" (8)

(fuel zone)

I 2 Reactor Pressure Recorder 0-1500 psig (1) (2) (3)

Indicator 0-1200 psig d

l 2 Drywell Pressure Recorder 0-70 psig (1) (2) (3) 1 Wide Range Drywell Recorder 0-225 psig (8) .

Pressure 1 Subatmospheric Drywell Recorder 5-25 psia (8) .

i Pressure

! 2 Drywell Temperature Recorder 0-400*F (1) (2) (3).

I Indicator 0-400*F 2 Suppression Chamber Water Recorder 0-600*F. (1) (2) (3)

Temperature Indicator 0-400*F 2 Suppression Chamber Water Recorder 0-2 ft. (1) (5)

Level Indicator 0-2 ft.

1 Wide Range Suppression Recorder 1-21 ft. (8)

Chamber Water Level 1

+ = . .

4 TABLE 3.2.F (Cont'd) - SURVEILLANCE INSTRUMENTS Minimum No.

of Operable Type Instrument Indication Channels Instrument and Range Action .

________________________________.___________________________________________________________________c 1 Control Rod Position 28 Volt Indicating )

- Lights )

) (1) (2) (3) (4) 1 Neutron Monitoring SRM, IRM, LPRM )

0-100% )

1 Safety-Relief Valve Acoustic or (8)

Position Indication thermocouple 1 Containment High Recorder 1-108R/hr (8)

Range Radiation i Monitors w

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' I TABLE 4.2.B- '

MINIMUM TEST AND CALIBRATION _ FREQUENCY FOR'CS'CS '

Instrument Channel Instrument Functional Test Calibration Frecuency Instrume.nt Check j

Once/ day I 1) Reactor Water (1) (3) Once/ operating-cycle Level (7) ,

(1) (3) Once/operatincj cycle Once/ day

2) Drywell Pressure .

(7) ,

I Once/ day

3) Reactor Pressure (1) (3) Once/ operating cycle (7) l Once/ operating cycle None
4) Auto Se:quencing NA Timers (1) Once/3 nonths None

! 5) ADS - LPCI or CS Pump Disch. Pressure i Interlocks l l None

('1 ) NA a> 6) Trip System Bus Power Monitors (1) Once/6 months Once/ day

7) Core Spray ,

Sparger d/p 1 (1) Once/3 months None

8) Steam Line High Flow (HPCI & RCIC)

Steam Line High NA Once/ operating cycle None 9)

Flow Timers (HPCI and RCIC)

Steam Line High Once/ operating cycle Once/ day -

10) (1) (3)

Temp. (HPCI & RCIC)

(1) Once/3 months None

11) Safeguards Area High Temp.

(1) Once/3 months None

12) HPCI and RCIC l Steam Line Low Pressure

7_

TABLE 4.2.B'(CONTINUED) 3 MINIMUM TEST AND CALIBRATION FREQUENCY FOR CSCS- k#'

l . . .

Instrument Channel Instrument Functional Test Calibration Frequency - -

Instrument Check.

(1) Once/3 months None. '

13) HPCI Suction Source Levels , ,
14) 4KV Emergency Power Once/ operating cycle !Once/5 years '

None' ( i.-

' 4 System Voltage ,

Relays

?

Once/operati'ng cycle None t

15) ADS Relief Valvec Once/ operating cycle

+

i '- '

Bellows Pressure ,.

Switches ~<

16) LPCI/ ross Connect Once/ refueling cycle N/A N/A Valve Position
17) Condensate Storage Once/3 months Once/ operating cycle None Tank Level (RCIC)(7) t i

P I

9 s..

TABLE 4.2.F UNIT MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION Instrument Channel Calibration Frequency Instrument Check. ,

1) Reactor Water Level Once/ operating cycle Once Each Shift (narrow range)
2) Reactor Water Level Once/ operating cycle Once/ day (wide range)
3) Reactor Water Level Once/ operating cycle Once/ day (fuel zone) .
4) Reactor Pressure Once/6 months Once Each Shift 4
5) Drywell Pressure Once/6 months Once Each Shift
6) Wide Range Drywell Pressure Once/operacing cycle Once/ day Subatmospheric Drywell Pressure Once/ operating cycle Once/ day 7) 8 a3 8) Drywell Temperature Once/6 months Once Each Shift 0%

' 9) Suppression Chamber Temperature once/6' months Once Each Shift

10) Suppression Chamber Water Level Once/6 months Once Each~ Shift i 11) Wide Range Suppression Chamber Once/ operating cycle Once/ day Water Level
12) Control Rod Position NA Once Each Shift ,
13) Neutron Monitoring (APRM) Twice Per Week Once Each Shift
14) Safety / Relief' Valve Position Once/ operating cycle Once/ month Indicator (acoustics)
15) Safety / Relief Valve Position UA* Once/ month Indicator ( ther.aocouple)
16) Safety Valve Position Indicator Once/ operating cycle Once/ month (acoustics)
17) Safety Valve Position Indicator NA* Once/ month T T

TABLE 4.2.F' -

UNIT s

. MINIMUM TEST AND CALIBRATION FREQUENCY FOR SURVEILLANCE INSTRUMENTATION .

. Instrument Channel Calibration Frequency Instrument Check .

(thermocouple)

18) Containment Radiation Monitors Once/ operating cycle Once/ day
  • Perform instrument functional check once per operating cycle.

Y i

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1 3

PBAPS

. r 3.2 BASES (Conti d) trip and the other a downscale trip. There is a fifteen minute delay before the air ejector off-gas isolation valve l is closed. This delay is accounted for by the 30-minute holdup timelof the off-gas before it is released to the stack

, during reactor power operation when the recombiner system is ,

not operating.

Both instruments are required for trip but'the instruments i are so designed that any instrument failure gives a downscale l

trip. The trip settings of the instruments are set so that j the instantaneous stack release rate limit given in Sepcification 3.8 is not exceeded. j Four sets of two radiation monitors are provided which initiate the Reactor Building Isolation function and operation of the standby gas treatment system. Four  !

instrument channels monitor the radiation from the refueling i area ventilation exhaust ducts and four instrument channels monitor the building ventilation below the refueling floor. l Each set of instrument channels is arranged in a 1 out of 2 twice trip logic.

Trip settings of<16 mr/hr for the monitors in the refueling  !

area ventilation exhaust ducts are based upon initiating normal ventilation isolation and standby gas treatment system operation so that none of the activity released during the refueling accident leaves the Reactor Building via the normal ventilation path but rather all the activity is processed by the standby gas treatment system.

Flow integrators are used to record the integrated flow of liquid from the drywell sumps. The alarm unit in each integrator is set to annunciate before the values specified in Specification 3.6.C are exceeded. An air sampling system is also provided to detect leakage inside the primary containment.

l For each parameter monitored, as_ listed in Table 3.2.F, there are at least two (2) chan aels of instrumentation. By l comparing readings between the channels, a near continuous i surveillance of instrument performance is available. Any deviation in readings will initiate an early recalibration, thereby maintaining the quality of the instrument readings.

The recirculation pump trip has been added at the suggestion ,

of ACRS as a means of limiting the consequences of the unlikely occurrence of a failure to scram during an anticipated transient. The response of the plant to this postuleted event fall within the envelope of study events given in General Electric Company Topical Report, NEDO-10349,  ;

dated March, 1971. l 1

l TABLE 3.7.1 (Cont'd.) ,

PRIMARY CONTAINMENT ISOLATION VALVES ,

No. of Power Maximum Action on Operated Valves Operating Normal Initiating Group Valve Indentification Inboard Outboard Time (sec.) Position Signal

~ .

2 5 O GC 2D Drywell equipment drain dis-charge isolation valves

  • 2D Drywell floor drain discharge 2 5 O GC isolation valves Traveling in-core probe 5 NA C SC 2D HPCI steam line drains 2 NA O GC 4A 5A RCIC steam line drains 2 NA O GC RCIC condensate pump drain 2 NA O GC i 5A b 4A HPCI condensate pump drain 2 NA C SC I

Torus water filter pumps 2 NA O GC 2D suction isolation valves 4B HPCI Turbine Exhaust Vacuum 1 15 O GC Breaker Isolation Valve 5B RCIC Turbine Exhaust Vacuum 1 15 O GC Breaker Isolation Valve 4 HPCI steam line exhaust drain 2 NA O GC HPCI steam line warm-up* 1 NA C SC 4

Nitrogen supply to ADS valves 1 NA C SC 6

. PBAPS -

1. Reactor vessel low water level.
2. High drywell pressure.
3. Reactor building ventilation exhaust high radiation.
4. Refuel floor ventilation exhaust high. radiation.

GROUP 4 : T'e h valves in Group 4 are actuated by any one of the following conditions:

1. HPCI steam line high flow.
2. HPCI steam line space high temperature.
3. HPCI steam line low pressure.

GROUP 4A: The valves in Group 4A are actuated by either of the following conditions:

1. Reactor vessel low-low water level.
2. High drywell pressure.

GROUP 4B: The valve in Group 4B is actuated when both of the

-following conditions are present:

1. High drywell pressure.
2. HPCI steam line low pressure.

GROUP 5 : The valves in Group 5 are actuated by any one of the following conditions:

1. RCIC steam line high flow.
2. RCIC steam line space high temperature.
3. RCIC steam line low pressure.

GROUP 5A: The valves in Group 5A are actuated by the following condition:

1. Reactor vessel low-low water level.

GROUP SB: The valve in Group SB is actuated when both of the following conditions are present:

1. High drywell pressure.
2. RCIC steam line low pressure.

GROUP 6 : The valves in Group 6 are actuated by either of_the following conditions:

1. Drywell pressure exceeds nitrogen supply pressure.
2. High nitrogen supply gas flow.

-183-

PBAPS Unit 3 TABLE 3.7.4 (Cont'd.) .

PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen:No. Notes 22 AO-2969A; Check Valve (1)(2)(4)(5)(10) 25 AO-2520; AO-2505; AO-2519; (1)(2)(4)(5)(9)

AO-2521A; AO-2521B 25 AO-2523; Check valves (1)(2)(4)(5) 26 AO-2506; AO-2507 (1)(2)(4)(5)(9)-

26 SV-2671G; SV-2978G (1)(2)(4)(5) t 26 AO-2509; AO-2510; AO-4235 (1)(2)(4)(5)(9) 26 SV-4960B; SV-4961B; SV-4966B (1)(2)(4)(5) 26 SV-8100* (1)(2)(4)(5) 26, 51C SV-0101* (1)(2)(4)(5) 203, 219 39A MO-10-31B; MO-10-26B (1)(2)(4)(5)(9) 39A SV-4949B; SV-4948B (1)(2)(4)(5) 39B MO-10-31A;'MO-10-26A (1)(2)(4)(5)(9) 39B SV-4949A; SV-4948A (1)(2)(4)(5) 41 AO-2-39; AO-2-40 (1)(2)(4)(5)(9) 42 Check Valve 11-16, XV-14A, XV-14B (1)(2)(4)(5)(10) 47 SV-8130A, Check Valve (1)(2)(4)(5) 51A SV-2671E; SV-2978E (1)(2)(4)(5) 51B SV-2671D; SV-29780 Sic SV-2671C; SV-2978C SIC SV-4960C; SV-4961C; SV-4966C 51D SV-2980; Check Valve 52F. AO-2969B; Check Valve (1)(2)(4)(5)(10) 57 AO-2-316; AO-2-317 (1)(2)(4)(5)(9) 102B Breathing Air System-2 Gate (1)(2)(4)(5)(9)

Valves

(1)(2)(4)(5) 203 SV-2671B; SV2978B (1)(2)(4)(5)

. -186-

PBAPS Unit 3 TABLE 3.7.4 (Cont'd.)

PRIMARY CONTAINMENT TESTABLE ISOLATION VALVES Pen No. Notes 22 AO-3969A; Check valve (1)(2)(4)(5)(10) 25 AO-3520; AO-3505; AO-3519; (1)(2)(4)(5)(9)

~AO-3521A; AO-3521B 25 A0-3523; Check Valves (1)(2)(4)(5) 26 AO-3506; AO-3507 (1)(2)(4)(5)(9) 26 SV-3671G; SV-3978G (1)(2)(4)(5) 26 AO-3509; AO-3510; AO-5235 (1)(2)(4)(5)(9) 26 SV-5960B; SV-5961B; SV-5966B (1)(2)(4)(5) 26 SV-9100*

26, 51C SV-9101*

203, 219 39A MO-10-31B; MO-10-26B (1)(2)(4)(5)(9) 39A SV-5949B; SV-5948B (1)(2)(4)(5) 39B MO-10-31A; MO-10-26A (1)(2)(4)(5)(9) 39B SV-5959A; SV-5948A (1)(2)(4)(5) 41 AO-2-39; AO-2-40 (1)(2)(4)(5)(9) 42 Check Valve 11-16, XV-14A, XV-14B (1)(2)(4)(5)(10) 47 SV-9130A, Check Valve (1)(2)(4)(5) 51A SV-3671E; SV-3978E (1)(2)(4)(5) 51B SV-3671D; SV-3978D 51C SV-3671C; SV-3978C 51C SV-5960C; SV-5961C; SV-5966C 51D SV-3980; Check Valve 52F AO-3969B; Check Valve (1)(2)(4)(5)(10) 57 AO-2-316; AO-2-317 (1)(2)(4)(5)(9) 102B Breathing Air System-2 Gate Valves

  • SV-9130B, Check Valve (1)(2)(4)(5) l102B 203 SV-3671B; SV-3978B (1)(2)(4)(5)

-186-

m

, ~.

. PBAPS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.D Mechanical Vacuum Pump 4.8.D Mechanical Vacuum Pump 1.- The mechanical vacuum pump At least once during each' shall be capable of being operating cycle verify isolated and secured on a automatic securing and signal of high radio- isolation of the mechanical activity in the steam vacuum pump.

lines whenever the main steam isolation valves are open.

2. If~the limits of 3.8.D.1 are not met the vacuum pump shall be isolated.

3.8.E High Range Radiation 4.8.E High Range Radiation Monitoring Systems Monitoring Systems-

1. The high range (10Y Ci/cc) 1. The high range ef fluent ,

effluent gas monitors shall gas monitors shall have ,

be operable on the following an instrument check at release paths: least daily, an instrument functional test.at least

a. Unit 2 reactor building monthly, and calibration at exhaust least every fuel cycle
b. Unit 3 reactor building with a known radioactive exhaust source.
c. Plant stack
2. The post accident sampling 2. The operability of the post-station and associated accident sampling station analytical equipment shall and associated analytical be capable of sampling equipment shal] be  ;

and analyzing the reactor verified at least once coolant and containment every six months.

atmosphere.

L

- 209a - ,

5

f

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.8.E (Cont'd) 4.8.E (Cont'd)

3. If the' requirement of specification 3.8.E.1 cannot be satisfied, either restore the equipment to an operable status within 30 days or be in at least hot shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
4. If the requirement of specification 3.8.E.2 cannot be satisfied, confirm within 30 days that alternate arrangements for sampling and analysis of the required samples can be made available within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in the event that such an analysis is needed or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, then restore the complete sampling and analysis capability within 90 days or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

- 209b -

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