Text

Proposed Tech Specs,Providing More Explicit Info & Surveillance Requirements for Main Control Room Environ Control Sys for Actuation Instrumentation
	ML20214A261
Person / Time
Site:	Hatch
Issue date:	11/10/1986
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20214A254	List: ML20214A253; ML20214A261;
References
	TAC-63412, NUDOCS 8611190346
	Download: ML20214A261 (23)
	v • d • e

.-

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION 3/4 3-1 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION 3/4 3-9 3/4.3.3 EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-24 3/4.3.4 REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION 3/4 3-33 3/4.3.5 CONTROL R00 WITHDRAWAL BLOCK INSTRUMENTATION 3/4 3-37 3/4.3.6 MONITORING INSTRUMENTATION Radiation Monitoring Instrumentation 3/4 3-43 l

Seismic Monitoring Instrumentation 3/4 3-47 Remote Shutdown Monitoring Instrumentation 3/4 3-50 Post-Accident Monitoring Instrumentation 3/4 3-53 Source Range Monitors 3/4 3-56 Traversing Incore Probe System 3/4 3-57 Main Control Room Environmental Control System 3/4 3-58 (MCRECS) Actuation Instrumentation Fire Detection Instrumentation 3/4 3-59 Radioactive Liquid Effluent Instrumentation 3/4 3-60a Radioactive Gaseous Effluent Instrumentation 3/4 3-60f 3/4.3.7 TURBINE OVERSPEED PROTECTION SYSTEM 3/4 3-61 3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM Recirculation Loops 3/4 4-1 Jet Pumps 3/4 4-2 Idle Recirculation Loop Startup 3/4 4-3 HATCH-UNIT 2 V Proposed TS/0091q/86-XX 8611190346 861110 PDR ADOCK 05000366 P PDR

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

i i Sk

-A ,

i r3 DC ,

i TABLE 3.3.2-1 e t j

j C: ISOLATION ACTUATION INSTRUMENTATION

se

! >=

-4 VALVE CROUPS MINIMUM NUMBER APPLICABLE n3 OPERATED BY

.' TRIP FUNCTION OPERA 8LE CHANNELS OPERATIONAL SI GMAL( a ) PER TRIP SYSTEM (b)(c) CONDITION ACTION 1

l

1. PRIMARY C088TA110 MENT ISOLATION

s. Reactor Vessel Water Level j

! 1 Low (Level 3) 2, 6, 10, 2 1,2,3 20 (2B21-N680 A, 8, C, D) 11, 12 4

2. Low-Low ( Level 2) 5,

2 1,2,3 20 3 ,

l (2B21-N682 A, 8, C, D) l

3. Low-Low-Low (Level 1) 1 2 1, 2, 3 20

(2821-N681 A, 8, C, D)

b. D rywe l l Pressure - High 2, 6, 7, 10, 2 1,2,3 (2C71-N650 A, 8, C, D) 12,

20

! l

c. Main Steam Line

1. Radiation - High 1, 12, (d) 2 1, 2, 3 21 1

(2D11-k603 A, 8, C, D) l

2. Pressure - Low 1 2

(2B21-N015 A, 8, C, D) 1 22 1

La 3. Flow - High 1 2/line 1, 2, 3

} 32 (2B21-N686 A, 8, C. D) 21 t (2821-N687 A, 8, C, D) 1 j* (2821-N688 A, 8, C, D)

r. (2821-N689 A, 8, C, D)

F

d. Main Steam Line Tunnel

,l Tempe ra tu re - High 1 2/line'** 1,2,3 (2821-N623 A, 8, C, D) 21

} (2821-N624 A, B, C, D) j (2s21-N625 A, 8, C, D) l 1

, (2B21-N626 A, B, C, D) "

e. Condenser Vacuum - Low 1 2 1, 2,,38'8 i

(2B21-N056 A, 8, C, D) 23 !

f. Turbine Building Area Temperature - High 28*8 l

(2061-R001, 2061-R002, 2061-R003, 1 1,2,3 21 !

l 2061-R004)

,s ,

O 15

, v 4 m

.' EL i U! .

c.

k N) 1 s E

j

. O.R ,

C

! t 4

r 3>

h$ .'

=c -

TABLE 3.3.2-1 (Continued) i e C ISOLATION ACTUATION INSTRUMENTATION 2

_4 VALVE GROUPS MINIMUM NUMBER APPLICABLE P0 OPERATED BY OPERA 8LE CHANNELS OPERATIONAL TRIP FUNCTION SIGNAL ( a ) PER TRIP SYSTEM (b)(c) CON 01 TION ACTION

, 2. SECONDARY CONTAINMENT ISOLATION

a. Reactor Building Exhaust Radiation - High 6, 19, 12, *

(2D11-K609 A, B, C, D) 2 1,2,3,5 a nd** 24

6. Drywe l l Pressure - High 2, 6, 7, 10, (2C71-N650 A, B, C, D) 2 1, 2, 3 24 12, *

c. Reactor Vessel Water l Level - Low Low (Level 2) 5* 2 1, 2, 3 24 j (2B21-N682 A, B, C, D) l

d. Refueling Floor Exhaust Radiation - High 6, 10, 12,

2 1,2,3,5 and** 24

}, LJ (2D11-K611 A, B, C, D) l 32 3. REACTOR WATER CLEANUP SYSTEM ISOLATION i T' a. A Flow - High (2G31-N603 A, B) 5 1 1, 2, 3 25 E$

b. Area Temperature - High 5 (2G31-N662 A, D, E, H, J, M) 1 1, 2, 3 25 a

' c. Area Ventilation A Temp. - High 5 1 1,2,3 (2G31-N663 A, D,E,H,J,M; 25 2G31-N661 A, D, E, H J.M; 2G31-N662 A, D, E,H,J,M)

{ d. SLCS Initiation (NA) 5888 NA 1, 2, 3 25 3 e. Reactor Vessel Water Level - Low Low 5,

2 (Level 2) (2821-N682 A, B, C, D) 1, 2, 3 25

! 72

> ,lo, s

.a CL 4

23 D

1 17 .

, ~~

l .

1 x

4 1

TABLE 3.3.2-1 (C*ntinuid)

ISOLATION ACTUATION INSTRUMENTATION ACTION ACTION 20 - Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 21 - Be in at least STARTUP with the main steam line isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 - Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 - Be in at least STARTUP with the Group 1 isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 -

Establish SECONDARY CONTAINNENT INTEGRITY with the standby gas treatment system operating within one hour.

ACTION 25 - Isolate the reactor water cleanup system.

ACTION 26 - Close the affected system isolation valves and declare the affected system inoperable.

ACTION 27 - Verify power availability to the bus at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or close the affected system isolation valves and declare the af fected system inoperable.

ACTION 28 - Close the shutdown cooling supply and reactor vessel head spray isolation valves unless reactor steam dome pressure s 145 psig.

NOTES Actuates the standby gas treatment system. I When handling irradiated fuel in the secondary containment.

a. See Specification 3.6.3, Table 3.6.3-1 for valves in each valve group.

b. A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring tnat parameter,

c. With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

d. Trips the mechanical vacuum pumps.

e. A chanr.el is OPERABLE if 2 of 4 instruments in that channel are OPERABLE.

f. May be bypassed with all turbine stop valves closed.

g. Closes only RWCU outlet isolation valve 2G31-F004.

h. Alarm only.

1. Adjustable up to 60 minutes.

I HATCH - UNIT 2 3/4 3-15 Proposed TS/0091g/86-XX

INSTRUMENTATION MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM (MCRECS) ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.6.7 The MCRECS actuation instrumentation channels shown in Table 3.3.6.7-1 shall be OPERABLE, with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.6.7-2.

APPLICABILITY: As shown in Table 3.3.6.7-1.

ACTION: As shown in Table 3.3.6.7-1.

SURVEILLANCE REQUIREMENTS 4.3.6.7 Each MCRECS actuation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations during the OPERAlIONAL CONDITION and at the frequencies shown in Table 4.3.6.7-1.

HATCH - UNIT 2 3/4 3-58 Proposed TS/0091g/86-XX

Y

-4 i

r4 TABLE 3.3.6.7-1 (SHEET 1 0F 2) 2C MCRECS ACTUATION INSTRUMENTATION .

$E MINIMUM NUMBER

- APPLICABLE

~d OPERABLE CHANNELS OPERATIONAL TRIP FUNCTION PER TRI P SYSTEMf a lf bl ro . CONDITION ACTION

1. Reactor Vessel Water Level -

2 1,2,3 52

,! Low Low Low (Level 1) (c) 2821-N691 A, B, C, D I

2. D rywe l l Pressure - High (c) 2 1,2,3 2E11-N694 A, B,C,D 52

3. Main Steam Line Radiation - High (c) 2 1, 2, 3 2D11-K603 A, B, C, D 53

4. Main Steam Line Flow - High (c) 2/line 1, 2, 3 4 2821-N686 A, B, C, D 53 2821-N687 A, B, C, D 2821-N688 A, B,C,D j 2821-N689 A, B, C, D l 5. Refueling Floor Area Radiation - High (c) i u, 2D21-K002 A, D 1 1,2,3,5,* 54 N

Jh

6. Cont rol Room Air inlet Radiation - High (d) 1 1, 2, 3,5,* 54 a 1Z41-R615 A, B 0"

7. Control Room Air inlet Chlorine Level - High (d)

EI 1Z41-NO22 A, B 1 1,2,3,4,5 55

]

4

)

J i

I O

1 l.i.

M CL h

s

, $3 ss 1

at c >J i

7

TABLE 3.3.6.7-1 (SHEET 2 0F 2)

MCRECS ACTUATION INSTRUMENTATION ACTION ACTION 52 -

Take the ACTION required by Specification 3.3.3.

ACTION 53 -

Take the ACTION required by Specification 3.3.2.

ACTION 54 -

a. With one of the required radiation monitors inoperable, restore the monitor to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of the MCRECS in the pressurization mode of operation.

b. With no radiation monitors OPERABLE, within I hour initiate and maintain operation of the MCRECS in the pressurization mode of operation.

c. The provisions of Specification 3.0.4 are not applicable.

ACTION 55 -

a. With one of the required chlorine detectors inoperable, restore the ,

inoperable detector to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of the MCRECS in the isolation mode of operation.

b. With no chlorine detectors OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the MCRECSs in the isolation mode of operation.

c. The provisions of Specification 3.0.4 are not applicable.

NOTES When handling irradiated fuel in secondary containment.

a. A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition, provided at least one other OPERABLE channel in the same trip system is monitoring that parameter,

b. With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.6.7-1 for that Trip Function shall be taken.

c. Actuates the MCRECS in the control room pressurization mode.

d. Actuates the MCRECS in the control room isolation mode.

HATCH - UNIT 2 3/4 3-58b Proposed TS/0091q/86-XX

h y TABLE 3.3.6.7-2 1

, MCRECS ACTUATl001 INSTRUMENTATION SETPolNTS

C

-4 TRIP FUSICTION TRIP SETPOINT ALLOWASLE VALUC N

1. Reactor vessel Water Level - 2 -113 inches 2 - 113 Inches Low Low Low (Lovei 1)

2. DryweII Pressure - High 5 1.92 psig 5 1.92 psig

3. Mein Steam Line Radiation - High 1 3 x full-power background 5 3 x full-power background

4. Main Steam Line Flow - High 51381 rated flow 5 138% rated flow

5. Refueling Floor Area Radiation - High 5 20 er/ hour 5 20 er/ hour

6. Control Room Air Inlet Radiation - High 51 er/ hour 5 1 er/hou r

7. Control Room Air inlet s 5 ppe chlorine 5 5 ppe chlorine Chlorine Level - High Y.

O 7

X a.

Y s

3 x

N R,

M

. _ _ _ _ _ _ . _ _ _ _ . ____ _ __.____ _ _ . - . . _ _ _ _ __.__m _ _ - . _ _ _ . ..____ _ _ _ _ _ _ _

_ _.._.m. . . _ - . . _ _ _ _ _ _ _ . . _ _ _ _ _ _ .

x .

3=

-4 n TABLE 4.3.6.7-1 I

MCRECS ACTUAT1001 INSTRUMENTATION SURVEILLA8eCE REQUIREMENTS c

Z CHAleNEL OPERATIOMAL CHANNEL FU8eCT 10NAL Q TRIP FUseCTIOel CHECK TEST CHANNEL Call 8 RAT 1000 CONDITIONS IN WHICH N SURVEILLA8eCE REQUIRED

1. Reactor Vessel Water Level - S M R 1, 2, 3 Low Low Low (Level 1)

2. Drywe I I Pressure - High S M R 1,2,3

3. Main Steam Line Radiation - High D W'*8 R 1, 2, 3 N. Mein Steam Line Flow - High S M R 1, 2, 3

5. Refueling Floor Area Radiation - D M'**

High Q 1, 2, 3, 5 *

6. Control Room Air Inlet NA M

Radiation - High R 1,2,3,5,*

7. Control Room Air inlet NA M Chlorine - High R 1,2,3,4,5 Nb us e ,

en Cn Q.

When handling irradiated fuel in the secondary containment,

s. Instrument alignment using a standard current source.

O u

O sa fD E

s Y

O O

to J3 C3 m

e M

>C L

i I

7 i

) >

1

. TABLE 4.3.6.7-1 MCRECS ACTUATION INSTRUMENTATION SURVEILLANCES REQUIREMENTS CHANilEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS IN WHICH

, TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

{ 1. Reactor Vessel S M R 1,2,3 Water Level Low Low Low i

2. Drywell S M R 1,2,3 Pressure-High l 3. Main Steam D W(a) R 1,2,3 Line Radiation-High l

4. Main Steam Line S M R 1,2,3

.i Flow-High ,

5. Refueling Floor D it(a) Q 1,2,3,5,*

Area Radiation-High

, 6. Control Room NA M(a) R 1,2,3,5,*

Air Inlet i Radiation-High

7. Control Room Air NA M R 1,2,3,4,5 i Inlet Chlorine Level-High I

When handling irradiated fuel in the secondary containment

a. Instrument alingment using a standard calibration source.

i l

l l

i i .

IIATCil - UNIT 2 3/4 3-58e i

l

PLANT SYSTEMS 3/4.7.2 MAIN CONTROL ROOM ENVIRONMENTAL CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.7.2 Two independent main control room environmental control (MCREC) systems shall be OPERABLE.

APPLICABILITY: CONDITIONS 1, 2, 3, 4*, 5, and **.

ACTION:

a. With one main control room environmental control system inoper-able, restore the inoperable system to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. With both main control room environmental control systems inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.2 Each main control room environmental control system shall be demonstrated OPERABLE:

a. At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that the control room air temperature is s 105*F.

b. At least once per 31 days, by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes,

c. At least once per 18 months or (1) after any structural main-tenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any venti-lation zone communicating with the system by:

1. Performing a visual inspection of the system and all associated components before each leak test in accordance with Section 5 of ANSI N510-1975.

l

Isolation mode only required to be OPERABLE.

- When handling irradiated fuel in secondary containment.

HATCH - UNIT 2 3/4 7-6 Proposed TS/0092q/86-XX i

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

3. Verifying that on each of the below pressurization mode actuation test signals, the system automatically switches to the pressurization mode of operation and maintains the main control room at a positive pressure of 2 0.1 inch W.G. relative to the adjacent Turbine Building during system operation at a flow rate s 400 cfm.

a) Reactor vessel water level - low low low b) Drywell pressure - high c) Refueling floor area radiation - high d) Main steam line radiation - high e) Main steam line flow - high f) Co, trol room intake monitors radiation - high

! 4. Verifying that on a high chlorine concentration actuation test signal, the system automatically switches to the isolation mode of operation.

f. After each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter banks remove 2 99% of the DOP when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 cfm i 10%.

g. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorbers remove 2 99% of a halogenated hydrocarbon refrigerant test gas when they are tested in place in accordance with ANSI N510-1975 while operating the system at a flow rate of 2500 cfm i 10%.

I HATCH - UNIT 2 3/4 7-8 Proposed TS/0092q/86-XX

__ _ _ _ _ _ _ _ _ _ _

v t e Letter Sequence Other
TAC:63412, (Open)
Initiation Request, Request Acceptance... Administration Questions Answers Results Approval... Other: ML20214A261
MONTHYEAR1986-11-10 [Table View]

ML20214A261

Text

Navigation menu

Search