Text

Proposed Tech Specs Making Administrative Changes to Eliminate Differences Between Units 1 & 2 Tech Specs
	ML20012E501
Person / Time
Site:	Limerick
Issue date:	03/20/1990
From:	; PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
To:	;
Shared Package
ML20012E493	List: ML20012E492; ML20012E501;
References
	NUDOCS 9004050273
	Download: ML20012E501 (30)
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L ATTACHMENT 2 !

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LIMERICK GENERATING STATION -

UNIT 1 i

Docket No. 50-352 License No. NPF-39 .

PROPOSED TECHNICAL SPECIFICATIONS CHANGES 4

LIST OF ATTACHED PAGES ListofChanges-(2Pages) 3/4 3-16 3/4 7-4 3/4 3-31 3/4 7-5 3/4 3-15 3/4 7-6 3/4 6-50 B 3/4 7-la 3/4 3-68 xiii ;

3/4 3-70 xiv 3/4 3-71 xx1 3/4 3-72 3/4 8-1 3/4 6-54 3/4 8-la 3/4 7-7 3/4 8-2 B 3/4 6-5 3/4 8-2a 3/4 6-52 B 3/4 8-1 3/4 7-2 B 3/4 4-3 3/4 7-3 6-16 l .

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' h'DR ADOCK 05000352 PDC g

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LIST Of CHANGES !

h TS Section Change l

1. 3/4 3-16 T 3.3.2-1 Revise Note *.as shown, t

3/4 3-31 T 4.3.2.1-1 Revise Note

as shown.

Make i symbol a superscript in item 7.c.1 and 2. :

(editorial). j 3/4 3-15 T 3.3.2-1 Make i symbol a superscript in item 7.c.1 and 2.

i (editorial).

3/4 6-50 3.6.5.2.2 Revise Note

as shown. i Make " Operational Condition" all capitals (editorial). l

2. 3/4 3-68 4.3.7.2.2 Revise as shown. I 3/4 3-70 T 3.3.7.2-1 Revise measurement range of items 1.c.1) '

and 3.a. as shown. :

Addlocationtoitems1.c.1)and4.

Change 117 to 177 in item 3.a(editorial).

Delete underline under OPERABLE in ,

Note ***(editorial). i 3/4 3-71 T 4.3.7.2-1 Change 117to177initem1.a.3)(editorial).

3/4 3-72 T 4.3.7.2-1 Changes " activities" to " activates" in item 1.c.1) (editorial). ;

3. 3/4 6-54 4.6.5.39 Delete " Prior to initial criticality of Unit 2 or." t 3/4 7-7 4.7.2e.3. Delete

and Note *.

B 3/4 6-5 3/4.6.5 Delete " prior to initial criticality of Unit 2 or."

4. 3/4 6-52 3.6.5.3 Add "-CO MON SYSTEM" to title.

Make " Operational Condition" all capitals in ACTIONS a.2. and b. (editorial). ,

i 3/4 7-2 3.7.1.1 Change " general" to " generator" in Note * (editorial). ;

l 3/4 7-3 3.7.1.2 Add "-COMON SYSTEM" to title (editorial). !

( This change approved in Amendment 27 but i not included on issued TS page. ;

1 j 3/4 7-4 3.7.1.3 Add " ACTION: (Continued)" to title (editorial).

3/4 7-5 3.7.1.3 Make " Operational Condition" all capitals in ACTION c. (editorial).

3/4 7-6 3.7.2 Add "- CO MON SYSTEM" to title.

Make " Operational Condition" all capitals in ACTION c. (editorial).

B 3/4 7-la B 3/4.7.2 Add "COMON SYSTEM" to title.

1 Page 1 of 2 '

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.' 1. - . j LIST OF CHANGES (Cont'd)

P, age TS Section- Change

4. xiii Index Add "-CO M ON SYSTEM" to SGIS.

(Cont'd). UnderlineINDEXtitle(editorial). l xiv Index Add "-CO W ON SYSTEM" to CREFAS.

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xx1 Index Add "-CO M ON SYSTEM" to CREFAS.

Change page number "B 3/4 7-1" to "B 3/4 7-la" i for Sections 3/4.7.2.and 3/4.7.3 (editorial).

5. 3/4 8-1 3.8.1.1 Change 92 dr.ys to 30 days. 1 Add "See also ACTION e." to ACTION a. 4 Delete " Perform requirements of ACTION e." from -

and add "See also ACTION e." to ACTION b.

Delete comma after " maintenance" in ACTION a. t (editorial). j 3/4 8-la 3.8.1.1 Add "See also ACTION e." to ACTION c. and '

ACTION d. -

Delete comma after " maintenance" in ACTION d.

(editorial).

Delete "3 4.8.1 A.C. SOURCES" and "A.C. RT3 6MRATING" from titles and add

" ACTION: (Continued)" to titles (editorial).

3/4 8-2 3.8.1.1 Revise ACTION e. as shown.

Add "Sec also ACTION e." to ACTION h.

3/4 8-2a 3.8.1.1 Add new page with ACTIONS f., g. and h.

from previous page (editorial).

B 3/4 8-1 8 3/4.8 Revise Bases as shown.

6. B 3/4 4-3 B 3/4.4.3.2 Add sentence as shown.

7. 6-16 6.9.1.6 Add "*" to title.

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TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION L '

ACTION STATEMENTS L - ACTION 20 - Be in at least tiOT SHUTDOWFwithin 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 .

L ACTION 21 - Be in ct least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or 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 .

ACTION 22 - Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - In OPERATIONAL CONDITION 1 or 2 verify the affected system isolation valves are closed within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and declare the affected system inoperable. In OPERATIONAL CONDITION 3, be in at least COLD SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 24 - Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or close the affected system isolation valves within the next hour and declare the affected system inoperable 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 .

ACTION 25 - Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 26 - Close the affected system isolation valves within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

TABLE NOTATIONS Required when (1) handling irradiated fuel in the refueling area secondary containment, or (2) during CORE ALTERATIONS, or (3) during operations with a

. potential for draining the reactor vessel with the vessel head removed and fuel in the vessel.

May be bypassed under administrative control, with all turbine stop valves closed.

During operation of the associated Unit 1 or Unit 2 ventilation exhaust system.

(a) See Specification 3.6.3, Table 3.6.3-1 for primary containment isolation valves which are actuated by these isolation signals.

(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 channel or trip system in the tripped condition provided at least the other OPERABLE channel in the same trip system is monitoring that parameter. In addition, for the HPCI system and RCIC' system isolation, provided that the redundant isolation valve, inboard or outboard, as applicable, in each line is OPERABLE and all required actuation instrumentation for that valve is OPERABLE, one channel may be placed in an inoperable status for up to 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months for required surveillance ;

without placing the channel or trip system in the tripped condition.

(c) Actuates secondary containment isolation valves shown in Table 3.6.5.2.1-1 '

and/or 3.6.5.2.2-1 and signals B H, S U, R and T also start the standby gas treatment system.

(d) RWCU system inlet outboard isolation valve closes on SLCS "B" initiation.

RWCU system inlet inboard isolation valve closes on SLCS "A" or SLCS "C" initiation.

LIMERICK - UNIT 1 3/4 3-16

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TABLE 4.3.2.1-1 (Continued) - I ISOLATION ACTUATION INSTRUMENTATION SURVEILLANCE REQUIREMENTS :-

CHANNEL OPERATIONAL -

CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH TRIP FUNCTION CHECK TEST CALIBRATION SURVEILLANCE REQUIRED

7. SECONDARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level Low, Low - Level 2 S M R 1, 2, 3 'l

b. Drywell Pressure - High S M R 1,~2, 3

c. 1. Refueling Area Unit 1 Ventilation Exhaust Duct Radiation - High S M R I

2. Refueling Area Unit 2 Ventilatifon Exhaust Duct Radiation - High S M R

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d. Reactor Enclosure Venti?ation Exhaust Duct Radiation - High S M R 1, 2, 3

e. Outside Atmosphere To Reactor Enclosure a Pressure - Low N.A. M Q- 1,2,3

f. Outside Atmosphere To Refueling Area A Pressure - Low N.A. M Q *

g. Reactor Enclosure Manual Initiation N. A. . R N.A. 1, 2, 3

h. Refueling Area Manual Initiation N.A. R N.A. *

' Required when (1) handling irradiated fuel in the refueling area secondary containment, or (2) during CORE ALTERATIONS, or (3) during operations with a potential for draining the reactor vessel with the vessel head removed and fuel in the vessel.

- When not administratively bypassed and/or when any turbine stop valve is open.

During operation of the associated Unit I cr Unit 2 ventilation exhaust system.

LIMERICK - UNIT 1 3/4.3-31

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. . ig TABLE 3.3.2-1 (Continued)

ISOLATION ACTUATION' INSTRUMENTATION MINIMUM APPLICAB8.E OPERABLE CHANNE OPERATIONAL TRIP FUNCTION ISOLATIW),(c)

SIGNAL ta PERTRIPSYSTEM(g) CONDITION ACTION

7. SECONDARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level Low, Low-level 2 B 2 1,2,3 25

b. Drywell Pressure - High H 2 1,2,3 25

c. 1. Refueling Area Unit 1 Ventilation Exhaust Duct Radiation - High R 2 *# 25

2. Refueling Area Unit 2 Ventilation Exhaust Duct Radiation - High *,

R 2 25 l

d. Reactor Enclosure Ventilation Exhaust Duct Radiation - High S 2 1,2,3 25

e. Outside Atmosphere To Reactor Enclosure a Pressure - Low U 1 1,2,3 -25

f. Outside Atmosphere To Refueling Area A Pressure - Low T 1

25

g. Reactor Enclosure Manual Initiation NA 1 1,2,3 24

h. Refueling Area Manual Initiation NA +

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,f0NTAINMlNTSYSTEMS e

, ' REFUELING AREA SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES I B

[, LIMITING CONDITION FOR OPERATION !

l 3.6.5.2.2 The refueling area secondary containment ventilation system automatic ,

isolation valves shown in Table 3.6.5.2.2-1 shall be OPERABLE with isolation times i less than or equal to the times shown in Table 3.6.5.2.2-1.

1 APPLICABILITY: OPERATIONAL CONDITION *.

ACTION:

i With one or more of the refueling area secondary containment. ventilation system automatic isolation valves shown in Table 3.6.5.2.2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penet,ation that is open and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either:

a. Restore the inoperable valves to OPERABLE status, or

b. Isolate each affected penetration by use of at least one deactivated valve secured in the isolation position, or

c. Isolate each affected penetration by use of at least one closed manual, valve, blind flange, or slide gate damper.

Otherwise, in OPERATIONAL CONDITION *, suspend handling of irradiated fuel in l

, the refueling area secondary containment CORE ALTERATIONS and operations with

.a potential for draining the reactor vessel. The provisions of Specification 3.0.~3'are not applicable.

SURVEILLANCE REQUIREMENTS 4.6.5.2.2 Each refueling area secondary containment ventilation system automatic isolation valve shown in Table 3.6.5.2.2-1 shall be demonstrated OPERABLE:

a. Prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control or power circuit by cycling the valve through at least one complete cycle of full travel and verifying the specified isolation time. 4

b. At least once per 18 months by verifying that on a containment isolation test signs 1 each isolation valve actuates to its isolation position. ,

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c. By verifying the isolation time to be within its limit at least once per I 92 days.

Required when (1) irradiated fuel is being handled in the refueling area secondary L contaitment, or (2) during CORE ALTERATIONS, or (3) during operations with a !

potential for draining the reactor vessel with the vessel head removed and fuel i

in the vessel.

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INSTRUMENTA110N j

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SEISMIC MONITORING INSTRUMENTATION i

LIMITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1* shall l' be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required seismic monitoring instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for i restoringtheinstrument(s)toOPERABLEstatus,

b. The provisions of Specifications 3.0.3 are not applicable. ,

SURVEILLANCE REQUIREMENTS k

4.3.7.2.1 Each of the above required seistic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK CHANNEL

FUNCTIONAL TEST, and CHANNEL CALIBRATION operations at the freauencies shown in Table 4.3.7.2-1.

t 4.3.7.2.2 Each of the above regoired seismic monitoring instruments which is accessible during power operation and which is actuated during a seismic event ,

greater than or equal to 0.01g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CAllBRATION performed within 5 days following the seismic event. Data shall be retrieved from actuated instruments and analyzed to ;

determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum and resultant effect upon unit features important to safety.

Each of the above seismic monitoring instruments which is actuated during a seismic event greater than or equal to 0.01 g but is not accessible during power :

operation shall be restored to OPERABLE status and a CHANNEL CAllBRATION performed the next time Unit 1 enters OPERATIONAL CONDITION 4 or below. A supplemental report shall then be prepared and submitted to the Commission within 14 days pursuant to Specification 6.9.2 describing the additional data from these instruments.

Shared with Unit 2.

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TABLE 3.3.7.2-1 (Continued) i ,

i SEISMIC MONITORING INSTRUMENTATION !

b, MINIMUM l MEASUREMENT INSTRUMENTS L INSTRUMENTS AND SENSOR LOCATIONS RANGE OPERABLE

i. c. TriaxialSeismicTrigger(S/T) *

1) XSH-VA-001 (Activates Items NAT 1 1.b.1) thru 5) above)!

(Loc. Area 16. El 177')

2. Triaxial Peak Recording Accelerograph (P/A's)

.a. XR-VA-151 Reactor Equipment 0-2g 1***

< (Top of reactor vessel head)

b. XR-VA-152 Reactor Piping 0-2g 1 (Mn. Stm. Line 'D', El 313',

incontainment) ,

c. XR-VA-153 Reactor Equipment Outside 0-2g 1 :

Containment (RHR Heat Exchanger, ;

Loc.203-R15-201) '

3. Triaxial Seismic Switches a.. XSHH-VA-001 Primary Containment NAU 1*

foundation (Loc.118-R16-177) ,

4. Triaxial Response Spectrum Analyzer 1-33.5 Hz 1*, **

(RSA); (Loc. Control Room) l ,

t TThe triaxial' seismic trigger setpoint is 0.005g.

U This switch triggers at 5 0.15g horizontal and 5 0.10g vertical.

With reactor control room indication and annunciation.

- Receives signal from playback unit fed with data from the Triaxial Accelerographs, Item 1.a above.

- - Not required to be OPERABLE when reactor vessel head is removed. l LIMERICK - UNIT 1 3/4 3-70

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} TABLE 4.3.7.2-1 t

SE!SMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL i

INSTRUMENTS AND SENSOR LOCATIONS CHECK TEST CALIBRATION

1. Triaxial Time-History Accelerographs (T/A's)

a. Sensors

1) XE-VA-102 Primary Contain. N.A. SA R ment foundation (Loc.109-R15-177)

2) XE-VA-103 Containrent N.A. SA R Structure (Diaphragm Slab)

3) XE-VA-104 Reactor Enclosure N.A. SA R Foundation (Loc.111-R11-177) I

4) XE-VA-105 Reactor Piping N.A. SA R Support (Mn. Stm. Line 'D '

El313',incontainment)

5) XE-VA-106 Outside Contain. N.A. SA R ment on Seismic Category I Equipment,(RHRHeat Exchanger, Loc. 102-R15-177)

6) XRSH-VA-107* Foundation of N.A. SA R an Independent Seismic Category I Structure (Spray Pond Pump House, El 237')

l b. Recorders (Panel 000693) i 1 XR-VA-102 for YE-VA-102 N.A. SA R 2 XR-VA-103 fer XE-VA-103 N.A. SA R 3 XR-VA-104 for XE-VA-104 N.A. SA R 3 4 XR-VA-105 for XE-VA-105 N.A. SA R l 5) XR-VA-106 for XE-VA-106 N.A. SA R

Includes sensor, trigger, recorder, and backup power supply.

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TABLE 4.3.7.2-1 (Continued) ;

SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS r.

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CHANNEL CHANNEL FUNCTIONAL CHANNEL

{ INSTRUMENTS AND SENSOR LOCATIONS CHECK TEST CALIBRATION t,l'

c. Triaxial Seismic Trigger (S/T) ' '

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1) XSH-VA-001 (Activates N.A. SA R l ,

Items 1.b.1) thru 5) above)

2. TriaxialPeakRecordingAccelerograph(P/A's)

a. XR-VA-151 Reactor Equipment N.A. N.A. R I l

(Top of reactor vessel he:d) >

b. XR VA-152 Reactor Piping N.A. N.A. R (Mn. Stm. Line 'D,' El 313',

in containment)

c. XR-VA-153 Reactor Equipment N.A. N.A. R Outside Containment (RHR Heat Exchanger, Loc. 203-R15-201)

1

3. Triaxial Seismic Switches

, a. XSHH-VA-001 Primary Containment N.A. SA R foundation (Loc.118-R16-177) '

4. Triaxial Response Spectrum Analyzer N.A. SA R ;

(RSA) ,

b l

llMERICK - UNIT 1 3/4 3-72

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b* . CONTAINMENT SYSTEMS 7

SURVEILLANCEREQUIREMENTS(Continued)

2. Verifying that the fan starts and isolation valves necessary to 4

draw a suction from the refueling area or the reactor enclosure recirculation discharge open on each of the following test signals:

a) Manual initiation from the control room, and b) Simulated automatic initiation signal.

3. Verifyiggthatthetemperaturedifferentialacrosseachheater is 1 15 F when tested in accordance with ANSI N510-1980.

c. After each complete or partial replacement of a HEPA filter bank by '

verifying that the HEPA filter bank satisfies the inplace penetration and leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1980 while operating the system at a flow rate of 3000 cfm i 10%.

f. After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and leakage testing acceptance criteria of less'than 0.05%

in accordance with ANSI N510-1980 for.a halogenated. hydrocarbon refrigerant test gas while operating the system at a flow rate of_3000 cfm i 10%.

g. After any major system alteration:

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1. Verify that when the SGTS fan is running the subsystem flowrate is 2800 cfm minimum from each reactor enclosure (Zones I and II) and 2200 cfm minimum from the refueling area (Zone III).

2. Verify that one standby gas treatment subsystem will drawdown reactor enclosure Zone I secondary containment to greater than or equal to 0.25 inch of vacuum water gauge in less than or equal to 121 seconds with the reactor enclosure recirculation system in operation and the adjacent reactor enclosure and refueling area zones are in their isolation modes.

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SUR'VElLLANCEREQUIREMENTS(Continued) !

L 2. Verifying within 31 days af ter removal that a' laboratory analysis of i a representative carbon sample obtained in accordance with 1 Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2 March 1978, meets the laboratory testing criteria of Regulatory I Position C.6.a of Regulatory Guide 1.52, Revision 2. March 1978, for a methyl iodide penetration of less than 1%; and

3. Verifying a subsystem flow rate of 3000 cfm 4 10% during subsystem

{ operation when tested in accordance with ANST N510-1980,

d. After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying within 31 uays after removal that a laboratory analysis of a representative f

carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2 March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52 Revision 2. March 1978, for a methyl iodide penetration of less than 1%.

e. At least once per 18 months by:

1. Verifying that the pressure drop across the combined profilter, upstream and downstream HEPA filters, and charcoal adsorber banks is less than 6 inches water gauge while operating the subsystem at a flow rate of 3000 cfm + 10%; verifying that the prefilter pressure

drop is less than 0.8 Inch water gauge and that the pressure drop across each HEPA is less than 2 inches water gauge.

2. Verifying that on each of the below chlorine isolation mode

, actuation test signals, the subsystem automatically switches to the chlorine isolation mode of operation and the isolation valves close within 5 seconds:

a) Outside air intake high chlorine, and b) Manual initiation from the control room.

3. Verifying that on each of the below radiation isolation mode actuation test signals, the subsystem automatically switches to the radiation isolation mode of operation and the control room is maintated at a positive pressure of at least 1/8 inch water gauge relative to the turbine enclosure and auxiliary equipment room and outside atmosphere during subsystem operation with an outdoor air flow rate less than or equal to 525 cfm:

l a) Outside air intake high radiation, and I

b) Manual initiation from control room. '

1 LIMERICK - UNIT 1 3/4 7-7

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, , CONTAINMENT SYSTEMS L . 1 L

BASES i

I 3/4.6.5 SECONDARY CONTAINMENT i

Secondary containment is designed to minimize any ground level release of I radioactive material which may result from an accident. The Reactor Enclosure and ;

associated structures provide secondary containment during normal operation when ,

the drywell is sealed and in service. At other times the drywell may be open and, ;

when required, secondary containment integrity is specified.

Establishing and maintaining a vacuum in the reactor enclosure secondary '

containment with the standby gas treatment system once per 18 months, along with :

the surveillance of the doors, hatches, dampers and valves, is adequate to ensure that there are no violations of the integrity of the secondary containment.

The OPERABILITY of the reactor enclosure recirculation system and the i

standby gas treatment systems ensures that sufficient iodine removal capability will be available in the event of a LOCA or refueling accident (SGTS only). The reduction in containment iodine inventory reduces the resulting SITE BOUNDARY radiation doses associated with containment leakage. The operation of this system and resultant iodine removal capacity are consistent with the assumptions used in the LOCA and refueling accident analyses. Provisions have been made to continuously purge the filter plenums with instrument air when the filters are not in use to prevent buildup of moisture on the adsorbers and the HEPA filters. .

Although the safety analyses assumes that the reactor enclosure secondary containment draw down time will take 135 seconds, these surveillance requirements '

specify a draw down time of 121 seconds. This 14 second difference is due to the e diesel generator starting and sequence loading delays which is not part of this surveillance requirement.

The reactor enclosure secondary containment draw down time analyses assume a stcrting point of 0.25 inch of vacuum water gauge and worst case SGTS '

dirty filter flow rate of 2800 cfm. The surveillance requirements satisfy this assumption by starting the drawdown from ambient conditions and connecting the adjacent reactor enclosure and refueling area to the SGTS to split the exhaust flow.between the three zones and verifying a uinimum flow rate of 2800 cfm from the test zone. This simulates the worst case flow alignment and verifies adequate ;

flow is available to drawdown the test zone within the required time. The Technical Specification Surveillance Requirement 4.6.5.3.b.3 is intended to be a multi-zone air balance verification without isolating any test zone.

The SGTS fans are sized for three zones and therefore, when aligned to a single zone or two zones, will have excess capacity to more quickly drawdown the affected zones. There is no maximum flow limit to individual zones or pairs of zones and the air balance and drawdown time are verified when all three zones are connected to the SGTS.

The three zone air balance verification and drawdown test will be done after any major system alteration, which is any modification which will have an l effect on the SGTS flowrate such that the ability of the SGTS to drawdown the reactor enclosure to greater than or equal to 0.25 inch of vacuum water gage in less than or equal to 121 seconds could be affected.

LIMERICK - UNIT 1 B 3/4 6-5

,, *[CONTAINMENTSYSTEMS' STANDBY GAS TREATMENT SYSTEM - COMMON SYSTEN 'l V ;

P LIMITING CONDITION FOR OPERATION *

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3.6.5.3 Two independent standby gas treatment sobsystems shall be OPERABLE.

L APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, and *.

ACTION:

)

a. With one standby gas treatment subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days, or:

1. In OPERATIONAL CONDITION 1, 2, or 3, 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 .

2. InOPERATIONALCONDITION*,suspendhandlingofirradiatedfuelinl '

the secordary containment, CORE ALTERATIONS and operations with a l potential for draining the reactor vessel. The provisions of '

Specification 3.0.3 are not applicable. ,

b. With both standby gas treatment subsystems inoperable in OPERATIONAL -

CONDITION *, suspend handling of irradiated fuel in the secondary-containment, CORE ALTERATIONS or operations with a potential for i draining the reactor vessel. The provisions of Specification 3.0.3 are :

not applicable.

SURVEILLANCE REQUIREMENTS 4.6.5.3. Each standby gas treatment subsystem shall be demonstrated OPERABLE:

a. At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates with the heaters OPERABLE.

Required when (1) irradiated fuel is being handled in the refueling area secondary containment, or (2) during LORE ALTERATIONS, or (3) during operations with a potential for draining the reactor vessel with the vessel head removed and fuel in the vessel. ;

LIMERICK - UNIT 1 3/4 6-52 '

PLANT SYSTEMS-g _o 'C .,

n . ..

. LIMITING CUNDITION FOR OPERATION-(Continued)

ACTION: (Continued)

! 5. With two RHRSW pump / diesel generator pairs

inoperable, restore at

, least one inoperable RHRSW pump / diesel generator pair

to OPERABLE status within 30 days, or be in at least HOT SHVIDOWN within 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 . The provisions of specification 3.0.4 are not applicable.

6. With three RHRSW pump / diesel generator pairs

inoperable, restore at least one inoperable RHRSW pump / diesel generator pair

to OPERABLE status within 7 days, or 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 following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

7. With four RHRSW pump / diesel generator pairs

inoperable, restore at least one inoperable RHRSW pump / diesel generator pair

to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 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. InOPERATIONALCONDITION3or4withtheRHRSWsubsystem(s),whichis associated with an RHR loop required OPERABLE by Specification 3.4.9.1 or 3.4.9.2, inoperable, declare the associated RHR loop inoperable and take the ACTION required by Specification 3.4.9.1 or 3.4.9.2, as applicable.

~

c. In OPERATIONAL CONDITION 5 with the RHRSW subsystem (s), which is associated with an RHR' loop required OPERABLE by Specification 3.9.11.1 or 3.9.11.2, inoperable, declare the associated RHR system inoperable and' take the ACTION required by Specification 3.9.11.1 or 3.9.11 ? as applicable. '

t SURVEILLANCE REQUIREMENTS 4.7.1.1 At least the above required residual heat removal service water system subsystem (s)'shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

A RHRSW pump / diesel generator pair consists of a RHRSW pump and its associated diesel generator. If either a RHRSW pump or its associated diesel generator !

becomes ino9erable, then the RHRSW pump / diesel generator pair is inoperable. l l

l LIMERICK - UNIT 1 3/4 7-2.

eE o.

PLANT SYSTEMS EMERGENCY SERVICE WATER SYSTEM - COMMON SYSTEM l !

LIMITING CONDITION FOR OPERATION 3.7.1.2 At least the following independent emergency service water system loops, l with each loop comprised of:

a. Two OPERABLE emergency service water pumps, and i

b. An OPERABLE flow path capable of taking suction from the emergency ;

service water pumps wet pits which are supplied from the spray pond or i the cooling tower basin and transferring the water to the associated Unit !

I and common safety-related equipment, i shall be OPERABLE: 1

a. In OPERATIONAL CONDITIONS 1, 2, and 3, two loops.

l

b. In OPERATIONAL CONDITIONS 4, 5, and *, one loop. '

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

_ ACTION: i

a. In OPERATIONAL CONDITION 1, 2, or 3:

1. With one emergency service water pump inoperable, restore the inoperable pump to OPERABLE status within 45 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 i the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ;

2. With one emergency service water pump in each loop inoperable, restore at least one inoperable pump to OPERABLE status within 30 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 .

3. With one emergency service water system loop otherwise inoperable, declare all equipment aligned to the inoperable loop inoperable **,

restore the inoperable loop to OPERABLE states with at least one OPERABLE pump within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 l hours.

When handling irradiated fuel in the secondary containment. \

- The diesel generators may be aligned to the OPEP.ABLE emergency service water system loop provided confirmatory flow testing has been performed. Those diesel generators rot aligned to the OPERABLE emergency service water system loop shall be declared inoperable and the actions of 3.8.1.1 taken.

LIMERICK - UNIT 1 3/4 7-3 r

'~ ~

,,.LANT.$YSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTIONt (Continued) *

4. With three ESW pump / diesel generator pairs ** inoperable, restore at least one inoperable ESW pump / diesel generator pair ** to OPERABLt status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or be in at. least HOT SHU100WN within the i 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 .

5. Witiffour ESW pump / diesel generator pairs ** inoperable, restore at least one inoperable ESW pump / diesel generator pair ** to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 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. In OPERATIONAL CONDITION 4 or 5:

l. With only one en,ergency service water pump and its associated !

flowpath OPERABLE, restore at least two pumps with at least one flow path to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or declare the associated safety related equipment inoperable and take the ACTION required by Specifications 3.5.2 and 3.8.1.2. ;

c. In OPERATIONAL CONDITION *

1. With only one emergency service water pump and its associated flow r,ath OPERABLE, restore at least two pumps with at .least one flow path to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or verify adequate cooling remains available for the diesel generators required to be OPERABLE '

or declare'the associated diesel generator (s) inoperable and take the ACTION required by Specification 3.B.1.2. lhe provisions of.

Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.2 At~1 east the above required emergency service water system :

loop (s) shall be demonstrated OPERABLE:

a. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) that is not locked, sealed, or otherwise secured i in position, is in its correct por,ition.

b. At least once per 18 months by verifying that:

1. Each automatic valve actuates to its correct position on its appropriate ESW pump start signal.

2. Each pump starts automatically when its associated diesel generator starts.

When handling irradiated fuel in the secondary containment.

An CSW pump / diesel generator pair consists of an ESW pump and its associated >

die:;el generator. If either an ESW pump or its associated diesel generator becomes inoperable, then the ESW pump / diesel generator pair is inoperable.

LIMERICK - UNIT 1 3/4 7-4

5, kTIS$YSTh ,

, . VLTIMATE HE Al $1W:

LIMITING CONDITION FOR OPERATION

\'

f S. 7.'1. 3 1he spray pond shall be OPERABLE with:

a.. A minimum pond water level at or above elevation 250' 10" Mean Sea Level, and 5

b. A pond water temperature of less than or equal to 880 f.

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

, , ACTION f With the requirements of the above specification not satisfiedt

a. In OPERATIONAL CONDITION 1, 2, or 3, 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 ,

b. In OPERATIONAL CONDITION 4 or 5, declare the RHR$W system and the emergency service water system inoperable and take the ACTION required by

)

Specifications 3.7.1.1 and 3.7.1.2.

c. In OPERATIONAL CONDITION *, declare the energency service water system l 1eoperable and take the ACTION required by Specification 3.7.1.2. The

f. provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.3 The spray pond shall be determined OPERABLEt

4. By verifying the pond water level to be greater than its limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

Byverifyingthewatersurfacetemperatgf:re surface) to be less than or equal to 88 (within the upper two feet of the

1. at least once per 4 0hours when the spray pond temperature is greater than or equal to 80 f; and

2. at least onct per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the spray pond temperature is greater than or equal to 85 0ft and

3. atleasgonceper24hourswhenthespraypondtemperatureisgreater than 32 F.

c. By verifying all piping above the frost line is drained within 1 bour after being used.

When handling irradiated fuel in the secondary containment.

- LIMERICK - UNIT 1 3/4 7-5 ;

e

, ; .c e PLANT $YST[Ns

, *3/4.7.2 CONTROL ROOM (MERGENCY FRESH AIR $UPPLY $Y$7FM . COMMON SY$1El l ,

t LIM 111NG CONDITION FOR OPERATION I

3.7.2 Two in m endent control room emergency fresh air supply system subsystems (

shall be OPLRAE M. '

l APPLICABILITY: All OPERATIOhAL CONDITIONS end *.

ACTION:

a. In OPERATIONAL CONDITION 1, 2, or 3 with one control room emergency fresh air supply subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next l 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. In OPERATIONAL CONDITION 4, 5. or *:

1. With one control room emergency fresh air supply subsystem inoperable, restore the inoperable subsystem to OPERABLE status within 7 days or initiate and maintain operation of the OPERABLE subsystem in the radiation isolation mode of operation.

2. With both control room emergency fresh air supply subsystems inoperable, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment and operations with a potential for draining the reactor vessel.

l C. The provisions of Specification 3.0.3 are nut applicable in OPERATIONAL CONDITION *,

SURVE!LLANCE REQUIREMENTS 4.7.2 Each control room emergency fresh air supply subsystem 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 gy verifying the control ro% air temperature to be less than or equal to 85 F effective temperature,

b. At least once per 31 days on a STAGGERED TEST BA$15 by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates with the heaters OPERABLE.

c. At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation rone communicating with the subsystem

by

I

1. Verifying that the subsystem satisfies the in-place penetration and bypass leakage testing ' acceptance criteria of less than 0.05% and uses the test procedure guidance in Regulatory Positions C.5.a. C.S.c. and C.S.d of Regulatory Guide 1.52. Revision 2 March 1978, and the system flow rate is 3000 cfm 1 10%.

When irradiated fuel is being handled in the secondary containment.

IIMERICK - UNIT 1 M' '-6

I 4 4

PLANT SYSTIMS i

BASES

! 3/4.7.? CONTROL ROOM IMERGINCY FRESH AIR $1)PPLY $YSi!M - COMMON SYSTEM l The OP[RABILITY of the control room emergency fresh air supply system ensures that the control room will remain habitable for operations personnel during and following all design basis accident conditions. Constant purge of the system at I cfm is sufficient to reduce the buildup of moisture on the i

adsorbers and HEPA filters. The OPERABILITY of this system in conjunction with control room design provisions is based on limiting the radiation exposure to personnel occupying the control room to 5 rem or less whole body, or its equivalent. This limitation is consistent with the requirements of General Design Criterion 19 of Appendix A. 10 CFR Part 50.

3/4.7.3 RfACTOR CORE ISOLATION C00LlWG SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactoi' isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without requiring actuation of any of the emergency core cooling system equipment. The RCIC system is conservatively required te be OPERABLE whenever reactor pressure exceeds 150 psig. This pressure is substantially below that for which low pressure core cooling systems can provide adequate core cooling.

The RCIC system specifications are applicable during OPERATJONAL CONDITION $

1. P. and 3 when reactor vessel pressure exceeds 150 psig because RCIC is the primary non-ECCS source of emergency core cooling when the reactor is pressurized.

Ilith the PCIC system inoperable, adequate core cooling is assured by the OPERABILITY of the HPCI system and justifies the specified 14 day out-of-service period.

The surveillance requirements provide adequate assurance that RCIC will be OPERABLE when required. Although all active components are testable and full flow can be demonstrated by recirculation during reactor operation. a complete functional test requires reactor shutdown. The pump discharge piping is maintained full to prevent water hammer damage and to start cooling at the earliest possible moment.

LIMERICK - UNIT 1 B 3/4 7-la L.. . . _ . . .

)^ V '

)

. . INDfX I

~

LIMlil] CONDITIONS FOR OPERAT!] AND SURVEILLANCE REQUIREMENTS i

i SECTION PAGE CONTAINMENT SY$TEMS (Continued) 3/4.6.4 VACUUM RELIEF

[ Suppression Chamber Drywell Vacuum Breakers................. 3/4 6-44 c

[ 3/4.6.5 SECONDARY CONTAIMENT l Reactor Enclosure Secondary Containment Integrity............. 3/4 6-46 Refueling Area Secondary Containment Integrity................ 3/4 6-47 I Reactor Enclosure Secondary Containment Automatic

[ Isolation Va1ves.............................................. 3/4 6-48 Table 3.6.5.2.1-1 Reactor Enclosure Secondary 3

Containment Ventilation System Automatic Isolation Va1ves................................. 3/4 6-49 i

Refueling Area Secondary Containment Automatic Isolation Va1ves.............................................. 3/4 6 50

Table 3.6.5.2.2-1 Refueling Area Secondary Contain-i ment Ventilation System Automatic L

Isolation Va1ves....................... 3/4 6-51 Standby Gas Treatment System - Common System..................

3/46-52l Reactor Enclosure Recirculation System........................ 3/4 6-55 3/4.6.6 PRIMARY CONTAINMEN1 ATMOSPHERE CONTROL Primary Containment Hydrogen Recombiner Systems............... 3/4 6-57 1

Drywell Hydrogen Mixing System................................ 3/4-6-58 Drywell and Suppression Chamber Oxygen Concentration.......... 3/4 6-59 3/4.7 Pt. ANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service dater System - Common System........................................................ 3/4 7-1 Emergency Service Water System - Common System................

3/4 7-3 Ultimate Heat Sink............................................ 3/4 7-5 LIMERICK - UNIT 1 xiii e

a

Ft

' ,o s 1

, INDEX

^

o-LIMITING CONDITIONS FOR OPERATION AND $URVI!LLANCE REQUIREMENi$

.$ECTION .

PAGE PLANT SYSTEMS (Continued) 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM - COMM SYSTEM...............................................ON ..... 3/4 7-6 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM...................... 3/4 7-9 3/4.7.4 SNVBBER.................................................... 3/4 7-11 Figure 4.7.4 1 Sample Plan 2) for Snubber Functional Test........................ 3/4 7-16 3/4.7.5 SEALED SOURCE CONTAMINATION................................ 3/4 7 17 3/4.7.6 FIRE SUPPRESSION SYSTEMS Fire Suppression Water System.............................. 3/4 7-19 Spray and/or Sprinkler Systems............................. 3/4 7-22 CO2 Systems........................................ . ... 3/4 7-24 Malon Systems..............................................

3/4 1-25 Fire Hose Stations......................................... 3/4 7-26 Table 3.7.6.5 1 Fire Hose Stations.................... 3/4 7-27 Yard fire Hydrants and Hose Cart Houses.................... 3/4 7-29

,~ Table 3.7.6.6-1 Yard fire Hydrants and Hose Cart Houses............................ 3/4 7-30 3/4.7.7 FIRE RATED ASSEMBLIES....................................... 3/4 7-31 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 'A.C. SOURCES

A.C. Sources - Operating................................... 3/4 8-1

Table 4.8.1.1.2-1 Diesel Generator Test Schedule............................ 3/4 8-8 i

A.C. Sources - Shutdown.................................... 3/4 8-9 3/4.8.2 D. C. SOURCES D. C. Sources - Operating.................................. 3/4 8-10 LIMERICK - UNIT 1 xiv i

i Im ' ,

r ,

o' INDEX BASES

[

t SECTION 1

PAGE CONTAINMENT SYSTEMS (Continued) 3/t. 6.3 PRIMARY CONTAINMENT ISOLATION VALVES................... B 3/4 6-4 3/4.6.4 VACUUM RElltf.......................................... B 3/4 6-4 3/4.6.5 SECONDARY CONTAINMENT.................................. B 3/4 6-5 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL................. B 3/4 6-6 3/4.7 PLANT SYSTEMS 3/4.7.1 SE RVICE WATER SYSTEMS - COMMON SYSTEMS. . . . . . . . . . . . . . . . .B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM -

COMMON SYSTEM............................................ 8 3/4 7-la 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM.................. B 3/4 7-la l 3/4.7.4 SNUBBERS............................................... B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION............................ B 3/4 7-3 3/4.7.6 flRE SUPPRESSION SYSTEMS............................... B 3/4 7-4 3/4.7.7 f!RE RATED ASSEMBLIES.................................. B 3/4 7-4 3/4.8 ELECTRICAL POWER SYS TMS 3/4.8.1, 3/4.8.2. and 3/4.8.3 A.C. SOURCES, D.C. $0 & ES, AND ONSITE POWER DISTRIBUTION SYSTEMS................................... B 3/4 8-1 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES................ B 3/4 8-3 3/4.9 REFUELING OPERATIONS 3/4.9.1 REACTOR MODE SWITCH.................................... B 3/4 9-1 3/4.9.2 INSTRUMENTAT10N........................................ B 3/4 9-1 3/4.9.3 CONTROL ROD POSIT 10H................................... B 3/4 9-1 3/4.9.4 DECAY TIME............................................. B 3/4 9-1 3/4.9.5 COMMUNICATIONS......................................... B 3/4 9-1 LIMERICK - UNIT 1 xxi

. } <3/4.8 . ELECTRICAL POWER SYST[MS 3/4.8.1 A.C. SOURCIS ,

A.C. SOURCES - OPERATING l LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources i shall be OPERABLE:

! a. Two physically independent circuits between the offsite transmission network and the onsite Class IE aistribution system, and

b. Four separate and independent diesel generators, each with: r

1. A separate day tank containing a minimum of 200 gallons of fuel, J 2. A separate fuel storage system containing a minimum of 33,500

, gallons of fuel, and

3. A separate fuel transfer pump.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

a. With one diesel generator of the above required A.C. eltictrical power sources inoperable, demonstrate the OPERABII,lTY of the T'emaining A.C.

sources by performing Surveillance Requirements 4.8.1.1.la. within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 7 days thereafter. If the diesel generator became inoperable for any reason other than preplanned preventative maintenance or testing, demonstrate the OPERABILITY of the remaining l operable diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.4 for one diesel generator at a time, within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months

and at least once per 7 days thereafter. Restore the inoperable diesel generator to OPERABLE status within 30 days or be in at least HOT l SHUTf>0WN 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 . See also ACTION e.

l

b. With two diesel generators of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C.

sources by performing Surveillance Requirement 4.8.1.1.la. within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. DemonstratetheOPERABILITYofl the remaining diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.4 for one diesel generator at a time, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

Restore at lease one of the inoperable diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN with 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 . See also ACTION e.

Con ~trary to the provisions of Specification 3.0.3, this test is required to be completed regardless of when the inoperable diesel generator is restored to OPERABILITY for failure that are potentially generic to the remaining Unit I diesel generators and for which appropriate alternative testing cannot be designed.

LIMERICK - UNIT 1 3/4 8-1

-o a

[LECTRICAL POWER SYSTEMS

LIMITING CONDITION FOR OPERATION (Continued)

L ACTION: (Continued) l ,

C. With three diesel generators of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining l A.C. sources by performing Surveillance Requirement 4.8.1.1.la, within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; and perform Surveillance Requirement 4.8.1.1.2.a.4 for the remaining diesel generator, within I hour. Restore at least one of the inoperable diesel generators to OPIRABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHU100WN within the next following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . See also 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ACTION e. and in COLD SHUTDOWN withi!

d. With one offsite circuit and one diesel generator of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY -

of the remaining A.C. Sources by performing Surveillance Requirement 4.8.1.1.la. within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. If ;

the diesel generator became inoperable for any reason other than i preplanned preventive maintenance or testing, demonstrate the l OPERABILITY of the remaining diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.4 for one diesel generator at a i time, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *. Restore at least two offsite circuits to '

' OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time of initial loss 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 SHU100WN withing the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . See also ACTION e. l l t

f I

Contrary to the provisions of Specification 3.0.2, this test is required to be completed regardless of when the inoperable diesel generator is restored to OPCRABILITY for failures that are potentially generic to the remaining Unit I diesel generators and for which appropriate alternative testing cannot be designed.

LIMERICK - UNIT 1 3/4 8-la

D r

.itLICTRICALPDWERSY$1tMS LIZITI:3 CONDITION FOR OPERATION (Continued) e ACTION: (Continued) ;

e. In addition to the ACTIONS above:

1. For two train systems, with one or more diesel generators of the 4 above required A.C. electrical power sources inoperable, verify within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and at least once per If hours thereaf ter that at !

least one of the required two train system subsystem, train, components, and devices is OPERABLE and its associated diesel gerert. tor is OPERABLE. Otherwise, restore either the inoperable diesei' generator or the inoperable system subsystem to an OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2. for the LPCI systems, with two or more diesel generators of the ,

above required A.C. electrical power sources inoperable, verify within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter that at i least two of the required LPCI system subsystems, trains, ,

components, and devices are OPERABLE and its associated diesel l generator is OPERABLE. Otherwise, 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 . i This ACTION does not apply for those systems covered in $pecifications 3.7.1.1 and 3.7.1.2.

/

l i

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i LIMERICK - UNIT 1 3/4 8 2

m L) n ECTRICAL POWER SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued) ,

f. With one offsite circuit of the above required A.C. electrical power '

sources inoperable, demonstrate the OPERABILITY of the remaining A.C.

Sources by performing Surveillance Requirements 4.8.1.1.la. and 4.8.1.2a.4, for one diesel generator at a time, within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereaf ter; restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months 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 .

g.

1 With two of the above required offsite circuits inoperable. demonstrate the OPERABILITY of all of the above required diesel generators by '

performing Surveillance Requirement 4.8.1.1.2.a.4. for one diesel generator et a time, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months unless the diesel generators are already operating; restore at least one of the inoperable offsite ,

circuits to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 . With only one offsite circuit restored to OPERABLE status, restore at least two offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss 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 .

h. With one offsite circuit and two diesel generators of the above required A.C. electrical power sources inoperable, demonstrate the OPERABILITY of the remaining A.C. Sources by performing Surveillance Requirements 4.8.1.1.16. within I hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; demonstrate the OPERABILITY of the remaining diesel !

generators by performing Surveillance Requirement 4.8.1.1.2.a.4 for one !

diesel generator at a time, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . Restore at least one of the above required inoperable A.C. sources to OPERABLE status within 12 ;

hours 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 . Restore at least two offsite circuits and at least three of the above required diesel ,

generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss '

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 . See also ACTION e.

i LIMERICK - UNIT 1 3/4 8-2a i

P 3/3.1 ELECTRICAL POWER SYSTEMS l 'BASEf. '

4.8.1, 3/4.8.2. and 3/4.8.3 A,C. SOURCES. D.C. SOURCES, and ONSITE POWER DISTRIB_UTION_

TEMS The OPERABILITY of the A.C. and D.C. power sources and associated distribution systems during operation ensures that sufficient power will be available to supply the safety-related equipment required for (1) the safe shutdown of the facility and (2) the Ditigation and control of accident conditions within the facility. The minimum specified independent and redundant A.C. and D.C. power sources and distribution systems satisfy the requirements of General Design Criterien 17 of Appendix A to 10 CFR Part 50.

The ACTION requirements specified for the levels of degradation of the power sources provide restriction upon continued facility operation commensurate with the level of degradation. The OPERABILITY of the power sources are consistent with the initial i

condition assumptions of the safety analyses and are based upon maintaining at least two cf the onsite A.C. and the correspohding D.C. power sources and associated distribution systems OPERABLE during accident conditions coincident with an assumed loss-of-offsite power and single failure of the other onsite A.C. and D.C. source. At least two onsite I

' A.C. and their corresponding D.C. power sources and distribution systems providing power for at at least two ECCS divisions (1 Core Spray loop, 1 LPCI pump and 1 RHR pump in

! suppression pool cooling) arc required for design basis accident mitigation as discussed l in FSAR Table 6.3-3. Onsite A.C. operability requirements for common systems such as i

RHRSW and ESW are addressed in the appropriate system specification action statements.

The A.C. and D.C. source allowable out-of-service times are based on Regulatory Guide 1.93, " Availability of Electrical Power Sources," December 1974. When one or more diesel l generators are inoperable, there is an additional ACTION requirement to verify that all remaining systems, subsystems, trains, components, and devices, that depend on the remaining OPERABLE diesel generators as a source of emergency power, are also OPERABLE.

The LPC1 mode of the RHR system is considered a four train system, of which only two trains are required. The verification for LPCI is not required until two diesel generators are inoperable. This requirement is intended to provide assurance that a loss-I cf-offsite power event will not result in a complete loss of safety function of critical systems during the period when one or more of the diesel generators are inoperable. The l 1 term verify as used in this context means to administrative 1y check by examining logs or t

, other information to determine if certain components are out-of-service for maintenance or j l other reasons. It does not mean to perform the surveillance requirements needed to !

l demonstrate the OPERABILITY of the component.

r The OPERABILITY of the minimum specified A.C. and D.C. power sources and associated ;

distribution systems during shutdown and refueling ensures that (1) the facility can be Caintained in the shutdown or refueling condition for extended time periods and (2) ,

sufficient instrumentation and control capability is available for monitoring and maintaining the unit status. i The surveillance requirements for demonstrating the OPERABILITY of the diesel l

. generators are in accordance with the recommendations of Regulatory Guide 1.9, " Selection ,

' of Diesel Generator Set Capacity for Standby Power Supplies," March 10, 1971, Regulatory i Guide 1.137 " fuel-011 Systems for Standby Diesel Generators," Revision 1, October 1979 and l

Regulatory Guide 1.108, " Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants," Revision 1. August 1977 except for paragraphs C.2.a(3), C.2.c(1), C.2.c(2), C.2.d(3) and C.2.d(4). The exceptions to l 3 Regulatory Guide 1.108 allow for gradual loading of diesel generators during testing and !

decreased surveillance test frequencies (in response to Generic Letter 84-16).

2

[ LIMERICK - UNIT 1 8 3/4 8-1 l 1 i

l l

IlcREACTORCOOLANT$YSTEM l . BASES 3/4.4.3 REACTOR COOL _ ANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DE ICTION SYSTI,M_5 i The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary. These !

detection systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems," May 1973. In conformance with Regulatory Guide 1.45, the channel calibration tests will verify ,

theabilitytodetecta1gpmleakinlgssthan1hourandanatmosphericgaseous '

radioactivity system sensitivity of 10' uC/cc. t 3/4.4.3.2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been based l

on the predicted and experimentally observed behavior of cracks in pipes, lhe normally expected background leakage due to equipment design and the detection i capability of the instrumentation for determining system leakage was also considered. The evidence obtained from experiments suggests that for leakage !

somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probability is '

small that the imperfection or crack associated with such leakage would grow rapidly. However, in all cases, if the leakage rates exceed the values specified j

or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor <

will be shutdown to allow further investigation and corrective action.

The ACTION requirements for pressure isolation valves (PlVs) are used in conjunction with the system specifications for which PlVs are listed in Table ,

3.4.3.2-1 and with primary containment isolation valve requirements to ensure that plant operation is appropriately limited. ,

The Surveillance Requirements for the RCS pressure isolation valves provide !

added assurance of valve integrity thereby reducing the probability of gross valve !

failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed 3/4.4.4 CHEMISTRY !

The water chemistry limits of the reactor coolant system are established to prevent damage to the reactor materials in contact with the coolant. Chloride ,

j limits are specified to prevent stress corrosion cracking of the stainless steel.

The effect of chloride is not as great when the oxygen concentration in the ;

coolant is low, thus the 0.2 ppm limit on chlorides is permitted during POWER OPERATION. During Snutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods. '

Conductivity measurements are required en a continuous basis since changes in I this parameter are an indication of abnormal conditions. When the conductivity is within limits, the pH, chlorides and other impurities aff ecting conductivity must also be within their acceptable limits. With the conductivity meter inoperable, ;

additional samples must be analyzed to ensure that the chlorides are not exceeding the limits.

The surveillance requirements provide adequate assurance that concentrations <

in excess of the limits will be detected in sufficient time to take corrective action, i

LIMERICK - UNIT 1 8 3/4 4-3

f#

, s o nlDMINISTRATIVECONTROLS o

ANNUAL REPORTS (Continued) dosimeter,thermoluminescentdosimeter(TLD),orfilmbadge measurements. Small exposures totaling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole-body dose received

, from external sources should be assigned to specific major work functions;

b. Documentation of all challenges to safety / relief valves; and

c. Any other unit unique reports required on an annual basis,

d. The results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5.

, The following information shall be included: (1) Reactor power history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radioiodine i

activity was reduced to less than limit. Each result should include date and time of sampling and the radioiodine i

concentrations; (3) Cleanup system flow history starting 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months prior to the first sample in which the limit was exceeded; (4) Graph of the 1 131 concentration and one other p radiciodine isotope concentration in microcuries per gram as U a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

MONTHLY OPERATING REPORTS

l

[

I 6.9.1.6 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the main steam system safety / relief valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission. ATTH: Document Control Desk Washington. 0.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC no later than the 15th 1

of each month following the calendar month covered by the report.

l ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

p 6.9.1.7 Routine Annual Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted prior to May 1 of each year. The initial report shall be submitted prior to May 1 of the year following initial criticality.

The Annual Radiological Environmental Operating Reports shall include summaries, interpretations, and an analysis of trends of the results of the radiological 1

!

A single submittal may be made for a multiple unit station.

LIMERICK - UNIT 1 6-16 L ;

ML20012E501

Text

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