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Amend 23 to License NPF-39,changing Tech Specs to Reflect Completion & tie-in of Standby Gas Treatment Sys & Refueling Area HVAC Sys
	ML20245C255
Person / Time
Site:	Limerick
Issue date:	06/14/1989
From:	Butler W; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20245C257	List: ML20245C255; ML20245C259;
References
	NUDOCS 8906260106
	Download: ML20245C255 (20)
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UNITED STATES

.f g-NUCLEAR REGULATORY COMMISSION y

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PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 23 License No. NPF-39 1.

The Nuclear Regulatory Comission (the Commission) has found that A.

The application for amendment by Philadelphia Electric Company (the licensee) dated January 27, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Lomission;

'C.

Thereisreasonableassurance(i)thattheactiviticsauthorizedby this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon defense and security or.to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Comission's regulations t ' all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2)

.of Facility Operating License No. NPF-39 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 23, are hereoy incorporated into this license. Philadelphia Electric Ccmpany shall operate the facility j

in accordance with the Technical Specifications and the Environmental Protection Plan.

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This license amendment'is. effective upon issuance of an' operating license;-

to Limerick Generating ' Station,- Unit No. 2.-

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7 Walter'R. Butler, Director.

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Attachment:

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This license' amendment is' effective upon-issuance ofjan: operating license:

to' Limerick Generating Station, Unit No. 2..

FOR THE NUCLEAR REGULATORY COMMISSION

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. Walter R. Butler, Director Project Directorate I 2

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Attachment:

Changes to'the' Technical Specifications

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Date of Issuance: June 14,'1989' I

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ATTACHMENT TO LICENSE AMENDMENT.NO. 23 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace..the following pages of the Appendix A Technical-Specifications with the attached page. The revised pages are identified by Amendment number and contain vertical lines indicating the area of change. Overleaf pages'are

i provided to maintain document completeness.*

Remove Insert a

3/4 3-15

.3/4 3-15 a

3/4 3-16 3/4 3-16 1

3/4 3-21 3/4 3-21*

3/4 3-22 3/4 3-22 3/4 3-25 3/4 3-25 3/4 3-26 3/4 3-26*

3/4 3 3/4-3-31 3/4 3-32 3/4 3-32*

3/4 6-43 3/4 6-43 3/4 6-44 3/4 6-44*

3/4 6-47 3/4 6-47*

3/4 6-48 3/4 6-48 3/4 6-49 3/4 6-49 3/4.6-50 3/4 6-50*

- 3/4 6-51 3/4 6-51 3/4 6-51a 3/4 6-51a

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ISOLATION ACTUATJ0N INSTRUMENTATION ACTION STATEMENTS

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ACTION.20 -

Be3n 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 21-

-Be in at 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 SHUT 00WN 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 When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor 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 i

required surveillance without placing the channel or trip system in the tripped condition provided at least one other OPERABLE channel in the same trip. system is monitoring that parameter.

In addition, for the HPCI systes 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 j

gas treatment system.

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

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

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. LIMERICK - UNIT 1 3/4 3-16 Amendment No. 23 I

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-RESPONSE TIME (Seconds)#

6.

PRIMARY CONTAINMENT ISOLATION a.

Reactor. Vessel Water Level 1)

Low, Low - Level.2

< 13(a) 2)'

Low, Low, Low.- Level 1 13(a).

b.

'Drywell Pressure - High

< 13(a) 4 c.

North Stack Effluent Radiation - High N.A.

d.

Deleted e.

Reactor Enclosure Ventilation Exhaust Duct - Radiation - High N.A.

f.

Outside Atmosphere'To Reactor Er, closure a Pressure - Low N.A.

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Deleted h.

Drywell Pressure - High/

Reactor Pressure - Low N.A.

i.

Primary Containment Instrument Gas to.

N.A.

Drywell a Pressure-Low j.

Manual Initiation N.A.

7.

SECONDARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level Low, Low.- Level 2 N.A.

b.

Drywell Pressure - High N.A.

c.1. Refueling Area Unit 1 Ventilation

. Exhaust Duct Radiation - High N.A.

2. Refholing Area Unit'2 Ventilation Exhaust Duct Radiation - High N. A.

d.

Reactor Enclosure Ventilation Exhaust Duct Radiation - High N.A.

e.

Outside Atmosphere to Reactor Enclosure a Pressure - Low N.A.

LIMERICK - UNIT 1 3/4 3-25 Amendment No. 23 s

l77i TABLE 3.3.2-3 (Continued)

ISOLATION SYSTEM INSTRUMENTATION RESPONSE TIME

TRIP FUNCTION RESPONSE TIME (Seconds)#

f-Outside Atmosphere To Refueling Area a Pressure.

Low N.A.

g-.

Reactor Enclosure Manual Initiation N.A.

h.

Refueiing Area Manual Initiation N.A.

TABLE NOTATIONS 4

(a)

Isolation system instrumentation response time specified includes 10 seconds diesel generator starting and 3 seconds for sequence loading delays.

(b) Radiation detectors are exempt from response time testing.

Response time shall be measured from detector output or the input of the first electronic component in the channel.

" Isolation system instrumentation response time for MSIV only.

No diesel generator delays assumed for MSIVs.

"" Isolation systent instrumentation response time for associated valves.,*

except MSIVs.

Isolation system instrumentation response time specified for the Trip Function actuating each valve group shall be added to isolation time shown in Tables 3. 6. 3-1, 3. 6. 5. 2.1-1 and 3. 6. 5. 2. 2-1 for valves in each valve group to obtain ISOLATION SYSTEM RESPONSE TIME for each valve.

1. With 45 second time delay.

LIMERICK - UNIT 1 3/4 3-26 Amendment No.6

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INSTRUMENTATION 3/4.3.3 ' EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION j

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LIMITING CONDITION FOR OPERATION 3.3.3 The. emergency core cooling system (ECCS) actuation instrumentation channels shown i1 Tacle 3.3.3-1 shall be CPERABLE.ith their trip setpoints

. set consistent with the values shown in the Trip Setooint column of Table 3.3.3-2 and with EMERGENCY CORE COOLING SYSTEN RESPONSE TIME as shown in Taole 3.3.3-3.

j APPLICABILITY: 'As shown in Table 3.3.3-1, ACTION:

With an ECCS actuation instrumentation channel trip setpoint less I

a.

conservative than the value shown in the Allowable Values column of i

Table 3.3.3-2., declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent i

with the Trip Setpoint value.

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b.

With one or more ECCS actuation instrumentation channels inoperable,-

take the ACTION required by Table 3.3.3-1.

c.

With either A05 trip system subsystem inoperable, restore the incperable trip system to OPERABLE status within:

1.

7 days, provided that the HPCI and RCIC systems are OPERABLE.

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2.

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

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 reduce reactor steam dome pressure to less than or equal to 100 psig within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each ECCS actuation instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the

'I frequencies shows in Table 4.3.3.1-1.

4.3.3.2 LOGIC WSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

4.3.3.3 The ECCS RESPONSE TIME of each ECCS trip function shown in Table 3.3.3-3 J

shall be demonstrated to be within the limit at least once per 18 months.

Each

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test shall include at least one channel per trip system such that all channels i

are tested at least once every N times 18 months where N is the total number 1

of redundant channels in a specific ECCS trip system.

LIMERICK - UNIT 1 3A 3-32

.I

E.

TABLE 1 3.6.3-1 i

o L*

PRIMARY CONTAINMENT ISOLATION VALVES k

NOTATION I

4 NOTES (Continue 6 21.

Automatic isolation signal causes TIP to retract'; ball valve _ closes when probe 'is fully retracted.

e 22.

Isolation barrier remains water filled or a water seal remains in the line post-LOCA.

Isolation valve may be tested with water.

Isolation valve leakage is not included in 0.60 La total Type B & C tests.

23.

Valve does not receive an isolation signal.

Valves will be open during Type A' test.

Type C test not required.

24.

Both isolation signals required for valve closure.

25.

Deleted 26.

Valve stroke times listed are maximum times verified by testing per.5peci-fication 4.0.5 acceptance criteria.

The closure times for isolation valves in lines in which high-energy line breaks could occur are identified with a single asterisk. -The closure times for isolation valves in lines which provide an open path from the containment to the environs are identified.

with a double asterisk.

27.

The reactor vessel head seal leak detection line -(penetration 29A) excess flow check valve is not subject to OPERABILITY testing.

This valve will not be exposed to primary system pressure except under the unlikely con-ditions of'a seal failure where it could be partially pressurized to reactor pressure.

Any leakage path is restricted at the source; therefore, this valve need not be OPERABILITY tested.

28.

(DELETED) 29.

Valve may be open during normal operation; capable of manual isolation from control room.

Position will be controlled procedurally.

30.

Valve normally open, closes on scram signal.

31.

Valve 41-1016 is an outboard isolation barrier for penetrations X-9A, B and X-44. = Leakage through valve 41-1016 is included in the total for penetration X-44 only.

~32.

Feedwater long path recirculation valves are sealed closed whenever the reactor is critical and reactor pressure is greater than 600 psig.

The valves _are expected to'be opened only'in the following instances:

a.

Flushing of the condensate-and feedwater systems during plant startup.

b..

Reactor pressure vessel hydrostatic testing, which is conducted follow-ing each refueling' outage prior to commencing plant startup.

Therefore, valve stroke timing in accordance with Specification 4.0.5 is not required.

33.

Valve-also constitutes a Unit 2 Reactor Enclosure Secondary Containment Automatic Isolation Valve and a Refueling Area Secondary Containment Automatic Isolation Valve as shown in Table 3.6.5.2.1-1 and Table 3.5.5.2.2-1 respectively.

LIMERICK - UNIT 1 3/4 6-43 Amendment No. 23 el

e CON?AINMENT SYSTEMS 3/4.6.4 VACUUM RELIEF SUPPRESSION CHAMBfR - ORYWELL VACUUM BREAKERS LIMITING CON 0! TION FOR OPERATION 3.6.4.1 Each pair of suppression chamber - drywell vacuum breakers shall be OPERABLE and closea.

APPLICA8ILITY:

OPERATIONAL CON **TIONS 1, 2, and 3.

ACTION:

With one or more vacuum breakers in one pair of suppression chamber a.

drywell vacuum breakers inoperable for opening but known to be closed, restore the inoperable pair of vacuum breakers to OPERA 8LE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least NOT 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 hourt.

b.

With one suppression chamber - drywell vacuum breaker open, verify i

the other vacuum breaker in the pair to be closed within 2 haurs; restore the open vacuum breaker to the closed position within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTOOWN 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 .

With one position indicator of any suppression chamber - drywell c.

vacuum breaker inoperable.

i 1.

Verify the other vacuum breaker in the pair to be closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and at least once per 15 days thereaf ter, or 2.

Vecify the vacuum breaker (s) with the inoperable position I

indicator to be closed by conducting a test which demonstrates that the AP is maintained at greater than or equal to 0.7 psi for one hour without makeup within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 15 days thereafter.

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 SHUT 00WN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

LIMERICK - UNIT 1 3/4 6-44

f. *

'I

' ' ' 'C0kTAINNENT SYSTEMS.

3/4.6.5 -SECONDARY CONTAINMENT

[

REFUELING AREA SECONDARY CONTAINMENT INTEGRITY

]

g !NG CONDITION FOR OPERATION

]

3 3.6.5.1.2 REFUELING APEA SECONDARY CONTAINMENT INTEGRITY shall be.Taintained.

APPLICAB!LITY: OPERATIONAL CONDITION *.

ACT!ON:

l Without REFUEllNG AREA SECONDARY CONTAINMENT INTEGRITY, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

The provisions of Specifica-

{

tion 3.0.3 are not applicable.

1 SURVEILLANCE REQUIREMENTS 4.6.5.1.2 REFUELING AREA SECONDARY CONTAINMENT INTEGRITY shall be demonstrated by:

a.

' Verifying at'least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the pressure within the refueling area secondary containment is greater than or equal to 0.25 inch of vacuuri: water ;suge.

b.

Verifying at least once per 31 days that:

1.

- All refueling area secondary containment equipment hatches.and 3

blowout panels are closed and sealed.

2.

At least one door in each access-to the refueling area secondary containment is closed.

3.

All refueling area secondary containment penetrations not capable of being closed by OPERABLE secondary containment automatic iso-lation dampers / valves and required to be closed'during accident conditions are closed by valves, blind flanges, slide gate i

dampers or deactivated automatic dampers / valves secured in position.

c.

At least once per 18 months:

Operating one standby gas treatment subsystem for one hour and main-taining greater than or ecual to 0.25 inch of vacuum water gauge in the refueling area secondary containment at a flow rate not exceeding 764 cfm.

j

When irradiated fuel is being handled in the refueling area secondary contain-ment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel, i

LIMERICK - UNIT 1 3/4 6-47 Amendment No. 6 3

1 JUL 2 tgp i

u

= -

.s

' REACTOR CONTAINMENT SYSTEMS REACTOR ENCLOSURE SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES

' LIMITING CONDITIOCf0R OPERATION-3.6.5.2.1 The rs or. enclosure secondary containment ventilation system auto-matic isolation valves shown in Table 3.6.5.2.1-1 shall be OPERABLE with isolation:

times less than~or equal to the times shown in Table 3.6.5.2.1-1.

J_

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

' ACTION:

With one or more of the reactor secondary containment ventilation system automatic isolation valves shown in Table-3.6.5.2.1-1 inoperable,. maintain at-least one isolation valve OPERABLE in each affected penetration 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 ute of at least one closed manual valve, blind flange or slide gate damper.

Otherwise, in OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWR 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 .

SURVEILLANCE REQUIREMENTS 4.6.5.2.1 Each reactor enclosure secondary containment ventilation system automatic isolation valve shown in Tc e 3.6.5.2.1-1 shall be demonstrated OPERABLE:

Prior to returning the valve to service after maintenance, repair or a.

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.

b.

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

c.

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

i l

i I

1, LIMERICK - UNIT 1 3/4 6-48 Amendment No. 23

)

1 1

A

7..

p..

. e-r

+

N

. TABLE 3.6.5.2.1-1 REACTOR ENCLOSURE SECONDARY CONTAINMENT VEN!!LATION SYSTEM AUTOMATIC ISOLATION VALVES j

~

REACTOR ENCLOSUR F(ZONE I)

MAXIMUM

' ISOLATION TIME.

-.ISOLATIgg)

BLVEFUNCTION (Seconds)

SIGNALS 1.

Reactor Enclosure Ventilation Supt'y Valve HV-76-107 5

B,'H,5,0

-2.

Reactor-Enclosure. Ventilation Supply Valve HV-76-108 5

B,H,5,U' a

3.

Reactor Enclosure Ventilation Exhaust Valve HV-76-157 5

B,H,S,U 4.

Reactor Enclosure Ventilation Exhaust Valve HV-76-158-5 B,H,5,U-5.

Reactor Enclosure Equipment Compartment Exhaust Valve HV-76-141-5

'B,H,S,U 6.

Reactor Enclosure Ecuipment Compartment Exhaust Valve.HV-76-142 5

B,H,S,0

7., Drywell Purge Exhaust Valve HV-76-030 5

B,H,S,U,R,T-

8. ~ 0rywell Purge Exhaust Valve HV-76-031 5

B,H S,U,R,T.

9.

Dr well Purge Exhaust Inboard 5

B,H,S,0,1#,R,T-s Valve HV-57-214 (Unit 2) 10.

Drywell Purge Exhaust. Outboard -

6

.8,H,5,U,W,R,T' Valve HV-57-215.(Unit'2)

11. -Suppression Pool Purge Exhaust 5

B,H,S U,W,R,T.

Inboard. Valve HV-57-204-(Unit 2) 1

12. ' Suppression Pool Purge Exhaust 6

B,H,5,U,W,R,T Outboard Valve HV-57-212 (Unit 2)

I i

4 1

(a)See Specification 3.3.2, Table 3.3.2-1, for isolation signals that operate each automatic valve.

4 LIMERICK - UNIT 1 3/4 6-49 Amendment No. 23 I

f

{

s CONTAINMENT SYSTEMS

~{

REFUELING AREA SECONDARY CONTAINMENT AUTOMATIC ISOLATION VALVES f

LIMITING CONDITIOK70R OPERATION I

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 less than or ecual to the times shown.in Table 3.6.5.2.2-1.

APPLICA8!LITY: OPERATIONAL CONDITION *.

ACTION:

With one or more of the refueling area secondary containment vent;1ation system automatic isolation valves shown in Table 3.6.5.2.2-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration 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 af fect.d penetration by use of at least one closed manual valve, blind flange or slide gate damper.

l Otherwise, in Operational Condition *, suspend handling of irradiated fuel in 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 auto-matic isolation valve shown ja 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 isolaticn i

time.

1 b.

.At least once per 18 months by verifying that on a containment iseBation test signal each isolation valve actuates to its isolation position.

c.

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

When irradiated fuel is being handled in the refueling area secondary contain-ment. and during CORE ALTERATIONS and operations with a potential for drafning the reactor vessel.

I i

LIMERICK - UNIT 1 3/4 6-50 Asundment te. 6 L ',

JUl. 8 15 6.'

u sg.

N y

,n

)

y 1

,l

-!,1,

. TABLE 3.6.5.2.2-1 p

-REFUELING AREA' SECONDARY CONTAINMENT VENTILATION SYSTEM-

-AUTOMATIC ISOLATION VALVE 5 1

REFUELINGAREA([0kE-III)

MAXIMUM ISOLATION TIME-

. VALVE FUNCTION ISOLATIgg)'

j

_(Seconds)

' SIGNALS

1. ' Refueling A'rea Ventilation Supply Valve HV-76-117 (Uni t 1) 5

.R, T.

s 2.

Refueling %rea Ventilation Supply R,T.

J Valve HV-76-118;.(Unit 1) 5 3.

Refueling Area Ventilation Exhaust 1

]

Valve Hv-76-167 (Unit 1) 5

'R,T

'4.

Refueling Area Ventilation Exhaust Valve HV-76-168--(Unit 1) 5 R, T.

5. ; Refueling Area Ventilation Supply Valve HV-76-217'(Unit 2) 5

- R., T.

j','

6.

Refue;ing. Area Ventilation Supply Valve HV-76-218 (Unit 2) 5' R,T ' '

l; 7.

Refueling Area Ventilation Exhaust

~

Valve HV-76-267 (Unit 2) 5 R,T-

[:

i 8.

Refueling Area Ventilation Exhaust H

. Valve.HV-76-268 (Unit 2) 5 R,T-c'

[

9.

Drywell Purge Exhaust Valve HV-76-030 5

B',H,S,0jR'TJ

~

7 10.

Drywell' Purge Exhaust Valve HV-76-031 5

B H.,S,U,R;Tc Ill. _ Drywell Purge Exhaust Inboard 5

8,H,S,0,W,R,T, Valve.HV-57114'(Unit'1)-

12

'Drywell, Purge Exhaust Outboard 6

B,H,5,U,W,R,T j

Valve:HV-57-115 (Unit 1)'

r13;' Suppression Pool Purge Exhaust Inboard 5

.B,H,5,U,W,R,T m*

Valve HV-57-104 (Unit.1)

W' 14-Suppression Pool Purge Exhaust Outboard

.6 B'H.S,U,W,R,T.

4 Velve HV-57-112 (Unit'1)

't 5

)

g

!l;L (tl

..v I'.!'

,{

?-

LIMERICK UNIT I 3/4 6-51 Amendment No. 23

..j:

_-a-

'- - - - ' - ^ ~ ^ ' " ' " ^ ~~' ' ^ ^ ^

^

~

TABLE 3.6.5.2.2d (Continued)

REF'JELING AREA SECONDARY CONTAINMENT VENTILATION SYSTEM

~~

AUMHATIC ISOLATT5ff74IVES

~

c REFUELING AREA (20ffE IIQ MAXIMUM

~

~'

ISOLATICN TIME ISCLATigg)

I VALVE FUNCTION (Seconds)

SIGNALS 15.

Dry.' ell Purge Exhaust Inbaard 5

B,H,S,U,W,R,T I

Valve HV-57 214 (Unit 2)

\\

{

16.

Drywell Purge Exhaust Outboard 6

B,H,5,U,W,R,T

'/alve HV-57-215 (Unit 2) l

.j 17.

Suppression Pool Purge Exhaust Inboard 5

B,H,$,U,W,R,I j

valve HV-57-204 (Unit 2) l j

i 18.

Suppression Pool Purge Exhaust Outboard 6

B,H,5,U,W,R,T Yalve HV-57-212 (Unit 2) l l

i i

i l

I l

I (a) See Specification 3.3.2, Table 3.3.2-1, for isolation signals that operate each automatic isolation valve.

LIMERICK - UNIT 1 3/4 6-51a Amendment No. 23 l

~

ML20245C255

Text

Attachment:

Attachment:

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