ML20245F910

From kanterella
Jump to navigation Jump to search
Amend 27 to License NPF-39,revising Tech Specs Re RHR & Emergency Svc Water Sys to Reflect Unit Operation
ML20245F910
Person / Time
Site: Limerick Constellation icon.png
Issue date: 06/20/1989
From: Butler W
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20245F914 List:
References
NUDOCS 8906280293
Download: ML20245F910 (15)
v • d • e


Text

_

.. A

/ fL Kf0g%

g UNITED STATES NUCLEAR REGULATORY COMMISSION n

h WASHINGTON, D. C. 20555

/

^

PHILADELPHIA ELECTRIC COMPANY DOCKET NO. 50-352 LIMERICK GENERATING STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 27 License No. NPF-39 1.

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

The application for amendment by Philadelphia Electric Company (thelicensee)datedApril 10, 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 Comission; C.

There is reasonable assurance (1) that the activities authorized by this amendment can be conducted withoet 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 and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicatcd 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 l

through Amendment No. 27, are hereby incorporated into this license. Philadelphia Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Irotection Plan.

8906280293 890620

~

PDR ADDCK 05000352 ya P

PNV

~

.)

y 7 -

RA..

I 4.

2-3.

This-license' amendment'is effective upon issuance.of an operating license to Limerick Generating Station, Unit No. 2.

('

FOR THE NUCLEAR REGULATORY COMMISSION

/s/

Walter R. Butler, Director.

Project Directorate'I-2.

Division of Reactor-Projects I/II-

Attachment:

Changes to.the Technical Specifications P

Date of Issuance: June 20, 1989 r

1 L

,e

}

M f

)

PDI-2/D PDI-2/PM OG 1.

en

'RClark:

At t WButler p '

W,/s(/89 ff/9 (p /20/89 g/g89 C=__.i_ _ _ _ __ _

i L

L.

'3.-

This license amendment'is effective upon. issuance 'of an operating license to Limerick. Generating ~ Station, Unit No. 2.

l

- 3 FOR THE NUCLEAR REGULATORY COMMISSION v

Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II c.

Attachment:

Changes to'the. Technical

' Specifications-Date of Issuance: June 20, 1989 W

I e

0 0

_______E._______-_-

ATTACHMENT T0 1.ICENSE AMENDMENT NO.

27 FACILITY OPERATING LICENSE NO. NPF-39 DOCKET NO. 50-352 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contains vertical lines indicating the area of change, Overleaf pages are provided to maintain document completeness.*

Remove Insert xiii xiii xiv xiv*

xxi xxi xxii xxii

  • 3/4 7-1 3/4 7-1 3/4 7-2 3/4 7-2 3/4 7-3 3/4 7-3 3/4 7,4 3/4 7-4 B 3/4 7-1 B 3/4 7-1 B 3/4 7-2 B 3/4 7-la B 3/4 7-2 i

I I

1 j

l i

l INDEX i

LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS

{

l SECTION PAGE i

CONTAINMENT SYSTEMS (Continued)

)

)

3/4.6.4 VACUUM RELIEF Suppression Chamber - Drywell Vacuum Breakers...........

3/4 6-44 3/4.6.5 SECONDARY CONTAINMENT Reactor Enclosure Secondary Containment Integrity.......

3/4 6-46 Refueling Area Secondary Containment Integrity..........

3/4 6-47 Reactor Enclosure Secondary Containment Automatic Isolation Va1ves........................................

3/4 6-48 Table 3.6.5.2.1-1 Reactor Enclosure Secondary Containment Ventilation System Automatic Isolation Valves..........................

3/4 6-49 Refueling Area Secondary Containment Automatic Isolation Va1ves........................................

3/4 6-50 Table 3.6.5.2.2-1 Refueling Area Secondary Contain-ment Ventilation System Automatic Isolation Valves................

3/4 6-51 Standby Gas Treatment System............................

3/4 6-52 Reactor Enclosure Recirculation System..................

3/4 6-55 3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE CONTROL Primary Containment Hydrogen Recombiner Systems.........

3/4 6-57 Drywell Hydrogen Mixing System..........................

3/4 6-58 Drywell and Suppression Chamber Oxygen Concentration....

3/4 6-59 3/4.7 PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS Residual Heat Removal Service Water System - Common System..................................................

3/4 7-1 Emergency Service Water System - Common System..........

3/4 7-3 l

Ultimate Heat Sink......................................

3/4 7-5 LIMERICK - UNIT 1 xiii Amendment No. 27

INDEX LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS SECTION PAGE PLANT SYSTEMS (Continued) 3/4.7.2 CONTROL-ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM..........

3/4 7-6 l

3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM...................

3/4 7-9 3/4.7.4 SNUBB~RS................................................

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 CO Systems.r...........................................

3/4 7-24 2

Halon Systems.......~.....................................

3/4 7-25 Fire Hose Stations......................................

3/4 7-?6 Table 3.7.6.5-1 Fire Hose Stations................

3/4 7-27 Yard Fire Hydrants and Hydrant Hose. Houses..............

3/4 7-29 Table 3.7.6.6-1 Yard Fire Hydrants and Associated I

Hydrant Hose Houses...............

3/4 7-30 3/4.7.7 FIRE RATED ASSEMBLIES...................................

3/4 7-31 3/4.8 ELECTRICAL POWER SYSTEMS j

3/4.8.1 A.C. SOURCES A.C. Sources - Operating................................

3/4 8-1 i

Table 4.8.1.1.2-1 Diesel Generator Test Schedule...............

3/4 8-8 A.C. Sources - Shutdown.................................

3/4 8-9 3/4.8.2 0.C. SOURCES

I 0.C. Sources - Operating................................

3/4 8-10 LIMERICK - UNIT 1 xiv

-__._._m._._____.____._._..m___

I

.p i

INDEX

)

' BASES SECTION PAGE

)

i CONTAINMENT SYSTEMS (Continued) j 3/4.6.3

-PRIMARY CONTAINMENT ISOLATION VALVES...............

8 3/4 6-4 1

3/4.6.4 VACUUM RELIEF......................................

B 3/4 6-4 l

1 3/4.6.5 SECONDARY C0NTAINMEVT..............................

B 3/4 6-5 1

3/4.6.6 PRIMARY CONTAINMENT ATMOSPHERE' CONTROL.............

B 3/4 6-6 3/4.' 7 - PLANT SYSTEMS 3/4.7.1 SERVICE WATER SYSTEMS - COMMON SYSTEMS.............

B 3/4 7-1 3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM.....

B 3/4 7-1 3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM...............

B 3/4 7-1 3/4.7.4 SNUBBERS"............................................

B 3/4 7-2 3/4.7.5 SEALED SOURCE CONTAMINATION........................

B 3/4 7-3 3/4.J. 6 FIRE SUPPRESSION SYSTEMS........................

B 3/4 7-4 3/4.7.7 FIRE RATED ASSEMBLIES..................

B 3/4 7-4 3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1, 3/4.8.2, and 3/4.8.3 A.C. SOURCES, D.C. SOURCES, 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 LPERATIONS 3/4.9.1 REACTOR MODE SWITCH................................

B 3/4 9-1 3/4.9.2 INSTRUMENTATION....................................

B 3/4 9-1 3/4.9.3 CONTROL R0D P0SITION...............................

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 Amendment No. 27

z h,

'[

1 p

L} i p

b INDEX:

BASES L

SECTIONf PAGE REFUELING OPERATIONS:(Continued) oq '

3/4.9.6 REFUELING PLATF0RM................................

83/49-2' 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P00L............

B 3/4 9-2' 3/4.9.8 and 3/4.9.9 WATER LEVEL - REACTOR VESSEL and WATER LEVEL - SPENT FUEL STORAGE P00L.........

B 3/4.9-2 3/4.9.10 ' CONTROL R00 REM 0 VAL...............................

B 3/4 9-2 L

3/4.9.11 ' RESIDUAL'H' EAT REMOVAL AND COOLANT CIRCULATION.....

B 3/4'9.3/4.'10?SPECIAL TEST EXCEPTIONS 3/4.10.1 PRIMARY CONTAINMENT INTEGRITY.....................

B 3/4 10-1 3/4.10.2 ER00 WORTH MINIMIZER................................

B 3/4 10-1:

3/4.10;3 SHUTDOWN MARGIN DEMONSTRATIONS...................

B 3/4 10-1 3/4.10.4 RECIRCULATION L00RS...............................

B 3/4 10-1 3/4.10.5 OXYGEN CONCENTRATION....................,.........

B 3/4 10-1 3/4~10.6 TRAINING STARTUPS.................................

B 3/4 10-1

~3/4.11 RADIOACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS Concentration...............................

B 3/4 11-1 0ose..............................................

B 3/4 11-1 Liquid Radwaste Treatment System..................

B 3/4 11-2 Liquid Holdup Tanks...............................

B 3/4 11-2 3/4.11.2 GASEOUS EFFLUENTS Dose Rate.........................................

B 3/4 11-2 Dose - Noble Gases................................

B 3/4 11-3 Dose

' Iodine-131. Iodine-133, Tritium, and Radionuclides in Particulate Form..................

B 3/4 11-3 Ventilation Exhaust Treatment System..............

B 3/4 11-4 LIMER'ICK - UNIT 1 xxii Amendment No. 17 MAR 2 21989

3/4.7 PLANT S'YSTEMS

-3/4.7.1 SERVICE WATER SYSTEMS RESIDUAL HEAT REMOVAL SERVICE WATER SYSTEM - COMMON SYSTEM i

LIMITING CONDITION FOR OPERATION 3.7.1.1 At least the following independent residual heat removal service. water (RHRSW) system subsystems, with each subsystem comprised of:

a.

Two OPERABLE RHRSW pumps, and b.

An OPERABLE flow path capable of taking suction from the RHR service water pumps wet pits which are supplied from the spray pond or the cooling tower basin and transferring the water through one Unit 1 l

RHR heat exchanger, shall be OPERABLE:

a.

In OPERATIONAL CONDITIONS 1, 2, and 3, two subsystems.

b.

In OPERATIONAL CONDITIONS 4 and 5, the subsystem (s) associated with systems and components required OPERABLE by Specification 3.4.9.2, 3.9.11.1, and 3.9.11.2.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

ACTION:

a.

In OPERATIONAL CONDITION 1, 2, or 3:

_1.

With one RHRSW pump inoperable, restore the inoperable pump to OPERABLE status within 30 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2.

With one RHRSW pump in each subsystem inoperable, restore at least one of the inoperable RHRSW pumps to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

3.

With one RHRSW subsystem otherwise inoperable, restore the inoperable subsystem to OPERABLE status with at least one OPERABLE RHRSW pump within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.

With both RHRSW subsystems otherwise inoperable, restore at least one subsystem to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN

  • within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as I

l

-low as practical by use of alternate heat removal methods.

?

LIMERICK - UNIT 1 3/4 7-1 Amendment No. 27 L-_--___-

PLANT SYSTEftS

' ' ]

i LIMITING CONDITION FOR OPERATION (Continued) l q

ACTION:

(Continued)

- 5.

With two RHRSW pump / diesel generator pairs

at least one inoperable RHRSW pump / diesel generator pair ^ to OPERABLE status within 30 days, or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

The provisions of specification 3.0.4 are not

j.

applicable.

]

6.

With three RHR$W pump / diesel generator pairs

]

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24-hours.

7.

With four RHRSW pump / diesel generator pairs

  • to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be-in at least HOT SHUTDOWN within.the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, b.

In OPERATIONAL CONDITION 3 or 4 with the RHRSW subsystem (s), which is associated with an RHR loop required OPERABLE by Specification i

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 j

3.4.9.2, as applicable.

c.

.In OPERATIONAL CONDITION 5 with the RHRSW subsystem (s), which is associated with an RHR loop required.0PERABLE 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 3.9.11.2, as applicable.

)

l SURVEILLANCE REQUIREMENTS 4.7.1.1 At least the above required residual heat removal service water system subsystem (s) shall be demonstrated OPERABLE:

i.

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 l

in its correct position, j

1 i

  • A RHRSW pump / diesel generator pair consists of a RHRSW pump and its associated i

diesel generator.

If either a RHRSW pump or its associated diesel generator becomes inoperable, then the RHRSW pump / diesel general pair is' inoperable.

8 I

LIMERICK - UNIT 1 3/4 7-2 Amendment No. 27

f:5.

i g

E l

PLANT SYSTEMS q

L EMERGENCY. SERVICE WATER ~ SYSTEM LIMITING CONDITION FOR OPERATION

~

3. 7.1. 2 At least the following independent emergency service water. system loops, with each loop comprised of:

a.

Two OPERABLE emergency service water pumps, and-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 the cooling tower basin and transferring the water to the associated Unit.I and-common safety-related equipment, shall be OPERABLE:

a.

In OPERATIONAL CONDITIONS 1, 2, ar.d 3, two loops.

b.

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

APPLICABILITY:' OPERATIONAL CONDITI0h51, 2, 3, 4, 5, and *.

ACTION:

. 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 i

least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

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 status with at least one OPERABLE pump within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

    • The diesel generators may be aligned to the OPERABLE emergency service water system loop provided confirmatory flow testing has been performed.

Those diesel generators not 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 Amendment No. 27

L PLANT SYSTEMS'

~

l1

. LIMITING CONDITION FOR OPERATION (Continued) 4.

With three ESW pump /diese1' generator pairs ** inoperable, restore at least one_ inoperable ESW pump / diesel generator pair ** to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least HOT SHUTDOWN within the next 12 hcurs and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5.

With four 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in~ COLD SHUTDOWN within the-following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

In OPERATIONAL CONDITION 4 or 5:

1.

With only one emergency 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 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 path OPERABLE,-restore at least two pumps with at least:

one flow path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or verify adequate cooling remains available for the diesel' generators required to be'0PERABLE or declare the associated diesel generator (s) inoperable and take the ACTION required by Specification 3.8.1.2.

The provisions of Specification 3.0.3-are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.1.2 At least 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 position.

f 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 j

generator starts.

1

.]

    • An ESW pump / diesel generator pair consists of an ESW pump and its associated diesel 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 Amendment No. 27

1 23/4.7 PLANT SYSTEMS BASES 1

3/4.7.1 SERVICE WATER SYSTEMS - COMMON SYSTEMS The OPERABILITY of the service water systems ensures that sufficient cooling capacity is available for continued operation of safety-related equipment during normal and accident conditions.

The redundant cooling capacity of these systems, assuming a single failure, is consistent with the assumptions used in-the accident conditions within acceptable limits.

{

The RHR and ESW systems are common to Units 1 and 2 and consist of two independent subsystems each with two pumps. -One pump per subsystem (loop) is pcwered from a Unit 1 safeguard bus and the other pump is powered from a Unit 2 safeguard bus.

In order to ensure adequate onsite power sources to the systems during a loss of offsite power event, the inoperability of these supplies are restricted in system ACTION statements.

RHRSW is a manually operated system used for core and containment heat removal.

Each of two RHRSW subsystems has one heat exchanger per unit.

Each RHRSW pump provides adequate cooling for one RHR heat exchanger.

By limiting operation with less than three OPERABLE RHRSW pumps with OPERABLE Diesel Generators, each unit is ensured adequate heat removal capability for the design scenario of LOCA/ LOOP on one unit and simultaneous safe shutdown of the other unit.

Each ESW pump provides adequate flow to the cooling loads in its associated loop. With only two divisions of power required for LOCA mitigation of one unit and one division of power required for safe shutdown of the other unit, one ESW pump provides sufficient capacity to fulfill design requirements.

ESW pumps are automatically started upon start of the associated Diesel Generators.

Therefore, the allowable out of service times for OPERABLE ESW pumps and their associated Diesel Generators is limited to ensure adequate cooling during a loss of offsite power event.

I i

LIMERICK - UNIT 1 B 3/4 7-1 Amendment No. 27

PLANT SYSTEMS

)

i BASES l

3/4.7.2 CONTROL ROOM EMERGENCY FRESH AIR SUPPLY SYSTEM j

The OPERABILITY 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 1 cfm is sufficient to reduce the buildup of moisture on the 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 f

Design Criterion 19 of Appendix A, 10 CFR Part 50.

j i

3/4.7.3 REACTOR CORE ISOLATION COOLING SYSTEM The reactor core isolation cooling (RCIC) system is provided to assure adequate core cooling in the event of reactor isolation from its primary heat j

sink and the loss of feedwater flow to the reactor vessel without requiring i

actuation of any of the emergency core cooling system equipment.

The RCIC system is conservatively equired to be OPERABLE whenever reactor pressure ex-ceeds 150 psig.

This pre.sure is substantially below that for which low pressure core cooling systems can provide adequate core cooling.

The RCIC system specifications are applicable during OPERATIONAL CONDITIONS 1, 2, 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.

With the RCIC system inoperable, adequate core cooling is assured by the g

OPERABILITY of the HPCI system and justifies the specified 14 day out-of service 1

period.

"he 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 Amendment No. 27

PLANT SYSTEMS l

BASES i

i 3/4.7.4 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.

Snub-bers excluded from this inspection program are those installed on nonsafety-related systems and then only if their failure or failure of the system on which they are installed would have no adverse effect on any safety related system.

Snubbers are classified and grouped by design and manufacturer but not by size.

For example, mechanical snubbers utilizing the same design features of the 2-kip,10-kip, and 100-kip capacity manufactured by Company "A" are of the same type.

The same design mechanical snubbers manufactured by Company "B" for the purposes of this Technical Specification would be of a different type, as would hydraulic snubbers from either manufacturer.

A list of individual snubbers with detailed information of snubber location and size and of system affected shall be available at the plant in accordance with Section 50.71(c) of 10 CFR Part 50.

The accessibility of each snubber shall be determined and approved by the Plant Operations Review Committee.

The determination shall be based upon the existing radiation levels and the expected time to. perform a' visual inspection in each snubber location as well as other factors associated with accessibility during plant operations (e.g.,

temperature, atmosphere, location, etc.), and the recommendations of Regulatory Guides 8.8 and 8.10.

The addition or deletion of any snubber shall be made in accordance with Section 50.59 of 10 CFR Part 50.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to each safety-related system.

Therefore, the required inspection interval varies inversely with the observed snubber failures on a given system and is determined by the number of inoperable snubbers found during an inspection of each system.

In order to establish the inspection frequency for each type of snubber on a safety-related system, it was assumed that the frequency of snubber failures and initiating events is constant with time and that the failure of any snubber on that system could cause the system to be unprotected and to result in failure during an assumed initiating event.

inspections performed before that interval has elapsed may be used as a new reference point to determine the next inspection.

However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspec-tion interval.

Any inspection whose results required a shorter inspection interval will override the previous schedule.

The acceptance criteria are to be used in the visual inspection to determine OPERABILITY of the snubbers.

LIMERICK - UNIT 1 B 3/4 7-2

t 8

4 e

e

+

0 0

9:

a e

I

(

l I

i 1

I I

Retrieved from "https://kanterella.com/w/index.php?title=ML20245F910&oldid=3910020"