ML20108A656

Proposed Tech Specs Re Part of Overall Effort to Improve Outage Performance at Plant

ML20108A656
Person / Time
Site:	Pilgrim
Issue date:	04/25/1996
From:	BOSTON EDISON CO.
To:
Shared Package
ML20108A648	List: BECO-LTR-96-040, Application for Amend to License DPR-35,proposing Part of Overall Effort to Improve Outage Performance at Plant ML20108A656
References
NUDOCS 9605020349
Download: ML20108A656 (29)

Text

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l 1.0 DEFINITIO.NR The succeeding frequently used terms are explicitly defined so that a uniform interpretation of the specifications may be achieved.

A. Safety Limit - The safety limits are limits below which the reasonable maintenance o' the cladding and primary systems are assured. Exceeding such a limit is cause for unit shutdown and review by the Nuclear Regulatory Commission before resumption of unit i

operation. Operation beyond such a limit may not in itself result in serious consequences but it indicates an operational deficiency subject to regulatory review.

B. Limitina Safety System Settino (LSSS) - The limiting safety system settings are settings on instrumentation which initiate the automatic protective action at a level such that the safety limits will not be exceeded. The region between the safety limit and these settings represent margin with normal operation lying below these settings. The margin has been established so that with proper operation of the instrumentation the safety limits will never be exceeded.

C. Limitina Conditions for Ooeration (LCO) - The limiting conditions for operation specify the minimum acceptable levels of system performance necessary to assure safe startup and operation of the facility. When these conditions are met, the plant can be operated safely and abnormal situations can be safely controlled.

D. Core Ooeratina Limits Reoort The CORE OPERATING LIMITS REPORT is a reload-cycle specific document, its supplements and revisions, that provides core operating limits for the current operating reload cycle.

These cycle specific core operating limits shall be determined for each reload cycle in l accordance with Specification 6.9.A.4. Plant operation within these operating limits is addressed in individual specifications.

E. Ooerable - Ooerability A system, subsystem, train, component or device shall be Operable or have Operability when it is capable of performing its specified function (s), implicit in this definition shall be the assumption that all necessary attendant instrumentation, controls, normal or emergency l electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

F. Operatina - Operating means that a system or component is performing its intended functions in its required manner.

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Amendment No. 443 1-1 9605020349 960425 PDR ADOCK 05000293 P PDR l

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I LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS

1

! 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM j (Cont) (Cont)

A. Normal System Availabilitv (Cont)

b. At least once during each refueling interval, while testing as specified in 3.13, manually initiate one of the Standby Liquid Control System loops l and pump demineralized water into the l reactor vessel.

This test checks explosion of the charge ,

l associated with the tested loop, proper l l operation of the valves, and pump l l

operability. He replacement charges to l be installed will be selected from the same manufactured batch as the tested l charg,e.

c. When testmg to satisfy requirement 4.4.A.2.b, both systems, including both i explosive valves, shall be tested in the ,

j course of two refueling intervals. l l

i B. Operation with Inooeisbjg Surveillance with Inoperable B. i Components: ~

Comoonents:

1. From and after the date that a redundant 1. When a component is found to be

component is made or fo'md to be inoperable, its redundant component shall l moperable, Specification 3.4.A.1 shall be be demonstrated to be operable immediate*' i considered fulfilled and cantinued operation and Ely thereafter until the inoperable permitted provided that the diesel generator component is repaired.

associated with the operable subsystem is operable and, the component is returned to

an operable condition within seven days.

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Amendment No. M2d49 3/4.4-2 1

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LIMITING CONDITION FOR OP,F. RATION SURVEILLI ACE REOUIREMENT 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING '

, SYSTEMS (Cont) SYSTEMS (Cont) t F. Minimum Low Pressure Cagline and Diesel F. Minimum Low Pressure Coolina and Diesel Generator Anilability Generator Availability

1. During any penod when one diesel 1. ' Wen it is determined that one diesel i generator is inoperable, continued reactor generator is inoperable, withia 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, j operation is permissible only during the determme that the operable diesel generator l

succeeding 14 days unless such diesel is not inoperable due to a common cause 1 l generator is sooner made operable, provided failure, or perform surveillance 4.9.A.I.a

! that all of the low pressure core and for the operable diesel generator, a_nd l i containment cooling systems are operable once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> verify correct breaker I and the remaining diesel generator is alignment and indicated power availability I l

operable in accordance with 4.5.F.1. If this for each offsite circuit.

l [ requirement cannot be met, an orderly l shutdown shall be initiated and the reactor i shall be placed in the Cold Shutdown i Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l

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2. Any combination ofinoperable components  ;

in the core and containment cooling systems )

shall not defeat the capability of the l

remaining operable components to fulfill the cooling functions.

! 3. When irradiated fuel is in the reactor vessel i and the reactor is in the Cold Shutdown

! condition, both core spray systems, the LPCI and containment cooling systems may l be inoperable, provided no work is being l done which has the poter+ial for draining the reactor vessel.

4. During a refueling outage, for a period of 30 days, refueling operation may continue provided that one core spray system or the LPCI system is operable or Specification ,

3.5.F.5 is met. l l

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Amendment No.15r445 3/4.5 7

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

A. Primary Containment (Cont)

With no H 2analyzer operable, reactor operation is allowed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. If one of the inoperable analyzers is not made fully operable within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall be in a least Hot Shutdown within the next 12 hovrs.

B. Standby Gas Treatment Svstem and Control Room High Efficiency Air Filtration System

1. Standby Gas Treatment System B. Standby Gas Treatment System and Control Room High Efficiency Air Filtration System

a. Except as specified in 3.7.B.I.c or 1. Standby Gas Treatment System 3.7.B.I.e below, both trains.of the standby gas treatment system shall be

a. 1. At least once per operating cycle' operable at all times when secondary it shall be demonstrated that containment integrity is required.

pressure drop across the combined high efficiency filters and charcoal

b. 1. The results of the in-place cold adsorber banks is less than 8 DOP tests on HEPA filters shall mches of water at 4000 cfm.

show 299% DOP removal. The results of halogenated 2. At least once per operating cycle, bydrocarbon tests on charcoal demonstrate that the inlet heaters adsorber banks shall show 299% on each train are operable and are halogenated hydrocarbon removal. capable of an output of at least 14 kW.

3. 'Ihe tests and analysis of Specification 3.7.B.I.b. shall be performed at least once per operating cycle or following painting, fire or chemical release in any ventilation zone communicating with the system while the system is operating that could contammate the HEPA filters or charcoal adsorbers.

4. At least once per operating cycle, automatic initiation of e

Amendment No. 45, 12,50,51,52,!!2, ! ", 151, 161 3/4.7-11

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l LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

! 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B. Standbv Gas Treatment System and Control 8. Standbv Gas Treatment System and Control Room Hiah Efficiency Air Filtration Syste n . Room Hiah Efficiency Air Filtration Svstem i

! (Cont) (Cont)

2. The results of the iaboratory each branch of the standby gas carbon sample analysis shall treatment system shall bs show 295% methyliodide demonstrated, with removal at a velocity within Specification 3.7.B.1.d 10% of system design,0.5 to satisfied.

1.5 mg/m3 inlet methyliodide concentration, 270% R.H. and 5. Each train of the standby gas 2190*F. The analysis results treatment system shall be are to be verified as acceptable operated for at least 15 minutes within 31 days after sample per month.

removal, or declare that train inoperable and take the actions 6. The tests and analysis of specified 3.7.B.1.c. Specification 3.7.B.1.b.2 shall i be performed after every 720 c From and after the date that one hours of system operation.

train of the Standby Gas Treatment System is made or found to be b. 1. In-place cold DOP testing shall inoperable for any reason, be performed on the HEPA l l continued reactor operation, filters after each completed or irradiated fuel handling, or new fuel partial replacement of the HEPA l handling over the spent fuel pool is filter bank and after any permissible only during the structural maintenance on the succeeding seven days providing HEPA filter system housing that within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> all active which could affect the HEPA I components of the other standby filter bank bypass leakage.

gas treatment train are demonstrated to be operable and 2. Halogenated hydrocarbon the diesel generator associated with testing shall be performed on the operable train is operabla. the charcoal adsorber bank after each partial or ccmplete if the system is not made fully replacement of the charcoal operable within 7 days, reactor adsorber bank or after any shutdown shall be initiated and the structural maintenance on the reactor shall be in cold shutdown charcoal adsorber housing within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and fuel which could affect the charcoal

! handling operations shall be adsorber bank bypass leakage.

terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Fuel handling operations in progress may be completed.

I Amendment No. 42.*^,51,!!2.!!!,10 3/4.7-12

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LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B. Standby Gas Treatment System and Control B. Standby Gas Treatment System and Control Room High Efficiency Air Filtration System Room Hich Efficienev Air Filtration System '

l (Cont) (Cont)

d. Fans shall operate within

• 10% of l

4000 cfm.

e. From and after the date that one train i of the Standby Gss Treatment System i is made or found to be inoperable for any reason during Refuel Outages, refueling operations are permissible only during the succeeding 7 days i providing that within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> all active components of the other train are l demonstrated to bc operable and the diesel generator associated with the operable train is operable.

If the system is not made fully operable within 7 days, l i) place the operable train in operation l immediately or l ii) suspend movement ofirradiated l fuel assemblies in secondary

containment or new fuel handling over

! the spent fuel pool or core.

Any fuel assembly movement in progress may be completed.

Amendment No. 12, 50, 51, 52,101, ! !2, !",161rM1 i 3/4.7-13 i

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B. Standby Gas Treatrecr.t System and Control B. Standby Gas Treatment System and Control Room High Efficiency Air Filtration System Room High Efficiency Air Filtration System (Cont) - (Cont)

2. . Control Room High Efficiency Air 2. Control Room High Efficiency Air Filtration System Filtration System  !

a Except as specified in Specification a. At least once per operating cycle the 3.7.B.2.c.or 3.7.B.2.e below, both pressure drop across each combined trains of the Control Room High filter train shall be demonstrated to be Efficiency Air Filtration System used less than 6 inches of water at 1000

- for the processing ofinlet air to the efm or the calculated equivalent.

control room under accident conditions shall be operable whenever secondary b. 1. He tests and analysis of containment integrity is required. ' Specification 3.7.B.2.b shall be performed once per operating

b. 1. The results of the in-place cold cycle or following painting, fire or DOP tests on HEPA filters shall chemical release in any ventilation show 299% DOP removal. The zone communicating with the results of the halogenated system while the system is hydrocarbon tests on charcoal operating.

adsorber banks shall show 299%

halogenated hydrocarbon removal 2. In-place cold DOP testing shall be when test results are extrapolated performed after each complete or to the initiation of the test. partial replacement of the HEPA filter bank or after any structural

2. He results of the laboratory maintenance on the system carbon sample analysis shall show housing which could affect the  ;

295% methyl iodide removal at a HEPA filter bank bypass leakage.  ;

velocity within 10% of system design,0.05 to 0.15 mg/m3 inlet 3. Halogenated hydrocarbon testing methyliodide concentration, shall be performed after each 270% R.H., and 2125 F. De complete or partial replacement of analysis results are to be verified the charcoal adsorber bank or as acceptable within 31 days after after any structural maintenance sample removal, or declare that on the system housing which could train inoperable and take the affect the charcoal adsorber bank actions specified in 3.7.B.2.c. bypass leakage.

4. Each train shall be operated with the heaters in automatic for at least 15 minutes every month.

I Amendment i  !,50,52,!!2,!'!,151,16! 3/4.7-14

1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B. Standbv Gas Treatment System and Control B. 3.tandbv Gas Treatment System and Cong l Room Hiah Efficiency Air Filtration Svstem Room Hioh Efficiency Air Filtration Svstem (Cont) (Cont)

5. The test and analysis of Specification 3.7 B.2.b.2 shall be performed after every 720 c From and after the date that one train of the Control Room High c. At least once per_ operating cycle Efficiency Air Filtration System is demonstrate that the inlet heaters made or found to be inoperable for on each train are operable and  !

any reason, reactor operation, capable of an output of at least 14 i irradiated fuel handling, or new fuel . kw. l handling over the spent fuel pool is permissible only during the I succeeding 7 days providing that d. Perform an instrument functional within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> all active test on the humidistats controlling components of the othar CRHEAF the heaters once per operating train are demonstrated to be cycle, l' operable and the diesel generator associated with the operable train is operable. If the system is not made i fully operable within 7 days, reactor shutdown shall be initiated and the reactor shall be in cold shutdown within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and fuel handling operations shall be terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. Fuel handling operations in progress may  ;

be completed.

d. Fans shall operate within i 10% of 1000 cfm.

e. From and after the date that one train of the Control Room High Efficiency Air Filtration System is made or found to be inoperable for any reason during Refuel Outages, refueling operations are permissible only during the succeeding 7 days providing that within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> all active components of the other train are demonstrated to be operable and the diesel generator associated with the operable train is operable.

If the system is not made fully operable within 7 days, Amendment No. 12,50,51,$?,!!2,It',151,15! 3/4,7 15

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REOUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont) i) perform surveillance 4.7.B.2.b.4 for the operable CRHEAF every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> M

l ii) suspend movement ofirradiated j fuel assemblies in secondary

! containment or new fuel handling over the spent fuel pool or core.

l Any fuel assembly movement in progress l may be completed.

C. Secondary Containment

1. Secondary containment surveillance shall j

1. Secondary containment integrity shall be be performed as indicated below:

maintamed during all modes of plant operation except when all of the following a. A preoperational secondary conditions are met. containment

apability test shall be conducted after isolating the reactor

a. The reactor is suben. .tical and building and placing either standby Specification 3.3.A is met. gas treatment system filter train in operation. Such tests shall

b. The reactor water temperature is demonstrate the capability to maintain below 212 F and the reactor coolant 1/4 nch of water vacuum under calm system is vented. wind (<5 mph) conditions with a filter

.. . train flow rate of not more than 4000 ,

c. No activity is being performed which cfm' can reduce the shutdown margin below i that specified in Specification 3.3.A. b. Additional tests shall be performed

. . during the first operating cycle under e d. The fuel cask or irradiated fuel is not an adequate number of different l l being moved in the reactor building. environmental wind conditions to enable valid extrapolation of the test l

2. If Specification 3.7.C.1 cannot be met, results' procedures shall be initiated to establish conditions listed in Specification 3.7.C.I.a c. Secondary containment capability to l through d. maintain 1/4 inch of water vacuu'm under i

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1 Amendment No. W 3/4.7 16

LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM (Cont) (Cont)

B. Operation with Inocerable Eauipment A. Auxiliary Electrical Equioment Surveillance Whenever the reactoris in Run Mode or (Cont)

3. ses 5-A6 Startup Mode with the reactor not in a Cold Condition, the availability of electric power rg4 shall be as specified in 3.9.B.1,3.9.B.2, 3.9.B.3, 3.9.B.4, and 3.9.B.5- a. Once each operating cycle, calibrate the alarm sensor.

1. From and after the date that incoming b. Once each 31 davs perform a channel

[ power is not available from the startup or functional test oi the alarm system.

shutdown transformer, continued reactor operation is permissible under this c. In the event the alarm system is l- condition for: determined inoperable under 3.b above, commence logging safety a) 3 days with the startup related bus voltage every 30 minutes transformerinoperable 91 until such time as the alarm is restored to operable status.

b) 7 days with the shutdown l transformer inoperable. 4. RPS Electrical Protection Assemblies During this period, both diesel generators a. Each pair of redundant RPS EPAs and associated emergency buses must be shall be determined to be operable at operable. least once per 6 months by j performance of an instrument l 2. From and after the date that incoming functional test.

power is not available from both startup and shutdown transformers, continued b. Once per 18 months each pair of l operation is permissible, provided both redundant RPS EPAs shall be diesel generators and associated determmed to be operable by l emergency buses are operable, all core and performance of an instrument 8 containment cooling systems are operable, calibration and by verifying tripping reactor power level is reduced to 25% of of the circuit breakers upon the design and the NRC is notified within one simulated conditions for automatic l (1) hour as required by 10CFR50.72. actuation of the protective relays -l within the following limits: l

! 3. From and after the date that one of the i diesel generators or associated emergency Overvoltage < 132 volts  ;

bus is made or found to be inoperable for Undervoltage 2108 volts i any reason, continued reactor operation is Underfrequency 257H z  !

permissible in accordance with Specifications 3.4.B.1, 3.5.F.1, 3.7.B. I .c, j 3.7.B.I.e,3.7.B.2.c, and 3.7.B.2.e if Specification 3.9.A.1 and 3.9.A.2.a are  ;

satisfied. j

4. From and after the date that one of the  ;

l. diesel generators or associated emergency ,

!- buses and either the shutdown or startup -l transformer power source are t l Amendment No. SS,127, H5,151 3/4.9-4

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REOUIREMENTS 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 AUXILIARY ELECTRICAL SYSTEM (Cont) (Cont)

B. Operation with Inoperable Eauipment (Cont) ,

made or found to be inoperable for any

! reason, continued reactor operation is permissible in accordance with Specification 3.5.F:

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a. For 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> provided the startup l l transformer and both offsite 345 kV transmission lines are available and capable of automatically supplying auxiliary power to the emergency 4160 volt buses.

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( b. For 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> provided a transmission line and associated shutdown transformer are available and capable of automatically supplying auxiliary l power to the emergency 4160 volt buses.

l S. From and after the date that one of the 125 or 250 volt battery systems is made or found to be inoperable for any reason, -

continued reactor operation is permissible during the succeedmg three days within electncal safety considerations, prosided repair work isinitiated in the most expeditious manner to return the failed component to an operable state, and Specification 3.5.F is satisfied.

6. With the emergency bus voltage less than j 3958.5V but above 3878.7V(excluding

transients) during normal operation,

! transfer the safety related buses to the diesel generators. If grid voltage continues to degrade be in at least Hot Shutdown within the next 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> and in Cold Shutdown within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> unless the grid conditions improve.

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Amendment No.42, 61, SS,120,127, !M 3/4.9-5 l

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BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont)

B.2 Control Room High Efficiency Air Filtration System (Cont)

The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly.

The filter testing is performed pursuant to appropriate procedures reviewed and approved by the Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing of charcoal filters is perfonned by injecting a halogenated hydrocarbon intc, the system upstream of the charcoal adsorbers. Measurements of the concentration upstream and downstream are made. The ratio of the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. A similar procedure substituting dioctyi phthalate for halogenated hydrocarbon is used to test the HEPA filters.

Air flow through the filters and charcoal adsorbers for 15 minutes each month assures operability of the system. Since the system heaters are automatically controlled, the air flowing through the filters and adsorbers will be 570% relative humidity and will have the desired drying effect.

If one train of the system is found to be inoperable, there is no immediate threat to the control room, and l

reactor operation or fue handling may continue for a limited period of time while repairs are being made.

In the event one CRHEAF train is inoperable, the redundant system's active components will be tested within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. During refueling outages, if the inoperable train is not restored to operable status within the required completion time, refueling operations may continue provided the operable CRHEAF train is placed in the pressurization mode daily. This action ensures that the remaining train is operable, that no failures that would prevent actuation will occur, and that any active failure will be readily detected. An alternative is to suspend activities that present a potential for releasing radioactivity that might require isolation of the control room. If both trains of the CRHEAF system are inoperable, the reactor will be brought to a condition where the Control Room High Efficiency Air Filtration System is not required.

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I Amendment No. 43r-H4 B3/4.7-12 l

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BASES:

3/4.7 CONTAINMENT SYSTEMS (Cont)

Tests ofimpregnated charcoal identical to that used in the filters indicate that a shelflife of five years leads to only minor decreases in methyl iodide removal efficiency. Hence, the frequency oflaboratory carbon sample analysis is adequate to demonstrate acceptability. Since adsorbers must be remcved to perform this analysis this frequency also muumizes the system out of service time as a result of surveillance testing. In addition, although the halogenated hydrocarbon testing is basically a leak test, the adsorbers have charcoal of known efficiency'and holding capacity for elemental iodine and/or methyl iodide, the testing also gives an indication of the relative efficiency of the installed system. The 31 day requirement for the ascertaining of test results ensures that the ability of the charcoal to perform its deigned function is demonstrated and known in a timely manner.

The required Standby Gas Treatment System flow rate is that flow, less than or equal to 4000 CFM which is needed to maintain the Reactor Building at a 0.25 inch of water negative pressure under calm wind conditions. This capability is adequately demonstrated during Secondary Contammen'. Leak Rate Testing performed pursuant to Technical Specification 4.7.C.I.c.

l The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly.

The filter testing is perfonned pursuant to appropriate procedures reviewed and approved by the .

i l Operations Review Committee pursuant to Section 6 of these Technical Specifications. The in-place testing of charcoal filters is performed by injecting a halogenated hydrocarbon into the system upstream of i the charcoal adsorbers. Measurements of the concentration upstream and downstream are made. The ratio  ;

i- of the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. A l similar procedure substituting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPA filters. j Pressure drop tests across filter and adsorber banks are performed to detect plugging or leak paths though j the filter or adsorber media. Considering the relatively short times the fans will be run for test purposes, plugging is unlikely and the test interval of once per operating cycle is reasonable.

System drains and housing gasket doors are designed such that any leakage would be inleakage from the l Standby Gas Treatment System Room. This ensures that there will be no b3 pass of process air around the  !

filters or adsorbers.

l Only one of the two Standby Gas Treatment Systems (SBGTS) is needed to maintain the secondary l containment at a 0.25 inch of water negative pressure upon contamment isolation. If one system is found to l be inoperable, there is no immediate threat to the containment system performance and reactor operation or l refueling activities may continue while repairs are being made. In the event one SBGTS is inoperable, the t redundant system's active components will be tested within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. 'Ihis substantiates the availability of the operable system and justifies continued reactor or refueling operations.

I During refueling outages, if the inoperable train is not restored to operable status within the required L ~ completion time, the operable train should immediately be placed in operation. His action ensures that the remaining train is operable, that no failures that could prevent automatic actuation have occurred, and that any other failure would be readily detected. An alternative is to suspend fuel movement, thus placing the plant in a condition that muumizes risk.

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1 Amendment No. 42, !12, !5 ! B3/4.7 1

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1 Attachment C 1

l Marked-up Technical Specifications Paaes i

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l 1.0 DEFINITIONS f The succeeding frequently used terms cra cxplicitly d2 fin 2d no that a uniform ,

l interpretation of the specifications may be achieved. I A. Safety Limit - The safety limits are limits below which the reasonable i maintenance of the cladding and primary systems are assured. Exceeding l such a limit is cause for unit shutdown and review by the Nuclear Regulatory Commission before resumption of unit operation. Operation i beyond such a limit may not in itself result in serious consequences but it indicates an operational deficiency subject to regulatory review.'

B. Limitine Safety System Settine (LSSS) - The limiting safety system l j

settings are settings on instrumentation which initiate the automatic protective action at a level such that the safety limits will not be exceeded. The region between the safety limit and these settings represent margin with normal operation lying below these settings. The l margin has been established so that with proper operation of the l instrumentation the safety limits will never be exceeded. l C. Limitine Conditions for Operation (LCO) - The' limiting conditions for j operation specify the minimum acceptable levels of system performance l necessary to assure safe startup and operation of the facility. When l these conditions are met, the plant can be operated safely and abnormal I situations can be safely controlled.

D. Core Operatina Limits Report The CORE OPERATING LIMITS REPORT is a reload-cycle specific document, its supplersents and revisions, that provides core operating limits for the current operating reload cycle. These cycle specific core operating limits shall be determined for each reload cycle in accordance with Specification 6.9.A.4. Plant operation within these operating limits is t.ddressed in individual specifications.

E. Operable - Operability l A system, subsystem,when have OPERABILITY train,itcomponent or performing is capable of device shallitsbe OPERABLE orh specified function (s). Implicit in this definition shall be the assumption that l

all necessary attendant instrumentation, controls, normal @ emergency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of l performing their related support function (s).

1 F. Ooeratine - Operating means that a system or component is performing its intended functions in its required manner.

l r

Revision 177 Amendment No. 133 1-1 l

, . . l 4

LIMITING CONDITIONS FOR OPERAT[9]i SURVEILIANCE REQUIREMENTS 3.4 STANDBY LIOUID CONTROL SYSTEM 4.4 STANDBY LIOUID CONTROL SYSTEM

(

i ,.

(Cont) (Cont) 1 l ( A. Normal System Availability (Cont)

b. At least once during each <

refueling interval, while I testing as specified in 3.13, manually initiate one of the Standby Liquid Control System loops and l

pump demineralized water l into the reactor vessel.

This test checks explosion of the charge associated with the tested loop, proper operation of the valves, and pump operability. The replacement charges to be '

installed will be selected l- from the same manufactured batch as the tested charge.

c. When testing to satisfy

! , requirement 4.4.A.2.b. both i B. Operation with Inoverable systems, in luding both Components: exp1 sive valves, shall be tested in the course of two

1. From and after the date that a refueling intervals, redundant component is made or found to be inoperable, B. Surveillance with Inocerable Specification 3.4.A.1 shall be Comeonents:

considered fulfilled and continued operation permitted 1. When a component is found to be inoperable,-its redundant provided thatfthe component is returned to an operable component shall be demonstrated condition within.seven days, .:o be operable iumediately and daily thereafter until the

, .- y -- - inoperable component is

• dh d,'e s,el e,e n e niw. g; 3 sopa /cd w ' C- repaired.

I h Qft:Qk W . n .... / s l-L an,cLw [ ybsq$+em\s O @p L

4 l

Revision 177 Amendment No. 192,.149 3/4.4 2

1 l LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.5 CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING SYSTEMS (Cont) SYSTEMS (Cont)

( F. Minimum Low Pressure Cooline and Diesel Generator Availability F. Minimum Low Pressure Cooline and Diesel Generator Availability l

1. During any period when one Je/femp).Whenit is determined that one I diesel generator is inoperable h diesel generator is inoperable, i continued reactor operation is the operable diesel generator permissible ng the br aemonstYatea to '~~

succeeding h S :; nless such diesel generator is sooner made

_3y I opera there e

unti and daily },

operab g

Ioperable, provided that all of sel is repairart _

I

! tthe low pressure core and ,

l concainment cooling systemshnd ' *n e l E ,the remaining diesel generator s h il G operable.f If this

q ), y j #

PM (l y

/ w, equirement cannot be met, an Mk*- l orderly shutdown shall be p a- m

( y k N. 6. [. / , initiated and the reactor shall ppg lfgg ,

L ._

be placed in the Cold Shutdown l Condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. -

l

2. Any combination of inoperable l l components in the core and containment cooling systems

'7'N'I'A h -

1 i

shall not defeat the capability 5i of the remaining operable ,

i components to fulfill the M

cooling functions.

l 3. When irradiated fuel is in the reactor vessel and the reactor d7t44.

gg l

is in the Cold Shutdown L

{

l condition, both core spray g systems, the LPCI and containment cooling systems may - dM be inoperable, provided no wor'. Q-

! is being done which has the potential for draining the i reactor vessel. (

4. During a refueling outage, for a period of 30 days, refueling operation may continue provided that one core spray system or the LPCI system is operable or l

Specification 3.5.F.5 is met.

Revision 177 Amendment No. 15,-135 3/4.5-7 l

i LIMITING CONDITIONS FOR OPERATION SURVEILIANCE REQUIREMENTS 1 1

j 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

A. Primary Containment (Cont) l With no H2 analyzer operable, reactor operation is allowed for up to 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />. If one of the inoperable analyzers is not made fully operable within

)

)

1 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the reactor shall i be in a least Hot Shutdown I within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. l l

B. Standby Gas Treatment System and Control Room Hizh Efficiency Air B. Standby Gas. Treatment System and Filtration System Control Room Hizh Efficiency Air pg7 gy

1. Standby Cas Treatment System

1. Standby Gas Treatment System

a. Except as specified in Q

3.7.B.1.c or 3.7 B.1. a. 1. At least once per j below, both' trains of the Peratin5 cycle, it shall standby gas treatment system be demonstrated that l Pressure drop across the a the diesel rators c mbined high efficiency

)

requ d for ra n of such tra 1 be ters aM charcoal operable at all times when adsorber banks is less seconda U containment than 8 inches of water at integrity is required j e - 4000 cfm*

! 9. Y 2. At least once per

, _ operating cycle,  ;

b. 1. The results of the in- dem nstrate that the l place cold DOF tests on inlet heaters on each train are operable and HEPA filters shall show

"#* **P* * "" "*P"E 2994 DOP removal. The results of halogenate1 hydrocarbon tests on l charcoal adsorber banks 3. The tests and analysis of I. shall show 299% SP ecification 3.7.B.1.b.

! halogenated hydrocarbon shall be performed at yg, least once per operating cycle or following painting, fire or chemical release in any ventilation zone

communicating with the l system while the system is operating that could contaminate the HEPA l filters or charcoal adsorbers.

t t 4. At least once per

,_ operating cycle,

^ -

automatic initiation of Revision ~179- .

l Amendment No. 15 i- 4h-M i'- S tr - 52, - 1121 - 1445 - 151, 161 3/4.7-11 l

LIMITING CONDITIONS FOR OPERATION SURVEII.IANCE REQUIREMENTS l 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont) l l B. Standby Cas Treatment System and B. Standby Cas Treatment System and Control Room Hinh Efficiency Air Control Room Himh Efficiency Air Filtration System (Cont) Filtration System (Cont)

2. The.results.of the each branch of the i laboratory carbon sample standby gas treatment i analysis shall show E954 system shall be methyl iodide removal at demonstrated, with a velocity within 10% of Specification 3.7.B.l.d j'

system design, 0.5 to 1.5 satisfied.

i ag/m ' inlet methyl iodide S

. concentration, 2704 R.H. 5. Each train of the standby anda190*F. The analysis gas treatment. system

. results are to be shall be operated for at 1 l

verified as acceptable least 15 minutes per j within 31 days after month. I sample removal, or decl.re that train 6. The tests and analysis of-inoperable and take the Specification 3.7.B.1.b.2 actions specified shall be performed after 3.7.B.1.c. every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation.

c From and after the date that one train of the Standby Gas b. 1. In-place cold DOP testing Treatment System is made or shall be performed on the l l found to be inoperable for HEPA filters after each j any reason,f hee p :: completed or partial l l y a ifi:2 1.- 2. 7. L. L i]J replacement of the HEPA {

continued reactor ~ filter bank and after any I operation, irradiated fuel structural maintenance on handling .or new fuel the HEPA filter system.

hanoung overfispent fuel housing which could i j pool (s errq is permissible [44a affect the HEPA filter i

only during'the succeeding die sel dj en t h*e) bank bypass leakage.

i seven days providing that A$50c.ls h d

• l within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> all act'ive 4 e 0 4 2,36LE' . Halogenated hydrocarbon

!. components of the other +reW b oeN4 testing shall be

! standby gas treatment train performed on the charcoal h g d1T W ,3 demonstrated to be operable /4

• y #

adsorber bank after each partial or complete

- ~.M I replacement of the 4 &y b4 dM charcoal adsorber bank or M* twa M jA, Ag9fx %3Ak, . 'maI$e Ec the charcoal adsorber housing bN oa s rber b nk 2 h - M N M 3(a b + bypass leakage.

i

su wu a a .w ,

M 6%

l

! App l

9ite 1.

Revision 179 l Amendment No.- 42 1 -59 t -515-112,-144, 161 3/4.7-12

mm . m m ..,wr o o m 1 o c, m o v o n F----) m u v m ' a o a ws e * ' ' r i c---------

3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Crnt)

8. Standby Cas Treatment System and B. Standby Cas Treatment System and

..- Control Room High Efficiency Aig Control Room Hinh Efficiency Air Filtration System (Cont) Filtration System (Cont)

d. Fans shall operate within i

% 10% of 4000 cfm. ^

e Exc as spec tea in l 3 .B.1.c or .7.B.1.f. b e From and after the date that rains of a Standby one train of the Standby Gas Treatme System sha be Treatment System is made or oper e during ir diated found to be inoperable for fu handling, o new fuel any reason during Refuel ndling over e spent fuel ,

outages, refueling pocf1 or cor . If the syste , operations ave permissible is not op able, fuel only during the succeeding seven days providing that movenert shall not be.

'ly within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> all active

( ,s no W y f$el

. ment assmaybe) in progre cesponents of the other

. train apleted, p_ .. ,

~ ~

are demonstrated to be

'f. During refueling, one operable and the diesel

/, train jo ',the Standby Ca generator associated with

/ 4 the OPERA 8 M train is TreattentSystemcan) wJeffout its safetpfe lated OPERABM. ;

< bus and/or emer ncy diesel

/ generator vi out entering If the system is not made the LCO a on statement fully cperable within 7

/

/' providp the following r d8Y81 conditions are met: /'f

,/ Fuel movement ytll not 6) Place the OPERABLE SGT ys 'M in operation

/'foccur until following five reap or shutdown 2 Immediately gg -

/ -

Prio ao and during f ,

fuel a ment, the SBg-6/C ,_

or Shutdown Tr,edIformer y fuel assembly mov

}s', required to,be operable rogress may be cospleted /

f and capable of supply power j /

to the emer'gency bus. (ii)suspendmovementof j Fues movement will, poi irradiated fuel oc, cut until the reac assemblies in secondary )

. vessel is flooded uj,ter to f containment or new fuel <

f elevation 114 y L handling over the spent

- The train of SCTS fuel pool or core -

without.its safety rel d _.

bus or without is e gency >/ - -

dienelgenerator/11have

,. power supplied'from a 3'

'/

normal offylfe source via a ,,.

non safetf-related bus. ,The' (-

norma 1'offsite sourc V '/ V consists of either'the Startup Transfosser or Unit

' Auxiliary Transformer QBackfeed- Node) .

Revision 179 l Amendment No. 42 r-59 -51r-52 1 1 -191 -112 1 1 -144 151,161 1 3f4,7 13

_ . _ _ _ _.. _ __ .m . . _ . _ _ . _ . _ _ _ _ . _ _ . . _ .._ _ _ _ . _ . _ _ _ _

LIMITING CONDITIONS FOR OPERATION SURVIILIANCE REQUIREMENTS t i 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

B. Standby Cas Treatment System and B. Standby Cas Treatment System and Control Room Himh Efficiency Air Control Room Himh Efficionev Air Filtration System (Cont) Filtration System (Cont)

2. Control Room Hiah Efficiency 2. Control Room Himh Efficiency Air Filtration Systag 61I Filtration System a Except as specified in a. At least once per operating Specification 3.7.B.2.c or cycle the pressure _ drop 3.7.B.2.e below, both trains across each combined filter

.of the Control Room High train shall be demonstrated Efficiency Air-Filtration to be less than 6 inches of System used for the water at 1000 cfm or the -

processing of inlet air to calculated equivalent.

the control room under acci_ dent condition and the T b. 1. The tests and analysis of raiese enerator(s) utred Q Specification 3.7.B.2.b l i

I for ope ion of each in / \ shall be performed once Lof the sys _s hall be per operating cycle or l operable whenever secondary following painting, fire J

containment integrity is or chemical release in  ;

j required duri fuel any ventilation zone (gtndMcig oper ]

l ns. communicating with the system while the system

b. 1. The results of the in- is operating. i

! place cold DOP tests on l i

HEPA filters shall show 2. In-place cold DOP testing l 2994 DOP removal. The shall be performed after l results of the each complete or partial l halogenated hydrocarbon replacement of the HEPA' l

^

tests on charcoal filter bank or after any adsorber banks shall show structural maintenance on i 2994 halogenated . the system housing which hydrocarbon removal when could affect the HEPA test results are filter bank bypass extrapolated to the leakage.

initiation of the test.

l

3. Halogenated hydrocarbon l

2. The results of the testing shall be laboratory carbon sample performed after each l

, analysis shall show 2954 complete or partial methyl iodide removal at replacement of the a velocity within 10% of charcoal adsorber bank or L - system design, 0.05 to after any structural

. 0.15 mg/m3 inlet methyl maintenance on the system

! iodide concentration, housing which could 270% R.H. , and 2125 'F. affect the charcoal The analysis results are adsorber bank bypass to be verified as leakage.

acceptable within 31 days after sample removal, or 4. Each train shall be declare that train operated with the heaters l inoperable and take the in automatic for at least i

15 minutes every month, Revision 179 l Amendment No. 42 1 50,-52 1-112 1-144,-151, 161 3/4.7-14

LIMITING CONDITIONS FOR OPEltATION SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont) i

1. Standby Cas Treatment System and Standby Cas Treatment System and B. B.

'. Control Room Hiah Efficiency Air Control Room Hieh Efficiency Air Filtration System (Cont) Filtration System (Cont) actions specified in 5. The test and analysis of 3.7.B.2.c. Specification 3.7.B.2.b.2 shall be performed after every 720 hours0.00833 days <br />0.2 hours <br />0.00119 weeks <br />2.7396e-4 months <br /> of system operation.

c From and after the date that one train of the Control c. At least once per operating  !

l Room High Efficiency Air cycle demonstrate that the ,

Filtration pS te. 3 --da o N

• g*

inlet heaters on each train l foun_d to brincep;tl:  : are operable and capable of l lsuppifle, e Illi u a_ li i % an output of at least 14 kw.

Lth: :=:- I = Tfor any t r o A ch 4 4 s le, ke ( rea reactog,,J2pe ra t iott

• gon,*12 ~'"A -"' "'- ' ' - d'**"'""*"'"'*"'"*"* l I

}

Jl'MN*#*

~

ermissible only during the functional test on the Iv e l L o w dl,q o ven succeeding 7 days providing j &.hesel g umidistats controlling the

( 94.d [we- l ool f O active that within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> components of all the_

q, ug,jy8j'yg}(

eaters cycle, once per operating l

c<* other CRHEAF train (s .11 emonstratepoperableg If he j gr o / .

t 'the system is not made fully operable within 7 days, e From and after the date that one train of the reactor shutdown shall be Control Room High Efficiency Air Filtration initiated and the reactor System is made or found to be inoperable for any reason during Refuel Outages, refueling I shall be in cold shutdown ,

! within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and {

operationsawpermissible only during the /

^ S fuel handling succeeding seven days providing that within 2 ,

hours all active components of the other operations shall be f terminated within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

Fuel handling operat' ions in f 1

r train are demonstrated to be operable and the dieselgenerator

\ \

progress may be completed. ass dated mth the OPERABLE train is OPERABLE.; <

i d. Fans shall operate within l 10s oE 1000 cfn. If the system is not made fury operable within 7 s l

days;

}

e. Durin ueling, one train f ( ,' ) perform surveillance 4.7.B.2.bA for the -

of CRHEAF ca be without s safety-re ed- bus 1 OPERABLE CHREAF every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 03 j and/or ese ency diesel i genera without entering \

the 0 actions s ement [Kny fuel assembT97 mrv'ement in progress mh I lowing (be completed , >  !

vided the conditions e met: /

I - Fuel a ment will n ( *)i) suspend movement of irradiated fuel I occur til five da assemblies in secondary containment or /

fol wing react shutdown, new fuel handling over the spent fuel pool \

/

- for to a during fuel ,

or core, l q movement, t e SB0 D/C or the .

k .M h

/

i l Revision 179 )

l Amenda.ent No. 421-501 -51, 57,-112,-144,-151, 61 3/4.'7-15 l

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

LIMITING _GQNDITIONS_FQR_QfERATIQM- SURVEILIANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS (Cont) 4.7 CONTAINMENT SYSTEMS (Cont)

Shutdown Transformer is required to be operable a apable of supply power o t emergency bus.

1 movement will ot occu until the re tor vessel s flood to elevatio 114'.

- The trai o CRHEAF without is fety related bus or wit ou its emergene dies generator will h e power pplied l from normal off te I

sou e via a non sa ty-re ted bus. The no 1 l

fsite source consist of  :

l either the Startup  !

j Transformer or Unit Auxiliary Transformer l

(Backfeed Mode). )

C. Secondary Containment C. Secondary Containment

1. Secondary containment

1. Secondary containment integrity surveillance shall be performed shall be maintained during all modes of plant operation except as indicated below:

1 when all of the following conditions are mer.. a. A preoperational secondary l containment capability test '

a. The reactor is suberitical shall be conducted after isolating the reactor  !

and Specification 3.3.A is

! met building and placing either '

standby gas treatment system

! filter train in operation.

f b. The reactor water i temperature is below 212' Such tests shall demonstrate the capability to maintain and the reactor coolant system is vented. 1/4 inch of water vacuum under calm wind (<5 mph) conditions with a filter

c. No activity is bein8 performed which can reduce train flow rate of not more the shutdown margin below than 4000 cfa. -l4 that specified in Specification 3.3.A.

b. Additional tests shall be performed during the first operating cycle under an

d. The fuel cask or irradiated adequate number of different fuel is not being moved in environmental wind the reactor building, 1 conditions to enable valid I j

extrapolation of the test

2. If Specification 3.7.C.1 cannot results.

be met, procedures shall be initiated to establish 1

c. Secondary containment conditions listed in Speci-capability to maintain 1/4

{ 'fication 3.7.C.1.a through d. inch of water vacuum under Revision 179 l Amendment No. 9, 161 3/4.7-16

l,o .

LIMITING CONDITION FOR OPERATION S M J M g C,g_gggyJE g g g g, 3.9 AUXILIARY ELECTRICAL SYSTEM (Cont) 4.9 AUXILIARY ELECTRICAL SYSTEM (Con:.

B. Operation with Inoperable A. Auxiliary Electrical Eautoment Eautonent Surveillance (Cont) 1 Whenever the reactor is in Run 3. Emergency 4160V Buses AS-A6 Mode or Startup Mode with the Degraded Voltage Annunciation i reactor not in a Cold Condition, System.

the availability of electric power shall be as specified in 3.9.B.1, a. Once each operating cycle, 3.9.B.2, 3.9.B.3, 3.9.B.4, and calibrate the alarm sensor.

i 3.9.B.5. b. Once each 31 days perform a l channel functional test on

1. From and after the date that the alarm system.

l incoming power is not available i

c. In the event the alarm i

4. tM M ) from the startup transformer, or shutdown continued reactor system is determined eke sO / operation is permissible under inoperable under 3.b above.

d**

this condition forhi ma(

During this period, both diesel commence logging safety related bus voltage every 30

) .C} generators and associated minutes until such time as

) b, e t emergency buses must be the alarm is restored to

&~-mn;: - nos operable, operable status.

T l , . From and after the date thac 4. RPS Electrical Protection incoming power is not available Assemblies from both startup and shutdown transformers, continued a. Each pair of redundant RPS operation is permissible, EPAs shall be determined to provided both diesel generators be operable at least once and associated emergency buses per 6 months by performance are @ r tr n d = @ ( of an instrument functional operable, all core and test.

! containment cooling systems are l operable, reactor power level b. Once per 18 months each pair is reduced to 25% of design and of redundant RPS EPAs shall l the NRC is notified within one be determined to be operable (1) hour as required by by performance of an 10CFR50.72. instrument calibration and by verifying tripping of the

3. From and after the date that circuit breakers upon the one of the diesel generators or simulated conditions for associated emergency bus is automatic actuation of the made or found to be inoperable protective relays within the l for any reason, continued following limits:

reactor operation is y x l r, permissible in accordance with 23 ,4/,b,j, Overvoltage $ 132 volts l @ _ Specificatiorf43.5.F,yf Wu Undervoltage 2 108 volts Underfrequency Specification 3.9.A.T and 2 57H z 3.9.A.2.a are satisfied.

4. From and after the date that

• b#"

one of the diesel generators or ( 3. 7' S'  !' Ob

'Jb* ' '

associated emergency buses and either the shutdown or startup transformer power source are.

, Revision 177 l Amendment No. 88 7 -127;-145,-151 3/4.9-4 l

3 .

g LIMITING CONDITION FOR OPERATION SURVEILIABCE REQUIREIENTS 3.9 AUXILIARY ELECTRICAL SYSTEM (Cont) 4.9 AUXILIARY ELECTRICAL SYSTEM (Con:)

r:~- B. Operation with Inonerable-Eauioment (Cont) t . j nade or found to be inoperable for any reason, continued reactor operation is  ;

l permissible in accordance with _ ,

Specification 3.5.F2@ r de Mthe folIhQpg ; -

mm- m ' r - -- : r--  : : y l

- a.he startup transformer and - [p r M #"d MV#

=

^

both offsite 345 kV --

l transmission lines are available and capable of automatically supplying

, auxiliary power to the

! emergency 4160 volt buses OY" , - ~ . , .

l b.h transmission line and ' f' y pg fours provn/r/ \

l associated shutda.w .s~ ^A" /

l transformer are available

! and capable of automaticall, supplying auxiliary power to the emergency 4160 volt buses.

5. From and after the date that one of the 125 or 250 volt battery systems is made or found to be inoperable for any reason, continued reactor operation is permissible during the succeeding three days within electrical safety considerations, provided repair I

work is initiated in the me t expeditious manner to return the failed component to an operable state, and Specification 3.5.F is satisfied.

6. With the emergency bus voltage less than 3958.5V but above 3878.7V(excluding transients) during normal operation, cransfer the safety relat< d buses to the diesel genetators.

If grid voltage cc.ntinues to degrade be in at least Hot i .chutdown within the next 4 I hours and in Cold Shutdown

within the following 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> j unless the grid conditions j improve.

Ravision 177

{ Amendment No. 42 7 611 -8S t-120r-1271-151 3/4.9 5 i

I 5

.s .

EEiEE:

'3/4.7 D NTAINMENT SYSTEMS (Cont)

Tests of impregnated charcoal identical to that used in the filters indicate that a shelf life of five years leads to only minor decreases in methyl iodide removal efficiency. Hence, the frequency of laboratory carbon sample analysis

! is adequate to demonstrate acceptability. Since adsorbers must be removed to perform this analysis this frequency also minimizes the system out of service i

time as a result of surveillance testing. In addition, although the Palogenated hydrocarbon testing is basica"y a leak test, the adsorbers have charcoal of known efficiency and holding capacity for elemental iodine and/or i

j methyl iodide, the testing also gives an indication of the relative efficiency of the installed system. The 31 day requirement for the ascertaining of test l

results ensures that the ability of the charcoal to perform its designed '

i function is demonstrated and known in a timely manner.

l l

The required Standby Gas Treatment System flow rate is that flow, less than or l

i equal to 4000 CFM which is needed to maintain the Reactor Building at a 0.25 4

inch of water negative pressure under calm wind conditions. This capability is adequately demonstrated during Secondary Containment Leak Rate Testing performed pursuant to Technical Specification 4.7.C.1.c.

The test frequencies are adequate to detect equipment deterioration prior to significant defects, Ne the tests are not frequent enough to load the filters or adsorbers, thus rodering their reserve capacity too quickly. The filter ,

testing is performed pursuant to appropriate procedures reviewed and approved l by the Operations Review Committee pursuant to Section 6 of these Technical l Specifications. The in place testing of charcoal filters is performed by i injecting a halogenated hydrocarbon into the system upstream of the charcoal l adsorbers. Measurements of the concentration upstream and downstream are made. The ratio of the inlet and outlet concentrations gives an overall indication of the leak tightness of the system. A similar procedure substituting dioctyl phthalate for halogenated hydrocarbon is med tc test the l HEPA filters.

Pressure drop tests across filter and adsorber banks are performed to detect Considering the plugging or leak paths though the filter or adsorber media. l relatively short times the fans will be run for test purposes, plugging is unlikely and the test interval of onu per operating cycle is reasonable.

System drains and housing gasket doors are designed such that any leakage would be inleakage from the Standby Gas Treatment System Room. This ensures that there will be no bypass of process air around the filters or adsorbers.

Only one of the two Standby Gas Treatment Systems (SBCTS) is needed to maintain the secondary containment at a 0.25 inch of water negative pressure upon containment inlation. If one system is found to be inoperable, there is no immediate threat to the containment system performance and reactor operation or refueling activities may continue while repairs are being made.

In the event one SBGTS is inoperable, the redundant system's active components will be tested within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. This substantiates the availability of s. the operable system and justifies continued reactor or refueling operati

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.,,4 4Js, Amendment No. 425-1125-151 -

j BASES: I 3/4.7 CONTAINMENT SYSTEMS (Cont)

$ B.2 Control Room Hirh Efficiency Air Filtration System (Cont) l The test frequencies are adequate to detect equipment deterioration prior to significant defects, but the tests are not frequent enough to load the filters or adsorbers, thus reducing their reserve capacity too quickly. The filter testing is performed pursuant to appropriate procedures reviewed and approved l by the Operations Review Committee pursuant to Section 6 of these Technical l

Specifications. The in place testing of charcoal filters is performed 'oy l

injecting a halogenated hydrocarbon into the system upstream of the charcoal ,

! adsorbers. Measurements of the concentration upstream and downstream are l j

made. The ratio of the inlet and outlet concentrations gives an overall l j indication of the leak tightness of the system. A similar procedure substituting dioctyl phthalate for halogenated hydrocarbon is used to test the HEPA filters.

1 Air flow through the filters and charcoal adsorbers for 15 minutes each month l assures operability of the system. Sines the system heaters are automatically controlled, the air flowing through the filters and adsorbers will be s 70s

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relative humidity and will have the desired drying effect.

If one train of the system is found to be inoperable, there is no immediate threat to the control room, and reactor operation or fuel handling may continue for a limited period of time while repairs are being made. In the '

event one CRHEAF train _is ino_perable, the redundant system's active components will be tested within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.T If both trains of the CRHEAF system are inoperable, the reactor will be brought to a condition where the control Room High Efficiency Air Filtration System is not required. A

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'r-AC DISTRIBUTION 4160V AND EMERGENCY  ;

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