ML022280358

Technical Specification Pages for Amendment No. 209, Operability of Alternate Trains

ML022280358
Person / Time
Site:	Vermont Yankee
Issue date:	08/14/2002
From:	Pulsifer R NRC/NRR/DLPM/LPD1
To:	Thayer J Entergy Nuclear Vermont Yankee
References
TAC MB2760
Download: ML022280358 (20)

Text

VY NPS 3.4 LIMITING CONDITIONS FOR 4.4 SURVEILLANCE REQUIREMENTS OPERATION

5. Testing the new trigger assemblies by installing one of the assemblies in the test block and firing it using the installed circuitry.

Install the unfired assemblies, taken from the same batch as the fired one, into the explosion valves.

6. Recirculating the borated solution.

B. Operation with Inoperable B. Operation with Inoperable Components Components From and after the date that Deleted.

a redundant component is made or found to be inoperable, reactor operation is permissible during the succeeding seven days unless such component is sooner made operable.

C. Standby Liquid Control System C. Standby Liquid Control System Tank - Borated Solution Tank - Borated Solution At all times when the Standby Liquid Control System is required to be operable, the following conditions shall be met:

1. The net volume versus 1. The solution volume in concentration of the the tank and temperature sodium pentaborate in the tank and suction solution in the standby piping shall be checked liquid control tank at least daily.

shall meet the requirements of Figure 3.4.1.

Amendment No. 442-, 4-14, 4-64, 4-L5, 209 93

BASES: 3.4 & 4.4 (Cont'd) to shutdown capability, and be inoperable, there is no immediate threat Assurance repairs are being made.

reactor operation may continue while is obtained from the its intended function that the system will perform in accordance with ASME results of the pump and valve testing performed Section XI requirements.

- Borated Solution C. Standby Liquid Control System Tank with the concentration of The solution saturation temperature varies above the sodium pentaborate. The solution shall be kept at least 10*F boron precipitation. The 10OF saturation temperature to guard against and liquid level 3.4.2. Temperature margin is included in Figure in the Control Room.

alarms for the system are annunciated concentration will not vary Once the solution has been made up, boron indication and alarm Level unless more boron or water is added. changed which might indicate a indicate whether the solution volume has Considering these factors, the possible solution concentration change.

test interval has been established.

within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Sodium pentaborate concentration is determined or if the solution following the addition of water or boron, The 24-hour limit allows for temperature drops below specified limits.

notification of shift 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> of mixing, subsequent testing, and personnel.

and volume are checked on a Boron concentration, solution temperature, operation of the system reliability of frequency to assure a high should it ever be required. Isotopic tests of the sodium pentaborate the proper boron-10 atom are performed periodically to ensure that percentage is being used.

Control System with a 10CFR50.62 (c) (4) requires a Standby Liquid equivalent to 86 gpm of 13 minimum flow capacity and boron content solution in the 251-inch weight percent natural sodium pentaborate vessel reference plant. Natural sodium pentaborate reactor pressure The relationship expressed in solution is 19.8 atom percent boron-10. M251/M to account for the Specification 3.4.C.3 also contains the ratio plant and Vermont reference difference in water volume between the lbs./401,247 lbs.)

Yankee. (This ratio of masses is 628,300 of three Standby Liquid To comply with the ATWS rule, the combination boron concentration, Control System parameters must be considered: and boron-10 enrichment.

Standby Liquid Control System pump flow rate, 3.4.C.3 at the minimum flow Fixing the pump flow rate in Specification system parameter that can a

rate of 35 gpm conservatively establishes as well as the original be used in satisfying the ATWS requirement, system design basis. If the product of the expression in Specification the Standby Liquid Control 3.4.C.3 is equal to or greater than unity, (4).

System satisfies the requirements of 10CFR50.62(c) 98 Amendment No. 442-, 14--,

4-, 209

Vfflps 4.5 SURVEILLANCE REQUIREMENT 3.5 LIMITING CONDITION FOR OPERATIONS CORE AND CONTAINMENT COOLING 4.5 CORE AND CONTAINMENT COOLING 3.5 SYSTEMS SYSTEMS Applicability:

Applicability:

Applies to the operational status of the Emergency Applies to periodic testing of the emergency cooling subsystems.

I Cooling Subsystems.

Objective:

Objective:

To verify the operability of the To assure adequate cooling core containment cooling capability for heat removal in subsystems.

the event of a loss-of-coolant accident or isolation from the normal reactor heat sink.

Specification:

Specification:

A. Core Spray and Low Pressure A. Core Spray and Low Pressure Cooling Injection Coolant Injection Surveillance of the Core

1. Except as specified in Spray and LPCI Subsystems Specifications 3.5.A.2 shall be performed as through 3.5.A.4 below follows.

and 3.5.H.3 and 3.5.H.4, both Core Spray and the 1. General Testing LPCI Subsystems shall be operable* whenever irradiated fuel is in the Item Frequency reactor vessel and prior to a. Simulated Each re a reactor startup from the Automatic fueling cold shutdown condition. Actuation outage Test

b. Operability testing of pumps and valves shall be in accordance with Specification 4.6.E.

c. Flow Rate Each re fueling Test-Core Spray pumps outage shall deliver at least

• Note: During Hot Shutdown, LPCI 3000 gpm subsystems may be considered (torus to OPERABLE during alignment and torus) operation for decay heat removal against a with reactor vessel pressure system head less than the RHR shutdown of 120 psig.

cooling permissive pressure, if Each LPCI capable of being manually pump shall realigned and not otherwise deliver inoperable.

7450 +/- 150 gpm (vessel to vessel).

-3, 4-2-, 449i 209 99 Amendment No. 44, 2-7-,

VYNPS 4.5 SURVEILLANCE REQUIREMENT 3.5 LIMITING CONDITION FOR OPERATION

2. Deleted.

2. From and after the date that one of the Core Spray Subsystems is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such subsystem is sooner made operable, provided that during such seven days, all active components of the other Core Spray Subsystem, the LPCI Subsystems, and the diesel generators required for operation of such components if no external source of power were available, shall be operable.

3. Deleted.

3. From and after the date that one of the LPCI pumps is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such pump is sooner made operable, providcý that during such seven days, the remaining active components of the LPCI Containment Cooling Subsystem and all active components of both Core Spray Subsystems and the diesel generators required for operation of such components if no external source of power were available, shall be operable.

209 100 Amendment No. 2-4, 9*4, 444, 4-2-,

VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION

4. Deleted.

4. a. From and after the date that a LPCI Subsystem is made or found to be inoperable due to failure of the associated UPS, reactor operation is permissible only during the succeeding thirty days, for the 1989/90 operating cycle, unless it is sooner made operable, provided that during that time the associated motor control center (89A or 89B) is powered from its respective maintenance tie, all active components of the other LPCI and the Containment Cooling Subsystem, the Core Spray Subsystems, and the emergency diesel generators shall be operable, the requirements of Specification 3.10.A.4 are met, and the 4160 volt tie line to the Vernon Hydro is the operable delayed access power source.

b. From and after the date that a LPCI Subsystem is made or found to be inoperable for any reason, other than failure of the UPS during the 1989/90 operating cycle, or Specification 3.5.A.4.a is not met, reactor operation is permissible only during the succeeding seven days unless it is sooner made operable, provided 2-, *-,-8, 209 101 Amendment No. 444,

VYNPS 4.5 SURVEILLANCE REQUIREMENT 3.5 LIMITING CONDITION FOR OPERATION that during that time all active components of the other LPCI and the Containment Cooling Subsystem, the Core Spray Subsystems, and the diesel generators required for operation of such components if no external source of power were available, shall be operable.

5. Recirculation pump

5. All recirculation pump discharge valves shall be discharge valves and tested to verify full bypass valves shall be open to full closed in operable or closed prior 27 < t < 33 seconds and to reactor startup. bypass valves shall be tested for operability in accordance with Specification 4.6.E.

6. If the requirements of Specifications 3.5.A cannot be met, an orderly shutdown of the reactor shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

B. Containment Spray Cooling B. Containment Spray Cooling Capability Capability

1. Surveillance of the

1. Both containment cooling drywell spray loops shall spray loops are required be performed as follows.

to be operable when the During each five-year reactor water temperature period, an air test shall is greater than 212'F be performed on the except that a Containment drywell spray headers and Cooling Subsystem may be nozzles.

inoperable for thirty days.

2. Deleted.

2. If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

209 102 Amendment No. 24, -, 44-4, 4-I, 14 ,

4.5 SURVEILLANCE REQUIREMENT 3.5 LIMITING CONDITION FOR OPERATION C. Residual Heat Removal (RHR)

C. Residual Heat Removal (RHR) Service Water System Service Water System Surveillance of the RHR Service Water System shall be performed as follows:

1. Except as specified in 1. RHR Service Water Subsystem testing:

Specifications 3.5.C.2, and 3.5.C.3 below, both operability testing of RHR Service Water pumps and valves shall be Subsystem loops shall be in accordance with operable whenever Specification 4.6.E.

irradiated fuel is in the reactor vessel and prior to reactor startup from a cold condition.

2. Deleted.

2. From and after the date that one of the RHR service water pumps is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding thirty days unless such pump is sooner made operable, provided that during such thirty days all other active components of the RHR Service Water Subsystem are operable.

3. Deleted.

3. From and after the date that one RHR Service Water Subsystem is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such subsystem is sooner made operable, provided that all active components of the other RHR Service Water Subsystem, both Core Spray Subsystems, and both diesel generators required for operation of such components if no external source of power were available, shall be operable.

103 Amendment No. a-14, !48, 476, 209

iE 4.5 SURVEILLANCE REQUIREMENT 3.5 LIMITING CONDITION FOR OPERATION I 4. If the requirements of Specification 3.5.C cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

D. Station Service Water and D. Station Service Water and Alternate Cooling Tower Alternate Cooling Tower Systems Systems Surveillance of the Station

1. Except as specified in Service Water and Alternate Specifications 3.5.D.2 Cooling Tower Systems shall and 3.5.D.3, the Station be performed as follows:

Service Water System and both essential equipment 1. Operability testing of cooling loops and the pumps and valves shall be alternate cooling tower in accordance with shall be operable Specification 4.6.E.

whenever irradiated fuel is in the reactor vessel and reactor coolant temperature is greater 0

than 212 F.

2. Deleted.

2. From and after the date that the Station Service Water System is made or found to be unable to provide adequate cooling to one of the two essential equipment cooling loops, reactor operation is permissible only during the succeeding 15 days unless adequate cooling capability to both essential equipment cooling loops is restored sooner, provided that during such 15 days all other active components of the remaining essential equipment cooling loop and the Station Service Water and Alternate Cooling Tower Systems are operable.

104 Amendment No. 44-4, 8, 1,- 209

4.5 SURVEILLANCE REQUIREMENT 3.5 LIMITING CONDITION FOR OPERATION

3. Deleted.

3. From and after the date that the Alternate Cooling Tower System is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days, unless the Alternate Cooling Tower System is made operable, provided that during such seven days all active components of the Station Service Water System and both essential equipment cooling loops are operable.

4. If the requirements of Specification 3.5.D cannot be met, an orderly shutdown shall be initiated and the reactor shall be in a cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E. High Pressure Coolant E. High Pressure Cooling Injection (HPCI) System Injection (HPCI) System Surveillance of HPCI System shall be performed as follows:

1. Testing

1. Except as specified in Specification 3.5.E.2, a. A simulated automatic whenever irradiated fuel actuation test of the is in the reactor vessel HPCI System shall be and reactor steam performed during each pressure is greater than refueling outage.

150 psig:

b. Operability testing of

a. The HPCI System the pump and valves shall be operable. shall be in accordance with Specification

b. The condensate 4.6.E.

storage tank shall contain at least c. Upon reactor startup, 75,000 gallons of HPCI operability condensate water. testing shall be performed as required by Specification 4.6.E within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after exceeding 150 psig reactor steam pressure.

4-7-7, 209 105 Amendment No. 24-, 44I-, 1-24, 4-6,

• VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION

2. From and after the date d. The HPCI System shall that the HPCI System is deliver at least 4250 gpm at normal reactor made or found to be inoperable for any operating pressure when reason, reactor operation recirculating to the Condensate Storage is permissible only during the succeeding 14 Tank.

days unless such system is sooner made operable, 2. Deleted.

provided that:

a. The RCIC System is immediately verified by administrative means to be operable, and

b. During such 14 days all active components of the Automatic Depressurization System, the Core Spray Subsystems, the LPCI Subsystems, and the RCIC System are operable.

3. If the requirements of either Specification 3.5.E or Specification 4.5.E.l.c cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to 5 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

F. Automatic Depressurization F. Automatic Depressurization System System Surveillance of the Automatic

1. Except as specified in Depressurization System shall Specification 3.5.F.2 be performed as follows:

below, the entire Automatic 1. Operability testing of Depressurization Relief the relief valves shall System shall be operable be in accordance with at any time the reactor Specification 4.6.E.

steam pressure is above 150 psig and irradiated fuel is in the reactor vessel.

2. Deleted.

I

2. From and after the date that one of the four relief valves of the Automatic Depressurization Subsystem are made or found to be inoperable Amendment No. a-2, -44,1-24-, 164, a &, 209 106

VYNPS 3.5 LIMITING CONDITION FOR 4.5 SURVEILLANCE REQUIREMENT OPERATION

b. During such 14 days d. The RCIC System shall all active components deliver at least 400 of the HPCI System are gpm at normal reactor operable. operating pressure when recirculating to the

3. If the requirements of Condensate Storage either Specification Tank.

3.5.G or Specification 4.5.G.l.c cannot be met, an orderly shutdown shall be initiated and the reactor pressure shall be reduced to

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

H. Minimum Core and Containment H. Minimum Core and Containment Coolinq System Availability Cooling System Availability

1. During any period when 1. Deleted.

one of the emergency I diesel generators is inoperable, continued reactor operation is permissible only during the succeeding seven days, provided that all of the LPCI, Core Spray and Containment Cooling Subsystems connecting to the operable diesel generator shall be operable. If this requirement cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

2. Any combination of inoperable components in the Core and Containment Cooling Systems shall not defeat the capability of the remaining operable components to fulfill the core and containment cooling functions.

3. When irradiated fuel is in the reactor vessel and the reactor is in either a refueling or cold shutdown condition, all Core and Containment Cooling Subsystems may be inoperable provided no work is permitted which has the potential for draining the reactor vessel.

Amendment No. -2, 114, 444, -7,4-9-, 205 209 108

VYNPS BASES:

3.5 CORE AND CONTAINMENT COOLANT SYSTEMS Injection System A. Core Spray Cooling System and Low Pressure Coolant cooling capability is This Specification assures that adequate standby Reactor Vessel.

available whenever irradiated fuel is in the Based on the loss-of-coolant analyses, the dissipate Core Spray and LPCI Systems to the energy associated provide sufficient cooling to the core the accident-caused core with the loss-of-coolant accident and to limit Appendix K. The analyses consider conditions as specified in 10CFR50, Subsystems and the two appropriate combinations of the two Core Spray locations and equipment LPCI Subsystems associated with various break failure assumptions.

availability in accordance with required single the recirculation pump (Each LPCI Subsystem consists of the LPCI pumps, which combine to inject discharge valve, and the LPCI in3ection valve torus water into a recirculation loop.)

cooling to the core by The LPCI System is designed to provide emergency This system is flooding in the event of a loss-of-coolant accident.

Spray System; however, it does completely independent of the Core to prevent excessive function in combination with the Core Spray System The LPCI and the Core Spray Systems provide fuel clad temperature. the double-ended adequate cooling for break areas up to and including the high pressure recirculation line break without assistance from emergency Core Cooling Subsystems.

allows LPCI subsystems Specification 3.5.A.1 is modified by a Note thatoperation for decay heat to be considered OPERABLE during alignment and shutdown cooling removal with reactor pressure less than the RHR realigned (remote) to permissive pressure, if capable of being manually inoperable. This allows operation in the the LPCI mode and not otherwise if necessary.

RHR shutdown cooling mode during Hot Shutdown, startup from the cold The intent of these specifications is to prevent operable. However, condition without all associated equipment being may be out of service for the during operation, certain components that the systems will specified allowable repair times. Assurance perform their intended function is obtainedwith from the results of the pump ASME Section XI and valve testing performed in accordance requirements referenced in Specification 4.6.E.

and RHR Service Water System B. and C. Containment Spray Cooling Capability System is provided to The containment heat removal portion of the RHR event of a loss-of-coolant remove heat energy from the containment in the pressure is accident. For the flow specified, the containment long-term more than aniple the flow is limited to less than 5 psig and, therefore,

Reference:

to provide the required heat removal capability.

Section 14.6.3.3.2 FSAR.

two RHR service water Each Containment Cooling Subsystem consists of Either set of equipment pumps, 1 heat exchanger, and 2 RHR (LPCI) pumps.

the containment cooling function. In fact, an is capable of performing one subsystem consisting analysis in Section 14.6 of the FSAR shows that water pump, 1 heat exchanger, and 1 RHR pump has of 1 RHR service Assurance that the sufficient capacity to perform the cooling function. from the results systems will perform their intended function is obtained performed in accordance with ASME of the pump and valve testing 4.6.E.

Section XI requirements referenced in Specification 444, 49-, 49-, 209 110 Amendment No. L7,

VYNPS BASES: 3.5 (Cont'd)

Tower Systems D. Station Service Water and Alternate Cooling pumps, valves and associated The Station Service Water System consists cf equipment cooling loops piping necessary to supply water to two essential Each nonessential equipment cooling loads.

and additional essential and cooling loops of the two Station Service Water essential equipment necessary to includes valves, piping and associated instrumentation Service Water essential equipment. The Station provide a flowpath to heat sinks to essential equipment cooling loops provide redundant Each Station a shutdown or accident.

dissipate residual heat after provides sufficient heat Service Water essential equipment cooling loop heat dissipation. Analyses have sink capacity to perform the required of providing adequate shown that any two service water pumps are capable cooling loops. To ensure cooling capability to the essential equipment two Service Water essential this capability, four Service Water pumps and equipment cooling loops must be operable. This ensures that at least two and one operable essential equipment cooling operable Service Water Pumps single active failure loop will be available in the event of the worst A Service Water pump off-site power.

occurring coincident with a loss of suction from an is considered operable when it is capable of taking Water essential equipment intake bay and transferring water to a Service An essential pressures and flow rates.

cooling loop at tne specified it has a flow path equipment cooling loop is considered operable when when required.

the essential equipment, capable of transferring water to the necessary heat sink The Alternate Cooling Tower System will provide the event that the Station Service for normal post-shutdown conditions in of the Vernon Dam with Water System becomes incapacitated due to a loss of the Service Water intake subsequent loss of the Vernon Pond, flooding river or an upstream dam structure (due to probable maximum flood in the which disables all failure) or fire in the Service Water intake structure four Service Water pumps.

are inoperable such If one or more Station Service Water component(s) capable of performing Water System would not be that the Station Service a pump, its safety function, assuming a single active failure (e.g., equipment cooling then at least one essential valve or diesel generator), inoperable such that If one or more component(s) are loop is inoperable. of performing its not be capable the Station Service Water System would active failure, then both safety function, even without assuming a single essential equipment cooling loops are inoperable.

can perform its safety Although the Station Service Water (SSW) System System may not be function with only two operable SSW pumps, the SSW performing its safety function assuming one or two inoperable capable of failure (e.g., failure SSW pumps and assuming a worst case single active SSW pump, SSW valve, etc.). Therefore, reactor of a diesel generator, to 15 days SSW pumps is limited operation with one or two inoperable power this time both the normal and emergency provided that during also operable, in supplies for the remaining operable SSW pumps are active components addition to requiring the operability of all remaining which perform a safety function and the alternate of the SSW system cooling tower fan.

its safety function If the SSW System would not be capable of performing assuming a one or two SSW pumps being inoperable, for a reason other than generator, of a diesel worst case single active failure (e.g., failure i11 Amendment No. X, 444, 1-&9, 209

VYIIPS BASES: 3.5 (Cont'd)

SSW pump, SSW valve, etc.), then reactor operation is limited to 15 days provided that during this time both the normal and emergency power supplies for the remaining operable equipment are also operable, in addition to requiring the operability of all remaining active components of the SSW system which perform a safety function and the alternate cooling tower fan.

If the SSW System would not be capable of performing its safety function for any reason, even without assuming a worst case single active failure, then the reactor must be placed in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

E. High Pressure Coolant Injection System The High Pressure Coolant Injection System (HPCIs) is provided to adequately cool the core for all pipe breaks smaller than those for which the LPCI or Core Spray Cooling Subsystems can protect the core.

The HPCIs meets this requirement without the use of outside power. For the pipe breaks for which the HPCIs is intended to function the core never uncovers and is continuously cooled; thus, no clad damage occurs and clad temperatures remain near normal throughout the transient.

Reference:

Subsection 6.5.2.2 of the FSAR.

In accordance with Specification 3.5.E.2, if the HPCI System is inoperable and the RCIC System is verified to be operable, the HPCI System must be restored to operable status within 14 days during reactor power operation. In this condition, adequate core cooling is ensured by the operability of the redundant and diverse low pressure emergency core cooling system (ECCS) injection and spray subsystems in conjunction with the Automatic Depressurization System (ADS). Also, the RCIC System will automatically provide makeup water at reactor operating pressures above 150 psig. During reactor power operation, immediate verification of RCIC operability is therefore required when HPCI is inoperable. This may be performed as an administrative check by examining logs or other information to determine if RCIC is out of service for maintenance or other reasons. It does not mean it is necessary to perform the surveillances needed to demonstrate the operability of the RCIC System.

If operability of the RCIC System cannot be verified, however, Specification 3.5.E.3 requires that an orderly shutdown be initiated and reactor pressure reduced to ! 150 psig within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

F. Automatic Depressurization System The Automatic Depressurization System (ADS) consists of the four safety relief valves and serves as a backup to the High Pressure Coolant Injection System (HPCI). ADS is designed to provide depressurization of the reactor coolant system during a small break loss-of-coolant accident if HPCI fails or is unable to maintain sufficient reactor water level.

Since HPCI operability is required above 150 psig, ADS operability is also required above this pressure.

ADS operation reduces the reactor pressure to within the operating pressure range of the low pressure coolant injection and core spray systems, so that these systems can provide reactor coolant inventory makeup.

i77, -9, 29s, 209 llla Amendment No. -4,  !-69,

';YNS BASES: 3.5 (Cont'd) core The low pressure ECCS injection/spray subsystems consist of two spray (CS) and two low pressure coolant injection (LPCI) subsystems.

requires During cold shutdown and refueling conditions, each CS subsystem to transfer water from the one motor driven pump, piping, and valves suppression pool or condensate storage tank to the reactor pressure vessel (RPV). Also, during cold shutdown and refueling conditions, each valves to LPCI subsystem requires one motor driven pump, piping, and Under these transfer water from the suppression pool to the RPV.

subsystem because of conditions, only a single LPCI pump is required per a CS subsystem. During the larger injection capacity in relation to subsystems may be considered shutdown and refueling conditions, LPCI decay heat operable during RHR system alignment and operation for are capable of being manually realigned to removal, if those subsystems the LPCI mode and are not otherwise inoperable. Because of low pressure and refueling, and low temperature conditions during cold shutdown initiate LPCI sufficient time will be available to manually align and prior to postulated fuel subsystem operation to provide core cooling uncovery.

I. Maintenance of Filled Discharge Pipe subsystems, LPCI Full discharge lines are required when the core spray preclude the subsystems, HPCI and RCIC are required to be operable to piping due to water hammer action possibility of damage to the discharge upon a pump start.

209 112 Amendment No. 4-&, BVY 99 144, i9s, 2

VYN PS BASES: 4.5 (Cont'd)

The Automatic Depressurization System is tested during refueling System.

outages to avoid an undesirable blowdown of the Reactor Coolant of the The HPCI Automatic Actuation Test will be performed by simulation with the accident signal. The test is normally performed in conjunction automatic actuation of all Core Standby Cooling Systems.

G. Reactor Core Isolation Cooling System are the The frequency and conditions for testing of the RCIC system with for the HPCI system. Testing is conducted in accordance same as will Specification 4.6.E and provides assurance that the system function as intended.

H. Minimum Core and Containment Cooling System Availability Deleted.

I. Maintenance of Filled Discharge Pipe vent as Observation of water flowing from the discharge line high point 4.5.1 assures that the Core Cooling Subsystems required by Specification pumps are will not experience water hammer damage when any of the started. Core Spray Subsystems and LPCI Subsystems will also be vented discharge line high point vent following a return from an through the for system is "solid" and ready inoperable status to assure that the operation.

4-4, 7, -144, 4-2-9, 7-, 209 114 Amendment No.

VYNPS 3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION once per operating

3. a. From and after the cycle not to exceed date that one train 18 months. If the of the Standby Gas ultrasonic test Treatment System is indicates the made or found to be presence of a leak, inoperable for any reason, reactor the condition will be evaluated and the operation is gasket repaired or permissible only replaced as during the necessary.

succeeding seven days unless such

f. DOP and halogenated train is sooner made hydrocarbon test operable, provided shall be performed that during such seven days all following any design modification to the active components of Standby Gas the other standby Treatment System gas treatment train housing that could shall be operable. have an effect on the filter If this condition efficiency.

cannot be met during reactor operation, or

g. An air distribution the inoperable train is test demonstrating not restored to uniformity within operable status within

+/-20% across the HEPA seven days, the actions filters and charcoal and completion times of adsorbers shall be Specification 3.7.B.4.a performed if the shall apply.

SGTS housing is modified such that

3. b. From and after the distribution air date that one train of the Standby Gas could be affected.

Treatment System is

3. a. At least once per made or found to be operating cycle inoperable for any automatic initiation reason, operations of each train of the requiring secondary Standby Gas containment are Treatment System permissible during shall be the succeeding seven demonstrated.

days unless such train is sooner made Operability testing b.

operable, provided of valves shall be that during such in accordance with seven days all Specification 4.6.E.

active components, including the

c. Deleted.

associated Emergency Diesel Generator of the other standby gas treatment train shall be operable.

If this condition cannot be met during a refueling or cold Amendment No. 4-1, 4-9, 444, 1-24, 4-44, 4-9-7, 209 154

VYNPS LIMITING CONDITIONS FOR 4.10 SURVEILLANCE REQUIREMENTS 3.10 OPERATION B. Operation With Inoperable B. Operation With Inoperable Components Components

1. Diesel Generator Whenever the reactor is in Run Mode or Startup Mode When one of the with the reactor not in the emergency diesel Cold Condition, the generators is made or requirements of 3.10.A found to be inoperable:

shall be met except:

Diesel Generators a. Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

1. determine that the remaining diesel From and after the date generator is not that one of the diesel inoperable due to generators or its common cause associated buses are made or found to be failure; or inoperable for any

b. The remaining diesel reason and the generator shall have remaining diesel been or shall be generator is operable, demonstrated to be the requirements of Specification 3.5.H.l operable within 24 shall be satisfied. hours.

2. Batteries

2. Batteries Samples of the Battery

a. From and after the Room atmosphere shall date that ventilation is lost be taken daily for hydrogen concentration in the Battery Room determination.

portable ventilation equipment shall be provided.

b. From and after the date that one of the two 125 volt Station Battery Systems is made or found to be inoperable for any reasons, continued reactor operation is permissible only during the succeeding three days provided Specification 3.5.H is met unless such Battery System is sooner made operable.

Amendment No. 4G, -*4--, 4-44, 209 215

VXYNPS 4.10 SURVEILLANCE REQUIREMENTS 3.10 LIMITING CONDITIONS FOR OPERATION

b. From and after the b. When either off-site power date that either source and one off-site power diesel or source and cne associated buses diesel generator are unavailable:

are made or found to be inoperable 1. The other for any reason, off-site power continued source and all operation is Low Pressure permitted for Core and 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> as long Containment as the remaining Cooling Systems off-site power shall have been source, the or shall be remaining diesel verified generator, operable within associated one hour and emergency buses once per eight and all Low hours Pressure Core and thereafter.

Containment Cooling Systems 2. The requirements are operable. of Specification 4.10.B.1 shall If this require be met within 24 ment cannot be hours.

met, an orderly shutdown shall be initiated and the reactor shall be in cold shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment No. 4-5-., 209 217a

VYNPS BASES: 4.10 (Cont'd) for the associated batteries. The results of these tests will be logged and compared with the manufacturer's recommendations of acceptability.

The Service Discharge Test (4.10.A.2.c) is a test of the batteries ability to satisfy the design requirements of the associated dc system. This test will be performed using simulated or actual loads at the rates and for the durations specified in the design load profile (battery duty cycle).

Assurance that the diesels will meet their intended function is obtained by periodic surveillance testing and the results obtained from the pump and valve testing performed in accordance with the requirements of ASME Section XI and Specification 4.6.E.

Specification 4.10.B.l.a provides an allowance to avoid unnecessary testing of the operable emergency diesel generator (EDG). If it can be determined that the cause of the inoperable EDG (e.g., removal from service to perform routine maintenance or testing) does not exist on the operable EDG, demonstration of operability of the remaining EDG does not have to be performed. If the cause of inoperability exists on the remaining EDG, it is declared inoperable upon discovery, and Limiting Condition for Operation 3.5.H.1 requires reactor shutdown within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Once the failure is repaired, and the common cause failure no longer exists, Specification 4.10.B.l.a is satisfied. If the cause of the initial inoperable EDG cannot be confirmed not to exist on the remaining EDG, performance of Surveillance Requirement (SR) 4.10.B.l.b suffices to provide assurance of continued operability of that EDG.

In the event the inoperable EDG is restored to operable status prior to completing either SR 4.10.B.l.a or SR 4.10.B.l.b, the plant corrective action program will continue to evaluate the common cause possibility. This continued evaluation, however, is'no longer under the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> constraint imposed while in the condition of SR 4.10.B.1 or SR 4.10.B.3.b.2.

According to NRC Generic Letter 84-15, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is a reasonable time to confirm that the operable EDG is not affected by the same problem as the inoperable EDG.

Verification of operability of an off-site power source and Low Pressure Core and Containment Cooling Systems within one hour and once per eight hours thereafter as required by 4.10.B.3.b.l may be performed as an administrative check by examining logs and other information to determine that required equipment is available and not out of service for maintenance or other reasons. It does not require performing the surveillance needed to demonstrate the operability of the equipment.

C. Logging the diesel fuel supply weekly and after each operation assures that the minimum fuel supply requirements will be maintained. During the monthly test for quality of the diesel fuel oil, a viscosity test and water and sediment test will be performed as described in ASTM D975-68. The quality of the diesel fuel oil will be acceptable if the results of the tests are within the limiting requirements for diesel fuel oils shown on Table 1 of ASTM D975-68.

Amendment No. 4-2,,4-535, BWv-01-40-, 209 223