ML20058Q149

Proposed Tech Specs Providing Option for Verifying Operability During LCO by Exam of Surveillance Records

ML20058Q149
Person / Time
Site:	Oyster Creek
Issue date:	10/18/1993
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20058Q136	List: ML20058Q131 ML20058Q140 ML20058Q149
References
NUDOCS 9310260091
Download: ML20058Q149 (8)

Text

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SECTION.I

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DEFINITIONS The following frequently used terms are defined to aid in the uniform interpre-tation of the specification.

i 1.1 OPERABLE-OPERABILITY 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 and emergency electrical power sources,-

cooling of 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).

A verification of operability is an administrative check, by examination of appropriate plant records (logs, surveillance test records) to determine that a system, subsystem, train, componentior device is not inoperable. Such verification does not preclude the demonstration (testing) of a given system, subsystem, train, component or device to determine operability.

i 1.2 OPERATING t

Operating means that a system or component is performing its required function.

1.3 POWER OPERATION Power operation is any operation when the reactor is in the startup mode or run mode except when primary containment integrity is not required.

1.4 STARTUP MODE The reactor is in the startup mode when the reactor mode switch is in the startup n: ode position.

In this mode, the reactor protection system scram trips initiated by condenser low vacuum and main steam line-isolation valve closure are bypassed when reactor pressure is less than 600 psig; the low pressure main steamline isolation valve closure is bypassed; the IRM trips for rod block and scram are operable; and the SRM trips for rod block are operable.

1.5 RUN MODE The reactor is in the run mode when the reactor mode. switch is in the run mode position.

In this mode, the reactor protection system is energized with APRM protection and the control rod withdrawal interlocks are in service.

1.6 SHUTDOWN CONDITION The reactor is in a shutdown condition when the reactor mode switch is in the shutdown mode position and there is fuel in the reactor vessel.

In this condition, the reactor is subcritical, a control rod block is initiated, all operable control rods are fully inserted, and specification 3. 2-A is met.

0YSTER CREEK 1.0-1 Amendment No.: 20, 44, 64 9310260091 931018 h

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The standby liquid control solution shall have a Boron-10 isotopic enrichment equal to or greater than 35 atom %, be maintained within the cross-hatched volume-concentration requirement area in Figure 3.2-1 and at a temperature not less than the temperature presented in Figure 3.2-2 at all times when the standby liquid control system is required to be operable.

3.(a)

If one standby liquid control system pumping circuit i

becomes inoperable during the RUN mode and Specification 3.2.A is met, the reactor may remain in operation for a period not to exceed 7 days, provided the pump in the i

other circuit is verified daily to be operable, otherwise be in the Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

l (b)

If the solution is outside the cross-hatched volume-concentration area but within the shaded volume-concentration area of Figure 3.2-1, return the solution to the cross-hatched area within 7 days.

If, after this time period, the requirement is still not met, submit a report to the NRC within 7 days advising them of plants to return the solution to the cross-hatched volume-concentration area.

(c)

If the solution is outside the cross-hatched volume concentration area and outside the shaded volume-concentration area of Figure 3.2-1, return the i

solution to within the shaded volume-concentration area of Figure 3.2-1 or be in the Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(d)

If the solution temperature is less than the minimum shown in Figure 3.2-2, increase the temperature to greater than the minimum and verify the solution is within the shaded l

volume-concentration area of Figure 3.2-1 or be in the Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

(e)

If the enrichment requirement of 3.2.C.2 is not met:

(1) Return the Boron-10 isotopic enrichment to greater than or equal to 35 atom % within 7 days of the receipt of the enrichment report.

If, after this time i

period, the enrichment requirement is still not met, submit a report to the NRC within 7 days advising them of the plans to return the solution to greater than or equal to 35 atom % Baron-10 isotopic enrichment.

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(2) A check shall be made to ensure that the sodium pentaborate solution meets the original design criteria by comparing the enrichment, concentration and volume to established criteria (Boron-10 equal to or greater than 82 pounds).

If the sodium pantaborate solution does not meet the original criteria, be in the Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

0YSTER CREEK 3.2-3 Amendment No: 75, 124 i

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3.4 EMERGENCY COOLING

'Apolicability:

Applies to the operating. status of the emergency cooling systems.

i Ob.iective:

To assure operability of the emergency cooling systems.

Soecifications:

A.

Core Sorav System 1.

The core spray system shall be operable at all times with irradiated fuel in the reactor vessel, except as otherwise specified in this section.

2.

The absorption chamber water volume shall be at least 82,000 l

ft.3 in order for the core spray system to be considered operable.

3.

If one core spray system-loop or its core spray header delta P instrumentation becomes inoperable during the run mode, the reactor may remain in operation for a period not to exceed 7 days (See Note below) provided:

a.

The remaining loop has no inoperable components and is verified daily to be operable and, b.

The average planar linear heat generation rate (APLHGR) of all the rods in any fuel assembly, as a function of average planar exposure, at any axial location shall not exceed 90% of the limits given.in Specification 3.10.A.

The action to bring the core to 90% of the APLHGR. Limits must be completed within two hours after the system has been determined to be inoperable.

4. The reactor may remain in' operation for a period not to exceed 15 days if one of the redundant active loop components in the core i

spray system becomes inoperable during the run mode provided:

l a.

In the event of an inoperable core spray booster pump, the other core spray booster pump in the loop is verified daily to be operable.

b.

In the event of an inoperable core spray main pump, the other core spray main pump in the loop is verified daily to be operable and the APLHGR of all the rods in any fuel assembly, as a function of average planar exposure, at any axial location shall not exceed 90% of the limits given in Specification 3.10.A.

The action to bring the core to 90%'of the APLHGR Limits must be completed within two hours after the component has been determined to be inoperable.

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OYSTER CREEK 3.4-1 Amendment No.: 75, 153

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automatic depressurization function) may be inoperable or-bypassed during the system hydrostatic pressure. test required by ASME Code Section XI, IS-500 at-or near the end of each ten year.

inspection interval.

2. If at any time there are only four operable.electromatic rel.ief valves, the reactor may remain in operation for a period not to

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exceed 3 days provided the motor operated isolation and condensate makeup valves in both isolation condensers are verified daily to be operable.

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3. If Specifications 3.4.8.1 and 3.4.B.2 are not met; reactor prersure shall be reduced to 110 psig or less, within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4. The time delay set point for initiation after coincidence of low-low-low reactor water level and high drywell pressure shall be set not to exceed two minutes.

C.

Containment Sorav vstem and Emeraency Service Water System e

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1. The containment spray system and the emergency service water system shall be operable at all times with irradiated fuel in the reactor vessel, except as specified in Specifications.

i 3.4.C.3, 3.4.C.4, 3.4.C.6 and 3.4.C.8.

2. The absorption chamber water volume shall not be less than 82,000 ft in order for the containment spray and emergency service water system to be considered operable.

5. If one emergency service water system loop becomes inoperable, its associated containment spray system loop shall be considered inoperable.

If one containment spray system loop and/or its associated emergency service water system loop becomes inoperable during the run mode, the reactor may remain in operation for a period not to exceed 7 days provided the' i

remaining containment spray system loop and its associr d emergency service water system loop each have no inoper sole components and are verified daily to be operable.

4. If a pump in the containment spray system or emergency service water system becomes inoperable, the reactor may remain in operation for a period not to exceed 15 days provided the other similar pump is verified daily to be operable. A maximum of two pumps may be inoperable provided the two pumps are not in the same loop.

If more than two pumps become inoperable, the limits of Specification 3.4.C.3 shal. apply.

5. During the period when onc A is inoperable, the containment spray loop anc.*

+ ncy service water system loop connected to the operable o<

shall have no inoperable components.

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6. If primary containment integrity is not required (see Specification 3.5. A), the containment spray system may be made inoperable.

0YSTER CREEK 3.4-4 Amendment No.: 75, 153 h:

t 1.1 Upon the accidental loss of secondary containment integrity, restored secondary containment integrity o

within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, or:

a.

During Power Operation:

(1)

Have the reactor mode switch in the shutdown I

mode position within the following 24 huurs.

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(2)

Cease all work on the reactor or its connected systems in the reactor' building which could result in inadvertent releases of radioactive materials.

(3)

Cease all operations in, above or around the i

Spent Fuel Storage Pool that could cause release of radioactive materials.

i b.

During refueling:

(1)

Cease fuel handling operations or activities which could reduce the shutdown m rgin 1

(excluding reactor coolant temperature changes).

(2)

Cease all work on the reactor or its connected systems in the reactor building which could

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result in inadvertent releases of radioactive i

materials.

(3)

Cease all operations in, above or around H

the Spent Fuel Storage Pool that could j

cause release of radioactive materials.

I 2.

Two separate and independent standby gas treatment system circuits stt'l be operable when secondary containment is r4 i except as specified by Specifi-I cation 3.5.B.3.

3.

With one standby gas treatment system circuit inoperable:

a.

During Power Operation:

(1)

Verify the operability of the cther standby gas treatment system circuit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. If testing is required to demonstrate operability i

and significant painting, fire, or chemical release has taken place in the reactor building within the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, then demonstration by testing shall take place within I hour of the expiration of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period, and (2)

Continue to verify the operability of the stanouy qas treatment system circuit once per 24

'trs until the inoperable standby gas t'aatment circuit is returned to operable status.

0YSTER CREEK 3.5-6 Amendment No.: 14,18,32,74,103

I (3)

Restore the inoperable standby gas treatment circuit to operable status within 7 days or be subcritical with reactor coolant tempera-ture less than 212*F within the next 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, b.

During Refueling:

(1)

Verify the operability of the'other standby gas treatment system circuit within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. If testing is required to demonstrate operability and significant painting, fire, or chemical release has taken place in the reactor building within the previous 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, then demonstration by testing shall take place within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of the expiration of the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> period, and (2)

Continue to verify the operability of the redundant standby gas treatment system r

once per 7 days until the inoperable system is returned to operable status.

(3)

Restore the inoperable standby gas treatment system to operable status within 30 days or cease all spent fuel handling, core altera-tions or operation that could reduce the shutdown margin (excluding reactor coolant temperature changes) 4.

If Specifications 3.5.B.2 and 3.5.B.3 are not met, reactor 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 /> and the condition of Specification 3.5.B.1 shall be met.

Bases:

Specifications are placed on the operating status of the containment systems to assure their availability to control the release of any radioactive materials from irradiated fuel in the event of an accident condition. The primary containment system (1) provides a barrier against uncontrolled release of fission products to the environs in the event of a break in the reactor coolant systems.

Whenever the reactor coolant water temperature is above 212*F, failure of the reactor coolant system would cause rapid expulsion of the coolant from the reactor with an associated pressure rise in the primary containment.

Primary containment is required, therefore, to contain the thermal energy of t:.e expelled coolant and fission products which could be released from any fuel failures resulting from the accident.

If the reactor coolant is not above 212*F, there would be no pressere rise in the containment.

In addition, the coolant cannot be expelled at a rate which could cause fuel failure to occur before the core spray systea restores cooling to the core.

Primary containment is not needed while performing-low power physics tests since procedures and the Rod Worth Minimizer would limit i

1 OYSTER CREEK 3.5-7 Amendment No.: 14,74,75,103

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3.8 ' ISOLATION CONDENSER Applicatrility:

Applies to operating status of the isolation condenser.

Ob.iective:

To assure heat removal capability under conditions of reactor i

vessel isolation from its normal heat sink.

Specification:

A. The two isolation condenser loops shall be operable during j

power operations and whenever the reactor coolant temperature j

is greater than 212*F except as specified.in C, below or during reactor vessel pressure testing.

B. The shell side of each condenser shall contain a minimum water volume of 22, 730 gallons.

If the minimum volume cannot be maintained or if a source of makeup water is not available to l

the condenser, the condenser shall be considered inoperable.

C. If one isolation condenser becomes inoperable during the run mode the reactor may remain in operation for a period not to exceed 7 days provided the motor operated isolation and condensate makeup valves in the operable isolation condenser are verified daily to be operable.

D. If Specification 3.8.A and 3.8.B are not met, or if an inoperable isolation condenser cannot be repaired within 7 l

days, the reactor shall be placed in the cold shutdown i

condition.

E. If an isolation condenser inlet (steam side) isolation valve (V-14-30, 31, 32 or 33) becomes or is made inoperable, in the open position during the run mode, the redundant inlet isolation valve shall be verified operable.

If the inoperable valve is not returned to service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> declare the affected isolation condenser inoperable, isolate it and comply with Specification 3.8.C.

l F. If an AC motor-operated isolation condenser outlet (condensate return) isolation valve (V-14-36 or 37) becomes or is made inoperable in the open position in the run mode, return the i

valve to service within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the affected l

isolation condenser inoperable, isolate it and comply with 6

Specification 3.8.C.

i 3

Basts:

The purpose of the isolation condenser is to depressurize the l

reactor and to remove reactor decay heat in the event that the turbig generator and main condenser is unavailable as a heat sink.

Since the shell side of the isolation condensers operate at atmospheric pressure, they can accomplish-their purpose j

when the reactor temperature is sufficiently above 212"F to i

provide for the heat transfer corresponding to reactcr decay I

heat. The tube side of the isolation condensers form a closed loop with the reacter vessel and can operate without reducing the reactor coolant water inventory.

0YSTER CREEK 3.8-1 Amendment No.: 72, 120

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1 '.17' Control room Heatina. Ventilatina, and Air-Conditionino System 3

. Applicatrility:

Applies to the operability of the control room heating, ventilating, and air conditioning (HVAC) system.

Obtdntive:

To assure the capability of the control room HVAC system to 1

minimize the amount of radioactivity from entering the control room in the event of an accident.

l Specification:

A.

The control room HVAC system shall be operable during all

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modes of plant operation.

B.

With the control room HVAC system determined inoperable:

1.

Verify once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> the partial recirculation mode of operation for the operable system, or place the operable system in the partial recirculation mode; and 2.

Restore the inoperable system within 7 days, or prepare and submit a special report to the Commission in lieu of any (ther report required by i

Section 6.9, within the next 14 days, outlining the action taken, the cause of the inoperability and the plans / schedule for restoring the HVAC system to operable status.

i C.

With both control room HVAC systems determined inoperable.

1.

During Power Operation: place the reactor in the cold shutdown condition with 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> 2.

During Refueling:

i (a)

Cease irradiated fuel handling operations; and (b)

Cease all work on the reactor or its connected systems in the reactor building whi,;n could

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result in inadvertent releases of radioactive s

materials.

Basis:

The operability of the control room HVAC system ensures that the control room will remain habitable for operations personnel during a postulated design basis accident. The control room envelope includes the control room panel area, the shift supervisor's office, toilet room, kitchen, and lower cable spreading room.

Since Systems A and B do riut have HEPA filters or charcoal absorbers, the supply fan and dampers for each system minimize the beta and gamma doses to the operators by providing positive pressurization and limiting the makeup and infiltration air into the control room envelope. For the supply of 100% outside air to the control room envelope, the dose increase to 29.1 rem beta and 3.14 rem gamma for the assumed 30 days, however, these values are within the allowable limits.

OYSTER CREEK 3.17-1 Amendment No.:

115, 139

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