Text

Amend 59 to License DPR-37,revising Tech Specs to Reflect Changes as Result of Mods Made to Alleviate NPSH Problems W/Low Head Safety Injection & Recirculation Spray Pumps
	ML19331E106
Person / Time
Site:	Surry
Issue date:	08/01/1980
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
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ML19331E107	List: ML19331E106; ML19331E112; ML19331E115;
References
	NUDOCS 8009050510
	Download: ML19331E106 (27)
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NUCLEAR REGUt.ATORY COMMISSION a

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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SU_RRY POWER STATION, UNIT NO. _2 AMENDMENT T0 FACILITY OPERATING LICE _NSE Amendment No. 59 License No. DPR-37 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Virginia Electric and Power Company (the licensee) dated June 30, 1980, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regula-tions set forth in 10 CFR Chapter I; B.

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

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

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

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable require-ments have been satisfied.

i 80090505/02

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2.

Accordingly, the license is amended by deleting paragraph 3.F of the license and by changes to the Technical Specifications as indicated in the attachment to the license amendment,'and para-graph 3.B of Facility Operating License No. DPR-37 is amended to read as follows:

l B.

Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 59, are hereby

'l incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specification:.

3.

This license amendment is effective as of the date of its issuance.

FC R THE NUCLEAR REGULATORY COMMISSION f

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. Steven A. V rga, C (kf Operating Reactors BYanch #1 4

Div's ion of Licensing

Attachment:

Changes to the Technical Specifications

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Date of Issuance: August 1,1900 i

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ATTACHMENT TO LICENSE AMEN 0 MENT NO. 59 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NO. 50-PH1 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by amendment number and certain vertical lines indicating the area of change.

Remove Insert 3.3-1 3.3-1 3.3-2 3.3-2 3.3-3 3.3-3 3.3-4 3.3 4 3.3-5 3.3-5 3.3-6 3.3-6 3.3-7 3.3-7 3.3-8 3.3-8 3.3-9 3.3-9 3.4-1 3.4-2 3.4-3 3.4-4 3.4-5 3.4.2-1 3.6-3 3.4.2-2 3.4.2-3 3.8-1 3.4.2-4 3.8-2 3.4.2-5 3.8-3 3.6-3 3.8-4 TS Figure 3.8-1 4.1-7 3.8.2-1 3.8.2-2 3.8.2-3 3.8.2-4 TS Figure 3.8.2-1 TS Figure 3.8.2-1 (Continued) 4.1 -7 4.5-6 4.11-5

TS 3.3-1 3.3 SAFETY INJECTION SYSTEM Applicability Applies to the operating status of the Safety Injection System.

Objective To define those limiting conditions for operation *. hat are necessary to provide sufficient borated cooling water to remove decay heat from the core in emergency situations.

Specifications A.

A reactor shall not be made critical unless the following conditions t

are met:

1.

The refueling water storage tank contains not less than 385,200 gal (Unit 1) or 387,100 gal (Unit 2) of borated water. For Unit 1 only, the boron concentration shall be at least 2300 ppm.

For Unit 2 only, the boron concentration shall be at least 2000 ppm and not greater than 2200 ppm.

2.

Each accumulator systec is pressurized to at least 600 psia and 3

3 contains a minimum of 975 ft and a maximum of 989 ft of borated water with a, boron concentration of at least 1950 ppm.

3.

The boron injection tank and isolated portion of the inlet and outlet piping contains no less than 900 gallons of water with a boron concentration equivalent to at least 11.5% to 13% weight boric acid solution at a temperature of at least 145 F.

Addi-tionally, recirculation between a unit's Boron Injection Tank and the Boric Acid Tank (s) assigned to the unit shall be main-tained.

Amendment No. 59, Unit 2

T.S. 3.3-2 4.

Two channels of heat tracing shall be available for the flow paths.

i 3.

Two charging p' umps are operable.

6.

Two low head safety injection pumps are operable.

7.

All valves, piping, and interlocks associated with the above components which are required to operate under accident condi-1 tions are operable.

4 8.

The Charging Pump Cooling Water Subsystem shall be operating as follows:

Make-up water from tae Component Cooling Water Subsystem a.

shall be available.

4 b.

Two charging pump c;.conent cooling water pumps and two charging pump service water pumps shall be operable.

Two charging pump intermediate seal coolers shall be c.

operable.

9.

During power operation the A.C. power shall be removed from the following motor operated valves with the valve in the open position:

Unit No. 1 Unit No. 2 MOV 1980C MOV 2890C

10. During power operation the A.C. power shall be removed from the following motor operate'd valves with the valve in the closed position:

Unit No. 1 Unit No. 2

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M0V 1869A M0V 2869A

'MOV 1869B MOV 2869B MOV 1890A MOV 2890A 110V 1890B MOV 2890B Amendment No.-59, Unit 2

T.S. 3.3-3 i

11. The accumulator discharge valves listed below in non-isolated loops shall be blocked open by de-ei.ergizing the valve motor operator when the reactor coolant system pressure is greater than 1000 psig.

Unit No. I Unit No. 2 MOV 1865A MOV 2865A M0V 1865B MOV 2865B MOV 1865C MOV 2865C

12. Power cperation with less than three loops in service is pro-hibited. The following loop isolation valves shall have AC power removed and be locked in open position during power operation.

Unit No. 1 Unit No. 2 li MOV 1590 MOV 2590 MOV 1591 MOV 2591 MOV 1592 MOV 2592 i

MOV 1593 MOV 2593 MOV 1594 MOV 2594 MOV 1595 MOV 2595

13. The total system uncollected leakage from valves, flanges, and pumps located outside containment shall not exceed the limit i

shown in Table 4.11-1 as verified by inspection during system l

testing.

Individual component leakage may exceed the design value given in Table 4.11-1 provided that the total allowable i

system ur. collected leakage is not exceeded. The leakage limits are for each unit.

The leakage limits are for each unit.

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Amendment No. 59, Unit 2

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TS 3.3-4 t

8.

The requirements of Specification 3.3-A may be modified to allow one of the following components to be inoperable at any one time.

If the system is not restored to meet the requirements of Specification 3.3-A within the time period s'pecitied, the reactor shall initially e

be placed in the hot shutdown condition.

If the requirements of j

Specification 3.3-A are not satisfied within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the reactor shall be placed in' the cold shutdown condition.

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1.

One accumulator may be isolated for a period not to exceed 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

2.

Two charging pumps per unit may be out of service, provided immediate attention is directed to making repairs and one pump is restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

3.

One low head safety injection pump per unit may be out of service, a

provided immediate attention is directed to making repairs and the pump is restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . The other low head safety injection pump shall be tested to demonstrate operability prior to initiating repair of the inoperable pump and shall be tested once every eight (8) hours thereaf ter, until both pumps are in an operable status or the reactor is shutdown.

4.

Any one valve in the Safety Injection System may be inoperable provided repairs are initiated immediately and are completed within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Prior to initiating repairs, all automatic valves in the redundant system shall be tested to demonstrate operability.

5.

One channel of heat tracing may be inoperable for a period not to exceed 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , provided immediate attention is directed to making repairs.

Amendment No. 59, Unit 2

1 T.S. 3.3-5 J

6.

One charging pump component cooling water pumps or one charging pump service water pump may be out of service provided the pump is restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

7.

One charging pump interme,diate seal cooler or other passive comp < nent may be out of service provided the system may still i

operate at 100 percent ca'pacity and repairs are completed within j

48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

t 8.

Power may be restored to any valve referenced in 3.3.A.9 and 3.3.A.10 for the purpose of valve testing or maintenance pro-viding no more than one valve has power restored and provided I

that testing and maintenance is completed and power removed

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i within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

9.

Power may be restored to any valve refe.r,enced in 3.3.A.11 for the purpose of valve testing or maintenance providing no more than one valve has power restored and provided that testing or maintenance is completed and power removed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

10.

Recirculation between a unit's Boron Injection Tank and the Boric Acid Tank (s) assigned to the unit may be terminated for i

a period not to exceed two hours, provided all other parameters (temperatures, boron ccatentration, volume) of the Boron Injec-tion Tank are within Specification 3.3. A.i and immediate attention is directed to making repairs.

i 11.

The total uncollected system leakage for valves, flanges, and pumps located outside containment can exceed the limit shown in Table 4.11-1 provided immediate attention is directed to making repairs and system leakage is returned to within limits within 7 days.

Amendment No. 59, Unit 2

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T.S. 3.3-6 3

Basis The normal procedure for starting the reactor is, first, to heat the reactor coolant to near operating temperature by running the reactor coolant pumps. The reactor is then made critical by withdrawing control ir E

rods and/or diluting boron in the coolant. With this node of startup the Safety Injection System is required to be operable as specified.

During low power physics tests there is a negligible amount of energy stored in the system; therefore an accident comparable in severity to the Design Basis Accident is not possible, and the full capacity of the Safety Injection System is not required.

The operable status of the various systems and components is to be demonstrated by periodic tests, detailed in TS Section 4.1.

A large fraction of these tests are performed while the reactor is operating in the power range.

If a component is found to be inoperable, it will be possible in most cases to-effect repairs and restore the system to full hk b

operability within a relatively short time. A single ccmponent being

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inoperable does not negate the ability of the system to perform its function, but is reduces the redundancy provided in the reactor design and thereby limits the ability to tolerate additional equipment failures.

To provide maximum assurance that the redundant component (s) will operate I

if required to do so, the redundant component (s) are to be tested prior D

to initiating repair of the inoperable component and, in some cases are to be retested at intervals during the repair period.

In some cases, i.e.

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charging pumps, additional components are installed to allow a component E

to be inoperable without affecting system redundancy. For those cases I:

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F Amendment No. 59, Unit 2 i

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,T.S. 3.3-7

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which are not so designed, if it develops that (a) the inoperable component is not repaired within the specified allowable time period, or (b) a second component in the same or related system is found to be inoperable, the reactor will initially be put in the hot shutdown condition to provide for reduction of the decay heat from the fuel, and consequent reduction of cooling requirements after a postulated loss-of-coolant accident. After 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months in the hot shutdown condition, if the matfunction(s) are not corrected the reactor will be placed in the cold shutdown condition, following normal shutdown and cooldown procedures.

The Specification requires prompt action to effect repairs of an inoperable component, and therefore in most cases repairs will be completed in less than the specified allowable repair times. Furthermore, the specified repair times do not apply to regularly scheduled maintenance of the Safety Injection System, which is normally to be performed during refueling shut-downs. The liniting times for repair are based on: estimates of the time required to diagnose and correct various postulated malfunctions using safe and proper procedures, the availability of tools, materials and equipment; health physics requirements and the extent to which other systems provide functional redundancy to the system under repair.

Assuming the reactor has been operating at full rated power for at least 100 days, the magnitude of the decay heat production decreases as follows after initiating hot shutdown.

Time After Shutdown Decay Heat, % of Rated Power 1 min.

3.7 1

30 mi.

1.6 l

Amendnent No. 59, Unit 2 f

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T.S. 3.3-8

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f Time After Shutdown Decay Heat, % of Rated Power 1.3 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 0.75 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 0.48 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months Thus, the requirement for core cooling in case of a postulated loss-of-coolant accident while in the hot shutdown condition is reduced by orders i

of magnitude below the requireu. ants for handling a postulated loss-of-coolant accident occurring during power. operation.

Placing ard maintain-E' ing the reacter in the hot shutdown condition significantly reduces the n

potential consequences of a loss-of-coolant accident, allows access to some of the Safety Injection System components in order to effect repairs, E

and minimizes the exposure to thermal cycling.

Failure to complete repairs within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of going to hot shutdown condition is considered indicative of unforeseen problems, i.e., possibly the need of major maintenance.

In such a case the reactor is to be put

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into the cold shutdown condition.

The accumulators are able to accept leakage from the Reactor Coolant System without any effect on their availability. Allowable inleakage is based on the volume of water that can be added to the initial amount without exceed-ing the volume given in Specification 3.3.A.2.

The maximum acceptable j

l inleakage is 14 cubic feet per tank.

i Amendment No. 59, Unit 2 I

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T. S. 3.3-9 J

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The accumulators (one for each loop) discharge into the co.'.d leg of the

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reactor coolant piping when Reactor Coolant System pressure decreases below accumulator pressure, thus assuring rapid core cooling for large 1

breaks. The line from each accumulator is provided with a motorized p

valve to isolate the accumulator during reactor start-up and shutdown r

to preclude the discharge of the contents of the accumulator when not

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i required. These valves receive a signal to open when safety injection b

is initiated.

To assure that the accumulator valves satisfy the single failure i

criterion, they will be blocked open by de-energizing the valve motor 4

operators when the reactor coolant pressure exceeds 1000 psig. The 4

operating pressure of the Reactor Coolant System is 2235 psig and safety p

injection is initiated when this pressure drops to 600 psig. De-energiz-ing the motor operator when the pressure exceeds 1000 psig allows I

L sufficient time during normal starttp operation to perform the actions g

required to de-energize the valve.

This procedure will assure that there is an operable flow path from each accumulator to the Reactor Coolant System during power operation and that safety injection can be accom-plished.

1 4

The removal of power from the velves listed in the specification will a

assure that the systems of which they are a part satisfy the single fail,ure criterion.

4 Continuous recirculation between the Boron Injection Tank and the Boric 4

Acid Tank (s) ensures that a unit's Boron Injection Tank is full of con-centrated boric acid at all times.

Amendment No. 59, Unit 2

lT.S. 3.4.2-1 3.4.2 SPRAY SYSTEMS (UNIT 2)

Applicability I

Applies to the operational status of the Spray Systems.

Objective To define those conditions of the Spray Systems necessary to assure safe unit operation.

Specification A.

A unit's Reactor Coolant System temperature or pressure shall not be made to exceed 350 F or 450 psig, respectively, or the reactor shall not be made critical unless the following Spray System conditions in the unit are met:

Two Containment Spray Subsystems, including containment spray 1.

pumps and motor drives, piping, and valves shall be operable.

2.

Four Recirculation Spray Subsystems, including recirculation i

spray pumps, coolers, piping, and valves shall be operable.

3.

The refueling water storage tank shall contain not less than 387,100 gal and not greater than 398,000 gal of borated water at a maximum temperature as shown in Fig. 3.8.2-1.

If this volume of water cannot be maintained by makeup ec the temperature maintained below that specified in 7 1'

3. 8. 2-1, the reactor shall be shutdown until repairs can be made. The water shall be borated to a boron concentration not less than Amendment No. 59, Unit 2

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, T.S. 3.4.2-2 l

2,000 ppm and not greater than 2200 ppm which will assure that p

L the reactor is in the refueling shutdown condition when all

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control rod assemblies are inserted.

4.

The refueling water chemical addition tank shall contain not i

less than 4,200 gal of solution with a sodium hydroxide concen-tration of not less than 17 percent by weight and not greater i

than 18 percent by weight.

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5.

All valves, piping, and interlocks associated with the above components which are required to operate under accident

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conditions shall be operable.

6.

The total uncollected system leakage from valves, flanges, and pumps located outside cont.ainment shall not exceed the limit shown in Table 4.5-1 as verified by inspection during system testing. Individual component leakage may exceed the design value given in Table'4.5-1 provided that the total allowed system uncollected leakage is not exceeded.

B.

During power operation the requirements of specification 3.4.2-A may be modified to allow the following components to be inoperable.

If the components are not restored to meet the requirements of Specifi-cation 3.4.2-A within the time period specified below, the reactor l

l shall be placed in the hot shutdown condition. If the requirements of Specification'3.4.2-A are not satisfied within an additional 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months the reactor shall be placed in the cold shutdown condition using normal operating procedures.

Amendment No. 59, Unit 2 I

e T.S. 3.4.2-3 One Containment Spray Subsystem may be out of service, provided 1.

immediate attention is directed to making repairs and the sub-The

' system can be restored to operable status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

other Containment Spray Subsystem shall be tested as specified in Specification 4.5-A to demonstrate operability prior to 1

initiating repair of the inoperable system.

One outside Recirculation Spray Subsystem may be out of service 2.

provided immediate attention is directed to making repairs and the subsystem can be restored to operable status within 24 The other Recirculation Spray subsystems s' hall be tested hours.

as specified in Specification 4.5-A to demonstrate operability prior to initiating repair of the inoperable system.

One Inside Recircylation Spray Subsystem may be out service 3.

provided immediate attention is directed to making repairs and the subsystem can be restored to operable status within 72 hcurs.

The other Recirculation Spray subsystems shall be tested as specified in Specification 4.5-A to demonstrate operability prior to initiating repair of the inoperable subsystems.

4.

The total uncollected system leakage from valves, flanges, and pumps located outside containment can exceed the limit shown in Table 4.5-1 provided insediate attention is directed to making repairs and system leakage is returned to within limits within 7 days.

C.

Should the refueling water storage tank temperature fail to be maintained at or below 45'F, the containment pressure and tempera-ture shall be maintained in accordance with TS Fig. 3.8.2-1 to maintain the capability of the Spray System with the higher refueling water temperature. If the containment temperature and 3.8.2-1 pressure cannot be maintained within the limits of TS Fig.

the reactor shall be placed in the cold shutdown condition.

Amendment No. 59, Unit 2

,T.S. 3.4.2-4 i

T Basis l

The Spray Systems in each reactor unit consist of two separate parallel u

Containment Spray Subsystems, each of 100 percent capacity, and four i

separate parallel Recirculation Spray Subsystems, each of 50 percent I

capacity.

Each Containment Spray Subsystem draws water independently fr; the 398,000 gal. capacity refueling water storage tank. The water in the f

tank is cooled to 45 F or below by circulating the tank water through one p

of the two refueling water storage tank coolers through the use of one of I

I the two refueling water recirculating pumps. The water temperature is maintained by two mechanical refrigerating units required.

In each Containment Spray Subsystem, the water flows from the tank through an i

electric motor driven containment spray pump and is sprayed into the containment atmosphere through two separate sets of spray nozzles. The i

capacity of the Spray Systems to depressurize the containment in the event of a Design Basis Accident is a function of the pressure and temperature of the containment atmosphere, the service water temperature, and the I

l temperature in the refueling water storage tanks as discussed in Specifi-cation 3.8.2-B.

Each Recirculation Spray Subsystem draws water from the common containment In each subsystem the water flows through a recirculation spray pump pump.

and recirculation spray cooler, and is sprayed into the containment atmos-phere through a separate set of spray nozzles. Two of the recirculation spray pumps are located inside the containment and two outside the contain-i ment in the containment auxiliary structure.

Amendment No. 59, Unit 2 L

, T.S. 3.4. 2-5 With one Containment Spray Subsystem and two Recirculation Spray Sub-systems operating together, the Spray Systems are capable of cooling and depressurizing the containuent to subatmospheric pressure in less than 60 minutes following the Design Basis Accident. The Recirculation Spray Subsystems are capable of maintaining subatmospheric pressure in the con-tainment indefinitely following the Design Basis Accident when used in conjunction with the Containment Vacuum System to remove any long term air in leakage.

In addition to supplying water to the Containment Spray System, the refuel-ing water storage tank is also a source of water for safety injection following an accident. This watt. ts borated to a concentration which assures reactor shutdown by app oximately 10 percent ak/k when all control rod assemblies are inserted and when the reactor is cooled down for refueling.

References FSAR Section 4 Reactor Coolant System FSAR Section 6.3.1 Containment Spray Subsystem FSAR Section 6.3.1 Recirculation Spray Pumps and Coolers FSAR Section 6.3.1 Refueli..g Water Chemical Addition Tank FSAR Section 6.3.1 Refueling Water Storage Tank FSAR Section 14.5.2 Design Basis ~ Accident FSAR Section 14.5.5 Containment Transient Analysis Amendment No. 59, Unit 2 i

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,T.S. 3.6-3 450 psig, respectively, residual heat removal requirements are normally a

satisfied by steam bypass to the condenser.

If the condenser is unavail-F i

able, steam can be released to the atmosphere through the safety valves, E

power operated relief valves, or the 4 inch decay heat release line.

The capability to supply feedwater to the generators is normally provided by the operation of the Condensate and Feedwater Systems.

In the event of I

complete loss of electrical power to the station, residual heat removal would continue to be assured by the availability of either the steam driven auxiliary feedwater pump or one of the motor driven auxiliary feedwater pumps and the 110.000 gal lon condenmac stornne tank.

A minimum of 92,000 gallons of water in the 110,000 gallon condensate tank is sufficient for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of restdaal heat removal following a reactor trip and loss of all off-site electrical power.

If the protected condensate storage tank level is reduced to 60,000 gallons, the immediately available replenishment water in the 300,000 gallon condensate tank can be gravity-feed to the protected tank if required for residual heat removal. An alter-nate supply o[ f eedwater to the auxiliary feedwater pu..,' suction is also available from the Fire Protection System Main in the auxiliary feedwater pump cubicle.

The five main steam code safety valves associated with each steam generator have a total combined capacity of 3,725,575 pounds per hour at their individual set pressure; the total combined capacity of all fifteen main steam code safety valves is 11,176,725 pounds per hour.

The ultimate power rating steam flow is 11,167,923 pounds per hour. Trae j

combined capacity of the cafety valves required by Specification 3.6 always exceads the total steam flow corresponding to the maximum steady-state power than can be obtained during one, two or three reactor Amendment No. 59, Unit 2

,T.S. 3.8.2-1 3.8.2 CONTAINtiENT (UNIT 2)

Appl icabili_ty containment.

Applies to the integrity and operating pressure of the reacter t

i-Objective To define the limiting operating status of the reactor containment for unit operation.

Specification A.

Containment Integrity and Op_e_ rating Pressure 1.

The containment integrity, as defined in TS Section 1.0, shall not be violated, except as specified in A2, below, unless tiie reactor is in the cold shutdown condition.

2.

The reactor containment shall not be purged while the reactor is

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operating, except as stated in Specification A.3.

3.

During the plant startup, the remote manual valve on the steam jet air ejector suction line may be open, if under administrative control, while containment vacuum is being established.

The Reactor Coolant System temperature and pressure must not exceed 350 F and 450 psig, respectively, until the air partial pressure in the containment has been reduced to a value equal to, or below, that specified in TS Figure 3.8.2-1.

4.

The containment integrity shall not be violated when the reactor vessel head is unbolted unless a shutdown margin greater than 10 percent Ak/k is maintained.

5.

Positive reactivity changes shall not be made by coil drive raotion or boron dilution unless the containment integrity is intact.

Amendment No. 59, Ur it 2 l

,T.S. 3.8.2-2 B.

Internal Pressure 1.

If the internal air partial pressure rises to a point 0.25 psi w

ebcVe the maximum allowable set point value of the air partial pressure (TS Figure 3.8.2-1), the reactor shall be brought to l

the hot shutdown coniition.

2.

If the leakage cond. tion cannot be corrected without violating the containment integrity or if the internal partial pressure continues to rise, the reactor shall be brought to the cold shutdown condition utilizing normal operating procedures.

3.

If the internal pressure falls below 8.25 psia the reactor shall be placed in the cold shutdown condition.

4, The minimum allowable set point for the air partial pressure is 9.1 psia.

If the air partial pressure cannot be maintained greater than or equal to 9.0 psia, the reactor shall be brought to the hot shutd;wn condition.

Basis The Reactor Coolant System temperature and pressure being below 350 F and 450 psig, respectively, ensures that no significant amount of flashing steam will be formed and hence that there would be no significant pressure build-up in the containment if there is a loss-of-coolant accident.

The shutdown margins are selected based on the type of activities that are being carried out. The 10 percent ak/k shutdown margin during refueling precludes criticality under any circumstance, even though fuel and control rod assemblies are being moved.

Amendment No. 59, Unit 2

--, T.S. 3.8.2-3 i

i The maximum allowable set point for the containment air partial pressure is presented in Figure 3.8.2-1 for service water temperature from 25 to 90 F.

The allowable set point varies as shown in Figure 3.8.2-1 for a given containment average temperature. The RWST water shall have a maximum temperature of 45 F.

The horizontal limit lines in Figure-3.3.2-1 are based on LOCA peak calcu-f lated pressure criteria, and the sloped line is based on LOCA subatmospheric peak pressure criteria.

The curve shall be interpreted as follows:

The horizontal limit line designates the maximum air partial pressure set point for the given average containment temperature.

The horizontal limit line applies for service wat er temperatures from 25 F to the sloped line intersection value (maximum service water temperature).

t From Figure 3.8.2-1, if the containment average temperature is 112 E and the service water temperature is less than or equal to 83 F, the air partial pressure set point value shall be less than or equal to 9.65 psia.

If the average contair. ment temperature is 11PF and 'the service water temperature is less than or equal to 88 F, the air partial pressure set point value shall be less than or equal ro. 9.35 psia. These horizontal limit lines are a result of the higher allowable initial containment

.ivm a3r t empe rat ni e:. and t he analysi:, of t he pump r. net ion break.

ll Amendment No. 59, Unit 2 i

f l

l I

l T.S. 3.8.2-4 If the containment air partial pressure rises to a point C.25 psi above the maximum set point value, the reactor t.:ull be brought to the hot: r.huulcwn If a LOCA occurs at the time the containment air part ial pres-condition.

sure is 0.25 psi above the set poin,t value, the maximum containment pr. essure will be less than 45 psig, the containment will depressurize in less than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , and the maximun N.ubatmospheric peak pressure will be F

less than 0.0 psig.

The minimum allowable set point for the contal: ment air partial pressure is 9.1 psia.

If the containment air partial pressure cannot be maintained greater than or equal to 9.0 psia, the reactor shall be brought to the hot shutilown comlit ion.

The shel l : n.' dome plate liner o t he cont ainment are capable of withstanding an internal pressure as low as 3 psia, and the s

bottom mat liner is capable of withstanding an internal pressure as low as l

j

[

8 psia, 3eferences FSAR Section 4.3.2 Reactor Coolant Pump FSAR Section 5.2 Containment Iaolation FSAR Section 5.2.1 Design Bases FSAR Section 5.5.2 luolation Design Amendment No. 69, Unit 2

'T..S. Figure 3.8.2-1 MAXIMUM ALLOWABLE AIR PARTIAL PRESSURE SURRY PLWER STATION - UNIT NO. 2 s

t

+1c

-i i

t

.-e------

g._...

-10 t

.l l!

j

.i -

Q:_. M.ai" i

-i

'I / 710 F '

I'

.d

.I

.L.

- ~TC = 102

F '

i C

t I'

"l Tc - 1 o.1

F 730 F __S,

. 10. 2._

e

_21 j

i:

.9

. _. - Q~.

. -.50 F - g%,

g.g L

......[.

7 -

-i--

Tc - tco

r 6+

_ h _7 f-....'---..

.~.

4..

I l

_..,5_1_0. _.0_.

.t Tc - 1os

F 780 F a D,

e5

-w.

---.----.----rs---.-

p* ---.- -.._..

m

_.-a; g....,

1,

.,_...l.....

.p

=

810 F_ c _,

I

'l Tc. iso

F E_ 9 8_

i

.._3.-

[..;. _.t.

t s

i s.-

~

r

. _4 '

g.,_.

F 1

TC = 112

F 830F i

E 9.6 w-6

..._8_6.0 p..

.._.4.-_..4_+

Q r

Tc - 114

F

. 9.. _

o,

- ) __.. _k._. -... __ -. :.

..E_._9._4__

~1 i

Tc - 116

F ggog

.g__}

E

'1 l

i

i

__x<

.)r-- ' jJ '"fi H- -

j t

-F~

_. :F.__ _ _. -

! 9.2 i

7n Tc - t is

F

... 9.0 E._.

'j -

t.

s 92O l~.

5 I

TC = 120

F '

.i i.

i J.

l

' TC = 1208 F M AXIMUM 9.Q d5 45 55 65 75 85 95 I

25 h

SERVICE WATE R TEMPERATURE (8F)

Amendment No. 59, Unit 2 i

.m

e t

i FIGURE 3.8.2-1 (Continuedl

+'

if i

. FIGURE NOTATIGE t

- Setpoint value in containment vacuum system instrumentation.

TC - Containment average temperature.

i I~

FIGURE NOTES 4

I 1.

Maximum allowable operating air p artial pressure in the containment as a function of serv 'ce water temperature.

0 2.

Refueling Water Storage Tank temperature < 45 F.

l 3.

Horizontal lines designate maximum air partial pressure setpoint per given containment avern e temperature.

u 4

j' 4.

Each containment temperature line is a m.nimum for the given air partial pressure.

5.

Hot shutdown is required for containment air partial pressure setpoint increase greater than 0.25 psi or less than 9.0 psia.

6.

Cold shutdown 1,s required for containment air partial pressure less than 8.25 psia.

i i

l

)

Amendment No. 59, Unit 2 l

5 i

ihm 4

l l

TABl.E 4.1-1 (Continued)

Channel Check Calibrate Test Remarks Description 10.

Rod Position Bank Cot ?ters S (1,2)

N.A.

1) Each six inches of rod motion when data logger is our of service

2) With analog rod position 11.

Steam Cenerator Level S

R M

N.A.

R N.A.

12.

Charging Flow 13.

Pesidual Heat Removal Pump Flow N.A.

R' N.A.

D R

N.A.

14.

Boric Acid Tank Level u

15A. Unit 1 Refueling Water Storage W

R N.A.

Tank Level ISB. Unit 2 Refueling Water Storage Tank S

n M

Level W

N.A.

16.

Boron Injection Tank Level N.A.

R N.A.

17.

Volume Control Tank Level

D R

M (1)

1) Isolation Valve signal and 2I 18.

Reactor Containment Pressure-CLS spray signal N

19.

Process and Area Radiation Monitoring

{

D R

M Systems N.A.

R N.A.

20.

Boric Acid Control N.A.

R N.A.

yo 21.

Containment Pump Level c

S R

N.A.

S.

22.

Accumulator Level and Pressure ha i

23. Containment Pressure-Vacuum Pump S

R N.A.

System S

R H

24.

Steam Line Pres. r.

- ~.

i s

TABLE 4.5-1 t

RECIRCULATION SUBSYSTEM LEAKAGE

i Design Leakage to Uncollected Vent and

+

of Type of Leakage Control and Unit

Leakage, Drain System, No.

cc per br**

cc per hr item Units.

Leakage Rate 0

0 Recirculation spray.

2 No leak of spray water due to tandem seal arrangement i

pumps 40 drops per min per flange l

Flanges:

480 0

a.

pump 460 0

4 b.

Valves -

4 bonnet to body (larger than 2 in.)

~ Valves - Stem 4

Backscated, double packing with 0

16 leakoff - 4 cc per hr per in.1. tem leakoffs diameter 24 0

Flanges body, packed stem - 4 drop fliscellaneous 2

per min small valves F

964 16 Total a.

5 m

Po Mased on two subsystems in operation under DBA conditions.

Total Allowed System Uncollected Leakage is 964.cc/hr.

E ** Individual component uncollected leakage may exceed the design value provided that the total allowable sys k.m uncollected leakage is not exceeded.

E l

m l

l l

l i

.y....... g g. n.

.y

.. g 7.. g 11

TABLE 4.11-1 EXTERNAL RECIRCULATION LOOP LEAKAGE (Safety Injection System Only)

Design Design 1

Leakage to Leakage to No. of Type of Leakag-a Control and Unit Atmosphere Waste Disposal Items Units Leakage Rate cc per hr**

Tank, cc per ' t' n

Low Head Safety Injection 2

Mechanical Seal with leakoff -

0 24 Pumps 4 drop per min Safety Injection Charging 3

Mechanical Seal with leakoff -

0 36 4 drop per min Flanges:

a.

Pump 10 Gasket - adjusted to zero leakage 1,200 0

following any test - 40 drops per min, per flange 2,240 0

b.

Valves Bonnet to Body 54 (larger than 2 in.)

Valves - Stem Leakoffs 27 Backseated, double packing with 0

108 leakoff - 4 cc per hr per in stem diameter Misc. Valves 33 Flanges body packed stems - 4 drop per min 396 0

iiT e-Totals 3,836 168 G%

& Total Allowed System Uncollected Leakage is 3,836 cc/hr

~

$ ** Individual component uncollected leakage may exceed the design value provided that the total allowable system h

e-uncollected leakage is not exceeded.

0' c

1 N

+py" 7-

.

ML19331E106

Text

Attachment:

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