Text

Amends 143 & 140 to Licenses DPR-32 & DPR-37,respectively, Increasing Number of Auxiliary Feedwater Pumps Available for cross-connect to Opposite Unit to Two
	ML20058M475
Person / Time
Site:	Surry
Issue date:	08/02/1990
From:	Berkow H; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20058M479	List: ML20058M475; ML20058M487;
References
	NUDOCS 9008100145
	Download: ML20058M475 (17)
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VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-280 SURRY POWER STATION. UNIT NO. 1 AENOMENT TO FACILITY OPERATING LICENSE Amendment No.

143 License No. DPR-32 1.

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

A.

The application for amendment by Virginia Electric and Power Company (thelicensee)datedOctober 11, 1988, as superseded October 30, 1989, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations cet forth in 10 CFR Chapter I; B.

The facility will o)erate in conformity with the application, the provisions of tie Act, and the rules and regulations of the Comission; C.

Thereisreasonableassurance(1)thatthe4:tivitiesauthorized i

by this amendment can be conducted without endangering the health l

and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.8 of Facility Operating License No. OPR-32 is hereby amended to read as follows:

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. (B) Technical Specifications The Technical Specifications contained in Appendix A, as tvised through Amendment No. 143, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

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

FOR THE NUCLEAR REGU'.ATORY COMMISSION 9(

erbert N. Berkow, Director i

Project Directorate 11-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical' Specifications Date of Issuance: August 2, 1990 4

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i VIRGINIA ELECTRIC AND POWER COMPANY DOCKET NO. 50-281 SURRY POWER STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATI%, LICENSE Amendment No.140 License No. DPR-37 1.

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

A.

The application for amendment by Virginia Electric and T w er Company (the licensee) dated October 11, 1988, as superseded October 30 i

1989, complies with the standards and requirements of the Atomic Energy Act of.1954, as amended (the Act) and the Comission's rules and regulations set forth in 10 CFR Chapter It B.

The facslity will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; 0.

Thereisreasonableassurance(1)thattheactivitiesauthorized 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 Comission's regulations;-

D.

The issuance of this amendment will not be inimical to the comon defense and security or to the health and safety of the public; and l

l-E.

The issuance of this amendment is in accordance with 10 CFR Part i.

51 of the Comission's regulations and all applicable requirements p

have been satisfied.

2.

- Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 3.B of Facility Operating License No. DPR-37 is hereby amended to read as fd'"ws:

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(B) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.140, are hereoy i

incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

l 3.

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

FOR THE NUCLEAR REGULATORY COMMISSION Herbert N. Berkow, Director Project Directorate !!-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

-l Changes to the Technical Specifications Date of Issuance:' August 2, 1990 l

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e ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.

143 FACILITY OPERATING LICENSE N0. OPR-32 AMENDMENT N0.

140 FACILITY OPERATING LICENSE NO. DPR-37 DOCKET NOS. 50-280 AND 50-281 Revise Appendix A as follows:

Remove Pages Insert Pages TS 3.6-1 TS 3.6-1 TS 3.6-2 TS 3.6-2 TS 3.6-3 TS 3.6-3 TS 3.6-3a TS 3.6-4 TS 3.6-4 TS 3.9-1 TS 3.9-1 TS 3.9-2 TS 3.9-2 TS 3.16-1 TS 3.16-1 TS 3.16-2 TS 3.16-2 TS 3.16-3 TS 3.16-3 TS 3.16-5 TS 3.16-5 TS 3.16-6 TS 3.16-6 t

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TS 3.6L1 1

3.6 TURRINE CYCLE Aeolicability l

Applies to the operating status of the Main Steam and Auxiliary Feed Systems.

Objectives I

To define the conditions required in the Main Steam System and Auxiliary Feed System for protection of the steam generator and to assure the capability to remove residual heat from the core during a loss of station power /or accident situations.

Soecification I

1 A.

A unit's Reactor Coolant System temperature or pressure shall not exceed 350'F or 450 psig, respectively, or the reactor shall not be critical l

unless the five main steam line code safety valves associated with each steam generator in unisolated reactor coolant loops are operable.with lift settings as specified in Table 3.61 A and 3.61B.

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B.

To assure residual heat removal capabilities, the following conditions i

shall be met prior to the commencement of any unit operation that would establish reactor coolant system conditions of 350'F or 450 psig which l

would preclude operation of the Residual Heat Removal System.

1.

The following shall be operable:

a.

Two motor driven auxiliary feedwater pumps.

b.

Two of the three auxiliary feedwater pumps on the oppo?ite unit (automatic initiation instrumentation n?sd not be operable), capable of being used with the opening of the cross connect.

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Amendment Nos.

143 and 140 1

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2.

A minimum of 96.000 gallons of water shall be available in the tornado missile protected condensate storage tank to supply emergency water to the auxillary feedwater pump suctions. A minimum of 60,000 gallons of water shall be available in the tornado protected condensate storage tank of the opposite unit to supply emergency water to the auxiliary feedwater pump suction l

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of that unit.

3.

All main steam line code safety valves, associated with steam generators in unisolated reactor coolant loops, shall be operable with lift settings as specified in Table 3.61 A and 3.618.

J C.

Prior to reactor power exceeding 10%, the steam driven auxiliary feedwater pump shall be operable.

D.

System piping, valves, and control board indication required for operation of the components enumerated in Specifications 3.6.B.1, 3.6.B.2, 3c6.B.3, and 3.6.C shall be operable (automatic initiation i

instrumentation associated with the opposite unit's auxiliary feedwater pumps need not be operable).

E.

The lodine 131 activity in the secondary side of any steam generator,in an unisolated reactor coolant loop, shall not exceed 9 curies. Also, the specific activity of the secondary coolant system shall be s 0.10 pCl/cc DOSE EQUIVALENT l 131. If the specific activity of the secondary coolant system exceeds 0.10 pCl/cc DOSE EQUlVALENT l 131, the reactor shall be shut down and cooled to 500'F or less within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after deletion and in the cold shutdown condition within the following 30

hours, r

Amendment Nos. 143 and 140

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9i TS 3.6 3 -

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With one auxiliary feedwater pump inoperable, restore at least three auxiliary feedwater pumps (two motor driven feedwater pumps and one steam driven feedwater purp) to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in hot shutdown within the following 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

G.

The requirements of Specifications 3.6.B.1, 3.6.B.2 and 3.6.0 above l

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concerning the opposite unit's auxiliary feedwater pumpst associated piping, valves and control board indication; and, the protec.ted I

condensate storage tank may be modified to allow the following components to be inoperable, provided immediate attention is directed to,

making repairs.

1.

One train of the opposite unit's piping, valves, and control board indications or two of the opposite unit's auxiliary feedwater pumps may be inoperable for a period not to exceed 14 days.

2.

Both trains of the opposite unit's piping, valves, and control board indications; the opposite unit's protected condensato storage tank; the cross connect piping from the opposite unit; or three of the opposite unit's auxiliary feedwater pumps may be inoperable for a period not to exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

i if the above requirements are not met, be in at least hot shutdown within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in cold shutdown within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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t The requirements of Specification 3.6.8.2 above may be modified to allow utilization of protected condensate storage tank water with the L,

auxiliary steam generator feed pumps provided the water level. is maintained above 60,000 gallons, sufficient replenishment water is available in the 300,000 gallon condensate storage tank, and replenishment of the protected condensate storage tank is commenced within two hours after the cessation of protected condensate storage tank water consumption.

l Amendment Nos.143 and 140 L

TS 3.6 3a i

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'A reactor which has been shutdown from power requires removal of core residual heat. While reactor coolant temperatures or pressure is > 350'F or 450 psig, respectively, residual heat removal requirements are normally satisfied bi steam bypass to the condenser. If the condenser is unavailable, steam can be released to the atmosphere through the safety valves, power operated relief valves, or the 4 inch decay heat release line.

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Amendment Nos.133 and 140

i TS 3.6 4 i

The capability to supply feedwater to the generators is normally providad operation of the Condensate and Feedwater Systems, in the event of 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 j

110,000-i gallon condensate storage tank, in the event of a fire or high energy line break 4 which would render the aux'liary feedwater pumps inoperable on the affected unit, residual heat remove' would continue to be assured by the availability of either the steam driven auxillary feedwater pump or one of the motor driven auxillary feedwater pumps from the opposite unit. A minimum of two auxiliary feedwater pumps are required to be operable

on the opposite unit to ensure compilance with the design basis accident analysis assumptions, in that i

auxiliary feedwater can be delivered via the cross connect, even if a single active fallure results in the loss of one of the two pumps.

A minimum of 92,000 gallons of water in the 110,000 gallon condensate tank is -

sutficient for 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months of residual heat removal following a reactor trip and loss of all offsite electrical power, if the protected condensate storage tank levelis reduced to 60,000 gallons, the immediately available replenishment water in the 300,000 gallon condensate tank can be gravity fed to the protected tank if required for residual heat removal. An alternate supply of feedwater to the auxiliary feedwater pump suctions is also available from the Fire Protection Syste,n 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. The combined capacity of the safety valves required by Specification 3.6 always exceeds the total steam flow corresponding to the maximum steady state power than can be obtained during one, two, or three reactor coolant loop operation

The availability of the auxiliary feedwater pumps, the protected condensate storage tank, and the main steam line safety valves adequately assures that sufficient residual heat removal capability will be available when required.

excluding automatic initiation instrumentation l

Amendment Nos. I43 and-140

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TS 3.91 3.9 STATION SERVICE SYSTEMS AnnlicabHitv Applies to availability of electrical power for operation of station auxiliaries.

Obiective J

To define those conditions of electrical power availability necessary to provide for safe reactor operation.

Soncification A.

A unit's reactor shall not be made critical without:

1.

All three of the unit's 4.160V buses energized 2.

All six of the unit's 480V buses energized 3.

Both of the 125 V DC buses energized as explained in Section 3.16 4

One battery charger per battery operating as explained in Section 3.16 5.

Both of the 4,160V emergency buses energized as explained in Scotion 3,16 6.

All four of the 480V emergency buses energized as explained in l Section 3.16 l-I' Amendment Nos.143 and 140

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Two emergency diJsel generators operable as explained in Section 3.16.

B.

' A unit's reactor shall not be made critical without the requirements of Specification 3.9 A items 3,4,5,7, and 6 (for the 480V power supplies for the auxiliary fee'dwater cross connect valves) being rnet for tho opposite unit.

C.

The requirements of Specification 3.9 A above may be modified for two l reactor coolant loop operation to allow one of the unit's 4,160V normal buses and the two 480V normal buses feed frcm this 4,160V bus, to be unavailable or inoperable, D.

The requirements of Specifications 3.9 A items 3,4,5,6, and 7 may be modified as provided in Section 3.16 B.

i SA111 During startup of a unit, the station's 4,160V and 480V normal and emergency-buses are energized from the station's 34.5KV buses. At reactor power levels greater than 5 percent of rated power the 34.5KV buses are required to energize only the emergency buses because at this power level the station generator can supply sufficient power to the normal 4,160V and 480V lines to I

operate the unit.

t Three reactor coolant loop operation with all 4,160V and 480V buses energized i

is the normal mode of operation for a unit. Equipment redundancy and bus arrangements, however, allow safe unit startup and operation with one 4,160V l

normal bus and the two 480V normal buses feed from this 4,160V bus, unavailable or inoperable.

Emergency power supplies on the opposite unit are required to be operable to power the equipment necessary to supply auxiliary feedwater from one unit to another via the cross connect.

References

' FSAR Section 8.4 Station Service Systems FSAR Section 8.5 Emergency Power Systems Amendment Nos.143 and 140

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l-TS 3.161 3.16. EMERGENCY POWER SYSTEM Anoticability Applies to the avaliability of electrical power for safe operation of the station during an emergency.

Objective To define those_ conditions of electrical power availability necessary to shutdown the reactor safely, and provide for the continuing availability of.

Engineered Safeguards when normal power is not available.

Soecification l

A.

A reactor shall not be made critical nor shall a unit be operated such that the reactor coolant system pressure and temperature exceed 450 psig and 350'F, respectively, without:

1.

Two diesel generators (the unit diesel generator and the shared backup diesel generato') operable with each generator's day tank having at least 290 gallons of fuel and with a minimum on site supply of 35,000 gal ot fuel available, 2.

Two 4,160V emergency buses energized.

3.

Four 480V emergency buses energized.

Amendment Nos. 143 and 140 w

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TS 3.16 2 4.

Two physically independent circuits from the r,ffsite transmission network to energize the 4,160 and 480V eme/gency buses. One of these sources must be immediately available, i.e. primary -

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source; and the other must be capable of being made available within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ;i.e. dependable aNornate source.

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5.

Two operable flow paths for providing fuel to each diesel-generator.

I 6.

Two station batteries, two. chargers, and the DC distribution systems operable.

7.

Emergency diesel generator battery, charger and the DC contro I

circuitry operable for the Unit diesel generator and for the shared back up diesel generator.

8.

The requirements of Specifications A.1, A.2, A.5, A.6, A.7, and A.3 (for the 480V power suoply for the auxillary feedwater cross-connect valves) met for l'ie opposite unit. In addition, one of the two physically indepenr'en circuits from the offsite transmission network must energirs tN opposite unit's emergency buses.

B.

During power operation or the return to power from hot shutdown conditions, the requirements of specification 3.16 A may be modified by one of the following:

Either the unit's dedicated diesel generator or the shared backup 1.

diesel generator may be unavailable or inoperable provided the operability of the other diesel generator is demonstrated daily, if this diesel generator is not returned to an operable status within 7 days, the reactor shall be brought to a cold shutdown condition.

One diesel fuel oil flow path may be ' inoperable" for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided the other flow is proven operable, if after 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , the inoperable flow path cannot be returned to service, the diesel shall be considered " inoperable.'

When the emergency diesel generator battery, charger or DC control circuitry is inoperable, the diesel shall be considered ' inoperable."

Amendment Nos.143 and 140

TS 3.16 3 2.

If a primary source is not available, the unit may be operated for seven

(?) days provided the dependable alternate source can be operable within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . if specification A 4 is not satisfied within seven (7) days, 4

the unit shall be brought to the cold shutdown condition.

3.

One battery may be inoperable for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months provided the other battery and battery chargers remain operable with one battery charger carrying the DC load of the failed battery's supply system. If the battery is not

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returned to operable status within the 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period the reactor shall be l

placed in the hot shutdown condition, if the battery is not restored to 4

operable status 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.

4 A train of die opposite unit's emergency power system as required by Section 3.16.A.8 above may be inoperable for a period not to exceed 14 days. During this 14 day period, the following limitations apply:

a)

If the offsite power source becomes unable to energize the opposite unit's operable train, operation may continue provided its associated emergency diesel generator is energizing the operable train.

b)

If the opposite unit's operable train's emergency diesel generator becomes unavailable, operation may continue for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided the offsite power source is energizing the opposite unit's operable train, c)

Return of the originally inoperable train to operable status allows the second inoperable train to revert to the 14 day limitation.

if the above conditions are not met, the reactor shall be brought to hot j

shutdown conditions within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and cold shutdown condition within i

the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

C.

The continuous running electrical load supplied by an emergency diesel generator shall be limited to 2750 KW, flalldt The Emergency Power System is an on site, independent, automatically starting power source, it supplies power to vital unit auxiliaries if a normal power source is not available. The Emergency Power System consists of three L

diesel generators for two units. One generator is used exclusively for Unit 1, the second generator for Unit 2 and the third generator functions as a backup l

.for either Unit 1 or 2.

The diesel generators have a continuous 2,000 hour0 days 0 hours 0 weeks 0 months ating of 2750 KW and a two hour rating of 2850 KW. The actual loads using conservative Amendment Nos.

143 and 140 l

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TS 3.16 5

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The diesel generators function as an on site back up system to supply the emergency buses. Each emergency bus provides power to the following cperating Engineered Safeguards equipment:

1 A.

One containment spray pump B.

One charging pump 1

C.

One low head safety injection pump l

D.

One recirculation spray pump inside containment E.

One recirculation spray pump outside containment F.

One containment vacuum pump G.

One motor driven auxiliary steam generator feedwater pump I

H.

One motor control center for valves, instruments, control air compressor, l

fuel oil pumps, etc.

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Control area air conditioning equipment four air recirculating units, one l

l water chilling unit, one service water pump and one chilled water circulating pump J.

One charging pump service water pump for charging pump intermediate I

seal coolers and lube oil coolers K.

One charging pump cooling water pump for charging pump seal coolers, t

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Amendment Nos.143 and 140

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t The day tanks are filled by transferring fuel from any one of two buried tornado missile protected fusi oil storage tanks, each of 20,000 gal capacity. Two of 100' percent capacity fuel oil transfer pumps per diesel generator are powered from the emergency buses to assure that an operating diesel generator has a continuous supply of fuel.

The buried fuel oil storage tanks contain a seven (7) day supply of fuel,35,000 gal minimum, for the full load operation of one diesel generator;in addition, there is an above ground fuel oil storage tank on site with a capacity of 210,000 gal which is used for transferring fuel to the buried tanks.

If a loss of. normal power is not accompanied by a loss of coolant accident, the safeguards equipment will not be required.

Under this condition the following additional auxiliary equipment may be operated from each emergency bus:

A.

One component cooling pump B.

One residual heat removal pump C.

One motor driven auxiliary steam generator feedwater pump

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The emergency buses in each unit are capable of being interconnected under strict administrative procedures so that the equipment which would normally be operated by one of the diesols could be operated by the other diesel, if required.

The requirement for operability of the opposite unit's emergency power system is to ensure that auxiliary feedwater from the opposite unit can be supplied via the cross-connect in the event of a common mode failure of all auxiliary feedwater pumps in the affected unit due to a high energy line break in the main steam valve house. Without this requirement, a single failure (such as loss of the shared backup diesel generator) could result in loss of power to the opposite unit's emergency buses in the event of a L

loss of offsite power, thereby rendering the cross connect inoperable. The longer allowed outage time for the opposite unit's emergency power system is based on the i

low probability of a high energy line break in the main steam valve house coincident with a loss of offsite power, L

i Amendment Nos.143 and 140 1

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ML20058M475

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