ML20066J778
| ML20066J778 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 01/29/1991 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20066J774 | List: |
| References | |
| NUDOCS 9102050095 | |
| Download: ML20066J778 (11) | |
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3 0f0 SED TECilNICAI, SPECIFICATION CilANGES i
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9102050095 910129 PDR ADOCK 05000' iL4 6
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'3.3 EHERGENCY CORE COOLING,-REACTOR BUILDING EMERGENCY COOLING AND REACTOR l
BUILDING SPRAY SYSTEMS ApplisAbJlity Appl.les to the emergency core cooling, reactor building emergency cooling and-l-
reactor building spray systems.
Objectivity To define the conditions necessary to assure immediate availability of the emergency core cooling, reactor building omergency cooling and reactor building l
= spray systems.
Entsification 3.3.1 The following equipment shall be operable whenever containment integrity is established as required by Specifitation 3.6.1:
(A) One reactor building spray pumn and its assu' aced spray nozzle-header.
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(B) One train of reactor building emergency cooling.
l (C). Two out of three service water pumps rhall be-operable, powered from Judependent essential busca, to provide redundant and independent flow paths.
-(D) Two engineered safety feature actuated low pressure injection pumps shall be operable.
(E) Both low pressure injection coolers and their cooling weter supplies shall be operable.
(F) Two BWST lovel instrument channols shall be operable.
(G) The-borated water storage tank shall contain a level of 40.2 i 1.8 ft. (387,400 t 17,300 gallons) of water having a concentration of 2470 1 200 ppm boron-at-a-temperature not less than 40F.
The manual valve on-- the discharge line from the borated water storage tank shall be locked open.
(H) The four reactor building omergency cump isolation valves to the LPI system shall be either manually or remote-manually-operable.
Amendment No. 2f,, 79, ///,140 36 I-1
g (1) The engineered safoty features valves associated with each of the above systems shall be operabic or locked in the ES positfor.
3.3.2 in additinn to 3.3.1 above, the following ECCS cquipment shall be opernbb./.wn the reactor coolant system is above 350T and irr**?la nd fuel is in the core:
(A) Two out of three high pressure injectio:., makeup) pumps shall be maintained operable, powered from independent essential buses, to provjde redundant and independent flow na 's.
3 (B) Engineered refety features valves associated with 3.3.2.a above shall be operabic or locked in the ES position.
3.3.3 In addition to 3.3.1 and 3.3.2 above, the following ECCS equipment shall be operable when the reactor coolant system is above 800 psig:
(A) The two core flooding tanks shall each contain an indicated minimum of 13 1 0.4 feet (1040 1 30 ft') of borated water at 600 1 2", poig.
(D) Core flooding tank boron concentration shall not be ions than 2270 ppm borot.
(C) The electrically operated discharge valves from the core flood tanks shall be open and breakers locked open and tagged.
(U) One of the two pressure instrument channels and one of the two level instrument channels per core flood tank shall be oparable.
3.3.4 The reactor shall not be made critical unicas the following equipment in addition to 3.3.1, 3.?.2, and 3.3.3 above is operabic.
(A) Two reactor building spray pumps and their associated spray I
nozzle henders and two trains of reactor building emergency cooling. The two reactor building spray pumps shall be powered frcm opereblo independent emareency buses and the two reactor building emergency cooling trains shall be powered from operable independent emergency buses.
(D) The sodium hydroxide tank shall contain an indicated
'O it,of1B[3 wt % solution sodium hydroxide 34 g
(19,500 lb. 1 2500 lb.).
(C) All manunt valves in the main discharge lines of the sodium hydroxide tanks shall be locked open, j
Amendment No. 16, 17, J11, 140 37
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(D) Engineered safety feature valves and interlocks associated with 3.3.1, 3.5.2, and 3.3.3 shall be operable or locked in the ES position.
3.3.5 Haintenance shnll be allowed during power oraration on any cornponent(s) in the high pressure injection, low pressure injection, service water, reactor building spray and reactor building emergency cooling l
e Amendment. No. 39 37a 1
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systems which will not remove more than one train of each system from service.
Maintenanco shall not be performed on components which would make the affected system train inoperable for moro a
l than 2A :onsecutive hours.
Prior to initiotIng maintenance on any component of a train in any system, the redundant componont of a
that system s.iall be demonstrated to be operabic within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />
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prior to the maintenance, i
3.3.6 If the conditions of Specifications 3.3.1, 3.3.2, 3.3.3, 3.3.4 and 3.3.5 cannot be mot except as noted in 3.3.7 below, reactor shutdown shall be initiated and the reactor shall be in hot shutdown condition within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />, and, if not corrected, in cold shutdown condit. ion within an additional 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
3.3.7 Txceptions to 3.3.6 shall be as follows:
( A) If the conditions of Specification 3.3.1(F) cannot be met, reactor operation in permissiblo only during the succeeding seven days unless such components are sooner made operable, provided that during such seven days the other BWST level j
instrument channel shall be operable.
1 (B) If the conditions of Specification 3.3.3(D) cannot be mot, reactor operation is permissible only during the succeeding seven days unless such components are sooner made operabic, provided (bat during such seven days the other CPT Instrument channel (prossure of Icvol) shall be operablo.
l (C) If t hn conditions-of Specification 3.3.4(A) cannot be mot becau'so one train of the required reactor building emergency 1
J coollag is inoperabic but both reactor building spray systems are opotable, restore the inoperable train of cooling to oporable status within 7 days or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdrwn within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
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f (D) If t he conditions of Specification 3.3.4( A) carnot be mot because two trains of the requf red reactor building emergency cooling are inoperable but both reactor building spray systems are operabic, restore at least one train of cooling to opernble status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />..Rostore both abovo required cooling trains to operabic st.atus within 7 days of initial loss or be in nt least. hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
' Amendment No. 62 38
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(!;) If the conditions of Specification 3.3.4(A) cannot be met because one train of the req 11 red reactor building caergency cooling is inoperabic and one reactor building spray system is inoperable, restore the inoperable spray system to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
Ret. tore the inoperable reactor building emergency cooling train to operable status within 7 days of initial loss or be in at least hot shutdown within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.
i EAAEA The requirements of Specification 3.3.1 assure that below 350'F, adequate long term core cooling is provided. Two low pressure injection pumpa are specified, llowever, only one is necessary to supply emergency coolant to the reactor in the event of a less-of-coolant accident.
The post-accident reactor building emergency cooling and long-term pressure reduction may be accomplished by two spray units or by a l
combination of one cooling train and one spray unit.
Post-accident fodine removal may be accomplished by one of the two spray system strings.
The specified requiremm.c assure that the required post-accident components are available for both reactor building emergency cooling and iodine removal.
Ersciffention 3.3.1 ashares that the required equipment is operable.
A train consists of two coolers and their associated fans which have sufficient capacity to meet post accident heat removal requirements.
Conservatively each reactor building emetgency cooling train cons 3sts of two fans powered from the same emergency bus and their associated coils, but other combinations may be justified by an engineering evaluation.
The borated water storage tank is used for three purposes:
(A) As a supply of borated water for accident conditions.
(B) As an alternate supply of borated water for reaching cold shutdown.(8)
(C) As a supply of borated water for flooding the fuel transfer canal during refueling operation.(8) l l
Amnndment No. 16, 62 38a
1 370,100 gallona of bornted water are supplied for emergency core cooling and reactor building spray in the event of a losa-of-coolant accident.
This nmount fulfills requirements for emergency core cooling.
Approximately 16,000 gallons of borated water are required to reach cold shutdown. The original nominal borated water storage tank capacity of 380,000 gnllonn is bnned on tofueling volume requirements, llcatern malntain the borated water supply at a temperature to prevent crystallir.ntion and local freer.ing of the boric acid.
The boron concentration in not at a value that will maintain the core at least 1 percent Ak/k subtritical at 70*F without any control rods in the core.
The concentration for 1% Ak/k subcritiCality is 1609 ppm boron in the core, while the minimum value specified in the borated water storap tank is 2270 ppm boron.
Specification 3.3.2 assures that above 350*F two high pressure injection pumps are also available to provide injection water as the energy of the reactor coolant system is incre sed.
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Specification 3.3.3 assures that above 800 psig both core flooding tanks are operational.
Since their design pressure is 600 1 25 psig, they are not brought into the operational state until 800 psig to prevent spurious injection of borated water.
Both core flooding tanks are specified as a single core flood tank has insufficient inventory to reflood the core.(2)
Specification 3.3.4 assures that prior to going critical the redundant train of reactor building emergency cooling and spray train are operable.
The spray system utilizes common suction lines with the low pressure injection system, if a single train of equipment is-removed from either system, the other train must be assured to be operable in each system.'
When the reactor is critical, maintenance is allowed per Specification 3.3.5.
Operability of the specified components shall be based on the results of testing as required by Technical Specification 4.5.
The M iatenance period of up to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> is acceotable if 3e operability of equipment redundant to that removed from service is demonstrated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to removal.
Exceptions to Specification 3.3.6 permit continued operation for seven days if one of two BWST level instrument channels is operable or if either the pressure or level instrument channel in the CFT instrument channel is operable.
In the event that the need for emergency core cooling should occur, functioning of one train (one high pressure injection pump, one low pressure injection pump, and both core flooding tanks) will protect the core and in the event of a main cooler" loop severance, limit the peak clad temperature to less than 2300aF and the metal-water reaction to that representing less than 1 percent of the clad.
The service water system consists of two independent but interconnected, full capacity, 100% redundant systems, to ensure continuous heat removal.(*)
One service water pump is required for normal operation.
The normal operating requirements are grecter than the emergency requirements following a loss-of-coolant acc dent.
Amendment No. 140 39
l BEEERENCES (1)
FSAR Section 14.2.5 (2)
FSAR, Section 3.2 (3)
FSAR, Section 9.5.2 (4)
FSAR, Section 9.3.1 (5)
FSAR, Section 6.3 t
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t Amendment No. 10 39a i
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e 4.5.2 Reactor Bu11 dine Coo 11pc Systems Apulitabillis Applies to testing of the reactor building omergency cooling systems.
l DhleAL1YA To verify that the reactor building omergency cooling systems aro l
Snen111cAthn 4.5.2.1 Syrirm Tests 4.5.2.1.1 Reactor Bu11 dine Sprav System (a) Onco cycry 18 monthn, a system test shall be conducted to demonstrato proper operation of the system.
A test signal will be applied to demonstrato actuation of the reactor building spray system (except for reactor building inlet valvos to prevent water entering nozzles).
(b) Station compressed air or smoke will be introduced into the spray headers to verify the availability of the headers and spray nozzlan at least every five years.
(c) The test will be considorod satisfactory if visual observation and control board Indication verifles that all components have responded to the actuat.lon signal properly.
4.5.2.1.2 Kgan. tor Bo11 dine Cooline System (a) At least. onco per 14 days, each reactor building omergency cooling train shall be tested to demonstrato proper operation of the system. The test shall bo performed in accordance with the proceduto summarized belowt (1) Verifying a service water flow rate of 2 1200 gpm to each train of the reactor building omergency cooling.
l (2) Addition of a blacide to tho service water during the sutvoillanco in 4.5.2.1.2.a.1 above, whenever service water temperature is betwoon 60F and 80F.
(b) At least once por 31 days, each reactor building omergency l
cooling train shall be tested to demonstrate proper operation of the system. The test shall bo performed in accordance with the proceduro summarized below:
(1) Starting (unless already operating) each operational cooling fan from the control room.
Amendment No. RE. ft, 132 95
(2) Verifying that each operational cooling fan operates for 1
at least 15 minutes.
1 (c) Once every 18 months, a system test shall be conducted to demonstrato proper operation of the system.
The test shn11 be performed in accordance with the proceduro summarir.ed below:
(1) A test signal will be applied to actuate the reactor building emergency cooling operation.
l (2) Verification of the enginctfed safety features function of the service water system which supplies the reactor building emergency coolers shall be endo to demonstrate l
operability of the coolors.
(3) The test will be considered satisfactory if control board indication verliics that c11 components have responded to the actuation signal properly.
4.5.2.2 Gamponent Tests 4.5.2.2.1 Eympa At interynis not to exceed 3 months the reactor building spray pumps shill be started and operated to verify proper operatton.
Acceptabic performance will be indicated if the pump starts, operates for-fif teen minutes, and the dischargo pressuro and flow are within 110% of a po ut on the pump head curve.
3 4.5.2.2.2 yalyns At intervals not to exceed three months each engineered safety fonturen valve in the reactor building spray and reactor building emergency cooling system and each engineered safety featurce valve associnted with reactor building emergency cooling in the service water system shall be testod to verify-that IL 1s operable.
IlAata' The renctor building emergency cooling system and reactor building spray l
system are redundant to each other in providing post-accident cooling of the reactor building atmosphero to prevent the building pressure f rom exccoding the design pressure.
As a result of this redundancy in cooling capability, the allowabin out of nervice timo requirements for the react.or l
building emergency cooling system have boon appropriately adjusted.
llowever, the allowabic out of service timo requirements for the reactor building spray system have boon maintained consistent with that assigned other Inoperabic cugincored safeguard equipment since the reactor building spray system also provides a mechanism for removing iodino from the reactor building atmosphere.
O Amendment No. 27, 62 96
a Addition of a blocide to service ent *r la performed during reactor buliding emergency cooler surveillance to prevent buildup of Asian clams in the coolers when service water is pumped through the cooling coils.
This Is per formed when service water tempernt.ure is between 600 and 80F since in this water tempetoture range Asinn clams can spawn and produco Inrva which could pass through service water system strainers.
The delivery capability of one reactor building spray pump at a timo can be tested by opening the valve in the line from the borated water storage tank, opening the corrnsponding valvo in the test line, and starting the corresponding pump.
Pump dischargo pressure and flow indication demonstrate performanco, Wit.h the pumps e, hut down and the borated water storage tank outlet closed, the renctor building spray Jnjection valves can each be opened and closed by onerntor action. With the reactor building spray inlet valves closed, low pressurs air or smoke can be blown through the test connections of the renctor building spray nozzles to demonstrate that the flow paths are open.
The equipment, piping, valves, and instrumentation of the reactor building emergency cooling system are arranged so that. they can be visually luspected. The cooling fans and coils and.Tsacciated piping are locat.ed outside the secondary concreto shield.
Personnel can enter the reactor building dur1ng power operations to inspect and maintain this equipment.
The service water piping an6 valves outsido the reactor building are inspectable at all times.
Operational tests and inspections will be performed prior to initini startup.
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Two service water pumps are normally operating.
At Icast once por month operation of one pump 18 shifted to the third pump, so testing will be unnecessary.
As the reactor building fans are normally operating, starting for testing is unnecessary for those veriflod to be operating.
Entcunc.D TSAR, Sect.lon 6 Amend nnt No.1E. f1,132 97
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