ML20028G116

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Forwards Addl Info Re ex-vessel Storage Tank Cooling. Appropriate Info on Encl Charts Re Structural Temp Limitations,Decay Power Level & Alternate Heat Removal Paths Will Be Included in Section 9.1 of Future PSAR Amend
ML20028G116
Person / Time
Site: Clinch River
Issue date: 02/02/1983
From: Longenecker J
ENERGY, DEPT. OF, CLINCH RIVER BREEDER REACTOR PLANT
To: Grace J
Office of Nuclear Reactor Regulation
References
HQ:S:83:198, NUDOCS 8302070417
Download: ML20028G116 (11)
v • d • e


Text

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Department of Energy Washington. D.C. 20545 Docket No. 50-537 HQ:S:83:198 FEB 0 21983 Dr. J. Nelson Grace, Director l CRBR Program Office Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Dr. Grace:

CLINCH RIVER BREEDER REACTOR PLANT - EX-VESSEL STORAGE TANK (EVST) C0OLING Enclosed is additional infonnation regarding the EVST cooling capability.

Included are revisions to the Preliminary Safety Analysis Report (PSAR) table 6.1-1, section 9.1.3 and section 16.3.7.1 that will be part of a future PSAR amendment. The information in section 16.3.7.1 indicated as TBD (to be detennined) will be provided as part of the Final Safety Analysis Report.

Also enclosed are three charts containing additional information on EVST structural temperature limitations, decay power level, and alternate heat removal paths. As appropriate, the information in the charts will be included in section 9.1 of the PSAR in a future amendment.

Sincerely, b .

Jdfin R. Longeneckp Acting Director, Office of Breeder Demonstration Projects Office of Nuclear Energy Enclosure cc: Service List l Standard Distribution Licensing Distribution i

8302070417 830202 PDR ADOCK 05000537 A PDR

e ENCLOSURE e

TABLE 6.1-1 r

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l_IST OF ENGINEERFD SAFETY FEATURES IN CRBRP Eno i nee red Safety Features PSAR Section Reactor Conf inement/Contelnment 6.2 Reactor Containment isolation System 6.2.4 & 7.3.1 RCB Annulus Filtration System 6.2.5 Reactor Service Butiding Filtration System 6.2.6

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' Steam Generator Building 6.2.7, 7.4.1, l  !, Aerosol Release Mitigation System 9.13.2, 9.6 l

I f Habitability Systems 6.3 l

Reactor Guard Vessel 5.2 Guard Vessels of PHTS Major Components 5.3 Residual Heat Remeval System 5.6, 7.4.1 & 7.6.3 Celi Liner System 6.4, 3.8-B, a 3A.8 Catch Pan & Fire Suppression Deck System 6.5, 3.8-C, 3 A.9, 9.13.2 Ex-hsral Jh-a1e

  • Ta.,k G ue- d U x e l f./. a-fy. Veste i 3%c Ton K dodo S&cn Dcn(,ees 7,7 , 3 l

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' Amend. 64 6.1-2 Jan. 1982

The system provides the capability to maintain the oxygen content of the sodium in the EVST at, or below, 5 ppm. The cold trap used for this

( '44 service is separate from those used for reactor and primary loop sodium purification.

The system, working in conjunction with the Primary Sodium Storage and Processing System described in Section 9.3-2, provides a means of remov-44 ing reactor decay heat in the event of loss of normal heat removal paths.

These two systems, operating together, provide the Direct Heat Removal Service (DHRS). The DHRS is sized to limit the average bulk primary sodium temperature to approximately 11400F when the DHRS is initiated one-

. half hour af ter reactor shutdown. Under this condition, all primary pump pony motors are assumed operational. When the DHRS is initiated twenty-four hours af ter shutdown, the average bulk primary sodium temperature is main-tained below 9000F, assuming operation of a single primary pump pony motor.

59I Total heat rejection capability of the EVS Sodium Processing System is based on removal of the required reactor decay heat in addition to the heat generated by spent fuel within the EVST. The maximum simultaneous EVST and reactor decay

, heat load is approximately 11-1/2 MW, with DHRS initiated one-half hour after 26i reactor shutdown.

9.1.3.1.2 Design Description

, The EVST design and operating decay heat loads and sodium coolant outlet temperatures are given in Table 9.1-1.

The major assemblies of the EVST important to decay heat removal, other than the cooling ~ system itself, are the storage vessel, the guard 44 tank and'the internals. The internals, specifically the turntable, separate and support the spent fuel assemblies (contained in sodium-filled CCP's) permitting them to be satisfactorily cooled. The structural design of the 44 I turntable has already been discussed in 9.1.2.1.

59l The storage vessel has been classified as Safety Class 2 and is be designed, fabricated and inspected in conformance with the appropriate codes and standards (see Section 3.2) to provide a leak-proof containment for the sodium coolant. The sodium level is maintained at a high enough elevation so that normal fluctuations due to changes in temperature or number of stored componentLdo not uncover the too of the CCP's in which the_ spent fuel is stored. \During off-normal conditions, spch as a leak D

[ rupture in either the vessel or the cooling system', the vessel sodium out .

side .the CCP's cannot fall below the minimum safe' level./ This level is i defiried as that below which fuel cladding temperatures would exceed the \

44 l li its specified in Table 9.1-2 for the fuel assembly Itored at.'the highest '

sible location within t_he, storage vessel.! The~so'diIm nozzles in the4ei- '

/e locat'ed in the upper elevations of th'e vessejf wall (s

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The EYST sodium inl,et lines containtf antisy9 on devi/es whichpe prevent a Figure'9 44 cooling sy' stem leak from lowering 'the vessel sodium below the minimum

_ safe level .

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[ b N k[ 9. l. 3. l .1 Amend. 59 9.1 Dec. 1980

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INSERT 9.1.3.1.2 This level also prevents the loss of any of the EYST cooling systems 1

should a leak occur from the vessel which floods the EVST guard tank.

Should a leak occur in any of the EVST cooling systems, the resulting loss of sodium and EVST level drop will not result in disabling the other functional cooling circuits. During such leak events, the resulting sodium level outside the CCP's is in excess of that required to remove heat from the stored fuel assembly, at its highest possible location within the storage vessel, and to keep the fuel cladding temperatu're below the limits specified in Table 9.1-2.

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Th.e EVS Processing System consists of two normal independent forced convection cooling circuits, designated circuit Nos. I and 2, each 44 of which can remove the required EVST heat loads. f

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Ouring normal operation, one normal circuit is used for EVST cooling and the other is on standby. Each of the circuits is composed of two loops, one a sodium loop and the other a NaK loop. The sodium loop circulates sodium from the EVST through a sodium-to-NaK heat exchanger and back to the EVST. The NaK loop circulates NaK through the exchanger where it picks up EVST heat, to a forced-draft airblast heat exchanger, for dissipation of heat to the atmos-phere, and back to the sodium-to-NaK heat exchanger. The system also includes a cold trap to provide purification of the EVST sodium, in addition, the EVS Processing System consists of a third inde-pendent natural convection backup cooling circuit designated No. 3 which can also remove the required EVST heat loads. In the extremely unlikely event of loss of both' normal cooling circuits, the backup natural convection cooling circuit is used to remove the required EVST heat loads. Sodium circulates from the EVST through a backup sodium-to-NaK heat exchanger and back to the EVST.

The NaK loop circulates NaK through the exchanger where it picks up EVST heat, to a natural-draf t heat exchanger, for dissipation of heat to the

->lNM 2T katmosphere, and back to the sodium-to-NaK heat exchanger.

The EVST sodium outlet dowrcomers within the EVST terminate at different elevations above the stored fuel. Loop #2 (forced circulation) has two outlets; the highest outlet used for normal operation, and a second outlet at a lower elevation such tnat any sodium leakage from Loop #1 (forced circulation) will not uncover th Loop #2 outlet. Loop al has one outlet nozzle located at an elevation between the Loop #2 nozzles. The lower Loop #2 nozzle would be used only in off-normal conditions when both Loop #1 and the higher Loop #2 flow paths will not function. The third (backup) cooling circuit (Locp #3) has one outlet located below all Loop *1 and Loop 42 nozzles such that the Loop #3 outlet will not be uncovered by a leak in either Loop #1 or Loop #2. A leak in the Loop P3 piping will not uncover any of the loop outlets because it is entirely elevated abane the-minimum.-safe l e ;c! ' '.he EVM. ABom m3 Mr Mot.c.to

-- o ? s e 2 44 components:

The entire EVS prccessing system includes the following EVST Sodium Pumps (2)

EVST Sodium Coolers (2) i 44 I EVST Backup Sodium Cooler 't) s EVST NaK Pumps (2)

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Amend. 44 9.1-22 A ril 1973 i I

INSERT A - Page 9.1-22 The sodium nozzles in the. vessel are all located in the upper elevation of the EVST vessel wall (see Figure 9.1-6). The cooling circuit inlet lines contain anti-siphon devices which would prevent a cooling system leak from lowering the EVST sodium level and disabling the other func-tional cooling circuits. The anti-siphon device is cleaned semi-annually, and it will be periodically functionally tested.

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(l. -l/.~ The EVST shall have at least two heat removal systems operable.

Each of the two systems shall be capable of handling the maxi-mum design heat load of 1800 kW. Prior to scheduled inspection or routine maintenance of any heat removal system the two re-( maining heat removal systems shall be in an operable condition.

If during the inspection or maintenance period one of the two remaining heat removal systems fails, the heat removal system undergoing scheduled inspection or routine maintenance shall ..

be returned to service within the time which would be required for 59 the EVST sodium to reach 775 F with no cooling. j 44l df. The two forced convection, normal, independent EVST sodium cooling loops shall not be operated simultaneously, except when switching trains. When the loop is in operation, the 20 ther loop shall be kept on standby with its outlet valve closed.

44 e f.- Except when required for EVST cooling, the isolation valve in the lower EVST outlet line of loop 2 shall be locked closed.

Q. Before an inerted cell containing one of the EVST sodium cooling loops is to be exposed to the RSB atmosphere, the enclosed sodium cooling loop shall be isolated from the EVST and, if the sodium radioactivity concentration exceeds g g TBDu Ci/CC, the loop will be drained.

"TB O ,

59l j4q Coolant

'M levels

-iau, in the EVST shall not be less than n _ -

v. m i v.va uiu.

uiu m . ..

20l a'* %s.

If any of the above limiting conditions are not met, corrective action must be initiated to resolve the deficiency.

16.3.7.1.4 Bases The first specifications in Section 16.3.7.1.3 ensure equipment 44 redundancy for cooling spent fuel so that a single failure or an initiating event following a single failure cannot cause overheating of fuel.

Specification .

is required on the basis that a potential sodium spill in the EVST sodium cooling loop cell might result in radioactivity release with a site boundary dose exceeding one tenth of the 10CFR100 limits.

Specification

~rt..? E uw ww. vev.a. se.num ,w ensures that Aconlut- levelt ede""^ to, ma i n ta i n 0 d *

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_Aeven in the event of tak ruptureg ' '-- ~

te ' " m rd

$ re. a W u.* gfOOG I N L.s? 6-s MC. L I'd OM o f T m n r.c 5 AG by%scFsII$ ~

Amend. 59 16.3-15 Dec. 1980 L

INSERT B - Page 16.3-15 All three (3) EVST heat removal systems shall be operable (capable of removing up to TBD power) at the beginning of a refueling which will iricrease the decay power in the EVST to TBD. If one of the heat removal systems becomes inoperative during refueling, operations will be suspended if the power level exceeds TBD or the inoperative cooling system is not restored in TBD hours.

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STRUCTURAL TEMPEPATURE LIMITATIONS o THE EVST CAN WITHSTAND AT LEAST 1500 0F WITH A CREEP DEFORMATION STRAIN MARGIN OF

>1 S CONSIDERING DEAD WEIGHT LOADS ONLY [NOT INCLUDING SEISMIC OR ADDITIONAL 7 .L TRANSIENTS]

o LOCAL HOT SPOTS OF 6500F IN THE EVST CONCRETE SUPPORT LEDGE ARE ACCEPTABLE FOR SHORT PERIODS OF TIME

- AT EVST'Na TEMPERATURES OF 15000F OR GREATER, LOCAL HOT SPOT l

TEMPERATURE WILL BE LIMITED TO LESS THAN 6500F WITH CELL COOLING l

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- AT EVST Na TEMPERATURES UP TO 12000F, LOCAL HOT SPOT TEMPERATURES i 1

WILL BE LIMITED TO LESS THAN 6500F EVEN WITHOUT CELL COOLING l

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EVS PROCESSING SYSTEM 0FF NORMAL ALTERNATE HEAT REMOVAL PATHS

1. S0DIUM FROM ONE NORMAL LOOP CAN BE DIRECTED THRU THE C.T.

CIRCUIT, TO THE SUCTION SIDE OF THE PUMP IN THE OTHER NORMAL SODluf1 LOOP.

2. IT IS POSSIBLE T0 flAINTAIN EVST NA TEMP ( llD0*F WITH NATURAL CONVECTION ABHX AIRFLOW WITH AN 1800 KW POWER LEVEL IN THE EVST AND NORMAL SODIUM AND NAK LOOP FORCED CIRCULATION.
3. EVST HEAT CAN BE TRANSFERRED THRU THE 0HX TO THE REACTOR USli;G THE DHRS CROSS 0VER NAK CIRCUIT. THE REACTOR IS BROUGHT TO 400-600*F, AND USED AS A HEAT SINK. PRIMARY SODIUM FROM THE MAKEUP PUMPS IS DIVERTED THROUGH THE OllX.
4. NAK FROM ONE NORMAL LOOP CAN BE PUMPED THRU THE UPERATING ABHX OF THE OTHER NORMAL LOOP THRU THE DHRS CROSS 0VER NAK CIRCUIT.

HIGH OHX HYDRAULIC RESISTANCE PROVIDES CORRECT FLOW PATH. NAK FLOW IS IN Tile REVERSE DIRECTION THRU THE OPERATING ABHX. S. SODIUM FROM ONE NORMAL OR BACKUP LOOP CAN BE DIRECTED THRU THE SODIUM DRAIN CIRCulT TO THE SUCTION OF THE OPERATING PUMP IN Tile OTHER NORMAL LOOP.}}

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