ML20137G208

Proposed Tech Specs,Increasing SFP Storage Capacity & Increasing Maximum Fuel Enrichment from 4.9 W/O to 5.0 W/O U-235

ML20137G208
Person / Time
Site:	Waterford
Issue date:	03/27/1997
From:	ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20007F796	List: ML20137G202 ML20137G208 ML20137G214
References
NUDOCS 9704010351
Download: ML20137G208 (14)

Text

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NPF-38-193 Attachment I i

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l Existing Technical Specifications J

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l' 9704010351 970327 PDR ADOCK 05000382 P PDR

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i REFUELING OPERATIONS-i 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING l LIMITING CONDITION FOR OPERATION

) 3.9.7 Cranes in the fuel handling building shall be restricted as follows:

o a.

l The spent fuel handling machine shall be used* for the movement of I fuel assemblies (with or without CEAs) and shall be OPERA 8LE with:

1. A minimum hoist capacity of 1800 pounds, and l 2.

An and, overload cutoff limit' of less than or equal to 1900 pounds,

b. Loads in excess of 2000 pounds shall be prohibited from travel over

fuel assemblies in the spent fuel pool.

i APPLICABILITY:

l During movement of fuel assemblies in the fuel handling building, or with fuel assemblies in the spent fuel pool. i ACTION:

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' a. With the spent fuel handling machine inoperable, suspend the use of the spent fuel handling machine for movement of fuel assemblies and l

- place the crane load in a safe position.

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! b. With loads in excess of 2000 pounds over fuel assemblies in the q

1 spent fuel pool, place the crane load in a safe position.

j c. The provisions of Specification 3.0.4 are not applicable.

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! SURVEILLANCE REQUIREMENTS 1

I 4.9.7.1 The spent fuel handling machine shall be demonstrated OPERA 8LE within i

j 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of fuel assembly movement and at least once per 7 days thereafter by performing a load test of at least 1800 pounds and demon-t strating the automatic load cutoff when the hoist load exceeds 1900 pounds, j 4.9.7.2 The electrical interlock system which prevents crane main hook travel over fuel assemblies in the spent fuel pool shall be demonstrated OPERA 8LE j' within 7 days prior to crane use and at least once per 7 days thereafter j during crane eneration. i 4

4.9.7.3 Administrative controls which prevent crane auxiliary hook travel 3

with loads in excess of 2000 pounds over the fuel assemblies in the spent

fuel pool shall be enforced during crane operations.

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f *Not required for movement of new fuel assemblies outside the spent fuel pool.

j WATERFORD - UNIT 3 3/4 9-7 Amendment No. 6

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! REFUELING OPERATIONS l

BASES i

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3/4.9.6 REFUELING MACHINE l The OPERA 8ILITY requirements for the refueling machine ensure i that: (1) the refueling machine will be used for movement of CEAs and fuel

assemblies, (2) each hoist has sufficient load, capacity to lift a CEA or fuel-assembly, and (3) the core internals and pressure vessel are protected from l excessive lifting force in the event they are inadvertently engaged during

lifting operations.

l 3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING l -

The restriction on movement of loads in excess of the nominal weight of a i fuel assembly, CEA, and associated handling tool over other fuel. assemblies in i

the spent fuel pool ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuel in the storage racks will not result in a critical array. This assumption is consistent with the activity release assumed in the safety analyses.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION l i

The requirement that at least one shutdown cooling train be in operation l ensures that (1) sufficient cooling capacity is available to remove decay heat l and maintain the water in the reactor pressure vessel below 140*F as required l during the REFUELING M00E, and (2) sufficient coolant circulation is main- l tained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification. -

The requirement to have two shutdown cooling trains OPERABLE when there is i less than 23 feet of water above the reactor pressure vessel flange, ensures  ;

that a single failure of the operating shutdown cooling train will not result in a complete loss of decay heat removal capability. When there is no irradiated fuel in the reactor pressure vessel, this is not a consideration and only one shutdown cooling train is required to be OPERA 8LE. With the reactor vessel head removed and 23 feet of water above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency procedures to cool the core.

3/4.9.9 CONTAI! MENT PURGE VALVE ISOLATION SYSTEM The OPERASILITY cf this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY of this system is required to restrict the release of radioactive material from the containment atmosphere to the environment.

WATERFORD - UNIT 3 8 3/4 9-2

DrsicN FEATURES 5.3 REACTOR CORF j

j Furl AsEEMatItc 5.3.1 j assembly containing a maximum of 236 fuel rods clad w Each fuel i total weight of 1830 grams uranium. rod shall have a nominal active fuel l

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i maximum enrichment of 2.91 weight percent U-235.The initial core loading (sha in physical design to the initial core loading. Assemblies shall be similar j

maximum enrichment of 4.9 weight percent U-235 provided they contain suffic shall have a

fixed poisons to meet the final storage requirements described in Section 5.6.

j CONTROL ELEMENT ASSEMBLIES i 5.3.2 j control element assemblies.The reactor core shall contain 83 full-length and 8 pa 4

1 5.4 REACTOR COOLANT SYSTEM 1

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, DE11GN PRESSURE AND TEMPERATURE l 5.4.1 The Reacter Coolant System is designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable Surveillance Requirements,

b. For a pressure of 2500 psia, and c.

For a temperature which is 700*F. of 650'F, except for the pressurizer and surge line I IEEE l i

5.4.2 The total water and steam volume of the reactor coolant system is 11,800 400. -0 cubic feet at a nominal T, of 582.I'F. t 5.5 NETEnansnaltAL ToWEtt tneaffGN 5.5.1 on The primary Figure 5.1-1. and backup meteorological towers shall be located as shown i

WATERFORD - UNIT 3 5-5 AME W WIT No. h44, loa

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__Dt31GN FEATURES t ~~

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_CRfTitaLTTV i 5.6.1 i

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The spent fuel storage racks are designed andwith: shall

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A k,99 equivalent unberated water te less than er equal to 0.95 whe uncertainties. , which includes a tenservative allowance for i k

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l i A nominal essemblies 10.38 placed inchfuel in the spent center-to-center storage racks, distanc l 5.5.2 The k,,,

for new fuel for the first' core leading stored drye in th  !

spent is assumed. fuel storage racks shall not exceed 0.94 when aqueei i MAINAGE -

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5. 5. 3 1

A inadvertent draining of the peel below elevation 4

' CAPACITY -

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l storage capacity 11alled to no aere than 1088 f 1.7 COMPONfMT CYCLIC 02 TRANSIENT LIMITS j

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aaintained within the cyclic or transtant limita of \

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1RTERFORD - ISf!T 3 5-5 AME N 2 7' ""

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i NPF-38-193 i

Attachment il 1 I

Proposed Technical Specifications 1

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REFUELING OPERATIONS  ;

3/4.9.7 CRANE TRAVEL- FUEL HANDLING BUILDING i

LIMITING CONDITION FOR OPERATION '

3.9.7 Cranes in the fuel handling building shall be restricted as follows:

a. The spent fuel handling machine shall be used* for the movement of fuel assemblies (with or l without CEAs) and shall be OPERABLE with: l

1. A minimum hoist capacity of 1800 pounds, and

2. An overload cutoff limit of less than or equal to 1900 pounds, and,

b. Loads in excess of 2000 pounds shall be prohibited from travel over irradiated fuel assemblies in the Fuel Handling Building. Spe^* 're! pre!.

APPLICABILITY: During movement of irradiated fuel assemblies in the fuel handling building, or with  ;

irradiated fuel assemblies in the Fuel Handling Building.rpe-' 're' per' ACTION:

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a. With the spent fuel handling machine inoperable, suspend the use of the spent fuel handling i machine for movement of fuel assemblies and place the crane load in a safe position.  !

b. With loads in excess of 2000 pounds over irradiated fuel assemblies in the Fuel Handling Building, rpe-* 're' per', place the crane load in a safe position.

c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.7.1 The spent fuel handling machine shall be demonstrated OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> prior to the start of fuel assembly movement and at least once per 7 days thereafter by performing a load test of at least 1800 pounds and demonstrating the automatic load cutoff when the hoist load exceeds 1900 pounds.

4.9.7.2 The electrical interlock system which prevents crane main hook travel over irradiated fuel assemblies in the Fuel Handling Building rpe-* 'ue! ^^e'_shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereafter during crane operation.

I 4.9.7,3 Adrninistrative controls which prevent crane auxiliary hook travel with loads in excess of 2000 pounds over the irradiated fuel assemblies in the Fuel Handling Building rpe-' 'ue' pre! shall be enforced l during crane operations.

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• Not required for movement of new fuel assemblies outside the spent fuel pool and Cask Storage Pat. l WATERFORD - UNIT 3 3/4 9-7 AMENDMENT NO. 6 l- _ . _ . .

REFUELING OPERATIONS _

BASES 3/4 9.6 REFUELING MACHINE The OPERABILITY requirements for the refueling machine ensure that: (1) the refueling machine will be used for movement of CEAs and fuel assemblies, (2) each hoist has sufficient load capacity to lift a CEA or fuel assembly, and (3) the core internals and pressure vessel are protected from excessive lifting force in the event they are inadvertently engaged during lifting operations.

3/4.9.7 CRANE TRAVEL - FUEL HANDLING BUILDING The restriction on movement of loads in excess of the nominal weight of a fuel assembly, CEA, and associated handling tool over other irradiated fuel assemblies in the Fuel Handling Building sese E' pee' ensures that in the event this load is dropped (1) the activity release will be limited to that contained in a single fuel assembly, and (2) any possible distortion of fuelin the storage racks will not e result in a cntical array. This assumption is consistent with the activity release assumed in the safety analyses.

3/4.9.8 SHUTDOWN COOLING AND COOLANT CIRCULATION The requirement that at least one shutdown cooling train be in operation ensures that (1) suffbient cooling capacity is available to remove decay heat and maintain the water in the reactor pressure vessel below 140F as required dunng the REFUELING MODE, and (2) sufficient coolant circulation is maintained through the reactor core to minimize the effects of a boron dilution incident and prevent boron stratification.

The requirement to have two shutdown cooling trains OPERABLE when there is less than 23 feet of water above the reactor pressure vessel flange; ensures that a single failure of the operating shutdown cooling trail will not result in a complete loss of decay heat removal capability. When there is o

no irradiated fuel in the reactor pressure vessel, this is not a consideration and only one shutdown {

cooling train is required to be OPERABLE. With the reactor vessel head removed and 23 feet of water l above the reactor pressure vessel flange, a large heat sink is available for core cooling, thus in the event of a failure of the operating shutdown cooling train, adequate time is provided to initiate emergency t

procedures to cool the core.

3/4 9.9 CONTAINMENT PURGE VALVE ISOLATION SYSTEM The OPERABlLITY of this system ensures that the containment purge valves will be automatically isolated upon detection of high radiation levels within the containment. The OPERABILITY j 1

of this system is required to restrict the release of radioactive matenal from the containment atmosphere to the environment.

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f3 WATERFORD - UNIT 3 8 3/4 5 '

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DESIGN FEATURES ,

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l 5.3 REACTOR CORE FUEL ASSEMBLIES i

' 5.3.1 The reactor core shall contain 217 fuel assemblies wi'h each fuel assembly containing a maximum  !

of 236 fuel rods clad with Zircaloy-4. Each fuel rod shall have a nominal active fuel length of 150 inches j

! and contain a nominal total weight of 1830 grams uranium. The initial core loading shall have a i l maximum enrichment of 2.91 weight percent U-235. Reload fuel shall be similar in physical design to the l l initial core loading. Assemblies shall have a maximum enrichment of 5.0 44 weight percent U-235 p'ry;ded "'ey re-te re"de=ed pc42as.40 and meet the final storage requirements described in  !

l Section 5.6. .

CONTROL ELEMENT ASSEMBLIES  :

i j 5.3.2 The reactor core shall contain 83 full-length and 8 part-length control element assemblies. ,

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5.4 REACTOR COOLANT SYSTEM  !

DES:GN PRESSURE AND TEMPERATURE  !

i 5.4.1 The Reactor Coolant System is designed and shall be maintained: f;

! a. In accordance with the code requirements specified in Section 5.2 of the FSMR with  !

allowance for normal degradation pursuant of the applicable Surveillance Recoirements, l

b. For a pressure of 2500 psia, and f I

c. For a temperature of 650 F, except for the pressurizer and surge hne which is 700 F. l VOLUME ,

5.4.2 The total water and steam volume of the reactor coolant system is 11,800 +600, -0 cubic feet at a $

nominalT,g of 582.1*F.  ;

5.5 METEOROLOGICAL TOWERS LOCATION i i

5.5.1 The primary and backup meteorological towers shall be located as shown on Figure 5.1-1. j k

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l WATERFORD - UNIT 3 5-5 AMENDMENT NO. 408 l

DESIGN FEATURES 5.6 FUEL STORAGE C_RITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

a. A normal,, keff =""d"!40 of less than or equal to 0.95 when flooded with unborated l

water, which includes a conservative allowance for uncertainties. l i

b. A nominal 10.185 38 inch center-to-center distance between fuel assemblies placed in Region 1 (cask storage pit) me spent fuel storage racks.

c. A nominal 8.692 inch center to center distance between fuel assemblies ia the Region l 2 (spent fuel pool and refueling canal) racks, except for the four southem-most racks in the spent fuel pool which have an increased N-S center-to-center nominal distance of 8.892 inches.

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d. New or partially spent fuel assemblies may be allowed unrestricted storage in Region  !

1 racks. l I

e. New fuel assemblies may be stored in the Region 2 racks provided that they are )

stored in a " checkerboard pattern" as illustrated in Figure 5.6-1. l l

f. Partially spent fuel assemblies with a discharge burnup in the " acceptable range" of i Figure 5.6-2 may be allowed unrestricted storage in the Region 2 racks.

g. Partially spent fuel assemblies with a discharge bumup in the " unacceptable range" of Figure 5.6-2 may be stored in the Region 2 racks provided that they are stored in a

" checkerboard pattern", as illustrated in Figure 5.6-1, with spent fuel in the " acceptable range" of Figure 5.6-3.

5.6.2 The k., for new fuel for the first core loading stored dry in the spent fuel storage racks shall not exceed 0.98 when aqueous foam moderation is assumed.

DRAINAGE 5.6.3 The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation +40.0 MSL. When fuelis being stored in the cask storage pit and/or the refueling canal, these areas will also be maintained at +40.0 MSL.

CAPACITY 5.6 4 The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 40881849 fuel assemblies in the main pool,255 fuel assemblies in the cask storage pit and after permanent plant shutdown 294 fuel assemblies in the refueling canal.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.7-1.

WATERFORD - UNIT 3 5-6 AMENDMENT NO.%

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.j f ' CeNe with Fresh Fuel of less than or equel to 5%

l  ;.;; indial Enrichment l 1 1

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l Water-Filled Cells (Empty)

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Checkerboord Arrangement of fresh Assemblies i

and Empty cells t

Note: Either of these Checkerbcard Arrangements may l i be used in areas contiguous to each other or to

! areas of unrestricted storage in Region' 2.

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f j Cels with Fuel of f

s 7 '. 27 WWD/KgU Bumup l Cels with Fuel of l

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.. Enrichment-Burnvo tions i E 5 E " a' Saa'a 'a 'fe 5 s-3

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Checkerboord of Fuel Assemblies Bumed to 27 IdWD/KgU j and Fuel of Specified Enridhment-Bumup Combinations i

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Figure 5.6-1 Alternative Checkerboord Arrangements

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A 40

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Acceptable j  : Burr up Dom. sin 5

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o 30 g -  !

1 m -

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, / UriceceptoI>le Burnup Donicin

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U mit for 2 s Fuel

. Assumed for Fuet of less flion 2 2

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0.0 1.0 2.0 3.0 4.0 5.0 6.0 Initial Fuel Enrichment, wt. m U-235 l Figure 5.6-2 Acceptable Burnup Domoln for Unrestricted Sforoge of Spent Fuel in Reg *on 2

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I 70 5 '

60 - '

Acceptable

Burr up Dom sin 50 :

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I  : Ur iacce fol le Bur mupbon>oin l l 20 f -

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Assume d for Fuel .

of less than :ts 10 -

0~ ......... ......... ......... ......... ......... .........

0.0 1.0 2.0 3.0 4.0 5.0 6.0 Initial Fuel Enrichment, wt. s U-235 l

Ff9tire 5.6-3 Acceptable Burnup Domain for Spent Fuel In Checkerboard Arrangement with fuel of 5 s Enrichment (or less) at 27 MWD /KgU e

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NPF-38-193 Attachment IV Non-Proprietary Version of the Licensing Report for Reracking of 1

Waterford 3 Spent Fuel Pools i

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