Text

Proposed Tech Specs,Consisting of Change Request 443, Permitting Increase in Licensed Storage Capacity of Spent Fuel Pools,By Allowing Spent Fuel to Be Consolidated After Min Required Time in SFPs
	ML20116C680
Person / Time
Site:	San Onofre
Issue date:	07/29/1996
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20116C666	List: ML20116C663; ML20116C674; ML20116C680; ML20116C684;
References
	NUDOCS 9608010070
	Download: ML20116C680 (111)
	v • d • e

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ATTACHMENT A i

j AMENDMENT NOS. 127/128 j

APPROVED TECHNICAL SPECIFICATIONS

]

UNIT 2 I

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b 9608010070 960729 PDR ADOCK 05000361 P

PDR

k CREACUS 3.7.11 l

3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Cleanup System (CREACUS)

LC0 3.7.11 Two CREACUS trains shall be OPERABLE.

1 APPLICABILITY:

MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

l ACTIONS

NOTES------------------------------

1.

The provisions of LC0 3.0.4 are not applicable when 1

entering MODES 5, 6, or defueled configuration.

2.

Each Unit shall enter applicable ACTIONS separately.

l CONDITION REQUIRED ACTION COMPLETION TIME A.

One CREACUS train A.1 Restore CREACUS train 7 days inoperable, to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

associated Completion Time of Condition A AND not met in MODE 1, 2, l

3, or 4.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.

Required Action and C.1 Place OPERABLE Immediately associated Completion CREACUS train in i

Time of Condition A emergency radiation l

not met in MODES 5 protection mode.

j or 6, or during movement of irradiated 08 l

fuel assemblies.

l (continued)

I i

SAN ON0FRE--UNIT 2 3.7-24 Amendment No. +N,-128 L

CREACUS 3.7.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

C.

(continued)

C.2.1 Suspend CORE Immediately ALTERATIONS.

AND C.2.2 Suspend movement of Immediately irradiated fuel assemblies.

D.

Two CREACUS trains D.1 Enter LC0 3.0.3.

Immediately inoperable in MODE 1, 2, 3, or 4.

E.

Two CREACUS trains E.1 Suspend CORE Immediately inoperable in MODES 5 ALTERATIONS.

or 6, or during movement of irradiated AND fuel assemblies.

E.2 Suspend movement cf Immediately irradiated fuel assemblies.

SURVEILLANCE REQUIREllENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Operate each CREACUS train for 2: 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 31 days with the heaters on.

SR 3.7.11.2 Perform required CREACUS filter testing in In accordance accordance with Ventilation Filter Testing with the VFTP Program (VFTP).

(continued)

SAN ON0FRE--UNIT 2 3.7-25 Amendment No. +2h128

Fuel Storage Pool Water Level 3.7.16 3.7 PLANT SYSTEMS j

3.7.16 Fuel-Storage Pool Water Level 1

LC0 3.7.16 The fuel storage pool water level shall be a 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

i APPLICABILITY:

During movement of irradiated fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME a

l A.

Fuel storage pool A.1

NOTE---------

water level not within LC0 3.0.3 is not limit.

applicable.

i Suspend movement of Immediately irradiated fuel 2

assemblies in fuel storage pool.

l SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool water level is 7 days a 23 ft above the top of irradiated fuel assemblies seated in the storage racks.

4 SAN ON0FRE--UNIT 2 3.7-29 Amendment No. 127 4

l Fuel Storage Pool Boron Concentration 3.7.17 l

l 3.7 PLANT SYSTEMS 3.7.17 fuel Storage Pool Baron Concentration l

I LC0 3.7.17 The fuel storage pool boron concentration shall be l

a 1850 ppm.

l l

APPLICABILITY:

When fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool

NOTE-------------

boron concentration LCO 3.0.3 is not applicable, not within limit.

A.1 Suspend movement of Immediately fuel assemblies in the fuel storage pool.

l MQ A.2.1 Initia+e action to Immediately I

restore fuel storage l

pool boron l

concentration to l

within limit.

08 A.2.2 Verify by Immediately administrative means J

Region II fuel storage pool verification has been performed since the last movement of fuel assemblies in the fuel storage pool.

1 4

l SAN ON0FRE--UNIT 2 3.7-30 Amendment No. 127

- ~

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Spent Fuel Assembly Storage 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Spent Fuel Assembly Storage LC0 3.7.18 The combination of initial enrichment and burnup of each spent fuel assembly stored in Region Il shall be within the acceptable burnup domain of Figure 3.7.18-1 and Figure 3.7.18-2 or in accordance with Specification 4.3.1.1.

APPLICABILITY:

Whenever any fuel assembly is stored in Region II of the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1

NOTE---------

LC0 not met.

LC0 3.0.3 is not applicable.

Initiate action to Immediately move the noncomplying fuel assembly from Region II.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel assembly storing the is in accordance with Figure 3.7.18-1 and fuel assembly Figure 3.7.18-2 or Specification 4.3.1.1.

in Region II SAN ON0FRE--UNIT 2 3.7-32 Amendment No. 127

Spent Fuel Assembly Storage 3.7.18 E

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U-235 DRIOGENT (t/0)

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UNITS 2 & 3 FUEL MINIMUM BURNUP vs INITIAL ENRICHMENT FOR REGION II RACKS

i FIGURE 3.7.18-2 i

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SAN ON0FRE--UNIT 2 3.7-34 Amendment No. 127 3

4 er,.

-w:--

E

Design Features j

4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel' Storage 4.3.1 Criticality l

4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 4.1 weight percent; I

b.

K s 0.95 if fully flooded with unborated water, wf((chincludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; l

c.

A nominal 8.85 inch center to center distance l

between fuel assemblies placed in Region II; d.

A nominal 10.40 inch center to center distance l

between fuel assemblies placed in Region I; l

e.

Fuel assemblies may be stored in Region I with no restrictions; f.

Fuel assemblies with a burnup in the " acceptable

[

range" of Figure 3.7.18-1 and Figure 3.7.18-2 are allowed unrestricted storage in Region II; and g.

Fuel assemblies with a burnup in the " unacceptable range" of Figure 3.7.18-1 and Figure 3.7.18-2 will be stored in compliance with the Licensee Controlled Specification.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment l

of 4.1 weight percent; i

b.

K s 0.95 if fully flooded with unborated water, wf[ich includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; c.

K s 0.98 if moderated by aqueous foam, which iNcludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; and t

(continued)

SAN ON0FRE--UNIT 2 4.0-4 Amendment No. 127

i 1

1 Design Features l

4.0 4.0 DESIGN FEATURES l

4.3 Fuel Storage (continued) l d.

A minimum 29 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below Technical Specification 3.7.16 value (23 feet above the top of irradiated l

fuel assemblies seated in the storage racks).

l l

l 4.3.3 Capacity l

The spent fuel storage pool is designed and shall be maintained l

with a storage capacity limited to no more than 1542 fuel l

assemblies.

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i SAN ON0FRE--UNIT 2 4.0-5 Amendment No. 127

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ATTACHMENT B AMENDMENT NOS. 116/117 APPROVED TECHNICAL SPECIFICATIONS UNIT 3 l

CREACUS 3.7.11 j

3.7 PLANT SYSTEMS l

3.7.11 Control Room Emergency Air Cleanup System (CREACUS) j LC0 3.7.11 Two CREACUS trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies.

ACTIONS

NOTES------------------------------

1.

The provisions of LC0 3.0.4 are not applicable when entering MODES 5, 6, or defueled configuration.

2.

Each Unit shall enter applicable ACTIONS separately.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One CREACUS train A.1 Restore CREACUS train 7 days inoperable.

to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2, 3, or 4.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.

Required Action and C.1 Place OPERABLE Immediately associated Completion CREACUS train in i

Time of Condition A emergency radiation not met in MODES 5 protection mode.

or 6, or during movement of irradiated 0B fuel assemblies.

(continued)

I 4

k SAN ON0FRE--UNIT 3 3.7-24 Amendment No. 146r117

CREACUS 3.7.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2.1 Suspend CORE Immediately ALTERATIONS.

AND C.2.2 Suspend movement of Immediately irradiated fuel assemblies.

D.

Two CREACUS trains D.1 Enter LC0 3.0.3.

Immediately inoperable in MODE 1, 2, 3, or 4.

E.

Two CREACUS trains E.1 Suspend CORE Immediately inoperable in MODES 5 ALTERATIONS.

or 6, or during movement of irradiated AND fuel assemblies.

E.2 Suspend movement of Immediately irradiated fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Operate each CREACUS train for a 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 31 days with the heaters on.

1 SR 3.7.11.2 Perform required CREACUS filter testing in In accordance accordance with Ventilation Filter Testing with the VFTP Program (VFTP).

(continued)

SAN ON0FRE--UNIT 3 3.7-25 Amendment No. 4%rll7 l

l

i l

l Fuel Storage Pool Water Level 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Water level J

LC0 3.7.16 The fuel storage pool water level shall be a 23 ft over the top of irradiated fuel assemblies seated in the storage racks.

APPLICABILITY:

During movement of irradiated fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool A.1

NOTE---------

water level not within LC0 3.0.3 is not limit.

applicable.

Suspend movement of Immediately irradiated fuel assemblies in fuel storage pool.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool water level is 7 days a 23 ft above the top of irradiated fuel assemblies seated in the storage racks.

SAN ONOFRE--UNIT 3 3.7-29 Amendment No. 116

Fuel Storage Pool Boron Concentration 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Fuel Storage Pool Boron Concentration LC0 3.7.17 The fuel storage pool boron concentration shall be a 1850 ppm.

APPLICABILITY:

When fuel assemblies are stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel assemblies in the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool

NOTE-------------

baron concentration LC0 3.0.3 is not applicable.

not within limit.

A.1 Suspend movement of Immediately fuel assemblies in the fuel storage pool.

AND A.2.1 Initiate action to Immediately restore fuel storage pool boron concentration to within limit.

08 A.2.2 Verify by Immediately administrative means Region II fuel storage pool verification has been performed since the last movement of fuel assemblies in the fuel storage pool.

SAN ON0FRE--UNIT 3 3.7-30 Amendment No. 116 1

Spent Fuel Assembly Storage 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Spent fuel Assembly Storage LC0 3.7.18 The combination of initial enrichment and burnup of each spent fuel assembly stored in Region Il shall be within the acceptable burnup domain of Figure 3.7.18-1 and Figure i

3.7.18-2 or in accordance with Specification 4.3.1.1.

APPLICABILITY:

Whenever any fuel assembly is stored in Region II of the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1

NOTE---------

LC0 not met.

LC0 3.0.3 is not l

applicable.

l I

Initiate action to Immediately l

move the noncomplying l

fuel assembly from Region II.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY l

l SR 3.7.18.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel assembly storing the l

is in accordance with Figure 3.7.18-1 and fuel assembly Figure 3.7.18-2 or Specification 4.3.1.1.

in Region II i

SAN ON0FRE--UNIT 3 3.7-32 Amendment No. 116

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I b.o 2.5 3.0 3.5 4.0 4.5 6.0 S.5 U-235 ENRIO400 (t/0) i UNIT 1 FUEL MINIMUM BURNUP vs INITIAL ENRICHMENT FOR REGION II RACKS FIGURE 3.7.18-1 SAN ON0FRE--UNIT 3 3.7-33 Amendment No. 116

Spent Fuel Assembly Storage 3.7.18 l

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$.S U-235 DatiCMGif (t/0) i UNITS 2 & 3 FUEL MINIMUM BURNUP vs INITIAL ENRICHMENT FOR REGION II RACKS FIGURE 3.7.18-2 i

SAN ONOFRE--UNIT 3 3.7-34 Amendment No. 116

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 4.1 weight percent; b.

K s 0.95 if fully flooded with unborated water, wNich includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; c.

A nominal 8.85 inch center to center distance between fuel assemblies placed in Region II; d.

A nominal 10.40 inch center to center distance l

between fuel assemblies placed in Region I; i

e.

Fuel assemblies may be stored in Region I with no restrictions; f.

Fuel assemblies with a burnup in the " acceptable range" of Figure 3.7.18-1 and Figure 3.7.18-2 are allowed unrestricted storage in Region II; and g.

Fuel assemblies with a burnup in the " unacceptable range" of Figure 3.7.18-1 and Figure 3.7.18-2 will be stored in compliance with the Licensee Controlled Specification, i

1 4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

a.

Fuel assemblies having a maximum U-235 enrichment of 4.1 weight percent; b.

K # s 0.95 if fully flooded with unborated water, wNichincludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; I

c.

K,ff 5 0.98 if moderated by aqueous foam, which includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and 1

1 l

(continued)

SAN ON0FRE--UNIT 3 4.0-4 Amendment No. 116

Design Features 4.0

)

l 4.0 DESIGN FEATURES l

4.3 Fuel Storage (continued) d.

A minimum 29 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining of the pool below Technical 1

Specification 3.7.16 value (23 feet above the top of irradiated fuel assemblies seated in the storage racks).

4.3.3 Capacity i

l The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel assemblies.

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SAN ON0FRE--UNIT 3 4.0-5 Amendment No. 116 i

ATTACHMENT C AMENDMENT NOS. 127/128 APPROVED TECHNICAL SPECIFICATIONS AS REVISED BY PCN-443 UNIT 2 l

l

CREACUS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Cleanup System (CREACUS)

LC0 3.7.11 Two CREACUS trains shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel ;;;cmblics.

ACTIONS

NOTE------------------------------

1.

The provisions of LC0 3.0.4 are not applicable when entering MODES 5, 6, or defueled configuration.

2.

Each Unit shall enter applicable ACTIONS separately.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One CREACUS train A.1 Restore CREACUS train 7 days inoperable.

to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2, 3, or 4.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months i

C.

Required Action and C.1 Place OPERABLE Immediately associated Completion CREACUS train in Time of Condition A emergency radiation not met in MODES 5 protection mode.

or 6, or during I

movement of irradiated OR I

fuel ;;;cmblics.

l (continued) l l

l SAN ON0FRE--UNIT 2 3.7-24 Amendment No. 127,128

1 l

l CREACUS 3.7.11 J

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

C.

(continued)

C.2.1 Suspend CORE Immediately ALTERATIONS.

l AND C.2.2 Suspend movement of Immediately irradiated fuel as:cmbl ies.

D.

Two CREACUS trains D.1 Enter LC0 3.0.3.

Immediately inoperable in MODE 1, 2, 3, or 4.

E.

Two CREACUS trains E.1 Suspend CORE Immediately inoperable in MODES 5 ALTERATIONS.

or 6, or during movement of irradiated AND fuel assemblics.

E.2 Suspend movement of Immediately irradiated fuel as cmblics.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Operate each CREACUS train for a 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 31 days with the heaters on.

SR 3.7.11.2 Perform required CREACUS filter testing in In accordance l

accordance with Ventilation Filter Testing with the VFTP Program (VFTP).

(continued)

SAN ON0FRE--UNIT 2 3.7-25 Amendment No. 427 428 7

i 4

Fuel Storage Pool Water Level 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Water Level LC0 3.7.16 The fuel storage pool water level shall be a 23 ft over the top of irradiated fuel

c=blic; seated in the storage racks.

1 i

APPLICABILITY:

During movement of irradiated fuel ;;;c=blic; in the fuel storagepooljjy@pikypol.

l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

'A.

Fuel storage pool A.1

NOTE---------

water level not within LC0 3.0.3 is not limit.

applicable.

Suspend movement of Immediately irradiated fuel

bMes-in fuel storage poolyndidsk

~

ROOl-SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool water level is 7 days a 23 ft above the top of irradiated fuel

Slic; seated in the storage racks.

i a

t SAN ON0FRE--UNIT 2 3.7-29 Amendment No. 4 W 4

i

Fuel Storage Pool Boron Concentration 3.7.17 j

3.7 PLANT SYSTEMS 3.7.17 Fuel Storage Pool Boron Concentration LC0 3.7.17 The fuel storage pool boron concentration shall be 2: 1850 ppm.

APPLICABILITY:

When fuel ;;;cmblic arcif ts stored in the fuel storage pool and a fuel storage iidol verification has not been performed since the last movement of fuel assemblic; in the fuel storage pool. TAlsoiwhen fuel 31sypresentiin th'd' caskipooll ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool

NOTES------------

li LCO 3.0.3 is' not boron concentration

applicable.

not within limit.

2 ?ActibiFA 2.2Jbe16w?isTriot applic:able1:when 1the :: sole" reasontfor.1 compliance withiLC0;E3.7;17 tis.iths peesencelofjfue.liin?the cask { pool A.1 Suspend movement of Immediately fuel a :cmblic in the fuel storage;; pool and lask pool.

~

AND A.2.1 Initiate action to Immediately restore fuel storage pool boron concentration to within limit.

OR A.2.2 Verify by Immediately administrative means Region II fuel storage pool verification has been performed since the last movement of fuel assemblic in the l

fuel storage pool.

t l

SAN ON0FRE--UNIT 2 3.7-30 Amendment No. -lW

Spent Fuel As:cmbly Storage 3.7.18 3.7 PLANT SYSTEMS 3.7.18 Spent Fuel A :c bly Storage LC0 3.7.18 The combination of initial enrichment and burnup of eseh spent fuel

c bly-stored in Region II shall be within the acceptable burnup domain of Figure 3.7.18-1-endi?or Figure 3.7.18-2 or theifdelishYllfbsistbf6d in accordaisce with Lidn s.. eeXC o.h..t_rol.. l e. d.s. spddi fi c a t i oh"T 3.1.1_54_?0 fl. 00.

APPLICABILITY:

Whenever any fuel :::c=bly is stored in Region II of the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l

A.

Requirements of the A.1

NOTE---------

LC0 not met.

LC0 3.0.3 is not applicable.

l Initiate action to Immediately move the noncomplying fuel :::c bly fro.n Region II.

l l

SURVEILLANCE REQUIREMENTS I

SURVEILLANCE FREQUENCY l

I SR 3.7.18.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel

cmbly storing the is in accordance with Figurc 3.7.18-4-and fuel

cmbly Figurc 3.7.18 2 cr Specification 4.3.1.1 in Region II LC,0 t3,1.7. ' 18.

,a t

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i SAN ONOFRE--UNIT 2 3.7-32 Amendment No. 447 l

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-.. -. =

Spent Fuel A;;c d'y Storage j

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k.S 2.0 2.5 3.s 3.S 4.0 4.4 S.8 S.S U-235 DRIC2ENT (1/0) j 3

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UNITS 2 & 3 FUEL MINIMUM BURNUP vs INITIAL ENRICHMENT FOR REGION II RACKS

)

i FIGURE 3.7.18-2 i

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SAN ON0FRE--UNIT 2 3.7-34 Amendment No. -1N 2

i

Design Features-4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

i a.

Fuel :::::blic; having a maximum U-235 enrichment l

of 4.1 weight percent; l

l b.

K s 0.95 if fully flooded with unborated water, wNchincludesanallowanceforuncertaintiesas l

i described in Section 9.1 of the UFSAR; c.

A nominal 8.85 inch center to center distance l

between fuel storagi?dellF--- - pl :cd in

^ * ' ' ' " ' " " ~ ~ ~ * ~ "

ReW W l

d.

A nominal 10.40 inch center to center distance between fuel stofagsitellih::::blic: phecd in r

*~"'*~ " "^"

Re@ h e.

Fuel :::::blic: may be stored in Region I with no l

puPnyp][ restrictions; f.

Fuel :::::blic: with a burnup in the " acceptable range" of Figure 3.7.18-1 anddi Figure 3.7.18-2 areis allowed unrestricted stdPage-in Region II; i

l and"~

g.

Fuel :::::blic: with a burnup in the " unacceptable range" of Figure 3.7.18-1 ando_f Figure 3.7.18-2 will be stored in compliance With % e-Licensee Controlled Specification _I410l100.

4.3.1.2 The new fuel storage racks are designed and shall be l

maintained with:

l a.

Fuel assemblies having a maximun U-235 enrichment of 4.1 weight percent; l

b.

K s 0.95 if fully flooded with unborated water, w$chincludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; c.

K s 0.98 if moderated by aqueous foam, which iN1udes an allowance for uncertainties as described in Section 9.1 of the UFSAR; and (continued)

SAN ON0FRE--UNIT 2 4.0-4 Amendment No. 4N l

i

R Design Features 4.0 4.0 DESIGN FEATURES (continued) d.

A minimum 29 inch center to center distance between fuel assemblies placed. in the storage racks.

\\

4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining _of the pool below Technical Specification 3.7.16 value (*23 feet above the top of irradiated fuel :::::blic: seated in the' storage racks).

4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained i

with a storage capacity limited to no more than 1542 fuel a s s emb1 1 e sI( tots 1 TTWi thoutis toFig6T6fifc6niol idatedifsel

con sol;idatedjj: fuelga s s embl i.s sembl i,ssg}otg)fWi t h)s f orapD Eiseinbli' sisori2867sfuelta s

es.

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s SAN ON0FRE--UNIT 2 4.0-5 Amendment No. 147 l

ATTACHMENT D AMENDMENT NOS. 116/117 APPROVED TECHNICAL SPECIFICATIONS AS REVISED BY PCN-443 UNIT 3 l

s

CREACUS l

3.7.11 1

3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) f I

LC0 3.7.11 Two CREACUS trains shall be OPERABLE.

4 APPLICABILITY:

MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel :::cmblic.

ACTIONS

NOTE------------------------------

1.

The provisions of LC0 3.0.4 are not applicable when entering MODES 5, 6, or defueled configuration.

2.

Each Unit shall enter applicable ACTIONS separately.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One CREACUS train A.1 Restore CREACUS train 7 days inoperable.

to OPERABLE status.

j B.

Required Action and 8.1 Be in MODE 3.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months associated Completion Time of Condition A AND not met in MODE 1, 2, 3, or 4.

B.2 Be in MODE 5.

36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months C.

Required Action and C.1 Place OPERABLE Immediately associated Completion CREACUS train in Time of Condition A emergency radiation not met in MODES 5 protection mode.

1 or 6, or during movement of irradiated OR fuel

cmblics.

(continued)

SAN ON0FRE--UNIT 3 3.7-24 Amendment No. 116,117

CREACUS 3.7.11 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C.

(continued)

C.2.1 Suspend CORE Immediately ALTERATIONS.

AND C.2.2 Suspend movement of Immediately irradiated fuel a;;cmblics.

D.

Two CREACUS trains D.1 Enter LC0 3.0.3.

Immediately inoperable in MODE 1, 2, 3, or 4.

E.

Two CREACUS trains E.1 Suspend CORE Immediately inoperable in MODES 5 ALTERATIONS.

or 6, or during movement of irradiated AND fuel-a+semM4es.

E.2 Suspend movement of Immediately irradiated fuel assemblics.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Operate each CREACUS train for a 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 31 days with the heaters on.

SR 3.7.11.2 Perform required CREACUS filter testing in In accordance accordance with Ventilation Filter Testing with the VFTP Program (VFTP).

(continued)

SAN ON0FRE--UNIT 3 3.7-25 Amendment No. 116,117

Fuel Storage Pool Water Level 3.7.16 l

l 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Water Level LC0 3.7.16 The fuel storage pool water level shall be a 23 ft over the top of irradiated fuel as:cmblic; seated in the storage racks.

APPLICABILITY:

During movement of irradiated fuel assemblic: in the fuel storage poolkoMcaskj601.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool A.1

NOTE---------

water level not within LC0 3.0.3 is not limit.

applicable.

Suspend movement of Immediately irradiated fuel assemblic; in fuel storage pooliandfcask pgol.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool water level is 7 days a 23 ft above the top of irradiated fuel assemblics seated in the storage racks.

l l

i SAN ON0FRE--UNIT 3 3.7-29 Amendment No. 146

Fuel Storage Pool Boron Concentration 3.7.17

-3.7 PLANT SYSTEMS 3.7.17 Fuel Storage Pool Boron Concentration LC0 3.7.17 The fuel storage pool boron concentration shall be j

2: 1850 ppm.

APPLICABli.ITY:

When fuel ;;;c blic: arc}isstoredinthefuelstorage pool and a fuel storage pool verification has not been j

performed since the last movement of fuel

c=blic: in the fuel storage pool.Q1solvhengdjQijges~entlinQhe caskippo))

ACTIONS l

CONDITION-REQUIRED ACTION COMPLETION TIME 1

A.

Fuel storage pool

NOTES------------

boron concentration 17 LC0 3.0.3 is"not not within limit.

applicable.

2EliActi6h7AY2?2ibelois?Wnht PPitcab1.e reasonsf_ ora [wheMtheisyle~

~~E compilance withiLCOE317!17sistth'6 presencefofsfd&ltinithi i

caskilpoolf" ~ """ "

____g.g g m ____"____"____'___

A.1 Suspend movement of Immediately fuel cc:::blic in the fuel storage pool

~"

addKaskl pool.

AND A.2.1 Initiate action to Immediately restore fuel storage pool boron concentration to within limit.

OB A.2.2 Verify by Immediately administrative means Region II fuel storage pool 1

verification has been 1

performed since the last movement of fuel

blics in the fuel storage pool.

SAN ON0FRE--UNIT 3 3.7-30 Amendment No. 4 %

l

l Spent Fuel A::cably Storage 3.7.18 3.7 PLANT SYSTEMS i

l 3.7.18 Spent Fuel A;;c bly Storage 1

LC0 3.7.18 The combination of initial enrichment and burnup of each spent fuel assembly stored in Region Il shall be within the acceptable burnup domain of Figure 3.7.18-1-endTof Figure 3.7.18-2 or the3fuelfshallkbelstbf dijin accordancs with l

Liteh._s_ee & Cont. r. o1.1. ed. iSp6ci fitat16n~C3.1.174TO?1.0.. 0..

- m -.

_ ~-

~

or -

APPLICABILITY:

Whenever any fuel c::c bly is stored in Region II of the fuel storage pool.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1

NOTE---------

LC0 not met.

LCO 3.0.3 is not i

applicable.

l Initiate action to Immediately move the noncomplying fuel c::cably from Region II.

L i

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel c :cably storing the is in accordance with Figurc 3.7.18 1 cnd fuel c: cably Fi-in Region II L. C5.urc 3.7.18 2 cr Speci ficction 1.3.1.1 l

l sae7:18.

j x.- ---

a f

1 i

SAN GN0FRE--UNIT 3 3.7-32 Amendment No. 444

-.. _. - ~.. _ _

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2 SAN ON0FRE--UNIT 3 3.7-33 Amendment No. H 6 i

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$.5 2.0 2.8 3.8 3.8 4.8 4.3 8.8 S.S l

U.235 DelCMM (t/6) l 3

i 1

i UNITS 2 & 3 FUEL MINIMUM BURNUP vs INITIAL ENRICHMENT FOR REGION II RACKS j

I i

FIGURE 3.7.18-2

\\

A i

i SAN ON0FRE--UNIT 3 3.7-34 Amendment No. 4 %

j i

l

l 1

Design Features 4.0 1

4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality i

4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:

a.

Fuel ;; cablic; having a maximum U-235 enrichment of 4.1 weight percent; b.

K 5 0.95 if fully flooded with unborated water, wNfchincludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; I

c.

A nominal 8.85 inch center to center distance l

between fuel. stbrageTeellsh::c blic p hced in

~ ' ~ ~ ' ' ' ~ ~ ~

Re@ m d.

A nominal 10.40 inch center to center distance between fuel stgraggi;(ellsijassemblic: phced in l

Region I; e.

Fuel assemblies-may be stored in Region I with no burnup3 restrictions; f.

Fuel as:::blic with a burnup in the " acceptable range" of Figure 3.7.18-1 and68 Figure 3.7.18-2 areis allowed unrestricted stbiage in Region II; a nd -'

g.

Fuel :::c blies-with a burnup in the " unacceptable range" of Figure 3.7.18-1 andor Figure 3.7.18-2 will be stored in compliance With the-Licensee ControlledSpecification)).0J1qq.

4.3.1.2 The new fuel storage racks are designed and shall be maintained with:

i t

l a.

Fuel assemblies having a maximum U-235 enrichment of 4.1 weight percent; b.

K 5 0.95 if fully flooded with unborated water, wNfchincludesanallowanceforuncertaintiesas j

described in Section 9.1 of the UFSAR; K[cludes an allowance for uncertainties as5 0.98 if moderated by a c.

ifdescribed in Section 9.1 of the UFSAR; and 4

i i

(continued)

SAN ON0FRE--UNIT 3 4.0-4 Amendment No. 4 %

[

\\

l

Design Features l

4.0 4.0 DESIGN FEATURES (continued)

I d.

A minimum 29 inch center to center distance between fuel assemblies placed in the storage racks.

4.3.2 Drainaae j

The spent fuel storage pool is designed and shall be maintained to

{

prevent inadvertent draining.of the pool below Technical Specification 3.7.16 value (223 feet above the top of irradiated fuel

cmblic; seated in the' storage racks).

I 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel assemblies [ tofal)iWith6htistofagslofMonsolidat#dli

s;slsembliesn(ori2867f fuelBassbmb]iesg}ota}]ig}gjflibiofags]6f consolidatedsfu;e};agsembljpes.

1 l i l j l' l SAN ON0FRE--UNIT 3 4.0-5 Amendment No. 446 l l

l l l ATTACHMENT E AMENDMENT NOS. 127/128 APPROVED TECHNICAL SPECIFICATIONS AS REVISED BY PCN-443 AND PCN-449 UNIT 2 l l l l I

CREACUS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Cleanup System (CREACUS) LC0 3.7.11 Two CREACUS trains shall be OPERABLE. APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel ;;;cmblic;. ACTIONS

NOTES-----------------------------

1. The provisions of LC0 3.0.4 are not applicable when entering MODES 5, 6, or defueled configuration. 2. Each Unit shall enter applicable ACTIONS separately. CONDITION REQUIRED ACTION COMPLETION TIME A. One CREACUS train A.1 Restore CREACUS train 7 days inoperable. to OPERABLE status. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met in MODE 1, 2, 3, or 4. B.2 Be in MODE 5. 36 hours C. Required Action and C.1 Place OPERABLE Immediately associated Completion CREACUS train in Time of Condition A emergency radiation not met in MODES 5 protection mode. or 6, or during movement of irradiated OH fuel assemblics. (continued) I i SAN ON0FRE--UNIT 2 3.7-24 Amendment No. 447,128 l

l CREACUS 3.7.11 ACTIONS l CONDITION REQUIRED ACTION COMPLETION TIME l C. (continued) C.2.1 Suspend CORE Immediately l ALTERATIONS. AND l C.2.2 Suspend movement of Immediately irradiated fuel 0;;cmblics. D. Two CREACUS trains D.1 Enter LC0 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4. E. Two CREACUS trains E.1 Suspend CORE Immediately inoperable in MODES 5 ALTERATIONS. or 6, or during movement of irradiated NLD. fuel--as:cmbl i c s. E.2 Suspend movement of Immediately irradiated fuel

cmblic.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Operate ench CREACUS train for a 2 hours 31 days with the aeaters on. i SR 3.7.11.2 Perform required CREACUS filter testing in In accordance accordance with Ventilation Filter Testing with the VFTP Program (VFTP). (continued) SAN ON0FRE--UNIT 2 3.7-25 Amendment No. -1N,128

Fuel Storage Pool Water Level 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Water Level LCO 3.7.16 The fuel storage pool water level shall be a 23 ft over the top of irradiated fuel :::::blic; seated in the storage racks. l APPLICABILITY: During movement of irradiated fuel :::::blic in the fuel storagepool@'Q#ssQo6}. l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l A. Fuel storage pool A.1

NOTE---------

water level not within LC0 3.0.3 is not limit. applicable. Suspend movement of Immediately irradiated fuel

blic; in fuel.

PARl ge pool []sdg,a.,.K stora s. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool water level is 7 days l t 23 ft above the top of irradiated fuel

blic; seated in the storage racks.

l l l SAN ONOFRE--UNIT 2 3.7-29 Amendment No. 4N ) I l ) )

Fuel Storage Pool Boron Concentration 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Fuel Storage Pool Boron Concentration LC0 3.7.17 The fuel storage pool boron concentration shall be 2: 1850 ppm. APPLICABILITY: When fuel

c=blic: arcliis stored in the fuel storage poolandafuelstorage$601verificationhasnotbeen performed since the last movement of fuel :::c=blic; in the fuel toragepool.}!?Alsgy{enJfdeMisjyreihntyQt{e pistpool ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool

NOTES------------

boron concentration l1] LC0 3.0.3 is"not not within limit. applicable. ^ " ' ~ ~JActi6 IGA!2!2Ibe16WiisI66t i 2! applicableiwhenXthe> sole ~' reas0Mfork0mplLianci~- WithMC003i0175isithi presence?offfuelsiss_thi gg. g,) 7m-p ,,,,ge.3 =.gg,,,,,,,,,,,,,,, A.1 Suspend movement of Immediately fuel

blic in the fuel storageg~p~,o_ol pnd?yisjpool.

AND A.2.1 Initiate action to Immediately restore fuel storage pool boron concentration to within limit. 08 A.2.2 Verify by Immediately administrative means Region 11 fuel storage pool verification has been performed since the last movement of fuel

c=blic in the fuel storage pool.

SAN ON0FRE--UNIT 2 3.7-30 Amendment No. 424

l Spent Fuel A::cably Storage 3.7.18 l [ 3.7 PLANT SYSTEMS l l 3.7.18 Spent Fuel A :cebly Storage LC0 3.7.18 The combination of initial enrichment and burnup of-each SONGS?224ndi33 spent fuel as:c bly stored in Region 11 shall belithih'ths" acceptable burnup domain of Figure 3.7.18-1 and-6QFigure 3.7.18-2, or theffdel?E555$1f shillibdistoFed i in accordance with Licidsid2 Controlled 3Sp4cificatidn"C3^.r1 l " ~ ~ " " " ~ ~ " 4t.0;100 ~ < Ths* bliFndpI6ffeteM 50NGS11VUdhiUnfid tbWidslipsAtif6El 3:06:bly 's t ored hi ni Regiods! Inshall;i! be!greatedthn?osid tohl8:0tGWD/Tsfortintefionilscationner$5?5?GWD/Tifos""qdsl ~ ~~ peFiphspahl odations godthsTfuelM:udlyfshalls beistiffsd a hisccopd anceWi t hK i c 6h s ee t Cont rsl i ed (Sp"esi fi ea t ish"*"""**** 410 ; 100 T " """~"""'"""" ' ^~"*"*~* " * " " * ~ " * " " w ..c .a APPLICABILITY: Whenever any fuel :::c bly is stored in Region II of the fuel storage pool. ACTIONS 1 l CONDITION REQUIRED ACTION COMPLETION TIME A. Requirements of the A.1

NOTE---------

LC0 not met. LC0 3.0.3 is not applicable. Initiate action to Immediately move the noncomplying fuel ;;;c=bly from Region II. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel

c bly storing the is in accordance with Figurc 3.7.18 1 and fuel

cably Fi cre 3.7.18 2 cr Specification 4.3.1.1 in Region II LC07377f18.

~-- 1 1 SAN ON0FRE--UNIT 2 3.7-32 Amendment No. 4 W

i i Spent Fuel A;;=bly Storage 3.7.18 l 40 /... , 35 .r... 'f Q 30 .....,.... l ACCEPTABLE .......!........,l...../...,.........lc........,l..... 3 l ,c l (r)25 ~ a 3 .....;..........;........;.........p..... . 4.........;.........;..........;..... ',i .i ,i ,i / c n U e o s ,i 5 4,.........;....... ;..... l co e l cn 15-

f

- NOT ACCEPTABLE.;;..........;:..... g c 10 .I .I .i t I L) ....;.........',t........q'..... 8 .....;...._....q'. U) -Q 5 ,I B n I t .....p.... ....;.........p........q.........;.........p........g..... / O i 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 Initial U-235 Enrichment (w/o) MINIMUM BURNUP vs INITIAL ENRICHMENT FOR UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION II RACKS 1 FIGURE 3.7.18-1 i t i b } 4 SAN ON0FRE--UNIT 2 3.7-33 AMENDMENT NO. -1W i i

Spent Fuel A::=bly Storage 3.7.18 l 1 l l l l 40 ......,........s...... 35 ^k ....;.........y.........;.........;.........y........q..... i O 30 l 3l' .....l...... ACCEPTABLE ..... j..........l.........j.........l....'.x...j..... e.-,. ./ [ v 20 g 3 4.... .c c 's 20 ,/; co .....;..........;.........;.........l..........;... t e 16 l 9 7; m . NOT ACCEPTABLE r o 10 /.- m .. 6. O 5

f.... ;.........

y.... .....y.........;..... .....p.... ./ 0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 i Initial U-235 Enrichment (w/o) r l MINIMUM BURNVP vs INITIAL ENRICHMENT FOR PLACEMEN1 0F SONGS 2 AND 3 FUEL IN REGION II PERIPHERAL P00L LOCATIONS FIGURE 3.7.18-2 1 i 1 a ) l 7 1 SAN ON0FRE -UNIT 2 3.7-34 AMENDMENT NO. 4N i 4

Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with: a. Fuel

cmblic; having a maximum U-235 enrichment of 4.48 weight percent; b.

K s 0.95 if fully flooded with unborated water, wf((chincludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; c. A nominal 8.85 inch center to center distance between fuel 5tbrig~eTeellsic::cmblic: plcced in RegM H; ' ^ ' ' ~ ' ~ ~ ~ d. A nominal 10.40 inch center to center distance between fuel stdP, ass.R~. ells;P ~^"^ plcced in l gg e. Units 11H2?andi3?ffuel c::c=blics may be stored in Re@ s"I*W10"QpeM hs - f. UnitV123hndf3?ffuel c::cmblics with a burnup in the "acEeptable~ ringe" of Figure 3.7.18-1 and Figurc 3.7.18 2 cre :is7 allowed unrestricted storage ~~ in Region II; and g. Un i t s F2 Pandi3 %Ffuel fisd 5bblic?Ni t hTilibe r6hpM htt he "acceptsblelrkng'e"i;6fiFigure23?7V18924ee2fi~ '"~ al l owed i.unre s tri cthd Tsto racjsii nithelperi phe rs1Fpool

16bationskWithX1kor?2.sfacesitowsrditieispentifuel" p6ohwallM6QResidiisII;

~ ~^^'"'" " "'~ h. Fuel es:c=blics with a burnup in the " unacceptable l range" of Figure 3.7.18-1 and-bWFigure 3.7.18-2 l will be stored in compliance with M e-Licensee ControlledSpecificationf4J07100gand iT TTheibdFnU Vofleaeb;SONGSilluraniUmidiosidelipent t h aniorl egu alitoK 18 L O2 GWD/g t onil lish al li bsi:g reate "fuelhdd0:519 stoped!iniRe Tifodinteriorslocations bFiS ; 51GWD/Tifors pshi pheralkl oc st i on sh6hthelfuel

sidbifshallibef;storedkinisecordance91th* " '

[icenseeJControllsd3Specifijation.4)0fl00p" r (continued) SAN ON0FRE--UNIT 2 4.0-4 Amendment No. 4 N i i i

Design Features 4.0 4.0 DESIGN FEATURES 4.3 Fuel Storage (continued) 4.3.1.2 The new fuel storage racks are designed and shall be maintained with: j a. Fuel assemblies having a maximum U-235 enrichment of 4.48 weight percent; b. K ' s 0.95 if fully flooded with unborated water, wh,ich includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; s 0.98 if moderated by aqueous foam, which K 'c'ludes an allowance for uncertainties as c. in described in Section 9.1 of the UFSAR; and d. A minimum 29 inch center to center distance between fuel assemblies placed in the storage racks. 4.3.2 Drainaae The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining _of the pool below Technical Specification 3.7.16 value (223 feet above the top of irradiated fuel assemblics seated in ths storage racks). 4.3.3 Capacity The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel a s s embl i e sP ( total )7wi thout? s torage ~ofMon sol i dated ifdel assembi i es6 or L 2867dfuel t assemb1 les f(^ tot al )j,with ? storage [o f con'solidat'edifuelf assembliess ~ ~~ SAN ON0FRE--UNIT 2 4.0-5 Amendment No. 4N }

t l l l l ATTACHMENT F AMENDMENT NOS. 116/117 APPROVED TECHNICAL SPECIFICATIONS AS REVISED BY PCN-443 AND PCN-449 UNIT 3 1 i

CREACUS 3.7.11 3.7 PLANT SYSTEMS 3.7.11 Control Room Emergency Air Cleanup System (CPEACUS) LC0 3.7.11 Two CREACUS trains shall be OPERABLE. j l APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel-assemblics. ACTIONS

NOTES-----------------------------

7 l 1. The provisions of LC0 3.0.4 are not applicable when l entering MODES 5, 6, or defueled configuration. ) 2. Each Unit shall enter applicable ACTIONS separately. CONDITION REQUIRED ACTION COMPLETION TIME l A. One CREACUS train A.1 Restore CREACUS train 7 days inoperable. to OPERABLE status. B. Required Action and B.1 Be in MODE 3. 6 hours associated Completion Time of Condition A AND not met in MODE 1, 2, 3, or 4. B.2 Be in MODE 5. 36 hours C. Required Action and C.1 Place OPERABLE Immediately associated Completion CREACUS train in Time of Condition A emergency radiation not met in MODES 5 protection mode. or 6, or during movement of irradiated 08 fuel assemblics. (continued) SAN ON0FRE--UNIT 3 3.7-24 Amendment No. 146,117 i

CREACUS 3.7.11 l ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) C.2.1 Suspend CORE Immediately ALTERATIONS. AND C.2.2 Suspend movement of Immediately irradiated fuel as:cmblies. D. Two CREACUS trains D.1 Enter LC0 3.0.3. Immediately inoperable in MODE 1, 2, 3, or 4. E. Two CREACUS trains E.1 Suspend CORE Immediately inoperable in MODES 5 ALTERATIONS. or 6, or during movement of irradiated AND fuel-a;;cmblic;. E.2 Suspend movement of Immediately irradiated fuel a :cmblic. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.11.1 Operate each CREACUS train for a 2 hours 31 days with the heaters on. SR 3.7.11.2 Perform required CREACUS filter testing in In accordance accordance with Ventilation Filter Testing with the VFTP Program (VFTP). l (continued) l l SAN ON0FRE--UNIT 3 3.7-25 Amendment No. 444,117

Fuel Storage Pool Water Level 3.7.16 3.7 PLANT SYSTEMS 3.7.16 Fuel Storage Pool Water Level LC0 3.7.16 The fuel storage pool water level shall be a 23 f t over the top of irradiated fuel assemblics seated in the storage racks. APPLICABILITY: During movement of irradiated fuel as:cmblics in the fuel storage poolforicssk})ool. ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. Fuel storage pool A.1

NOTE---------

water level not within LC0 3.0.3 is not limit. applicable. Suspend movement of Immediately irradiated fuel as:c=blics in fuel storagepooljihndJdask Pool. SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.16.1 Verify the fuel storage pool water level is 7 days a 23 ft above the top of irradiated fuel

cmblic; seated in the storage racks.

I SAN ON0FRE--UNIT 3 3.7-29 Amendment No. 446 l

Fuel Storage Pool Baron Concentration 3.7.17 3.7 PLANT SYSTEMS 3.7.17 Fuel Storage Pool Boron Concentration LC0 3.7.17 The fuel storage pool boron concentration shall be a 1850 ppm. APPLICABILI1Y: When fuel-:::cmblic: crelis stored in the fuel storage pool and a fuel storage pool verification has not been performed since the last movement of fuel

cmblic; in the fuel storage pool.gAlpyhen}fuelgly[pfe5entligths cisk;pgql; ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Fuel storage pool

NOTES------------

boron concentration 17 LC0 3.0.3 is"not not within limit. applicable. i 2 Action A.2.2 below is not l ^ ^ applicable when the sole' reason for compliance I with LCO 3.7.17 is the presence of fuel in the ca,sk pool. i l A.1 Suspend movement of Immediately fuel

cmblic in l

the fuel storage [p*abl andisajkpool. ~ AND A.2.1 Initiate action to Immediately restore fuel storage pool boron concentration to within limit. OB A.2.2 Verify by Immediately administrative means Region II fuel storage pool verification has been performed since the last movement of fuel j

cmblic in the i

fuel storage pool. a -SAN ON0FRE--UNIT 3 3.7-30 Amendment No. 444 I

Spent Fuel A::cabbf-Storage 3.7.18 j l 3.7 PLANT SYSTEMS 3.7.18 Spent Fuel A::::bly Storage LC0 3.7.18 The combination of initial enrichment and burnup of eseh l SONGSi2fand]3? spent fuel

cably stored in Region II shall be Within"the* acceptable burnup domain of Figure 3.7.18-1 and-or? Figure 3.7.18-2, or th'effdel%ssbibl'ishhlisbe!5tdFed in accdrdance with Lidenseel:ControllediSpedifidat16n~tT.T!!

~ ^ " * " * ~ " ~ ~ ~ ~ ~ ~ $01100. Thi? bWnupT6f! eeeW-SONGS R1Thrini 0nEd i okide3phnt S f0el nds:bly; storedsinliRegion(IIsshalljbeigreaterithanioMiydsl l tos18.0!GWD/TifoFXinteriorklocationsforJ5154 GWD/llfor'" "^ ' l periphei al k16 cati orisp ont he? fuel ti:nabirshal li bentWid i n? accord anceb w i th i li bens eeT Control l ed C Sp"esi fi ehti oii'"*~~ ' ~ ' ' ~ ^ ^ " " ' ' ^ " ' ~ ~ " "^" " " " ~ 4_.0.1.100; l APPLICABILITY: Whenever any fuel :::c=bly is stored in Region II of the j. fuel storage pool. 1 4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME l A. Requirements of the A.1

NOTE---------

LC0 not met. LC0 3.0.3 is not applicable. Initiate action to Immediately move the noncomplying fuel

c=bly from Region II.

i SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.18.1 Verify by administrative means the initial Prior to enrichment and burnup of the fuel

bly storing the is in accordance with Figurc 3.7.18 1 and fuel :::cably Fi urc 3.7.18 2 cr Specification 4.3.1.1 in Region II

. O?.3_07,118. LC x l SAN ON0FRE--UNIT 3 3.7-32 Amendment No. 4 M

... =.. . - - -. ~ l Spent Fuel A::=t'y Storage l 3.7.18 i l l i l l 40 /... 35 I h [ h /....;h h h h h g D 1 0 30 3 ACCEPTABLE .......:c........!..../...,:......... :r.... ....,i..... J .....c.... O / 4 v25 a 3 4.........;.........:....... 4.........;.........;..........:.... c

/

' 20 2 4.,..... co 4,.........;.... e 15 m g . NOT ACCEPTABLE g 10 t i s ca m .....,t.........:..... .....:........ 3........t.,.... Q 5 f..3..... ....;.........p........q..... ....;.........p.... .....p.... t / ?. O 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 Initial U-235 Enrichment (w/o) MINIMUM BURNUP vs INITIAL ENRICHMENT FOR UNRESTRICTED PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION II RACKS FIGURE 3.7.18-1 I l l l l SAN ON0FRE--UNIT 3 3.7-33 AMENDMENT N0. 446

Spent Fuel A::=bly Storage 3.7.18 40 ....,........s,.............. 35 D ....;.........y........q.........;.........y.............. O 30 3 ....j..... . ACCEPTABLE .......[.........j.........j.........[/x...j..... (r) 2 5 /.....:......,..... a.3. .....c........,.........,... c. i i i g- 'a 20 ,,7 ; ca o 16 g 7 ;;......... . NOT ACCEPTABLE 4..... m .c o 10 /,. .3 y ( O i i 5

f.... ;.

i i .....y.... ....;.........y.........:..... .....:./... .....y.... 0 1.5 2.0 2.5 3.0 3.5 4.0 4.5 5.0 5.5 Initial U-235 Enrichment (w/o) MINIMUM BURNUP vs INITIAL ENRICHMENT FOR PLACEMENT OF SONGS 2 AND 3 FUEL IN REGION 11 PERIPHERAL POOL LOCATIONS FIGURE 3.7.18-2 1 l f I SAN ON0FRE--UNIT 3 3.7-34 AMENDMENT NO. 4%

l Design Features 4.0 4.0 DESIGN FEATURES (continued) 4.3 Fuel Storage 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with: a. Fuel c::cmblic; having a maximum U-235 enrichment of 4.48 weight percent; b. K s 0.95 if fully flooded with unborated water, wffchincludesanallowanceforuncertaintiesas described in Section 9.1 of the UFSAR; c. A nominal 8.85 inch _ center to center distance between fuel.storageW. ells?c::c=blics placed in Re @ II- ~~ ' ~ d. A nominal 10.40 inch center to center distance between fuel st6fige!cellsies:cmblics placed in ' ~ ' ' ' " ' ~ ~ '" Re @ I; UnitR.1R2?and?3ffuel c::cmblic may be stored in e. p ~T'M % p' Q $es M o m f. UnitsT2?and?3?ffuel assemb 4es-with a burnup in the W W M ge" of Figure 3.7.18-1 and F49ere 3.7.18 2 cre ;is3 allowed unrestricted storage in Region II; and g. Un'I t sj 2(:iand l3;f f061[idb5dblj fiNi t hia! bbrnspi:iin] t he " accep tabl e]iange"j.o fc F i g ure S3 ? 71:1892 l ere-i s~ all owedlunre s tri cted :Jstorage ii n lthe neri pheral s poo 1ocationstwlthillorf 2:# faces:8towardi;t ief spent; fuel } ~ pool l;.wal,MiofiRegtoniIIf ^' '~ ~~ ~ * ^ ~ ~~ ~ h. Fuel c::cmblics with a burnup in the " unacceptable range" of Figure 3.7.18-1 and-odFigure 3.7.18-2 will be stored in compliance with the-Licensee ControlledSpecificationf4J0[100gand 11 ?Thi! bdrnep ro fs'eac4-50NGS E1?[u ran i diCdi si dslispent ~ ' fuel:f dd:t:blyl st_ored Mnl Region?II!;shallj bej greatee orj: S : 5 ? GWD/T 4 fors pe ri pheralnl_oc)ati on s% o rsthe l l

cmbly ' sh'a1.li bel s toredli n:i accorda'nce fwi_tf j

Li ce_ns ee s. con t rol l ed !S. pec i f i c ati oni;4:0110_Of i (continued) 4 SAN ON0FRE--UNIT 3 4.0-4 Amendment No. 446

Design Features 4.0 4.0 DESIGN FEATURES l 4.3 Fuel Storage (continued) 4.3.1.2 The new fuel storage racks are designed and shall be maintained with: a. Fuel assemblies having a maximum U-235 enrichment of 4.18 weight percent; b. K 5 0.95 if fully flooded with unborated water, wf((ch includes an allowance for uncertainties as described in Section 9.1 of the UFSAR; 5 0.98 if moderated by aqueous foam, which K[cludes an allowance for uncertainties as c. iEdescribed in Section 9.1 of the UFSAR; and d. A minimum 29 inch center to center distance between fuel assemblies placed in the storage racks. 4.3.2 Drainaae l The spent fuel storage pool is designed and shall be maintained to prevent inadvertent draining _of the pool below Technical Specification 3.7.16 value (223 feet above the top of irradiated fuel c :cmblic; seated in thd storage racks). 4.3.3 Capacit_y The spent fuel storage pool is designed and shall be maintained with a storage capacity limited to no more than 1542 fuel assembliesE total)Withont3stbra(jeibfB6riidlidat6difdel isiemb1 i esi)(o r#2867) fuel $as s embl.1 es{( tot al)[wi thist orgg[(B f consolidated;fuelgassembljes. l i SAN ON0FRE--UNIT 3 4.0-5 Amendment No. -146

[ 1 l 1 I ATTACHMENT G ADMINISTRATIVE CONTROLS PERTAINING TO FUEL CONSOLIDATION (for information only) l l l I l

1 l ATTACHMENT G l ADMINISTRATIVE CONTROLS PERTAINING TO FUEL CONSOLIDATION l (for information only) During preparation of the Fuel Consolidation and Storage Report, Revision 0, which is included as Enclosure 2, it became evident that certain restrictions l would be required on the consolidation process and storage configuration of l fuel in the spent fuel pool. Many of these restrictions are similar to those already in place for standard fuel, such as storage pattern limitations. However, additional restrictions are required which are specific to consolidated fuel. These additional restrictions will be implemented to ensure that the circumstances experienced during normal and accident conditions remain within the configurations assumed in evaluations of the fuel consolidation and storage process. The restrictions and limitations will be implemented as administrative controls through Licensee Controlled Specifications (LCS) and are provided here for information only. These administrative controls will be reevaluated for their validity, adequacy, and usefulness after completion of the consolidation process system design and may undergo changes as the result j of this reevaluation. These administrative controls will be implemented prior to performance of any fuel consolidation activities. Administrative Controls for Fuel Movement, Processes, and Storage 1. Performing the fuel consolidation process will be prohibited during fuel movement for plant refueling operations or during fuel reconstitution operations, in order to minimize the total amount of fuel that would simultaneously be outside of the storage racks. 2. Use of the fuel consolidation equipment will be prohibited if any of the following occurs: a) The air temperature near the consolidation equipment exceeds 104*F, b) The spent fuel pool (SFP) water temperature exceeds 145 F, c) The SFP water soluble baron falls below 1850 ppm (measured). 3. Candidate fuel for consolidation shall be allowed to cool a minimum of six months following discharge from the reactor and prior to being moved into the cask pool for consolidation. i 4. The burnup of candidate fuel for consolidation must be estimated with the best available methodology prior to its consolidation. If the two source assemblies are eligible for unrestricted storage in Region II, the resulting consolidated fuel canister may be stored in Region II without restrictions. However, if one of the source assemblies is not eligible for unrestricted storage, the resulting consolidated fuel canister shall meet the storage criteria stated for standard fuel in Technical Specification 4.3.1.1. Consolidated fuel canisters shall meet surveillance requirement SR 3.7.18.1 of the Technical Specifications prior to being stored in Region II. 5. SONGS 1 fuel and SONGS 2 and 3 fuel shall not be mixed within the same consolidated fuel canister, or damaged fuel canister or basket. l 6. A SONGS 1 consolidated fuel canister shall contain at least 324 rods, fuel or non-fuel (such as stainless steel replacement rods or burnable poison rods) prior to storage in the SFP racks. Additional stainless i steel rods may be introduced if the total number of rods eligible for consolidation is less than 324.

. 7. A SONGS 2 and 3 consolidated fuel canister shall contain at least 400 rods, fuel or non-fuel (such as stainless steel replacement rods or burnable poison rods) prior to storage in the SFP racks. Additional stainless steel rods may be introduced if the total number of rods eligible for consolidation is less than 400. l 8. The rod pitch inside partially loaded canisters shall be maintained by l restraints inserted within the canister to ensure against rod l displacement during canister movement. 9. The total spent fuel which will be permitted in the cask ool at any given time is 553 fuel rods. This is inclusive of two fu 1 spent fuel assemblies or one full consolidated fuel canister together with, in each case, a damaged fuel rod storage canister or basket with a maximum of 81 rods. l f

10. Fuel assemblies, consolidated fuel canisters, and damaged fuel rod canisters or baskets moving to and from the consolidation work station or i

present in the work station shall be separated from each other by more than 12 inches of water to ensure that they are neutronically isolated. The 12 inch distance shall be measured from edge to edge. i

11. The gate between the spent fuel pool and the cask 3001 shall be kept open and not moved or removed when fuel is located in t1e cask pool during consolidation.

12. Operation of the cask handling crane (CHC), including the CHC load block without load, will be prohibited within ten feet of the edge of the cask pool when fuel is present in the cask pool during consolidation.

13. The following lift height and weight restrictions are currently in place for moving gate and test equipment:

Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the spent fuel pool except for the following two cases: a. Spent fuel pool gates (4650 pounds, including rigging) shall be carried at a height less than 30 inches (elevation 36' 4") over the fuel racks. b. Test equipment skid (4500 pounds, including rigging) shall not be carried at a height greater than 72 inches (elevation 39' 10") over rack cells which contain Unit 2/3 fuel assemblies. The test equipment skid height shall be limited to 30 feet 8 inches (elevation 64 6") over rack cells which contain Unit 1 fuel assemblies. The following additional exception will be added to support the fuel consolidation process: c. Consolidated fuel canisters (2904 pounds maximum dry weight) and damaged fuel canisters or baskets shall be subject to the same lift height limits as standard fuel assemblies. The fuel movement prerequisites shall be verified in accordance with Procedure S023-X-7.2 prior to handling fuel usemblies or consolidated fuel canisters. l f

ATTACHMENT H UNIT 2 AMENDMENT NOS. 127/128 AND UNIT 3 AMENDMENT NOS. 116/117 APPROVED BASES AS REVISED BY PCN-443 (forinformationonly)

l I NOTE TO ATTACHMENT H PCN-443 changes to the Units 2 and 3 Bases as shown in this attachment include certain changes not related to fuel consolidation and storage. Most of these changes are editorial corrections or clarifications that are self-explanatory. Also included are the three changes described below. 1-In B 3.7.16, under BACKGROUND and LCO, the term " fuel handling accident" is changed to " design basis fuel handling accident," which is more accurate. 2-In B 3.7.16, under APPLICABLE SAFETY ANALYSES, it is presently stated: "The resultant 2 hour thyroid dose to a person at the exclusion area boundary is a small fraction of the 10 CFR 100 (Ref. 5) limits." The p'hrase "a small fraction of" is changed to "well within (25% or less of). This change is consistent with the guidance provided in Section 15.7.4 of the Standard Review Plan (NUREG-0800). Section 15.7.4 of NUREG-0800 defines "well within" as "25 percent or less of the 10 CFR Part 100 exposure guideline values, i.e., 75 rem for the thyroid and 6 rem for the whole-body doses." 3-In B 3.7.16, under SURVEILLANCE REQUIREMENTS, an incorrect citation for the LC0 that contains Refueling Water Level requirements is corrected. l

l l CREACUS ) B 3.7.11 l l BASES l l APPLICABILITY In MODES 1, 2, 3, and 4, the CREACUS must be OPERABLE to limit operator exposure during and following a DBA. l l i In MODES 5 and 6, the CREACUS is required to cope with the release from a rupture of a waste gas tank. During movement of irradiated fuel

cmblics, the CREACUS must be OPERABLE to cope with the release from a fuel handling accident.

1 Thsit ermi"m@emen t?" s as7 appl i sd [tb71 Wad i s tsd f fu613i_ n l Sp'eci fica ti o n #337;11N re f e rsitoi t heimoveme nt(o f j i rrad i ded 1 fuels iellet(~ )bfuel; rod (s)Maipartial2 fuel sassembinoi l s as s em )l i e s ea s compl etei fuel Ea s s cmbl y 20r]as s embl i e s, k. or " consolidated t fuel WThetfuel Lmovementimayf beAfor6 any~ purpose W i ncl udi ngM buti not R11 mi ted 4 to Mfuel bi nspect i oni l fuellrecon s t,i t u t_t o ngand ifuelicon s ol i d at i.on] ~^~ l l ACTIONS ACTION statements are modified by two NOTES. NOTE 1 says: l "The provisions of LC0 3.0.4 are not applicable when l entering MODES 5, 6, or defueled configuration." Therefore, since CREACUS can be inoperable during each individual MODE, it should not be required to have two OPERABLE CREACUS trains before MODE change from defueled from MODE 6 to l defueled configuration, and from MODE 4 to MODE 5. l Specification 3.0.4 establishes that entry into an operational mode or other specified condition shall not be l made unless the conditions of the LC0 are met. l Applicability statement "During movement of irradiated fuel as:cmblic " ensures the OPERABILITY of both CREACUS trains prior to the start of movement of irradiated fuell ' ; ="tl i =. NOTE 2 says: "Each Unit shall enter applicable ACTIONS separately." CREACUS is a shared system between Unit 2 and Unit 3. LC0 doesn't address the operational situation when l the Units are in different operational MODES. Without this l NOTE it may not be clear what ACTIONS should be taken. A.1 i With one CREACUS train inoperable, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE CREACUS subsystem is adequate to aerform control room radiation protection function. iowever, the overall reliability is reduced because a single failure in the OPERABLE CREACUS train could result in loss SAN ON0FRE--UNIT 2 B 3.7-59 Amendment No. 427,'28

CREACUS B 3.7.11 BASES ACTIONS of CREACUS function. The 7 day Completion Time is based on (continued) the low probability of a DBA occurring during this time period, and the ability of the remaining train to provide the required capability. 8.1 and B.2 If the inoperable CREACUS cannot be restored to OPERABLE status within the required Completion Time in MODE 1, 2, 3, or 4, the unit must be placed in a MODE that minimizes the accident risk. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 5 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. C.1. C.2.1. and C.2.2 In MODE 5 or 6, or during movement of irradiated fuel

cmblies, if Required Action A.1 cannot be completed within the required Completion Time, the OPERABLE CREACUS train must be immediately placed in the emergency mode of operation. This action ensures that the remaining. train is OPERABLE, that no failures preventing automatic actuation will occur, and that any active failure will be readily detected.

An alternative to Required Action C.1 is to immediately suspend activities that could result in a release of radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes the accident risk. This does not preclude the movement of fuel :::cmblic; to a safe position. D.1 1 If both CREACUS trains are inoperable in MODE 1, 2, 3, or 4, the CREACUS may not be capable of performing the intended function and the unit is in a condition outside the accident i analyses. Therefore, LC0 3.0.3 must be entered immediately. j E.1 and E.2 When in MODES 5 or 6, or during movement of irradiated fuel i a :cmblic with two trains inoperable, action must be taken j immediately to suspend activities that could result in a i release of radioactivity that might enter the control room. i SAN ON0FRE--UNIT 2 B 3.7-60 Amendment No. 127,128 i

Fuel Storago Pool Water Level B 3.7.16 B 3.7 PLANT SYSTEMS B 3.7.16 Fuel Storage Pool Water Level BASES BACKGROUND The minimum water level in the fuel storage pool meets the assumptions of iodine decontamination factors following a fuel handling accident. The specified water level shields and minimizes the general area dose when the storage racks are filled to their maximum capacity. The water also provides shielding during the movement of spent fuel. A general description of the fuel storage pool design is given in the UFSAR, Section 9.1.2, Reference 1, and the Spent Fuel Pool Cooling and Cleanup System is given in the UFSAR, Section 9.1.3 (Ref. 2). The assumptions of the design 5 basis? fuel handling accident are given in the UFSAR, Section"15:7l4 (Ref. 3). APPLICABLE The minimum water level in the fuel storage pool meets the SAFETY ANALYSES assumptions of the fuel handling accident described in Regulatory Guide 1.25 (Ref. 4). The resultant 2 hour thyroid dose to a person at the exclusion area boundary is a j =11 fraction-ef-well@ithiC(25%IoWiehslof) the ~ ' ~ 10 CFR 100 (Ref 5)"limitsT j According to Reference 4, there is 23 ft of water between the top of the damaged fuel bundle and the fuel pool surface for a fuel handling accident. With a 23 ft water level, the i assumptions of Reference 4 can be used directly. In practice, this LC0 preserves this assumption for the bulk of the fuel in the storage racks. In the case of a single bundle, drop)ed and lying horizontally on top of the spent fuel racks,10 wever, there may be < 23 ft of water above the top of the bundle and the surface, by the width of the bundle. To offset this small nonconservatism, the analysis assumes that all fuel rods fail, although analysis shows that only the first few rods fail from a hyp[othetical 1 maxim.um drop. T_hefcons eque6bes?o _f{drbpp i'ng; a@o;n sbl idatid consequences ; o ffdropp;ofJtheNackstare il es siseverei thani the fuel? canister [onitop i ng f alfuell as sembly?overg thesel racksi assumingi72shours<decaystime:forsthetassembly?anduix monthi decayjtimej for; thef fuelj;in gheMnisteM;Theldecsyf timelof " I i (continued) I SAN ON0FRE--UNIT 2 B 3.7-68 Amendment No. 124 4

Fuel Storage Pool Water Level B 3.7.16 BASES (continued) APPLICABLEC JSiRinorithsibsf6rsTa?fdelMssbmbly?isisid9?f6Febbsolidation SAFETYFANALYSES; iallowslatil.e.ast,99[9(ofsthelradioactlyefga,se' jtoidecayf ' s (continued) ~ ' ' ' ' ' The fuel storage pool water level satisfies Criterion 3 of the NRC Policy Statement. LC0 The specified water level preserves the assumptions of the de'signtbasissfuel handling accident analysis (Ref. 3). As suh,"it"is'the minimum required for fuel storage and movementwithinthefuelstoragepool@gcask[ pool. APPLICABILITY This LC0 applies during movement of irradiated fuel

cmblic inthefuelstoragepooloffcask?poolifsincethe potential for a release of fission pPoducts*'eRists.

l Theliturm!"moVementifisstippliedstolirrsdi'atedifuelM6 SpecificationT3 7!16Hrefersito{the?movementioffirradis{ed as sembl i e s ;y(s) S fdelyrod ( s } na t parti al s fuella ss emblyiorf fuelfpellet a t compl e telfuel 2 a s sembl y; or #as sembl i e s n oc ^ con s'ol;idated i fuel nThelfuelsmovements maVibelfordany ? purpo s e Mi ncl udi ng,s butinottl imi ted s toMf0ellJ~i n s pectibiQ fue Greconstitut1on gang fuelfggnsoJidatio g ~~~ "~ ACTIONS A,_1 Required Action A.1 is modified by a Note indicating that LC0 3.0.3 does not apply. l When the initial conditions for an accident cannot be met, l steps should be taken to preclude the accident from occurring. When the fuel storage pool water level is lower than the required level, the movement of irradiated fuel assemblic: in the fuel storage pool add Maskip60131s immediately suspended. This effectiVelfirealudes a spent l fuel handling acciden_t from occurring. T11s does not precludemovinga-thejfuela:cmblytoasafeposition. 4 (continued) SAN ON0FRE--UNIT 2 B 3.7-69 Amendment No. 4 N 1 l 6 l

d Fuel Storage Pool Water Level r B 3.7.16 i i BASES ACTIONS L]. (Continued) If moving irradiated fuel c::c blics-while in MODE 5 or 6, LC0 3.0.3 would not s)ecify any action. If moving irradiated fuel 00:02:110 while in MODES 1, 2, 3, and 4, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel c::c=blic; is not sufficient reason to require a reactor shutdown. SURVEILLANCE SR 3.7.16.1 REQUIREMENTS This SR verifies sufficient fuel storage pool water is available in the event of a fuel handling accident. The water level in the fuel storage pool must be checked periodically. The 7 day Frequency is appropriate because the volume in the pool is normally stable. Water level changes are controlled by unit procedures and are acceptable, based on operating experience. During refueling operations, the level in the fuel storage pool is at equilibrium with that of the refueling canal, and the level in the refueling canal is checked daily in accordance with LC0 3.7.17, "Fuc1 Sterege Pccl Scron Cen c en t ret 4m3]9 Aj:l]RefnelpgjWsteMLevel. " petweeg! elpoolsys(fselsstorage:1poolissin DQHiig3fd61?Ebhibliditi6dMthsMsVERihlthe2Easkni6611sli ths samefasithatsintthe }keptiopenturingithoseioperations d th REFERENCES 1. .UFSAR, Section 9.1.2. 2. UFSAR, Section 9.1.3. 3. UFSAR, Section 15.7.4. 4. Regulatory Guide 1.25 5. 10 CFR 100.11. . SAN ON0FRE--UNIT 2 B 3.7-70 Amendment No. W

Fuel Storage Pool Boron Concentration B 3.7.17 B 3.7 PLANT SYSTEMS B 3.7.17 Fuel Storage Pool Boron Concentration BASES BACKGROUND As described in LC0 3.7.18, " Spent Fuel A::cmbly Storage," fuelfii c::cmblic: cre stored in the spent fuel racks in acco'rdance with criteria based on initial enrichment and discharge uurnup. Although the water in the spent fuel pool is normally corated to a 1850 ppm, the criteria that limit the storage of a fuel assembly to s)ecific rack locations is conservatively developed without ta(ing credit for boron. Additionall hwithThiminim0m?l850ippm?b6fohM6ndentthtionsin thel:poolL::(allowingiSO ppm measurementL dncertainty)JandEthe^ _ Region II racks!1oaded with:cfuelithat(nteetsithe' storage' ' cri t e ri a i o f; Techn i ca14 Sp eci fi c at i o n l 3. 71183:k s e f f! i sj l e s s than 0.95Jfor a' consolidated l fuel;(canisterimisp~ositionedlin the1Regi_on)IIiracks?" ~ ~ '~' ' ~ Duri ng" fuel Tdorisbl i dati dnIiii!the~c as kjool kc red i tIi s? take n forsthefininimum boronTconcentiationfin thefapilicable' accident: analysis? JThereforep theiwaterlinit1elcask pbol mustibe borated tota!1850;pp~m whileifuellistpresent11nTthd casypooli ~ ~ ' " ^ ' ' ~ ^ ~ ~' APPLICABLE A fuel assembly could be inadvertently loaded into a spent SAFETY ANALYSES fuel rack location not allowed by LC0 3.7.18 (e.g., an unirradiated fuel assembly or an insufficiently depleted fuel assembly). This accident is analyzed assuming the extreme case of completely loading the fuel pool racks with unirradiated assemblies of maximum enrichment._ A consolidated!fuelmcanister:packedTsith maximumtenrichinent consol idatedifuel 'could J al so : be l i rjadvertently i mi sposi tiondd inithef Region J IITracks.': ;Thistaccident:11s s also? analyzed a An oth e F typ'e"o f~ po s t ul ated " acc i dent ~ i s*a s s'o'c i ated ^wi t h~ a' fuel assembly drJ a cons 611datedifuel3 ca'nister?that is c dropped onto the" fully'16aded" fuel" Tool" storage rack. Postui ated accidentst associatedTWi t Cfuel Tc6nsolidation~ in the cask pool:havejlesser consequencesTthansthose'::forithe' preceding accidentsibecause"of theilimited 'amountlofifuel all owed : 1 n : theicas k : pool Eand e the? requi red decay; timetofisi k monthsLprior to fueleconsolidationn HEithdr' Howeverb anysone of these li'ncidents"could' have"a~ positive readtivity effect,~ decre' sing the margin to criticality. However, tThe a negative reactivity effect of the soluble boron c6mpensates for the increased reactivity caused by cither one of the diffeFent~twe-postulated accident scenarios. (continued) SAN ON0FRE--UNIT 2 8 3.7-71 Amendment No. -lN

i Fuel Storage Pool Baron Concentration B 3.7.17 BASES APPLICABLE The concentration of dissolved boron in the fuel pool SAFETYzANALYSES satisfies Criterion 2 of the NRC Policy Statement. (continued) LCO The specified concentration of dissolved baron in the fuel pool preserves the assumptions used in the analyses of the potential accident scenarios described above. This concentration of dissolved boron is the minimum required concentration for fuel consolidationsini;the7 cask 0poolfahd fu'elas:cmbly storage and movement'WithiYthrfuel hbor. APPLICABILITY This LC0 applies whenever fuel isas:cmblics are stored in the spent fuel pool until a complete spent fuel pool verification has been performed following the last movement of fuel

cmblic in the spent fuel pool.

This LC0 does not apply following the verification since the verification would confirm that there aeeis no misloaded fuel

cmblics.

With no further fuel

cmbly^ movements in progress, there is no potential for a misloaded fucl

cmbly or a dropped fuel assemblygfdelNanist'erfor?fde1[b'asket.

Th i's ? LCO ?al solkppl i.esj whenifdel[consol id atio#1(" fubl mo vement" )fi s ? i n[progres s ?i nithe : c as k[ppoli ~ ACTIONS A.l. A.2, and A.3 l The Required Actions are modified by a Note 11 indicating that LC0 3.0.3 does not apply a6dlNots129estrictinciths applicability; _offActionTA.222 When the concentration of boron in the spent fuel pool is less than required, immediate action must be taken to preclude an accident from happening or to mitigate the consequences of an accident in progress. This is most efficiently achieved by immediately suspending fu'el cohsolida'tiodTandithe movement of fuel

cmblins.

This doss ~n'ot~ pre'clude"the movement of fuel

cmblic to a safe position.

In addition, action must be immediately initiated to restore boron concentration to within limit. ]gontinuydj SAN ONOFRE--UNIT 2 8 3.7-72 Amendment No. 4 N

Fuel Storage Pool Boron Concentration B 3.7.17 i BASES 1 l ACTIONS A.1. A.2, and A.3 (continued) I j Alternately, jiHbBtdysssmitiy3bipsndsdifselini5Vsmeht5th the3pentifuel E pool M an~i mmid i at e*V&i fiufi ali^, " by" ' ~ l hdininistFit'inmeiss; of the fuel storage pool fuel locations, to ensure proper locations of the fuel since the l last movement of fuel

c=blic in the fuel storage pool, can be performed.

If moving irradiated fuel :::::blics while in MODE 5 or 6, LC0 3.0.3 would not specify any action. If moving irradiated fuel

blics while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation.

Therefore, inability to suspend movement of fuel

blic:

is not sufficient reason to require a reactor shutdown. SURVEILLANCE SR 3.7.17.1 REQUIREMENTS This SR verifies that the concentration of boron in the spent fuel pool is within the required limit. As long as this SR is met, the analyzed incidents are fully addressed. The 7 day Frequency is appropriate because no major replenishment of pool water is expected to take place over a short period of time. l During)!fue1[sonsolidati6nNtheib6ronit6nfentpatf6Sinithi c e e ep n g oji l PPerations; i REFERENCES 1. UFSAR, Section 9.1. l l l I. j l SAN ON0FRE--UNIT 2 B 3.7-73 Amendment No. W

{ Spent Fuel A;;cably Storage B 3.7.18 4 B 3.7 PLANT SYSTEMS i l B 3.7.18 Spent Fuel A::c=bly Storage i BASES I BACKGROUND Thespentfuelstoragefacilityisdesignedtostoreeither i new (nonirradiated) nuclear fuel :::c b.ics, or burned ] (irradiated) fuel es:cablic; in a vertical. configuration 4 underwater. The storage pool is sized to store 1542 fuel I as s hmbl i'e s h(totaUi si thohtistof ajiIoff ddniol id atedifdhlorf 2867/f assemblies 7 3 consol i dat ed ifdel fassembl i es'. Tw6* typ s i/s i"zh f"o f"s pen t"fd s1 'st6 rag 6~ tacks"are"Us6d~"(Redion I and Region II). The two Region I racks each contain 156 storage locations each spaced 10.40 inches on center in a 12x13 array. The six l Region II storage racks contain 210 storage locations in a 14x15 array. The remaining two Region II racks contain 195 locations in a 13x15 array. All locations are spaced 8.85 inches on center. This spacing and " flux trap" construction, whereby the fuel assembliesMfselid'ahfiteFiT6F fuelibaiketi5are inserted into neutron absoibing"stainisss" 4 st'eWdn'Cis sufficient to maintain a k [, of :s 0.95 for spent fuel of original enrichment of up tE 4.1%.

However, as higher initial enrichment fuel 15 ::::blic: are stored in the spent fuel pool, jteey must bs' stored in a checkerboard pattern taking into account fuel burnup to maintain a k,ff of 0.95 or less.

APPLICABLE The spent fuel storage facility is designed for and " flux trap" noncriticality by use of adequate s) acing,fdel?'Einihtersfoh SAFETY ANALYSES construction whereby the fuel assem)11esW ~ tesl^ cans'; ]are inserted into neutron absb'rbing"stairiless' fuslThisketi s The spent fuel assembly storage satisfies Criterion 2 of the NRC Policy Statement. LC0 The restrictions on the placement of fuel

c blic; within the spent fuel pool, cccrding to Figurc 3.7.181 and Figurc 3.7.18 2, in the accompanying LCO, ensures that the k,ff of the spent fuel pool will always remain < 0.95 assuming the pool to be flooded with unborated water.

The restrictions are consistent with the criticality safety analysis performed for the spent fuel pool according tolths; LCO) Figurc 3.7.18 1 and Figurc 3.7.18 2, in the-(continued) SAN ON0FRE--UNIT 2 B 3.7-74 Amendment No. 4 N

i l Spent Fuel A;;cmbly Storage B 3.7.18 BASES i LC0 accompanying LCO. Fuel ;;;cmblic not meeting the criteria (continued) sf Figure 3.7.18 1 and Figurc 3.7.18 2 LCOshall be stored in accordance with Lic'en eelControlledjSpe' ification 4.3.1.1 s c 4;0.100. ~ ( l APPLICABILITY This LCO applies whenever any fuel a;;cmbly is stored in Region II of the spent fuel pool. l l ACTIONS atl Required Action A.1 is modified by a Note indicating that LCO 3.0.3 does not apply. When the configuration of fual

cmblic; stored in Region II of the spent fuel pool is not in accordance with l

l Figure 3.7.18-1 orand Figure 3.7.18-2, immediate action must be taken to make~ the necessary fuel assembly-movement (s) to I bring the configuration into compliance with Figure 3.7.18 1 andFigurc3.7.182(theiLCO. 1 If moving irradiated fuel

cmblic; while in MODE 5 or 6, LCO 3.0.3 would not specify any action.

If moving l irradiated fuel c;;cmblic; while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation. Therefore, in either case, inability to move fuel as cmblic: is not sufficient reason to require a reactor shutdown. SURVEILLANCE SR 3.7.18.1 REQUIREMENTS This SR verifies by administrative means that the initial enrichment and burnup of the fuel assembly is in accordance with Figurc 3.7.18 1 and Fi urc 3.7.18 2 in the accompanying LCO ? p ri. ort t o Ts tori ng it he :sfu e1 [a s s embl y Efe el ?c arii s t e r Ror fuel,baskettin :RegionVII. ^ Fo'r^ fuel ~cs:6mblierirFthe-l un' acceptable range'ofithe LCO Figurc 3.7.181 and Figure l 3.7.18 2, performance ~of"this SR will ensure compliance with l Specification 4.3.1.1?;0T100. j i l l REFERENCES UFSAR, Section 9.1.2.2. 1 l l SAN ON0FRE--UNIT 2 B 3.7-75 Amendment No. 147 l

CREACUS B 3.7.11 BASES APPLICABILITY In MODES 1, 2, 3, and 4, the CREACUS must be OPERABLE to limit operator exposure during and following a DBA. In MODES 5 and 6, the CREACUS is required to cope with the release from a rupture of a waste gas tank. During movement of irradiated fuel as cmblics, the CREACUS l must be OPERABLE to cope with the release from a fuel handling accident. The' term'"mciv'ement',""as applied"to' irradiated fuel 'iti Specification 3,7.11, refers to the movement of irradiated fuel pellet (s),' fuel rod (s), a partial fuel assembly or ' assemblies, a' complete fuel assembly or assemblies, or~ j consolidated fuel., The fuel movement may be for any purpose, including, but not limited to, fuel inspection l fue1' reconstitution, and fuel consolidationi ACTIONS ACTION statements are modified by two NOTES. NOTE 1 says: l "The provisions of LC0 3.0.4 are not applicable when l entering MODES 5, 6, or defueled configuration." Therefore, since CREACUS can be inoperable during each individual MODE, it should not be required to have two OPERABLE CREACUS trains before MODE change from defueled from MODE 6 to defueled configuration, and from MODE 4 to MODE 5. l Specification 3.0.4 establishes that entry into an l operational mode or other specified condition shall not be l made unless the conditions of the LC0 are met. l l Applicability statement "During movement of irradiated fuel I assemblics" ensures the OPERABILITY of both CREACUS trains prior to the start of movement of irradiated fuely encmbl ics. NOTE 2 says: "Each Unit shall enter applicable ACTIONS separately." CREACUS is a shared system between Unit 2 and Unit 3. LC0 doesn't address the operational situation when the Units are in different operational MODES. Without this NOTE it may not be clear what ACTIONS should be taken. l A.1 With one CREACUS train inoperable, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE CREACUS subsystem is adequate to perform control room radiation protection function. l SAN ON0FRE--UNIT 3 B 3.7-59 Amendment No. 116,117 l

CREACUS B 3.7.11 ) BASES ACTIONS However, the overall reliability is reduced because a single (continued) failure in the OPERABLE CREACUS train'could result in loss of CREACUS function. The 7 day Completion Time is based on the low probability of a DBA occurring during this time period, and the ability of the remaining train to provide the required capability. 8.1 and 8.2 If the inoperable CREACUS cannot be restored to OPERABLE status within the required Completion Time in MODE 1, 2, 3, or 4, the unit must be placed in a MODE that minimizes the accident risk. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 5 within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. C.1. C.2.1. and C.2.2 In MODE 5 or 6, or during movement of irradiated fuel c;;cablic:, if Required Action A.1 cannot be completed' within the required Completion Time, the OPERABLE CREACUS train must be immediately placed in the emergency mode of operation. This action ensures that the. remaining train is OPERABLE, that no failures preventing automatic actuation will occur, and that any active failure will be readily detected. An alternative to Required Action C.1 is to immediately suspend activities that could result in a release of radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes the accident risk. This does not preclude the movement of fuel c :::blic: to a safe position. l El If both CREACUS trains are inoperable in MODE 1, 2, 3, or 4, the CREACUS may not be capable of performing the intended function and the unit is in a condition outside the accident analyses. Therefore, LC0 3.0.3 must be entered immediately. i I I SAN ON0FRE--UNIT 3 8 3.7-60 Amendment No. 115,117

CREACUS B 3.7.11 BASES ACTIONS E.1 and E.2 (continued) When in MODES 5 or 6, or during movement of irradiated fuel

=blic; with two trains inoperable, action must be taken immediately to suspend activities that could result in a release of radioactivity that might enter the control room.

I I i I SAN ON0FRE--UNIT 3 8 3.7-60a Amendment No. 146

Fuel Storage Pool Water Level 8 3.7.16 B 3.7 PLANT SYSTEMS B 3.7.16 Fuel Storage Pool Water Level BASES BACKGROUND The minimum water level in the fuel storage pool meets the assumptions of iodine decontamination factors following a fuel handling accident. The specified water level shields and minimizes the general area dose when the storage racks l are filled to their maximum capacity. The water also provides shielding during the movement of spent fuel. i A general description of the fuel storage pool design is given in the UFSAR, Section 9.1.2, Reference 1, and the Spent Fuel Pool Cooling and Cleanup System is given in the UFSAR, Section 9.1.3 (Ref. 2). The assumptions of the i de'signi:bsifsilfuel handling accident are given in the UFSAR, Sedti6d"15~;774 (Ref. 3). APPLICABLE The minimum water level in the fuel storage pool meets the SAFETY ANALYSES assumptions of the fuel handling accident described in Regulatory Guide 1.25 (Ref. 4). The resultant 2 hour thyroid dose to a person at the exclusion area boundary is--a =11 fracticn of?we11Nithiss(~25%f6rGTeisi~ of) the i ^ ~ ~ " ~ * ~ l 10 CFR 100 (Ref. 5) TNit5T"" According to Reference 4, there is 23 ft of water between the top of the damaged fuel bundle and the fuel pool surface for a fuel handling accident. With a 23 ft water level, the i assumptions of Reference 4 can be used directly. In practice, this LC0 preserves this assumption for the bulk of the fuel in the storage racks. In the case of a s' ingle bundle, dropped and lying horizontally on top of the spent fuel racks, however, there may be < 23 ft of water above the top of the bundle and the surface, by the width of the bundle. To offset this small nonconservatism, the analysis assumes that all fuel rods fail, although analysis shows that only the first few rods fail from a hypothetical l idats;d maximum drop.fMhdiconisi uindes?6fidpoppfhgfiNohsbllhnithe i fuelicanistetonytoploff theirackseareiless severesth consequencesioff droppi.n'giatfdelfas'sembly"o;verithesei racksi j As s unsi nf724odFs(decayitinisifos ths3ssssmblyfahd ss ixP moh th s decayjtjme Mo M hetfue Mi M h y shistb Q hejdecag timf @ f I l (continued) SAN ON0FRE--UNIT 3 B 3.7-68 Amendment No. 4 M 1

Fuel Storage Pool Water Level B 3.7 16 BASES (Continued) APPLICABLEE..., Esikfii6 nth'ssbef6reiEfu61?iss#mblyMiWesdfif6WEosibliditIdd SAFETYJA.NALYSESi jallows[atgeasg99j9%jofsthegadi.osctije[giseytofd6 cay {~ (continued) The fuel storage pool water level satisfies Criterion 3 of ^ ^ ~ ~ the NRC Policy Statement. LC0 The specified water level preserves the assumptions of the 5bisitifuel handling accident analysis (Ref. 3). As ds'siin.,g..W~the minimum required for fuel storage and g movement within the fuel storage poolfogyasiQpool.. APPLICABILITY This LC0 applies during movement of irradiated fuel

blic; in the fuel storage pool p$VisR~po61Msince the potential for a release of fission proddcts exists.

The' term " movement," as^ applied to irradiated fuer in Specification 3,7.16,, refers to the movement of irradiated fuel pellet (s), fuel rod (s), a partial fuel assembly or ' ' assemblies', a complete fuel assembly or assemblies, or ~ consolidated fuel. The fuel movement may be for any' purpose, including, but not limited to, fuel inspec,tio'n'{ fuel reconstitution,,and fuel consolidation.'""' ACTIONS A.1 Required Action A.1 is modified by a Note indicating that l LCO 3.0.3 does not apply. l When the initial conditions for an accident cannot be met, l steps should be taken to preclude the accident from l occurring. When the fuel storege pool water level is lower I than the required level, the movement of irradiated fuel

cmblic in the fuel storage pool ahdgibigiiooljis immediately suspended. This effectiVsly precludes a spent fuel handling accident from occurring. This does not preclude moving e-phsyfuel as:c bly to a safe position.

i i i f SAN ON0FRE--UNIT 3 B 3.7-69 Amendment No. 4 M

Fuel Storage Pool Water Level B 3.7.16 BASES ACTIONS A.1 (Continued) If moving irradiated fuel a;;cmblic; while in MODE 5 or 6, LC0 3.0.3 would not specify any action. If moving irradiated fuel as:cmblic while in MODES 1, 2, 3, and 4, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel as:cmblic; is not sufficient reason to require a reactor shutdown. SURVEILLANCE .S R 3.7.16.1 REQUIREMENTS This SR verifies sufficient fuel storage pool water is available in the event of a fuel handling accident. The water level in the fuel storage pool must be checked periodically. The 7 day Frequency is appropriate because the volume in the pool is normally stable. Water level changes are controlled by unit procedures and are acceptable, based on operating experience. During refueling operations, the level in the fuel storage pool is at equilibrium with that of the refueling canal, and the level in the refueling canal is checked daily in accordance with LCO 2.7.17, "Fucl Storage Poc1 Scron Concentration."3:9;6f"Refseling; Water]l.evelU DuringTfuel~::' con' sol idation? the:Revellinf th'e3askfl cal;?;i6ths i between1the;poolskishkgppoppn;duringjthose3operati_tel same' as zthatLin the6fuelf storage Jpoolnsincel:!the Lga onst REFERENCES 1. UFSAR, Section 9.1.2. l 2. UFSAR, Section 9.1.3. 3. UFSAR, Section 15.7.4. 4. Regulatory Guide 1.25 1 5. 10 CFR 100.11. I SAN ONOFRE--UNIT 3 B 3.7-70 Amendment No. -146

fuel Storage Pool Boron Concentration B 3.7.17 B 3.7 PLANT SYSTEMS B 3.7.17 Fuel Storage Pool Boron Concentration BASES BACKGROUND As described in LC0 3.7.18, " Spent Fuel A::cmbly Storage," fuelsis a;;cmblic are-stored in the spent fuel racks in acco'rdance with criteria based on initial enrichment and discharge burnup. Although the water in the spent fuel pool is normally borated to a 1850 ppm, the criteria that limit the storage of a fuel assembly to s)ecific rack locations is conservatively developed without ta(ing credit for boron. - Additi onal19,1 with 1ai mi' i_msm ;:1850 < ppmL boron 7cohcentration ifih n the pool L(allowing:L50. ppm measurementluncertainty)iandithe" Region <II;; racks 11caded with fuel;;.that?meetsstheistorage._ cri ter i a ? o f fTechni c al i Speci fi cati on;13). 7%.186(kf e f f.!;i s11.e~s s _. than"0.95Lforca consolidated fuel canisterfmispositionedsin the 'Re'gion);-IIirack'sl Du ri rinfu el1"coYis ol i d a ti onVi nTtheTai k?pbo1 M c red i t Ti sita ke n forsthelminimum' boron concentration (in atheLapilicable" accident 1 analysis.JfThereforedtheNater$inytleicask1001 mustibef borateds toLa(1850;ppmlwhileitfueMisjpresentiintthe ~ g; .. ~. ~ APPLICABLE A fuel assembly could be inadvertently loaded into a spent SAFETY ANALYSES fuel rack location not allowed by LCO 3.7.18 (e.g., an unirradiated fuel assembly or an insufficiently depleted fuel assembly). This accident is analyzed assuming the extreme case of completely loading the fuel pool racks with unirradiated assemblies of maximum enrichment. A consolidated 1fdel 3 cani ster" packed. with: maximum -. enri chm _ent. cons ol i d at ed.;f uel ic o ul d Eal s o ; be ? i n'ad verten t lyimi s p o si ti 6n dd in the': Region 5:II.;racksi;This; accident <is?alsosanalyzed ~ Another~ type offpostulated accident"is" associated with"a ~ fuel assembly or a consolidatedsfuelicaniste6that is dropped onto the" fully ^ loaded ^ fuel ~ )oo1* storage rack. PostulatedLaccidentsEass6ciated wit 6fueliconsolidat16niin the' cask ~ pool &have lesser consequenceslthan"thoseiforithe~ preceding accidents!because;of theylimitedt amountSofifuel allowed fin theicask::poolLand the-' required; decay;timeioffsix monthse priorsto fuel consolidation.s Either However;dffedt, nany one ofsthese? incidents'could"hase"t pos'itive reaEtivity decreasing the mafgin to criticality. Mcwever, tThe negative reactivity effect of the soluble baron compensates for the increased reactivity caused by Mther cr.c cf the different} he-postulated accident scenarios. (continued) SAN ON0FRE--UNIT 3 B 3.7-71 Amendment No. 4%

Fuel Storage Pool Boron Concentration B 3.7.17 BASES APPLICABLE The concentration of dissolved boron in the fuel pool SAFETYiANALYSES satisfies Criterion 2 of the NRC Policy Statement. ]continueQ LCO The specified concentration of dissolved boron in the fuel pool preserves the assumptions used in the analyses of the potential accident scenarios described above. This concentration of dissolved boron is the minimum required concentration for fuel horisolidsti6niin^theiciskip6olTand fuel a s:cmbly storage and"'nieVessnt"Wi thin'thTf0El y6ol. 1 APPLICABILITY This LC0 applies whenever fuel isas:cmblic cre stored in l the spent fuel pool until a complete spent fuel pool l verification has been performed following the last movement of fuel as:cmblic; in the spent fuel pool. This LC0 does i j not apply following the verification since the verification would confirm that there ;isen no misloaded fuel-assemblics. t With no further fuel as:cinbly movements in progress, there is no potential for a misloaded fuel :::cmbly or a dropped fuel assemblyMf66c?cssi.s. te6~T6E7fd_el!bhskht.. 1 s a ~~ n l Thi s? LC0T al16f appl fist %e6Tfsel Wohiol id sti d6f"( " f U el l moveme n tg i s?lii n;ppig re s s(i nit hel e ss k5001 f ACTIONS A.l. A.2 and A.3 The Required Actions are modified by a Note Bindicating that LCO 3.0.3 does not applyEahdfhiNote?2Restritti@jthe MPl;i;bsb;il i gof7 fact;i o nIA(2!2 ' When the concentration of boron in the spent fuel pool is less than required, immediate action must be taken to preclude an accident from happening or to mitigate the consequences of an accident in progress. This is most efficiently achieved by immediately suspending fubl i conso11dationiandQthe movement of fuel assemblics. This does'nat"pfsslude the movement of fuel as:cmblic; to a safo position. In addition, actior, must be immediately initiated to restore boron concentration to within limit. i f (continued) SAN ON0FRE--UNIT 3 B 3.7-72 Amendment No. 4M I I 1 l t

Fuel Storage Pool Boron Concentration B 3.7.17 i BASES ACTIONS A.l. A.2. and A.3 (continued) Alternately, iiHoEt6WeismihhTssspindsdi?fdeMsdVissntY~id Edst n i s ffit i yb*po61 Waif" lisid i s f6*viFi fIEit iMjl ' by~^'~ thsfsiidht2fuelinisins; of the fuel storage pool fuel locations, to ensure proper locations of the fuel since the last movement of feel :::ceblic in the fuel storage pool, can be performed. If moving irradiated fuel

c=blic; while in MODE 5 or 6, LC0 3.0.3 would not specify any action.

If moving irradiated fuel

blic while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation.

Therefore, inability to suspend movement of fuel

c=blic is not sufficient reason to require a reactor shutdown.

SURVEILLANCE SR 3.7.17.1 REQUIREMENTS This SR verifies that the concentration of boron in the spent fuel pool is within the required limit. As long as this SR is met, the analyzed incidents are fully addressed. The 7 day Frequency is appropriate because no major replenishment of pool water is expected to take place over a short period of time. DQFing?fd61?Eodsplidsti365thilb6F66"EdhEshtFs;tidnitiilthi pas k ? p oolM s st hes s ame lasit hatFinit hsifesWs toragej po;oM" l sinsesthelgat {betwe gjthhj@ g is{kpgtj y snidupl1 @ $h6si ppera.tigsj l REFERENCES 1. UFSAR, Section 9.1. l l l l 4 1 SAN ON0FRE--UNIT 3 B 3.7-73 Amendment No. 146 i

l Spent Fuel A::cmbly Storage B 3.7.18 B 3.7 PLANT SYSTEMS B 3.7.18 Spent Fuel A;;cmbly Storage BASES BACKGROUND Thespentfuelstoragefacilityisdesignedtostoreeither new (nonirradiated) nuclecr fuel es:cmb.ics, or burned (irradiated) fuel c::cmblic in a vertical configuration underwater. The storage. pool is sized to store 1542 fuel assembl,ies[(ore 2857t6tal)7Without stb'Fspefbf7ddnsol._idatedifUel ponsol i dat edg~ nel@s fuel e a]s s embl i assembliesp ssembli es ~ Two^ types /s i zs5 "of"s isnt* fusi l storage'~ racks are~used (Rsgion I and Region II). T1e two Region I racks each contain 156 storage locations each spaced 10.40 inches on center in a 12x13 array. The six Region II storage racks contain 210 storage locations in a 14x15 array. The remaining two Region II racks contain 195 locations in a 13x15 array. All locations are spaced 8.85 inches on center. This spacing and " flux trap" construction, whereby the fuel assemblies?"fdelfE'snistsisl ~~ oRfdelibisketsiare inserted into neutron"'sbsorbing" stainisss"stesl' cans, is sufficient to maintain a k of 5 0.95 for spent fuel of original enrichment of up Yo 4.1%. However, as higher initial enrichment fuel ;isasemblic cre stored in the spent fuel pool, jtthey must bs stored in a checkerboard pattern taking into" account fuel burnup to maintain a k,ff of 0.95 or less. APPLICABLE The spent fuel storage facility is designed for , and " flux trap" noncriticality by use of adequate spacing $fdelidahisteFsMot SAFETY ANALYSES construction whereby the fuel assembliesi fde13 baskets are inserted into neutron abs 0rbihcj"st'ainidss" steel ~dsnst' The spent fuel assembly storage satisfies Criterion 2 of the NRC Policy Statement. LC0 The restrictions on the placement of fuel c::cmblic; within the spent fuel pool, cccording to Figurc 3.7.181 cnd Figurc 3.7.18 2, in the accompanying LCO, ensures that the i k,ff of the spent fuel pool will always remain < 0.95 assuming the pool to be flooded with unborated water. The restrictions are consistent with the criticality safety analysis performed for the spent fuel pool according to thi LC0} Figurc 3.7.18 1 cnd Figure 3.7.18 2, in the (continued) SAN-0N0FRE UNIT 3 B 3.7-74 Amendment No. F14

Spent Fuel A::cably Storage B 3.7.18 BASES l LCO accompanying E 0. Fuel

blic: not meeting the criteria (continued) cf Figurc 3.7.181 and Figure 3.7.18-0-LCO?shall be stored l

in accordau with Licens_selControllediSpscification

4. 3.1.1E4f 0,!100.

~ ~ =~ APPLICABILITY This LC0 applies whenever any fuel

cably is stored in Region II of the spent fuel pool.

l ACTIONS .A_d Required Action A.1 is modified by a Note indicating that LC0 3.0.3 does not apply. When the configuration of fuel

cablic; stored in Region II of the spent fuel pool is not in accordance with J

Figure 3.7.18-1 6tand Figure 3.7.18-2, immediate action must be taken to make'the necessary fuel

cably movement (s) to bring the configuration into compliance with Figure 3.7.18 1

nd Figure 3.7.14-QhplCO.

If moving irradiated fuel :::c:Mics while in MODE 5 or 6, LC0 3.0.3 would not s)ecify any action. If moving irradiated fuel

cm:lics-while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation.

Therefore, in either case, inability to move fuel

cablic is not sufficient reason to require a reactor shutdown.

SURVEILLANCE SR 3.7.18.1 REQUIREMENTS This SR verifies by administrative means that the initial enrichment and burnup of the fuel essemMy-is in accordance with Figure 3.7.18 1 and Fi urc 3.7.13 2 in the accompanying LC0 !p r;iorstOs t ori ngi t he f f0e17a s s embl y fuel? canister 1 fudl e ba s ketti n'i Re'g i on s I I T ^ Fo f"fu er*d :%sbl i 5 s ~ir t he~,lio

5 un's6beptable7snge"of* the3LC0; Figure 3.7.181 and Figure 3.7.10 2, performance of' th~is SR will ensure compliance with Specification 4.3.1.1M0fl00.

REFERENCES UFSAR, Section 9.1.2.2. I I i SAN-0N0FRE UNIT 3 B 3.7-75 Amendment No. -146 1 I r

J i l i 1 l l l i i 4 1 ] ATTACHMENT I UNIT 2 AMENDMENT NOS. 127/128 AND UNIT 3 AMENDMENT NOS. 116/117 APPROVED BASES AS REVISED BY PCN-443 AND PCN-449 (for information only) l l

l l i l l l NOTE TO ATTACHMENT I PCN-443 changes to the Units 2 and 3 Bases as shown in this attachment include certain changes not related to fuel consolidation and storage. Most of these changes are editorial corrections or clarifications that are self-explanatory. Also included are the three changes described below. 1-In B 3.7.16, under BACKGROUND and LCO, the term " fuel handling accident" is changed to " design basis fuel handling accident," which is more accurato. 2-In B 3.7.16, under APPLICABLE SAFETY ANALYSES, it is presently stated: "The resultant 2 hour thyroid dose to a person at the exclusion area boundary is a small fraction of the 10 CFR 100 (Ref. 5) limits." The phrase "a small fraction of" is changed to "well within (25% or less of)." This change is consistent with the guidance provided in Section 15.7.4 of the Standard Review Plan (NUREG-0800). Section 15.7.4 of NUREG-0800 defines "well within" as "25 percent or less of the 10 CFR Part 100 exposure guideline values, i.e., 75 rem for the thyroid and 6 rem for the whole-body doses." 3-In B 3.7.16, under SURVEILLANCE REQUIREMENTS, an incorrect citation for the LC0 that contains Refueling Water Level requirements is corrected. I l

l CREACUS l l B 3.7.11 l BASES APPLICABILITY In MODES 1, 2, 3, and 4, the CREACUS must be OPERABLE to limit operator exposure during and following a DBA. In MODES 5 and 6, the CREACUS is required to cope with the release from a rupture of a waste gas tank. During movement of irradiated fuel :::cmblic, the CREACUS l must be OPERABLE to cope with the release from a fuel handling accident. ThsitWmWm6Vementi"fiEippl i edito$ p?id iatsd ifdelglii S pec i fi cat i on? 3 :7111Mrefers tt o st helmoVemen tlof41 rradi atsd s:onsolidatedsfdelW1Theifuel?movementMiy/belforia'ny ('a s s em )1 i e s st( al)MfuelWod (s ) Ma?part i alifueMa s s embly @rP fue10 ellet s completeifueltassembly W Nassembiies Mo l purp'oseMinclsdingij b'ut(notslimitedits$fuellinspectMh? ^~~ fuelyecon sti t ut i o ngand ifuel[ con ~ s ol i.d atj ony ~ ACTIONS ACTION statements are modified by two NOTES. NOTE 1 says: "The provisions of LC0 3.0.4 are not applicable when l entering MODES 5, 6, or defueled configuration." Therefore, l since CREACUS can be inoperable during each individual MODE, j it should not be required to have two OPERABLE CREACUS trains before MODE change from defueled from MODE 6 to defueled configuration, and from MODE 4 to MODE 5. Specification 3.0.4 establishes that entry into an operational mode or other specified condition shall not be made unless the conditions of the LCO are met. Applicability statement "During movement of irradiated fuel

cmblics" ensures the OPERABILITY of both CREACUS trains prior to the start of movement of irradiated fuel?

~ = 0 dlics. NOTE 2 says: "Each Unit shall enter applicable ACTIONS separately." CREACUS is a shared system between Unit 2 and Unit 3. LC0 doesn't address the operational situation when the Units are in different operational MODES. Without this NOTE it may not be clear what ACTIONS should be taken. 8.d With one CREACUS train inoperable, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE CREACUS subsystem is adequate to perform control room radiation protection function. However, the overall reliability is reduced because a single failure in the OPERABLE CREACUS train could result in loss of CREACUS function. The 7 day Completion Time is based on q SAN ON0FRE--UNIT 2 B 3.7-59 Amendment No. 127,128

CREACUS B 3.7.11 BASES l ACTIONS A.1 (Continued) (continued) the low probability of a DBA occurring during this time period, and the ability of the remaining train to provide the required capability. B.1 and 8.2 If the ino)erable CREACUS cannot be restored to OPERABLE status wit 11n the required Completion Time in MODE 1, 2, 3, or 4, the unit must be placed in a MODE that minimizes the accident risk. To achieve this status, the unit must be l placed in at least MODE 3 within 6 hours, and in MODE 5 l within 36 hours. The allowed Completion Times are reasonable, based on operating experience, to reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems. C.l. C.2.1 and C.2.2 In MODE 5 or 6, or during movement of irradiated fuel as:cablics, if Required Action A.1 cannot be completed within the required Completion Time, the OPERABLE CREACUS train must be immediately placed in the emergency mode of operation. This action ensures that the remaining train is OPERABLE, that no failures preventing automatic actuatior, will occur, and that any active failure will be readily i detected. l An alternative to Required Action C.1 is to immediately suspend activities that could result in a release of radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes l the accident risk. This does not preclude the movement of L fuel

cmblic; to a safe position.

U If both CREACUS trains are inoperable in MODE 1, 2, 3, or 4, f the CREACUS may not be capable of performing the intended function and the unit is in a condition outside the accident analyses. Therefore, LC0 3.0.3 must be entered immediately. SAN ONOFRE--UNIT 2 B 3.7-60 Amendment No. 4 N

CREACUS B 3.7.11 l BASES i l i ACTIONS E.1 and E.2 l (continued) When in MODES 5 or 6, or during movement of irradiated fuel

=,blic; with two trains inoperable, action must be taken l

immediately to suspend activities that could result in a release of radioactivity that might enter the control room. 1 i f i l l l l l l l l i l l l l i l \\ l l SAN ONOFRE--UNIT 2 B 3.7-60a Amendment No. 4 W j i j

Fuel Storage Pool Water Level B 3.7.16 i L B 3.7 PLANT SYSTEMS i ) B 3.7.16 Fuel Storage Pool Water Level l l BASES BACKGROUND The minimum water level in the fuel storage pool meets the assumptions of iodine decontamination factors following a fuel handling accident. The specified water level shields and minimizes the general area dose when the storage racks are filled to their maximum capacity. The water also provides shielding during the movement of spent fuel. I A general description of the fuel storage pool design is given in the UFSAR, Section 9.1.2, Reference 1, and the Spent Fuel Pool Cooling and Cleanup System is given in the UFSAR, Section 9.1.3 (Ref. 2). The assumptions of the d6signibliis? fuel handling accident are given in the UFSAR, S6ctio P157774 (Ref. 3). APPLICABLE The minimum water level in the fuel storage pool meets the SAFETY ANALYSES assumptions of the fuel handling accident described in Regulatory Guide 1.25 (Ref. 4). The resultant 2 hour thyroid dose to a person at the exclusion area boundary is-a =11 frnti= cfNellHiiithis?(25CbElsiffbf) the 10 CFR 100 (Ref. 5)'^TimitC " ~"~~""" According to Reference 4, there is 23 ft of water between the top of the damaged fuel bundle and the fuel pool surface for a fuel handling accident. With a 23 ft water level, the assumptions of Reference 4 can be used directly. In practice, this LC0 preserves this assumption for the bulk of the fuel in the storage racks. In the case of a single bundle, dropaed and lying horizontally on top of the spent fuel racks, lowever, there may be < 23 ft of water above the top of the bundle and the surface, by the width of the bundle. To offset this small nonconservatism, the analysis assumes that all fuel rods fail, although analysis shows that only the first few rods fail from a hypothetical max i mum. d ro p.._ Thefc6nsequencis"o fj^droppi ng [a3on fol idjtid fue1 canister;onitopfoffthe>rackstarehless;;severejthan3the 4 consequences;off droppingfaifuelf assembly?oveythesewacksi _ assumingJ25 hours:(decay; time:forstherassemblygandjsixymonths, dpayMime;;fopthefuelginjthetcani,stegpThefecgtimegf d g l (continued) l SAN ON0FRE--UNIT 2 B 3.7-68 Amendment No. 4 W

i i Fuel Storage Pool Water Level B 3.7.16 BASES (continued) I APPLICABLEL.^. Isi bsonths? be foFeiO fueltasssinbly sisTrdidf7foUt6n sol idati on SAFETYTANALYSESilallowsisatileasM9919%:ofitheitadioictiVeigasesStoidsdsyF '~" ~ ~~ "' ~ ~ ~ ^ ~ ~ ' ~ ~ ~ ~ ~ ~ " ~ '

~ ' " * ^ ~ ^ '

'(c_ontinued)~ ~~ The fuel storage pool water level satisfies Criterion 3 of the NRC Policy Statement. LC0 The specified water level preserves the assumptions of the designibaMDfuel handling accident analysis (Ref. 3). As he ~h^the minimum required for fuel storage and movementwithinthefuelstoragepool@$yaskippbl. APPLICABILITY This LC0 applies during movement of irradiated fuel

cmblic; in the fuel storage pool opdasklijo61gsince the potential for a release of fission product ~5"ekist's.

The term " movement,'" as applied to' irradiated fuel in Specification 3.7.16, refers to the movement of irradiated fuel )ellet(s), fuel rod (s), a partial fuel assembly or ~'^ assem> lies, a complete fuel assembly or assemblies, or' consolidated fuel. The fuel movement may be for 'any" purpose, including,',but not limited to, fuel inspection ^l fu,el. reconsti.t,ution,, and fuel consolidation., i ~ l ACTIONS A.1 i Required Action A.1 is modified by a Note indicating that LC0 3.0.3 does not apply. When the initial conditions for an accident cannot be met, l steps should be taken to preclude the accident from l occurring. When the fuel storage pool water level is lower than the required level, the movement of irradiated fuel in the fuel storage pool andscasKTpbol;s a spent is

cmblic This effectiVEli~dbtTsde I

immediately suspended. fuel handling accident from occurring. T11s does not f preclude moving e-the] fuel

cmbly to a safe position.

i i (continued) i SAN ON0FRE--UNIT 2 8 3.7-69 Amendment No. 4 M

Fuel Storage Pool Water Level B 3.7.16 BASES ACTIONS A.1 (Continued) If moving irradiated fuel awemblics while in MODE 5 or 6, LC0 3.0.3 would not s)ecify any action. If moving irradiated fuel assem:110: while in MODES 1, 2, 3, and 4, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel cocemblics is not sufficient reason to require a reactor shutdown. SURVEILLANCE SR 3.7.16.1 REQUIREMENTS This SR verifies sufficient fuel storage pool water is available in the event of a fuel handling accident. The water level in the fuel storage pool must be checked periodically. The 7 day Frequency is appropriate because the volume in the pool is normally stable. Water level changes are controlled by unit procedures and are acceptable, based on operating experience. During refueling operations, the level in the fuel storage pool is at equilibrium with that of the refueling canal, and the level in the refueling canal is checked daily in accordance with LC0 3.7.17, "Fucl Storege Pocl Boren Gonc e r,t r ct i e n3) 9. 6{ pre fu el i ngyat eMevel. " Du r in95fu el ic'onsol id a ti on F:thell eveEi h1lth eMis kip ool[i s7t hd same;as "thati:<insthe s fuel;/ storage' pool g:since7the: gate'~ between!th el pool sti si keptiopeniduriggj those f operat io'n s? REFERENCES 1. UFSAR, Section 9.1.2. 2. UFSAR, Section 9.1.3. 3. UFSAR, Section 15.7.4. 4. Regulatory Guide 1.25 5. 10 CFR 100.11. SAN ON0FRE--UNIT 2 B 3.7-70 Amendment No. +24 l

Fuel Storage Pool Boron Concentration B 3.7.17 8 3.7 PLANT SYSTEMS B 3.7.17 Fuel Storage Pool Boron Concentration BASES r l BACKGROUND As described in LC0 3.7.18, " Spent Fuel A :c bly Storage," f fuelRis as:c=blic: cre stored in the spent fuel racks in accoFdince with criteria based on initial enrichment and discharge burnup. Although the water in the spent fuel pool is normally borated to a 1850 ppm, the criteria that limit l the storage of a fuel assembly to s)ecific rack locations is Additidhallhiitthliimed without ta(ing credit for boron.*!inlimsm:[1850 conservatively develop RegionsIh(alloWings504ppmimeasurementruncertainty)ianditha" thelpool? l rasksitloided withifuenthatFmsetssthelstorag(s~s bri tefi a fofsTechnLi cils Specificat i oni337318 Mkie f fEi41)d #i_n thanV0!953fonasconsolidatedifhsi?canisterimisositione l .th.elReg~isnillirA.cksi """*'""'"""*~" p"'*"""~ I + ~. ~ - - w Dupihgifdelidbnsbl iditidrQi nithsida5 k?Ti6 big &EditWiMtikiij fo6thelminimumibo_roniconcentrationlin.:sthelapiljcabl#*'[T " mu stt be? borated stoM>There fore a theiwater si nit 1e r cas k? pool 1850fppm shil sfselsissprese accidentianalysist + a~- n - ~ maa- ~-n APPLICABLE A fuel assembly could be inadvertently loaded into a spent SAFETY ANALYSES fuel rack location not allowed by LC0 3.7.18 (e.g., an unEirradiated fuel assembly or an insufficiently depleted fubl assembly). This accident is analyzed assuming ee extreme ::: cf ccm;:letely loading the Ripi6WIII fuel pool racks with #16e[(4mtWin'ehfibhdent"Whichib6u)"ijhsirradiated 3x3?iffiy.3fiilthi!W6Fst% ash assemblies ef"m4W hdil4?81W/6. A dossbl idat sd sfdelli'Eihi stsEipitkid?Wi t himaXi mUsienFi chme nt ~ consol idated sfuellcoul dial ioi bsii hidvettentlyf nii sp6s i tion 6d i n s t h61 Reg i 6 nil liacksMThi s?iEci dentii siai solan alfied W" l An o th e r 'ty self' p 6 s tul i tsd *a c Eide n t'i s"us s 6d i a tsd"W i t h*^i" fuel assem)1y 6bi7d6WsblidatidIfuslRinistedthat is dropped onto ths"fdllyT6sdsd"fdel~ibbl"stbFshe rack. P6s tulitsd[iddidehtilasi6diitid@i t 9 fdslid6h sdl i dat f6d?fH thefcask7poolihavellessedconsequencesithanthose;;focthe" preceding! accidents}becauseiofKthellimitediamountsof#uel months'prioritotfueleconsolidati}onMEf thcPHow it any Ofst.heselindidsnts*ddiJld*hivs'W^)Ositive reattiVity decFEas'ing the mafgin to criticality. Mcwe=r, tThe negative reactivity effect of the soluble boron cbmpensates for the increased reactivity caused by either one of the diffgenli4we-postulatedaccidentscenarios. g (continued) l SAN ON0FRE--UNIT 2 B 3.7-71 Amendment No. 4 W i L

3 Fuel Storage Pool Boron Concentration B 3.7.17 BASES APPLICABLE The concentration of dissolved boron in the fuel pool SAFETEANALYSES satisfies Criterion 2 of the NRC Policy Statement. ](contJnued)f LC0 The specified concentration of dissolved boron in the fuel pool preserves the assumptions used in the analyses of the potential accident scenarios described above. This concentration of dissolved boron is the minimum required concentration for fuel Ednsoljdat~i.;ohMhstheWiik? pool!Fsid fuel:::::bly storage and" movement With'in"the^' fuel 'p~oo17^ APPLICABILITY This LCO applies whenever fuel ;isas ::blic Orc stored in the spent fuel pool until a complete spent fuel pool verification has been performed following the last movement of fuel

c=blic in the spent fuel pool.

This LC0 does not apply following the verification since the verification would confirm that there +rei5 no misloaded fuel- ::c blic:. With no further fuel

cablf movements in progress, there is no potential for a misloaded fuel :::c=bly or a dropped fuel assemblyF.>fu'elstantiteFB6Efdelibsiket..

x a~. h. a.; ~ Thi s? LC0 f alioisppl i e 5%hedifdeKcon sol idati ohi p" fusi ~ mgeinent[)31s@gpogies~ yn@thydappolf~~ s 1 ACTIONS A.l. A.2. and A.3 J The Required Actions are modified by a Note ;13 indicating that LC0 3.0.3 does not applyfi6d7ajNotM 2[Festti;Etlihgithe Mplidabilityjof?Act;1on%2!27 ~^ When the concentration of boron in the spent fuel pool is i less than required, immediate action must be taken to preclude an accident from happening or to mitigate the consequences of an accident in progress. This is most l efficiently achieved by immediately suspending fuel i E6n'solidstionsa dithe movement of fuel

cabliss This does not7Fec10'de~the movement of fuel

blic; to a safe i

position. In addition, action must be immediately initiated l to restore boron concentration to within limit. l l \\ -v, V bMVh N hY /' / ! /hl* [UA hhN/ V V b 2"[ SAN ON0FRE--UNIT 2 B 3.7-72 Amendment No. W 3 3

l Fuel Storage Pool Boron Concentration l B 3.7.17 l I BASES ACTIONS A.I. A.2. and A.3 (continued) Alternately, ppI65to!Essdming3U5pshdsdIlfdsl?mdVimintA*fd theis p e6tsfuel ipool isin~iinmed i a t e ' V eF i fi Eit'i dn," by ~ l idministPstiVe"sein~s'? of the fuel storage pool fuel i locations, to ensure proper locations of the fuel since the last movement of fuel as:cmblic; in the fuel storage pool, l can be performed. If moving irradiated fuel

cmblics while in MODE 5 or 6, l

LC0 3.0.3 would not specify any action. If moving irradiated fuel as:cmblic; while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation. Therefore, inability to suspend movement of fuel ;;;cmblics is not sufficient reason to require a reactor shutdown. l SURVEILLANCE SR 3.7.17.1 REQUIREMENTS This SR verifies that the concentration of boron in the i spent fuel pool is within the required limit. As long as this SR is met, the analyzed incidents are fully addressed. l The 7 day Frequency is appropriate because no major I replenishment of pool water is expected to take place over a short period of time. l Ddri ngsfdel Mossol idat16h Kths7 bb p6'n7dohde htfit i onMnit he caskipoo.131sthels;smelas@haginithef fdelElitoragejpobl} T ' i nceqhelgatej bptween s t.hej poolgjgkepHopenjyupjg3h.oss s 9P! ray 1pns] l REFERENCES 1. UFSAR, Section 9.1. 1 i i l l i l-l l I 1 l l SAN ON0FRE--UNIT 2 B 3.7-73 Amendment No. 427 i l l

Spent Fuel A :cably Storage B 3.7.18 B 3.7 PLANT SYSTEMS B 3.7.18 Spent Fuel A :cably Storage BASES BACKGROUND The spent fuel storage facility is designed to store either new (nonirradiated) nuclear fuci :::c=blic, or burned (irradiated) fuel

cablic in a vertical configuration underwater.

The storage pool is sized to store 1542 fuel assemblies {(total)Nithoutjstbrages;6ficohi61idate.d{fusl_f consolidated s fuels assembl.ies7 ~TWtypes/si[zes~of'^ spent" fuel a'ssembiies_.yory286.1fuelsassembliesW(total) with?storageto 7 itorag'6"rdcks"afs"Used'(Redian I and Region II). The two Region I racks each contain 156 storage locations each spaced 10.40 inches on center in a IPx13 array. The six Region II storage racks contain 210 storage locations in a 14x15 array. The remaining two Region II racks contain 195 locations in a 13x15 array. All locations are spaced 8.85 inches on center. This spacing and " flux trap" construction, whereby the fuel assemblies %fdelNshistif5?6h fuel? basket 53are inserted into neutron abioirbing"stathisss~ spent fuel of original enrichment of up toMof 5 0.95 for steel ~cani^71s sufficient to maintain a k E4f8%. However, as higher initial enrichment fuel 15 d E= bite: cre stored in the spent fuel pool, itthey must be stored in a checkerboard pattern taking inth" account fuel burnup to maintain a k,,, of 0.95 or less. APPLICABLE The spent fuel storage facility is designed for , and " flux trap" noncriticality by use of adequate spacing $fubl?6anistepsf6E SAFETY ANALYSES construction whereby the fuel assemblies', fuelsbasketilare inserted into neutron absorbing' stainless" stebl" cans:' The spent fuel assembly storage satisfies Criterion 2 of the NRC Policy Statement. LCO The restrictions on the placement of fuel

c=blics within the spent fuel pool, according to Figurc 3.7.181 and Figure 3.7.18 2, in the accompanying LCO, ensures that the k,,, of the spent fuel pool will always remain < 0.95 assuming the pool to be flooded with unborated water.

The restrictions are consistent with the criticality safety analysis performed for the spent fuel pool according toith6 '~ LC0j Figurc 3.7.18 1 and Figurc 3.7.18 2, in the (continued) SAN ON0FRE--UNIT 2 B 3.7-74 Amendment No. W

l Spent Fuel A::cabit-Storage B 3.7.18 BASES LC0 acccmpar.ying LCC. Fuel a :c=blic not meeting the criteria (continued) of Figurc 3.7.18 1 and Figurc 3.7.13 2 LCOshall be stored in accordance with LWehtee7Contro11edISpedification 4.3.1.1 ~ ~ ~~~~ ~ ~ ""~" 4 0!100. ~-- APPLICABILITY This LC0 applies whenever any fuel ;;;c bly is stored in Region II of the spent fuel pool. ACTIONS A_d Required Action A.1 is modified by a Note indicating that LC0 3.0.3 does not apply. When the configuration of fuel

c=blic; stored in Region II of the spent fuel pool is not in accordance with Figure 3.7.18-1 ;6 rand Figure 3.7.18-2, immediate action must d

be taken to make~'the necessary fuel

cably movement (s) to bring the configuration into compliance with Figurc 3.7.18 1 and-Hgurc3.7.182EthyLCO.

If moving irradiated fuel :::cablic; while in MODE 5 or 6, LC0 3.0.3 would not s)ecify any action. If moving irradiated fuel

c=:lic; while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation.

Therefore, in either case, inability to move fuel :::::blic; is not sufficient reason to require a reactor shutdown. SURVEILLANCE 3R 3. 7.18_ _1. REQUIREMENTS This SR verifies by administrative means that the initial enrichment and burnup of the fuel

bly is in accordance with Figure 3.7.18 1 and Fi urc 3.7.18 2 in the accompanying LC0 f p Ei or2 to?s t oH ng 5t he? fuen as semblyjs fuelicihiit#rRor fu el i ba s ket si n ? Reg i on:1117' Fo F~ fd el '~h : :5bl !3 sri h* t h s~"~

Onacseptab1(' range ~6fsthsfLCC Figurc 3.7.18 1 and Figure 3.7.18 2, performance"6f"this SR will ensure compliance with J Specification 4.3.1.140J190. REFERENCES UFSAR, Section 9.1.2.2. SAN ONOFRE--UNIT 2 B 3.7-75 Amendment No. 42-7

CREACUS B 3.7.11 BASES APPLICABILITY In MODES 1, 2, 3, and 4, the CREACUS must be OPERABLE to limit operator exposure during and following a DBA. In MODES 5 and 6, the CREACUS is required to cope with the l release from a rupture of a waste gas tank. 1 l During movement of irradiated fuel ;;;cmblics, the CREACUS l must be OPERABLE to cope with the release from a fuel l handling accident. l The term " movement," as applied to irradiated fuel in Specification 3.7.11, refers to the movement of irradiated fuel )ellet(s), fuel rod (s), a partial fuel assembly or assem) lies, a complete fuel assembly or assemblies, or j consolidated fuel. The fuel movement may be for any~ ^ purpose, including; but not limited to, fuel inspectioni fuel reconst,f tution, and fuel consolidation'.; ' ACTIONS ACTION statements are modified by two NOTES. NOTE 1 says: "The provisions of LC0 3.0.4 are not applicable when entering MODES 5, 6, or defueled configuration." Therefore, since CREACUS can be inoperable during each individual MODE, it should not be required to have two OPERABLE CREACUS trains before MODE change from defueled from MODE 6 to defueled configuration, and from MODE 4 to MODE 5. Specification 3.0.4 establishes that entry into an operational mode or other specified condition shall not be made unless the conditions of the LC0 are met. Applicability statement "During movement of irradiated fuel

c=blic:" ensures the OPERABILITY of both CREACUS trains prior to the start of movement of irradiated fueli e:semblics.

NOTE 2 says: "Each Unit shall enter applicable ACTIONS separately." CREACUS is a shared system between Unit 2 and Unit 3. LC0 doesn't address the operational situation when the Units are in different operational MODES. Without this NOTE it may not be clear what ACTIONS should be taken. A.1 With one CREACUS train inoperable, action must be taken to restore OPERABLE status within 7 days. In this Condition, the remaining OPERABLE CREACUS subsystem is adequate to perform control room radiation protection function. l However, the overall reliability is reduced because a single l SAN ON0FRE--UNIT 3 B 3.7-59 Amendment No. -146,117

1 I CREACUS B 3.7.11 ) i BASES i ACTIONS M (Continued) (continued) failure in the OPERABLE CREACUS train could result in loss of CREACUS function. The 7 day Completion Time is based on the low probability of a DBA occurring during this time l period, and the ability of the remaining train to provide i the required capability. B.1 and B.2 If the inoperable CREACUS cannot be restored to OPERABLE status within the required Completion Time in MODE 1, 2, 3, l or 4, the unit must be placed in a MODE that minimizes the accident risk. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours, and in MODE 5 within 36 hours. The allowed Completion Times are l reasonable, based on operating experience, to reach the l required unit conditions from full power conditions in an orderly manner and without challenging unit systems. C.l. C.2.1. and C.2.2 In MODE 5 or 6, or during movement of irradiated fuel i assemblics, if Required Action A.1 cannot be completed j within the required Completion Time, the OPERABLE CREACUS l train must be immediately placed in the emergency mode of operation. This action ensures that the remaining train is OPERABLE, that no failures preventing automatic actuation will occur, and that any active failure will be readily detected. 1 i An alternative to Required Action C.1 is to immediately suspend activities that could result in a release of radioactivity that might require isolation of the control room. This places the unit in a condition that minimizes the accident risk. This does not preclude the movement of fuel as r:blict to a safe position. l M l If both CREACUS trains are inoperable in MODE 1, 2, 3, or 4, the CREACUS may not be capable of performing the intended function and the unit is in a condition outside the accident analyses. Therefore, LC0 3.0.3 must be entered immediately. SAN ON0FRE--UNIT 3 B 3.7-60 Amendment No. H6 1

f CREACUS B 3.7.11 BASES ACTIONS E.1 and E.2 (continued) When in MODES 5 or 6, or during movement of irradiated fuel

blic with two trains inoperable, action must be taken immediately to suspend activities that coula result in a release of radioactivity that might enter the control room.

l l l ) j i SAN ONOFRE--UNIT 3 8 3.7-60a Amendment No. 446

d I Fuel Storage Pool Water Level B 3.7.16 B 3.7 PLANT SYSTEMS B 3.7.16 Fuel Storage Pool Water Level 1 BASES BACKGROUND The minimum water level in the fuel storage pool meets the assumptions of iodine decontamination factors following a fuel handling accident. The specified water level shields and minimizes the general area dose when the storage racks are filled to their maximum capacity. The water also provides shielding during the movement of spent fuel. 1 A general description of the fuel storage pool design is given in the UFSAR, Section 9.1.2, Reference 1, and the Spent Fuel Pool Cooling and Cleanup System is given in the UFSAR, Section 9.1.3 (Ref. 2). The assumptions of the de~signibHiiifuel handling accident are given in the UFSAR, Settidn"1577!4 (Ref. 3). APPLICABLE The minimum water level in the fuel storage pool meets the SAFETY ANALYSES assumptions of the fuel hand 1'ing accident described in Regulatory Guide 1.25 (Ref. 4). The resultant 2 hour thyroid dose to a person at the exclusion area boundary is-a =11 fr=ti= cfNe117itithidly"25For51essibf) the ~ ~ ' " " 10 CFR 100 (Ref. 5)"liinifs': ~ According to Reference 4, there is 23 ft of water between the top of the damaged fuel bundle and the fuel pool surface for a fuel handling accident. With a 23 ft water level, the assumptions of Reference 4 can be used directly. In practice, this LC0 preserves this assumption for the bulk of the fuel in the storage racks. In the case of a single bundle, dropped and lying horizontally on top of the spent fuel racks, however, there may be < 23 ft of water above the top of the bundle and the surface, by the width of the bundle. To offset this small nonconservatism, the analysis assumes that all fuel rods fail, although analysis shows maximum drop.59he.)[bonishiiehd45 Eof [df6ppliig{pothetical that only the first few rods fail from a hy aftohiolidatid fuelic ani 5te ri onst opJo ff t hei racksiare tl e s s s:seve reithars the consequsncesfoffdropping?aifuellassemb1Movedthesefracks} ~ assumingj724hoursAdecay;timetfor@thesassembly[andisiximonths deca $ time go Qth;elfuel(161itheicaniste g @ ef.dedag tjme]6 f (continued) SAN ON0FRE--UNIT 3 B 3.7-68 Amendment No. 4 M

Fuel Storage Pool Water Level B 3.7.16 BASES (Continued) APPLICABLES..... EsiiE month 5TbsfoFEYsi1fdhlilsieinblystilfeidiffoFTdons611ditibij^ SAFETY f ANALYSESl f all owsjatjj eas tj 99 &oythe{Fadi oacti veiglaseskto 'dec ay] ^'(conti.nued). The fuel storage pool water level satisfies Criterion 3 of the NRC Policy Statement. LC0 The specified water level preserves the assumptions of the designibas;LisEfuel handling accident analysis (Ref. 3). As g q.s e he gW W fM s%e W movementwithinthefuelstoragepoolfogca;skgoo;1. APPLICABILITY This LC0 applies during movement of irradiated fuel

c=blic inthefuelstoragepoolb6Ei'5 kip 661Msincethe potential for a release of fission pF6ddcts~"eifits.

Thelte rmysiidVemen tiMa sliia ppl i editolf rrsd f.a ted1fdeT@i n Sp#cificationf317?l6Qrefersstostheimo. ementsofg;ifradi._ated v fuel!pell et ( s)M fu elir6d ( 5 )ifaj pa rti aMfuelfa s s embly)ig^ ~ a s s embl i e s M a20mpl e te i f uel fa s s embly tor.; a s s embl i e sEo r cons 011dat ed s fds1SThsifuel fmoVementt msy(belfoM ani" p u rpo s eni ncl udinghbut ^n_ots:l imi. t ed %t6d f u elli n s pecti ohj' fuelf reconsti tutiony;and guel{consol,idati.on! ~ ~ ~ ' ~ " ACTIONS .A_d Required Action A.1 is modified by a Note indicating that LC0 3.0.3 does not apply. When the initial conditions for an accident cannot be met, steps should be taken to preclude the accident from occurring. When the fuel storage pool water level is lower than the required level, the movement of irradiated fuel assemblic in the fuel storage pool hnd?bsskibboliis immediately suspended. This effectiile19'pFuciddE5 a spent fuel handling accident from occurring. This does not preclude moving e-thsjfuel ;;;cmbly to a safe position. SAN ON0FRE--UNIT 3 8 3.7-69 Amendment No. 4-14

Fuel Storage Pool Water Level B 3.7.16 BASES ACTIONS AL1 (Continued) If moving irradiated fuel c::cmblic; while in MODE 5 or 6, LC0 3.0.3 would not specify any action. If moving irradiated fuel es:cmblics while in MODES 1, 2, 3, and 4, the fuel movement is independent of reactor operations. Therefore, in either case, inability to suspend movement of irradiated fuel assemM4es-is not sufficient reason to require a reactor shutdown. SURVEILLANCE SR 3.7.16.1 REQUIREMENTS This SR verifies sufficient fuel storage pool water is available in the event of a fuel handling accident. The water level in the fuel storage pool must be checked periodically. The 7 day Frequency is appropriate because the volume in the pool is normally stable. Water level changes are controlled by unit procedures and are acceptable, based on operating experience. During refueling operations, the level in the fuel storage pool is at equilibrium with that of the refueling canal, and the level in the refueling canal is checked daily in acccrdance with LC0 3.7.17, "Fucl Stcr:g Pccl Bcron C o n c e n t r c t i o n. " 319_? 6]M Re.f.sel i sp,; Wa t sif7 LsV s.17 " s. - - + DiiFing sf del (co n s.ol;i d ati 6ii Mthell15Vsl $Ij hith eJ? silGJ6l61?il57t hs b'e tweenit h{31 ni the ji f uels storage) pool pisi n ce t t hel ga sameiasithat ^ l REFERENCES 1. UFSAR, Section 9.1.2. 2. UFSAR, Section 9.1.3. 3. UFSAR, Section 15.7.4. l l 4. Regulatory Guide 1.25 i 5. 10 CFR 100.11. l l l l l l SAN ON0FRE--UNIT 3 B 3.7-70 Amendment No. 4 M i

Fuel Storage Pool Boron Concentration B 3.7.17 8 3.7 PLANT SYSTEMS B 3.7.17 Fuel Storage Pool Baron Concentration BASES l BACKGROUND As described in LC0 3.7.18, " Spent Fuel A cmbly Storage," l fue1[is cc:cmblic cre stored in the spent fuel racks in accoFdance with criteria based on initial enrichment and l discharge burnup. Although the water in the spent fuel pool j is normally borated to a 1850 ppm, the criteria that limit i the storage of a fuel assembly to specific rack locations is conservatively developed without taking credit for boron.'l AdditionalliMWithiil:mihimsm?L1850$ppibbros?h6ndentPatidhlid t he spool s (h110wi ng ? 50 Tppmi mea surement$ unce rtai nty)?and st he" l ResionQI; racks slo ~aded:iwi.thhfuelj thatimestsstherstorage~ " criteri a!ofhTechhi calkSpec i ficati 6n f 3.17 ?I8p kie fffi s11 es s , thel:ReglohilI(rAckpf~~ *~ ~scasisterdnisp"ositiohed4:16 thanto;951for7aiconsolidat#dif6el ~ ~" ~ ' ~ ~ ~ ~ ~ " " D6ri ngIfu si gohsol i d a ti6nii rG theic hs kip 66.l M&edi.t@i iEtsksy fo rit h e @i nimsm Lbo ron (con c ent rat i o nji nf the7 appl i cabl e" _ l acci d sntRapaly s i st iiThere foregthe.;wate d nfthstc;ss.kipoo mu stt bsi borated ntoW. 1850 s ppm iwh i l e s.~fu elki sip res entii rn_th_e ~. w +- ~ APPLICABLE A fuel assembly could be inadvertently loaded into a spent SAFETY ANALYSES fuel rack location not allowed by LC0 3.7.18 (e.g., an unsirradiated fuel assembly or an insufficiently depleted fuel assembly). This accident is analyzed assuming the extreme cccc cf completely loading the RegionEII fuel pool rackswithhind;(3x3?hrFiysih3thletwdrsticase)~dhyirradiated as sembl i es of' sax imdM" an~ enrichment whi~ch? boundsif4181W/6. A c'onsolidated ffusReanisteM pact edlWith niaximuslehrichment ~ consolidated 3fuelEcouldtal'solbHunadvestehtlfisis;sositioned~ inTthel egioOII$acksGThisindidentsisfalsM: analyzed? R And t h e F"ty p d"o f ~ p6s t ul a t ed

HEE 7dlih t*i s" assb di s te'd "W i t h"a" fuel assembly oria7honsol;1dstidifuel!TbidfstsNthat is dropped onto ths~ fully ~T6sded"fael"psol"stoFsie rack.

Po s tul ated!aEciddntRais6c t ited @i t h]fdslic6hs b11 dst;E;dhli h i thelcasklLp'oolthavellesser!corisequencesithanythoseJ;fo :iiths" precedinglaccidentslbecauseFofithelllim_itedjamount.f of7fu61 al l owedli nithe ica s kipool s a nd ? the r re~qu i red idec ayst i melofjl s f 8 mo nth s p pri o rit of fu el (con s ol id a ti o n iiE i t h6P" Howeve r M a nys o ne of thesesincidentsfcobld~haVe~a~ positive reactivity'effedt; de[creasingthemaFgintocriticality. Mcwever, tThe negative reactivity effect of the soluble boron cbmpensates i (continued) SAN ON0FRE--UNIT 3 8 3.7-71 Amendment No. 4 %

l Fuel Storage Pool Boron Concentration B 3.7.17 BASES \\ APPi.ICABLE for the increased reactivity caused by either enc cf the SAFETY 1 ANALYSES ldiffeFeh_tstwe-postulatedaccidentscenarios. ~' ' ~(continued)~ ~ ~ The concentration of dissolved boron in the fuel pool satisfies Criterion 2 of the NRC Policy Statement. i LC0 The specified concentration of dissolved boron in the fuel pool preserves the assumptions used in the analyses of the potential accident scenarios described above. This concentration of dissolved boron is the minimum required concentration for fuel con 5olidsti6hlihiths7 disk 7jioolfind fueps:c=bly storage an'd~nidvenisht"Wittiin'ths* fuel isbol ~ APPLICABILITY This LC0 applies whenever fuel !fias:c=blic: are stored in the spent fuel pool until a comiilete spent fuel pool l verification has been performed following the last movement of fuel

cablic: in the spent fuel pool. This LC0 does not apply following the verification since the verification would confirm that there ;isare no misloaded fuel

c=blics.

With no further fuel

cihbly movements in progress, there i

l is no potential for a misloaded. fuel ;;;cably or a dropped l fuel assemblyjgfuelfcanistur_M.o#feelsbasket. movsmentgi.shinyppogfesyigthejcaskjpools; g" ^^ Th i s3 LC0ial s6Ta ppl ils@hehlfdlison sol.i_dat i oii fssl l l ACTIONS A.l. A.2 and A.3 The Required Actions are modified by a Note 1Mindicating ~ that LC0 3.0.3 does not applylihdf41N6th!'2ifestfiM'ingths Nkli.cibilitgbfyAdtiyn{AQ212^J^ ^ ~~ When the concentration of boron in the spent fuel prol is less than required, immediate action must be taken to preclude an accident from happening or to mitigate the l l consequences of an accident in progress. This is most i efficiently achieved by immediately suspending Nel EonsoliditionYihdiiithe movement of fuel :::::blici. This doeth 6t'pfsclu'de"the movement of fuel as:::blic; to a safe position. In addition, action must be immediately initiated to restore boron concentration to within limit. i m._,.-m~. g ggg) s.__ SAN ON0FRE--UNIT 3 B 3.7-72 Amendment No. 4 %

fuel Storage Pool Boron Concentration B 3.7.17 BASES l ACTIONS A.1. A.2. and A.3 (continued) Alternately, pFidBtbWiiUMniliiuspsndedifdbliisi6V4WstEih theTspint$fuilyo61jiih~'infsdinte vWiffeltf6lil'by'""~ ~ idninisfFitiV5"mui6s7 of the fuel storage pool fuel locations, to ensure proper locations of the fuel since the. last movement of fuel :::::blic; in the fuel storage pool, l can be performed. 2 If moving irradiated fuel ---- '"- while in MODE 5 or 6, LC0 3.0.3 would not specify any action. If moving l irradiated fuel :::: 5110: while in MODE 1, 2, 3, or 4, the fuel movement-is independent of reactor operation. Therefore, inability to suspend movement of fuel :::::blic; l is not sufficient reason to require a reactor shutdown. SURVEILLANCE SR 3.7.17.1 l. REQUIREMENTS This SR verifies that the concentration of boron in the spent. fuel pool is within the required limit. As long as this SR is met, the analyzed incidents are fully addressed. The 7 day Frequency is appropriate because no major l. replenishment of pool water is expected to take place over a short period of time. D6i'ihiffddlfEshiol idat idhNthus bbrbh?E66ushtFsti6hiihiths EasKspdo1MilthelsameissithatVfdsthsifue1%stespe36o1F" operationsf"~ "~' ";pb61sfissiep"t?bp~eh?durfmj"ith6sb siheestheijate!betWeshtthei " " " ~ " " "

' ~ "

REFERENCES 1. UFSAR, Section 9.1. l ( l I l SAN ON0FRE--UNIT 3 8 3.7-73 Amendment No. 4 M t 1 i i m -e

l Spent Fuel A :c=bly Storage B 3.7.18 B 3.7 PLANT SYSTEMS B 3.7.18 Spent Fuel A::::bly Storage l BASES BACKGROUND Thespentfuelstoragefacilityisdesignedtostoreeither new (nonirradiated) nuclear fuci ::: :b.ics, or burned I (irradiated) fuel

c=blic: in a vertical configuration underwater. The storage pool is sized to store 1542 fuel l

Wis smbl ie s%( thtal )?Wi t h60tisthFayeTofR6ris ol iditedifdsl assemblies ?k orJ 2867) fuels as s embi t eW(total )Ni thys t orage fbf ~ l bonsolidate'difdelf aisembliss': "Twb"typ~es/sizss"of'5 5snt"fusl st W F M b" W used"(Region I and Region II). Tie two Region I racks each contain 156 storage locations each spaced 10.40 inches on center in a 12x13 array. The six Region 11 storage racks contain 210 storage locations in a 14x15 array. The remaining two Region II racks contain 195 l locations in a 13x15 array. All locations are spaced 8.85 inches on center. This spacing and " flux trap" construction, whereby the fuel assembliesigfueMbasiitEps? bdfddisbiskets?are inserted into neutron"ibsdFb'ihcf ~~~ l stiihlsss" steel" cans, is sufficient to maintain a k of l 5 0.95 for spent fuel of original enrichment of up Yo-44 j 4:8%. However, as higher initial enrichment fuel 'i'sh c=blic: cre stored in the spent fuel pool, [itt-hey must b6 stored in a checkerboard pattern taking into 4Ecount fuel burnup to maintain a k,ff of 0.95 or less. l l APPLICABLE The spent fuel storage facility is designed for SAFETY ANALYSES noncriticality by use of adequate spacing, and " flux trap" construction whereby the fuel assembliesWfuelibinisthisg"6F fuel?hiskets are inserted into neutron absorbing stainles's l s tbsl ~'can f.' ' l The spent fuel assembly storage satisfies Criterion 2 of the i NRC Policy Statement. l LC0 The restrictions on the placement of fuel :::c=blic; within the spent fuel pool, according t Figurc 3.7.18 1 and Figurc 3.7.18 2, in the accompanying LCO, ensures that the k,,, of the spent fuel pool will always remain < 0.95 assuming the pool to be flooded with unborated water. The restrictions are consistent with the criticality safety analysis performed for the spent fuel pool according to the LCOJ Figure 3.7.18 1 and Figurc 3.7.18 2, in the ~ ~ ~ { (continued) SAN-0N0FRE UNIT 3 8 3.7-74 Amendment No. H 6 i

l Spent Fuel A::cmbly Storage B 3.7.18 l BASES LC0 accompanying LC0. Fuel :::cablic not meeting the criteria l (continued) of Figurc 3.7.18 1 and Figure 3 7.18 2 LC03shall be stored in accordance with Liceiiss'eIControlled4Spscification 4.3.1.1[K07100. ' ~ ~ ~ ^ ' APPLICABILITY This LC0 applies whenever any fuel

c bly is stored in Region II of the spent fuel pool.

l ACTIONS A.1 Required Action A.1 is modified by a Note indicating that LCO 3.0.3 does not apply. When the configuration of fuel

c=blic; stored in Region II of the. spent fuel pool is not in accordance with Figure 3.7.18-1 orand Figure 3.7.18-2, immediate action must i

be taken to make~the necessary fuel ;;;c=bly movement (s) to bring the configuration into compliance with Figurc 3.7.18 1 and Figurc 3.7.1821)he}LCO. If moving irradiated fuel

c=blic; while in MODE 5 or 6, LC0 3.0.3 would not s)ecify any action.

If moving irradiated fuel :::c::1100 while in MODE 1, 2, 3, or 4, the fuel movement is independent of reactor operation. Therefore, in either case, inability to move fuel as:c=blic; is not sufficient reason to require a reactor shutdown. 1 SURVEILLANCE SR 3.7.18.1 REQUIREMENTS This SR verifies by administrative means that the initial enrichment and burnup of the fuel :::c=bly is in accordance I with Figurc 3.7.18 1 and Fi urc 3.7.18 2 in the accompanying ) LC0? pFi orJ tois tori ngIt he7fd1?iiais embl yRfus1 Man is t# r p"o r fueltbsskstdnlRegiorj3II! T6Ffudl"EdSblT6i~in"the ^ ' ~0liadeeptabla"rsnge"of^thbiLCO? Figurc 3.7.181 and Figure 3.7.18 2, performance Of"this~SR will ensure compliance with Specification 4.3.1.14(0]I0g. REFERENCES UFSAR, Section 9.1.2.2. SAN-0NOFRE UNIT 3 8 3.7-75 Amendment No. 446

ENCLOSURE 2 Fuel Consolidation and Storage Report (Revision 0) ) l 1}}

ML20116C680

Text

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