ML17310B233

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Amends 74,60 46 to Licenses NPF-41,NPF-51 & NPF-74, Respectively Re Increase of Max Allowable Fuel Enriched from 4.05 Weight Percent U-235 to 4.30 Weight Percent U-235
ML17310B233
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 04/19/1994
From: Quay T
Office of Nuclear Reactor Regulation
To:
Shared Package
ML17310B234 List:
References
NUDOCS 9404220172
Download: ML17310B233 (24)
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UNITED STATES NUCLEAR REGULATORY. COMMISSION WASHINGTON, D.C. 2055&0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 74 License No. NPF-41 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by,the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Water and
Power, and Southern California Public Power Authority dated October 26,
1993, as supplemented by letter dated March 28,
1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by thi's amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Speci'fications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-41 is hereby amended to read as follows:

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(2)

Technical S ecifications and Environmental Protection 'Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 74, and the Environmental. Protection Plan contained. in Appendix B, are hereby, incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection

Plan, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

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Theodore R. quay, Director Project Directorate IV-3 Division of Reactor Projects III/IV'ffice of Nuclear, Reactor Regulation

Attachment:

Changes to the Technical

-Specifications Date of Issuance:

April 19, 1994

41

ATTACHMENT TO -LICENSE AMENDMENT AMENDMENT NO.

74 TO FACILITY OPERATING LICENSE NO.

NPF-41 DOCKET NO.

STN 50-'528 Replace the following pages of the Appendix A Technical Speci'fications with the enclosed pages.

The revised pages are identified. by amendment number

and, contain vertical lines indicating the areas of change..

Remove 5-5 Insert 5-5

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DESIG FEAT RES

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5.3.1 The reactor core shal.l contain 241,fuel assemhlies

.with each fuel, assembly normally containing 236 fuel rods or burnable.poison rods clad with Zircaloy-4 except that limited substitution of. fuel,rods by,filler rods consisting of Zircaloy-4 or stainless steel.,may be. made..i.f.justified by a cycle specific reload analysis.

Each fuel rod shal.l have a,nominal. active fuel length of 150 inches and,contain a maximum total.weight of approximately 1950 grams uranium.

Each burnable poison rod shall,. have.a nominal active poison length of 136,inches.,

The initial core loading shall. have-,a.maximum. enrichment of 3.35 weight percent U-235.

Reload fuel. shall be~;,similaq,in physical design to the initial.core loading and shall have a maximum:radially averaged enrichment of 4.30 weight percent U-235 at any axial location.*

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ASSEHB S

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5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element assemblies.

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

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a.

In accordance with the code requirements,,specified,.inSection 5.2 of the FSAR with allowance for.normaldegradation pursuant of the applicable surveillance requirements, b.

For a pressure of 2500 psia, and 1 ~ g

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For a temperature of 650'F, except for. the pressurizer which is 700 F.

5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900 + 300/-0 cubic feet at a nominal T, of 593'F.

  • No fuel with an enrichment greater than 4.0 weight percent U-235 shall be stored in a high density mode in the spent fuel storage facility.

PALO VERDE - UNIT 1 5-5 AMENDMENT NO. 34 74

DESIGN FEATURES

5. 5 METEOROLOGICAL TCMER LOCATION 5.5.1 The,aeteprqlogkcal tooer shall be 1&ated as shown on F)gure 5.1ol.',

5.6 FUEL STORAGE... ~,

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5.6.1.1 The spent fie). st>orage racks. are,,desfg&d and shall be aa1ntta$ ned a.

A k, equi'va'lent to less then or iqua]i to O.95 ikeinn> flooded w)th unbS/jLted iraterwh)ch inc.ludes a conservative allowance of 2PQ'elta klk, for.urcerta4nties is de(cri)bed fn'Section"'9".1 of'the FISAR.

b.

A noa)anal 9.5 inch center to-clntar 4$ 4tance between. fuel assembl)es placed

$ n this storage racks,$ g a hfghdensity conf 5gurat/ion.

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5.6.1.2 The keff for new fuel for the first core loading stored dry 4n tHe spent fuel storage racks shall not exceed 0<98 when aqueous foam aoderatfon

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5.6.2 The spent fuel storage pool )is designed and shall be aa$ nta$ ned to prevent fnadvewtent dr'a)nllng of the pool be)ow elevation 137 feet - 6 Inches.

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5 6.3 The spent fue'I storage pool

$s des)gned and shall be aa$ nta$ ned with a storage capacity lfatted.to no sorerthan: 1329 fuel asseetblies.

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O.T COMPONENT tCYCCIC OIN TAANSIENT LIMIT>t 5.7.1 The coeiponents 1dentlffed 4n Table 5.7-1 are designed and sha1ll Ibe aa$ nta$ ned w)thorn the cyc1)c oi transient lfa)its of Tables 5.7-1 and 5.7-2.

PALO VERDE - UNIT 1 5-6

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~o f)t*yW UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.

2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 60 License No.

NPF-51 The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application For amendment by the Arizona Public Service-Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement and Power District, El Paso Electric Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles Department of Water and
Power, and Southern California Public Power Authority dated October 26,
1993, as supplemented by letter dated March 28,
1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Part I; 2.

B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

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

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

Accordingly, the l,.icense is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No. NPF-51 is hereby amended to read as follows:

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3.

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications, contained in Appendix A, as revised through Amendment No. 60, and'he Environmental Protection Plan contained'n Appendix B, are hereby incorporated into this license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection

Plan, except where otherwise stated in specific license conditions.

This license amendment is:effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 19, 1994 Theodore R. quay, Director Project Directorate IV-3 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

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0 ATTACHMENT TO LICENSE-AMENDMENT AMENDMENT NO.

TO FACILITY OPERATING LICENSE NO.

NPF-51 DOCKET NO.

STN 50-529 4

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~,i Replace the following pages of the Appendix A Technical, Speci'fi'cations with the enclosed pages.

The revised pages are identified by amendment-number and contain vertical lines indicating the areas. of change.

Remove

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DESIGN FEATURES 5.3 0

C 5.3. 1 The reactor core shall contain 241 fuel assemblies with each fuel assembly normally containing 236 fuel rods or burnable poison rods clad with Zircaloy-4 except that limited substitution of fuel"rods by filler rods con-sisting of Zircaloy-4 or stainless steel may be made if justified by a cycle specific reload analysis.

Each fuel rod shall have' nominal active fuel length of 150 inches and contain a maximum total weight of approximately 1950 grams uranium.'ach bur nable poison rod shall have a nominal'ctive poison length of 136 inches.

The initiaT'ore loading'hall have 'a maximum enrichment of 3.35 weight percent U-235.

Reload fuel shall be similar'i'n physical design to the initial core loading and shall'have a maximum radi'ally averaged enrich-ment of 4.30 weight percent U-235 at any axial location.*

'"'ON RO ASSEHB 5.3.2 The reactor core shall contain 76 full-length and 13 part-length control element asseiti51ies.

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

a.

In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal'egradation pursuant of"the applicable surveillance requirements, b.

For a pressure of 2500 psia, and c.

For a temperature of 650 F, except for the pressurizer which is 700'F.

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5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900 + 300/-0 cubic feet at a nominal T, of 593 F.

  • No fuel with an enrichment greater than 4.0 weight percent U-235 shall be stored in a high density mode in the spent fuel storage facility.

PALO VERDE - UNIT 2 5-5 AMENDMENT NO. 84 60

DESIGN FEATURES 5.5 HETEOROLOaICAL revR LOCATION 5.5.1 The meteorologfcal tower shall ke 'lokat'ed as shown on Figure 51-1.

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5.6 FUEL STORAGE 5.6. 1 CRITICALITY

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5.6.1.1 The spent, fuel storage racks Are'aIsfgned and shall be eafntafnad Withr 0

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A k equivalent to less than or equal to 0,95 when flooded w'ft&

unbSQted water,, which fncludesIa 'conservatfve allowance of 2.6X delta:k/k for uncertafntfes as described fn Section-9.1 o'f the'EAR,',

b.

A nominal 9.5 inch center to~cehte'r IffstarIce between fuel assM)lfes placed.fn the storIagp r'acks in.'a~lhfgh'density configuration; r

5.6.1.2 The k ff for new fuel for the first core loadfng stored d+

$ n Ithe'pent fuel storage racks shill not exceed 0.9& wh>>en aqulious foam moderation fs assumed.

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-;C ~.lot".%>>-".1l ORAIRAGE 5.6.2 The spinet Tuel storape pool ls desiignisd and shaiil he nalntalhed th prevent'inadvertent draining of the'pool belows elevation s 137 feats -'

'inches.

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ia>>r CAPACITY 5.6>>3 The spent, fuel storage pool fs dasfgnkd 'and shall be maintained with a storage capacity lItafted,tio:no:core tha'n 1M9':Cue',I asseeblf<<s:""-'

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5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS, 5.7.1 The casponents fden'tfffed fn Tabl1e 5.$-1 are designed and shall be mafntafned wfthfn the cycl fc or transfe6t 'lf itis:bf Tables 5;7"1 and 5.7-2.

PALO VERDE - UNIT 2 5a6

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA 'PUBLIC SERVICE COMPANY ET AL.

DOCKET NO.

STN 50-530 PALO VERDE NUCLEAR GENERATING STATION'NIT NO.

3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 46 License No. NPF-74 The Nuclear Regulatory Commission (the Commission) has *found'that:

A.

B.

C.

D.

The application for amendment by the Arizona Public Service Company (APS or the licensee) on behalf of itself and the Salt River Project Agricultural Improvement 'and Power District, El Paso Electric Company, Southern California Edison

Company, Public Service Company of New Mexico, Los Angeles 'Department of Water and Power, and'outhern California. Public Power Authority dated October 26, 1993,,

as supplemented by letter dated March 28,

1994, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's regulations set forth in 10 CFR Chapter I; The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i,) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activi'ties'will be conducted in compliance with the Commission's regulations; The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

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

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C(2) of Facility Operating License No.

NPF-74 is hereby amended to read as follows:

~I

3.

(2)

Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as. revised

. through Amendment No. 46, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into, this, license.

APS shall operate the facility in accordance with the Technical Specifications and the Environmental Protection

Plan, except where otherwise stated in specific license conditions.

This license amendment is effective as of the date of issuance and must be fully implemented no later than 45 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

Attachment:

Changes to the Technical Specifications Date of Issuance:

April 19, 1994 Theodore R. quay, Director Project Directorate IV-3.

Division of Reactor Projects III/IV Office of Nuclear.

Reactor Regulation

4l 4i 0

ATTACHMENT TO LICENSE AMENDMENT AMENDMENT N0.46 TO FACILITY OPERATING LICENSE NO. NPF-74 DOCKET NO.

STN 50-530 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.

The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 5-5

4i i~

't

DES IGN EAT 5 3 R

CTO OR FU ASS M

5.3.1 The reactor core"shall contain 241 fuel assemblies with each fuel assembly normally containing 236, fuel rods or burnable poison rods clad with Zircaloy-4 except that limited substitution of fuel rods by filler rods con-sisting of Zircaloy-4 or stainless steel may be made if justified by a cycle specific reload analysis.

Substitution of up to. a total of 80 fuel rods clad with zirconium-based al.loys other than Zircaloy-4 may also be made in two fuel assemblies for in-reactor performance evaluation::purposes during Cycles 4, 5

and 6.

Each fuel rod shall have a nominal active fuel length of 150 inches and contain a maximum total weight of approximately 1950 grams uranium.

Each burnable poison. rod shal.l have a nominal, active poison length of 136 inches.

The initial core loading shal.l have a maximum enrichment of 3.35 weight percent U-235.

Reload fuel shall be similar in physical design to the initial core loading and shall have a maximum radially averaged enrichment of 4.30 weight percent U-235 at any axial location.*

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EM AS MB 5.3.2 The reactor core shall contain 76 ful,l-length and 13 part-length control element assemblies.

5.

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EMPERATUR 5.4.1 The Reactor Coolant System is designed and shall be maintained:

a.

In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance. for normal degradation pursuant of the applicable surveillance requirements, b.

For a, pressure of 2500 psia, and c.

For a temperature of 650'F, except for the pressurizer which is 700'F.

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5.4.2 The total water and steam volume of the Reactor Coolant System is 13,900 + 300/-0 cubic feet at a nominal T, of 593;F.

  • No fuel with an enrichment greater, than 4.0 weight percent U-235 shal.l be stored in a high density mode in the spent fuel storage facil.ity.

PALO VERDE UNIT 3 5-'5 AMENDMENT'NO. 8,8S 46

DESiGN FEATURES

.5.5 METEOROLOGICAL TM:R LOCATION, 5.5.1 The oeteoro'logicaal teer shal1l be located 4s shown'on'igure 5.1-1.

5. 6 FUEL STORAGE
5. 6. 1 CRITICALITY 5.6.1.1'he spent fuel storage racki~ ire.dekignedl.ahd 'shill'e maintained with:

a..:A k;equivalent to less, thin-or,equal'to 0.95 when flooded with unbSQted'water, which includis a conservative allowanc>> of 2.N,

'elta k/k for uncerta1lnties as discribedI

$ ~: Section 9.1 of the 0SAIR.

b.

A nominall-9.5 inch center-to;center distance between fuel assemblies placed in the storage ricky in a high density, configuration.

5.6. 1.2 The k ff for new fuel-for thee first 'core 'loading stored dry in the spent fuel storage racks shall not exceed O.98 i'~hen iquteouis foam moderation

's assumed.

DRAINAGE 5.6.2 The spent. fuel storage pool is designed And'. shall b'i maintained to~

prevent.ina'dvertintdraining.iof. the pool below elevation 137 feet - 6 inches.

CAPACITY 5.6.3

'The spent fuel storige pool is designed ind'hal'l be maintained with 4 storage capacity limited to no more than. 1329 fuel assemblies.

.5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identif fed, in Tabli 5.7-1 ar>> dlesigned'nd shall'e maintained within the cyclic or transient limitS of Tables 5.7-1 and 5.7-2.

PALO VEROE; UNIT 3 5a6
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