ML17311A327
| ML17311A327 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/07/1994 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17311A328 | List: |
| References | |
| NUDOCS 9410130125 | |
| Download: ML17311A327 (24) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR G
RA ING STATION UNIT NO.
MENDMENT TO FACILITY OPERATING LICENSE r
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Amendment No. 83 License No.
NPF-41 The Nuclear Regulatory Commission,(the Commission) has found that:
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.
A.
The application for amendment, by the Arizona. Public Servi'ce Company (APS or the licensee) on behalf of i.tself 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 August 18,
- 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; 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-41 is hereby amended to read's fol.lows:
II l
3.
(2) Technical S ecifications and Environmental Protection P1an The Technical Specifications contained in Appendix A, as revised through Amendment No. 83, 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 startup from the next refueling outage (refueling number 5).
FOR'HE NUCLEAR REGULATORY COMMISSION p~g~ g ~~.7 Theodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 7, 1.994
0 4
ATTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
'83
.TO FACILITY OPERATING 'LICENSE NO. 'NPF-41
.DOCKET NO.
STN 50-528 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised pages are identi.fied by amendment number and contain verti'cal lines indicating the, areas of'hange.
remove 6-20b nsert 6-20b
l~
AD>INISTRAT IVE CONTROLS CORE OPERATING LIMITS REPORT 6.9.1.9 Core operating limits shall be established'nd documented'in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
a.
Shutdown Margin K, Any CEA Withdrawn for Specification 3.1:1.2 b.
Hoderator Temperature Coefficient BOL and EOL limits for Specification 3. 1. 1.3 c.
Boron Dilution Alarms for Specification 3.1.2.7 d.
Movable Control Assemblies - CEA Position for Specification
- 3. 1.3. 1 e.
Regulating CEA Insertion Limits for Specification 3. 1.3.6 f.
Part Length CEA Insertion Limits for Specification 3. 1.3.7 g.
Linear Heat Rate for Specification 3.2.1 h.
Azimuthal Power Tilt - T, for Specification 3.2.3 i.
DNBR Margin for Specification 3.2.4 j.
Axial Shape Index for Specification 3.2.7 6.9.1.10 The analytical methods used to determine the core operating l.imits shall be those previously reviewed and approved by the NRC in:
a
~
b.
C.
"CE Method for Control Element Assembly Ejection Analysis,"CENPD-0190-A, January 1976 (Methodology for Specification 3. 1.3.6, Regulating CEA Insertion Limits).
"The ROCS and DIT Computer Codes for Nuclear Design,"
CENPD-266-P-A, April 1983 (Methodology for, Specifications
- 3. 1. 1.2, Shutdown Margin K., Any CEA Withdrawn; 3; 1. 1.3,. Moderator <<Temperature Coefficient BOL and EOL l.imits and 3. 1.3.6, Regulating CEA Insertion Limits).
"Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No.
STN 50-470, "NUREG-0852 (Novenber 1981}, Supplements No.
1 (March 1983),
No.
2 (September 1983),
No.
3 (December 1987)
(Methodology for Specifications
- 3. 1. 1.2, Shutdown Margin K., - Any CEA Withdrawn; 3.1.1.3, Moderator Temperature Coefficient BOL and EQL limits;
- 3. 1.2.7, Boron Dilution Alarms; 3. 1.3. 1, Movable Control Assemblies-CEA Position;
- 3. 1.3.6, Regulating CEA Insertion Limits; 3. 1.3.7, Part Length CEA Insertion Limits and 3.2.3 Azimuthal Power Tilt - T,),.
"Modified Statistical Combination of Uncertainties,"
CEN-356(V)-P-A Revision 01-P-A, May 1988 and "System 80 Inlet Flow Distribution,"
Supplement 1-P to Enclosure I-P to LD-82-054, February 1993 (Methodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial Shape Index).
PALO VERDE UNIT I 6-20a AMENDMENT NO. ~, ~
76
g<<Y<<
CORE OPERATING LIMITS REPORT (Continued) e.
"Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysiis iof CE and W Designed NSSS,"
CENPD-132, Supplement 3-P-A, June 1985.(Hethodo'iiogy f'r Specil,fication 3.2.1, Linear Heat Rate).
"Calculative Methods for the CE Small Break LOCA Evaluation Hodel,"
CENPD-137-P, August 1974 (Hethodology for Specii:ication '3.2. I, 'Lineair Heat Rate).
9 "Calculative Methods for the CE Small Brea'k LOCA Evaluation Model,"
CENPD-137-P,
.'Supplement 1P,, January 1977 (Methodology for Specificati,on 3.2.1, Linear Heat Rate).
h.
Letter:
0.
D. Parr,(INRC') to F.
M. Steer>
(CE), dated'une 131975 (NRC Staff Review of'the Combustioio Engineiering ECCS Evaluation Model).
NRC approval for:
6.9.1.10f.
Letter:
K. Kniel (NRC) to A. E. Scherer (CE), dated September 27, 1977.(Evaluation of Tiopica'll Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P)
NRC approval for 69. 1.10.g.
The core operating limits shall be determined so that all applicable limits (e.g
, fuel thermal-mechanical limit., core thermal-hydraulic lim'its, ECCS limits, nuclear liimits such
- is shutdown margin, and transient and analysis limits) of the safety analysi,s are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements
- thereto, shall be provided upon issuance,,
for each reload cycle, to the NRC Document C'ontrol Desk with ciopies to the lkegional Administrator and Resident Inspector.
PALO VERDE UNIT 1 6-20b AMENDMENT NO.
69-,
83
1 gP,S RE00
~4 "o
Cy qO t
UNITED'STATES NUCLEAR REGULATORY COMMISSION
.WASHINGTON, D.C. 20555-0001 RIZONA PUBLIC S RV CE COMPANY AL.
DOCKET NO.
STN 50-529 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
2 MENDMENT TO FACILITY OPERATING LICENSE Amendment No. 7o License No. NPF-51 2.
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 Mater and
- Power, and Southern California Public Power Authority dated August 18,
- 1994, complies with the standards and-requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commi'ssion's regulations
.set forth in 10 CFR Part 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 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 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-51 is 'hereby amended to read as follows:
ik
3.
(2) Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in, Appendix A, as. revised through.Amendment No. 7o, and the Environmental Protection Plan contai'ned in Appendix B, are hereby incorporated into this license.
APS shal;1 operate the facility in accordance with the Technical Specifications and the.Environmental Protection
- Plan, except where otherwise stated in specific license conditions.
Thi's license amendment is effective. as of the date of issuance and, must be ful.ly implemented no later than startup from the, current midcycle outage:(U2M5-2).
FOR THE NUCLEAR REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Theodore R. quay, Direcdor Project Directorate,IV-2
,Division.of -Reactor Projects III/IV Office of Nuclear Reactor Regulation Date of I'ssuance:
October 7,
1994
TTACHMENT TO LICENSE AMENDMENT AMENDMENT NO; 70 TO FACILITY"OPERATING'LICENSE NO. NPF-51 DOCKET NO.
STN.50-529 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 6-20b
- Insert 6-20b
Il
ADMINISTRATIVE CONTROLS CORE OP RATING L MITS REPORT 6 '.1.9 Core operating limits shall be established and documented in the CORE OPERATING LIHITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
a ~
b.
c d.
e.f.
g.
h.
1.j ~
Shutdown Margin K., - Any CEA Withdrawn for Specification 3.1. 1.2 Moderator Temperature Coefficient BOL and EOL limits for Specification 3.1.1.3 Boron Dilution Alarms for Specification 3. 1.2.7 Hovable Control Assemblies - CEA Position for Specification 3.1.3.1 Regulating CEA Insertion Limits for Specification 3. 1.3.6 Part Length CEA Insertion Limits for Specification 3.1.3.7 Linear Heat Rate for Specification 3.2. I Azimuthal Power Tilt - T, for Specification 3.2.3 DNBR Hargin for Specification 3.2.4 Axial Shape Index for Specification 3.2.7 6.9. 1. 10 The analyti'cal methods used to determine the. core operating limits shall be those previously reviewed and approved by the NRC in:
"CE Method for Control Element Assembly Ejection Analysis,"
CENPD-
'0190-A, January 1976 (Methodology for Specification 3. 1.3.6, Regulating CEA Insertion Limits).
b.
C.
d.
"The ROCS and DIT Computer Codes for Nuclear Design,"
CENPD-266-P-A,
'April 1983 (Methodology for Specifications 3.1.1.2, Shutdown, Margin K, - Any CEA Withdrawn; 3.1.1.3, Hoderator Temperature 'Coefficient BOL and EOL limits and 3.1.3.6, Regulating CEA Insertion, Limits).
"Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No.
STN 50-470, "NUREG-0852 (Novenber 1981),
Supplements No.
1 (March 1983),
No.
2 (September 1983),
No.
3 (December 1987)
(Methodology for Specifications
- 3. 1. 1.2, Shutdown Margin K., - Any CEA Withdrawn; 3.1.1.3',
Moderator Temperature Coefficient BOL and EOL limits;
- 3. 1.2.7',
.Boron Dilution Alarms; 3. 1.3..1, Movable Control Assemblies-CEA Position;
- 3. 1.3,6, Regulating CEA Insertion Limits; 3. 1.3.7, Part Length CEA Insertion Limits and 3.2.3 Azimuthal Power Tilt -,T,).
"Modified Statistical Combination of Uncertainties,"
CEN-356(V)-P-A Revision 0)-P-A, Hay 1988 and "System 80 Inlet Flow Distribution,"
Supplement 1-P to Enclosure 1-P to LD-82-054,, February 1993 (Methodology for 'Specification 3.2.4, DNBR Margin and 3.2.7 Axial Shape Index).
PALO VERDE - UNIT 2 6-20a AMENDMENT NO. m, 62
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) e.
"Calculative Methods for the CE Large Break LOCA IEvaluation Hodel'or the Ana'lysis of.CE and:
W 'Designed NSSS,"
CENPD-132, Supplement 3-.P-A, June 1985 (Methodology for Specification 3.2.1, Linear Heat Rate).
f.
"Calculative Methods for the CE Seawall 8'reak LOCA Lvaluation Ho~iel,"
CENPD-137-P, August 1974 (Methodology for Specification 3.2.1,',Li'near
'eat Rate).
g.
"Calculative Methods for the CE Seal)
Break LOCA Evaluation Model,,",
CENPD-137-P, Supplement 1P, January 1977 (Methodology for Specification 3.2.1, Linear Heat Rate).'.
Letter:
0.
D. Parr (NRC) to F. H; Stern (CE), dated June 13,
)97,'5 (NRC Staff Review of thee CombustioIn kngindering'CCS Evaluation Model).
NRC approval for:
6.9.1.10f.
Letter:
K. Kniel (NRC) to A. E. Scherer (CE), dat.ed September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement, 1-P).
NRC app&ov'al 'for 6.9.l.l0.g.
The core operating limits shall be determined so that all applicable limits'e.g.,
fuel thermal-mechanical 'limits, core thermal-hydraulic 'iimits, ECCS
'imits, nu'clear limits such as shutdown margin, ahd transient and analysis limits) of the safety analysis are met.
The CORE OPERATING LIMI'TS REPORT, including any mid-cycle revisions or supplements
- thereto, shall be providied upon iss'uahce',
for'each reload cycle,,
to the NRC Document Control'Desk with copies to the Regional Administrato'r And'esident Inspector.
PAI.O VERDE UNIT 2!
6;20b AMENDMENT NO. ~ 70
~AS RECy (4
~o Op n
IVl0 0
n UNITED STATES NUCLEAR REGULATORY COMIVIISSION-WASHINGTON, D.C. 2055&0001
'IZONA PUBLIC SERVICE COMPANY ET AL.
OCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
55 License No. NPF-74 2.
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 August 18,
- 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 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 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. 55,,
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 startup from the.next refueling
,outage (refueling number 5).
FOR THE NUCLEAR. REGULATORY COMMISSION
Attachment:
Changes to the Technical Specifications Theodore R. quay, Director Project Directorate IV-2 Division of Reactor Projects III/IV Office of Nuclear 'Reactor Regulation Date of Issuance:
October 7.,
1994
h
TTACHMENT TO LICENSE AMENDMENT AMENDMENT NO.
55 TO FACILITY OPERATING L'ICENSE 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'ontain vertical lines indicating the areas of change.
Remove Insert 6-20b
Ib 0
I
ADMINISTRATIVE CONTROLS CORE 'OPERATING LIMITS REPORT 6.9. 1.9 Core operating limits shall be established and documented in. the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining, part of a reload cycle for the following:
a ~
b.
C.
d.
e.
f..
g.
h.
1
~j ~
6 '.1.10
,a.
b.
C.
d.
Shutdown Margin K., - Any CEA Withdrawn for Specification 3. 1.1.2 Moderator Temperature Coefficient BOL and EOL limits for Specification 3.1. 1.3 Boron Dilution Alarms for Specification.3.'1.2.7 Movable Control Assemblies - CEA Position for Specification 3. 1.3. 1 Regulating CEA Insertion Limits for Specification 3. 1.3.6 Part Length CEA Insertion Limits for Specification 3. 1.3.7 Linear Heat Rate for Specification 3.2.1 Azimuthal Power Tilt - T, for Specification 3.2.3 DNBR Margin for Specification 3.2.4 Axial Shape Index for Specification 3.2.7 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
"CE Method for Control Element Assembly Ejection, Analysis,"
CENPD-0190-A,, January 1976 (Methodology for Specification 3. 1'.3.6, Regulating CEA Insertion Limits).
"The ROCS and DIT Computer Codes for Nuclear Design,"
CENPD-266-P-A, April 1983 (Methodology for Specifications. 3. 1. 1.2, Shutdown Margin K,, - Any CEA Withdrawn; 3;1. 1.3, Moderator. Temperature. Coefficient BOL and EOL limits and 3. 1.3.6, Regulating CEA Insertion Limits).
"Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply Reference Systems CESSAR System 80, Docket No.
STN 50-470, "NUREG-0852 (Novenber 1981),
Supplements No.
1 (March 1983),
No.
2 (September 1983),
No.
3 (December 1987)
(Methodology for Specifications
- 3. 1. 1.2, Shutdown Margin K., - Any CEA Withdrawn;
- 3. 1.1.3, Hoderator Temperature Coefficient BOL and EOL limits;
- 3. 1.2.7, Boron Dilution Alarms; 3. 1.3.1, Movable Control Assemblies-CEA Position;
- 3. 1.3.6, Regulating CEA Insertion Limits; 3. 1.3.7, Part Length CEA Insertion Limits and 3.2.3 Azimuthal Power Tilt - T,).
"Modified Statistical Combination of 'Uncertainties,"
CEN-356(V)-P-A Revision Ol-P-A, Hay 1988 and "System 80 Inlet Flow Distribution,"
Supplement 1-P to Enclosure 1.-P to LD-82-054, February 1993 (Methodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial Shape Index).
PALO VERDE - UNIT 3 6-20a AMENDMENT NO.~
48
ADMINISTRATIVE CONTROLS 0
e.
"Calculative Methods for the CE Large Break LOCA Evaluation Model'-for
'he Analysis of CE and W Designed,NSSS,"
CENPD-132, Supplement-'3-P-A,-
June 1985 (Methodology for Specification 3.2.1, Linear Heat Rate).
f.
"Calculative Methods for the CE Small Break LOCA Evaluation Ho~iel,"
CENPD-137-P, August 1974 (Methodology for Specification 3.2.1, Li'near Heat Rate).
g.
"Calculative Methods for the CE Seawall Break LOCA Evaluation Model,"
I CENPD-137-P, Supplement 1P, January 1977 (Methodology for Specification 3.2.1, Linear Heat Rate).
h.
Letter:
0.
D. Parr (NRC) to F. H. Stern (CE), dated June 13, f975 (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model).
NRC approval for:
6.9. 1. 10f.
i.
Letter:
K. Kniel (NRC) to A. E. Scherer (CE), dated September 27, 1977 (Evaluation of Top'ical Report's CENPD-133, Supplement 3-P and CENPD-137, Supplement,'1'-P).
NRC a~pproval 'for 6.9.1.10.g.
The core operating limits shall be determined so that all.applicable limits (e.g., fuel thermal-mechanical limits, core thdrmkl-hydraulic limits, ECCS
'imits, nuclear limits such as shutdown margin, ahd 'transient and analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle revi ions or supplements
- thereto, shall be provided upon 'issuahce, for each reload cycle to the NRC Document Control Desk with copies to the Regional Administratdr hand'esident Inspector.
PALO VERDE - UNIT 3 6-20b AHENDMENT NO. Al4 55