ML17311B219
| ML17311B219 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 10/04/1995 |
| From: | Thomas C NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17311B220 | List: |
| References | |
| NUDOCS 9510130397 | |
| Download: ML17311B219 (24) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 ARIZONA PUBLIC SERVICE COMPANY ET AL.
OCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 101 License No.
NPF-41 1.
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'ower 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 3, 1995, 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; 2.
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 Fac'ility Operating License No. NPF-41 is hereby amended to read as follows:
95i0130397 95f004 PDR ADQCK 05000528,'
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41
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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.
- 101, and the Environmental Protection Plan contained in Appendix B, are hereby, incorporated into this license.
APS shall operate
.the facil.ity 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 to be implemented prior to startup from RF06.
FOR THE NUCLEAR REGULATORY COMMISSION Charles R. Thomas, Project Manager 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 4, 1995
4I
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ATTACHMENT TO LICENSE AMENDMENT' NDMENT NO.
101 TO'ACILITY OPERATING LICENSE NO.
NPF-41 DOCKET NO.
STN 50-528 Replace the following page of the Appendix A Technical Specifications with the enclosed page.
The revised page is identified by Amendment number and contains marginal lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE 6-20b INSERT 6-20b
~I 41
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AD>1NISTRAT IV E CONTROLS CORE OP RATING IMITS R PORT c ~
d.
e.f.
9 ~
h.l.j-6.9. 1. 10 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
a.
"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.
"The ROCS and DIT Computer Codes for Nuclear Design,"
CENPD-266-P-A, April 1983 (Hethodology for Specifications
- 3. 1. 1.2, Shutdown.Hargin K; - Any CEA Withdrawn; 3. 1. 1.3, Moderator Temperature Coefficient BOL and EOL limits and 3. 1.3.6, Regulating CEA Insertion Limits).
c.
"Safety Evaluation Report related to the Final Design of the Standard Nuclear Steam Supply, Reference Systems CESSAR System 80, Docket. No.
STN 50-420, "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 Assembli'es-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,).
d.
"Modified Statistical Combination of Uncertainties,"
CEN-356(Y)-P-A Revision OI-P-A, Hay 1988 and "System 80 Inlet Flow Distribution,"
Supplement I-P to Enclosure I-P to LD-82-054, February 1993 (Hethodology for Specification 3.2.4, DNBR Margin and 3.2.7 Axial Shape Index).
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.
Shutdown Hargin K., - Any CEA itithdrawn for Specification 3. 1:1.2 b.
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 Specifi,cation 3.1.3.1 Regulating CEA Insertion Limits for, Specification 3.1.3.6 Part Length CEA Insertior 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 PALO VERDE - UNIT 1
6-20a AMENDMENT NO. ~, ~
76
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) e.
"Calculative Methods 1For tHe CE Large Break LOCA,Evalua'tion Model for the Analysis of CI= and W Designed NSSS,"
CENPD-132, Supplement 3-P-A, June '1985 (Methodology fair Speci1Fication 3.2.1, Linea'r Heat,'ate).
f.
"Calculative Methods
)For the CE Small Break LOCA Evaluation, Model ",
CENPD-137-P,
- August, 1974 (Methodology for Specification 3.2. 1, Linear Heat Rate).
g.
"Calculative Hethodls For'he CE Small Break LOCA Evaluation,Mo'del ",
CENPD-137-P, Supplement 1P January 1977 (Methodology for Specif'ication 3.2.1, Linear Heat Rate).
h.
Letter:
0.
D., Parr (NRC) to F.
M. Stern (CE), dated June 13, 197'5 (NRC StaiFf Review of the Combustion Engineering 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 Tiopical Reports CENPD-133, Supplement 3-P andi CENPD-137, Supplement 1-P).
NRC approval for 6.9. 1. 10.g.
j.
"Fuel Rod Maximum Allowable Pressu're,"
CEN-372-P-A, May 1990 (Methodo'logy for Specification 3.2. 1, Linear =Heat Rate).
k.
Letter:
A.
C.. Thadani (NRC) to,A., E. Scherer (CE), dated Apri'1 10,
.1990,
("Acceptance for Reference CE l'opical Report CEN-372-P").
NRC approval for 6.9.1.10.j.
The core operating limits shall be determined so thait all applicable l,imits (e.g., fuel therma'I-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits
. uch as shutdown mhrgin) aind 'transient and analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPOR'T, including any mid-cycle revisions or supplements
- thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with,copies to the Regional Administrator and Resident Inspector.
.PALO VERDE UNIT '1 6-20b
-'mendment No. 69-;83, 101
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~O 4~*~4 UNITED STATES NUCLEAR REGULATORY GOMMISSlON WASHINGTON, D.C. 2055&4001 ARIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-529 PALO VERDE NUCLEAR GEN RATING STATION UNIT NO.
2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 89 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 August 3,
- 1995, 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.
D.
E.
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; The issuance of this amendment wil.l not be inimical to the common defense and security or to the health and safety of the public; and 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 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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T 3.
(2)
Technical S ecifications and Environmental Protection 'Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.
89, and the Environmental Protection Plan contained in Appendix B, are heregy 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 to be implemented prior to startup from RF06.
FOR THE 'NUCLEAR REGULATORY COMMISSION Charles R. Thomas, Project Manager 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 4, 1995
41 e
~
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'TACHMENT TO LICENSE AMENDMENT MENDMENT NO.
89 TO FACILITY OPERATING LICENSE NO.
NPF-51 DOCKET NO.
STN 50-529 Replace the following page of the Appendix A Technical Specifications, with the enclosed page.
The revised page is identified by amendment number and conta'ins marginal lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE 6-20b INSERT 6-20b
0 1
I I
ADHINISTRATIVE CONTROLS OR OP RAT NG H TS R
PORT 6.9,1.9 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.
'c ~
d.
e.f.
9 ~
h.
1
~j ~
Shutdown Hargin K., - Any CEA Withdrawn for Specification 3.1. 1.2 Hoderator 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 Meat Rate for Specification 3.2.1 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 analytical methods used to determine the core operating limits shall be those previously reviewed and approved'y the NRC in:
a.
C.
d.
"CE Hethod for. Control Element Ass'embly Ejection Analysis,"
CENPD-0190-A, January 1976 (Hethodology for. Specification 3. 1.3.6, Regulating:
CEA Insertion Limits).
"The ROCS and DIT Computer Codes fot Nuclear Design,"
CENPD-266-P-A, April 1983 (Hethodology for Specifications 3.1.1.2, Shutdown Hargin 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 (Harch 1983),
No.
2 (September 1983),
No.
3 (December 1987)
(Hethodology for Specifications 3.1.1.2, Shutdown Hargin 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. I, Hovable 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 Ti:lt - T ).
"Hodified Statistical Combination of Uncertainties,"
CEN-356(V)-P-A Revision 01-P-A, Hay 1988 and "System 80 Inlet Flow Distribution,"
Supplement 1-P to Enclosure 1-P to LD-82-054, February 1993 (Hethodology for Specification 3.2.4, ONBR Hargin and 3.2.7 Axial Shape Index).
PALO VERDE - UNIT 2 6-20a AHENDHENT NO M 62
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ddldlllllld IRRTITI NNI I
~TI II RIMLT Td>>
I I)
"Calculative Methods
)For the CE La'rge, Break L'OCA,Evaluation ~Model~
for the Analysis of CE and M Designed NSSS,"
CENPD-132, Supgleietit
'-P-A, June 1985 (Methodology for Specification 3.2. 1, Linear Hea't Rate).
0 E 'OPERA e.
f.
"Calculative Methods
>For the.CE Small Break LOCA Evaluation Model,"
CENPD-137-P, August 1974 '(Methodology'for Specification 3.2,.1, Linear Heat 'Rate).
g; "Calculative Methods f'r the CE Small Break LOCA Evaluation Model
'-'ENPD-137,-P,
.Supplement.,lP, January 1977 (Methodology for Specification 3'.2.1, Linear Heat,'ate).
h.
Letter:
0.
D. Parr (NRC) to iF. M. Stern (CE), dated June 13,
- l975 (NRC Staff. Review of the Combustion Engineering ECCS EvaluatJioh Model).
NNRC approval for:
6.9.1.10f'.
i.
Letter:
K. Knie'il.(NRC) to A. E. Scherer (CE), dated September'27',
1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-'P And'ENPD-137, Supple'ment 1-P).
NRC approval for 6.9. 1. 10.g.
"Fuel IRod Maximum Allowable Pressure,"
CEN-372-IP-'A, May 1990 (Methodology f'r Specification 3'.2,.1, Linear Heat Rate).
k.
Letter:
A. C. Thadanii (NRC) to A. E. Scherer (CE), dated Apri'll 10,
- 1990,
("Accep'tance for Reference CE Topical Report, CEN-372-P")
~
NRC approval for 6.9.,1.10, j.
The core operating limits.hall be determi'ned s'o that.all'piplicable limits (e.g., fuel thermal-mechanical limits, core th'ermal-hydraulic 'limits, EC(S limits, nuclear limits such as shutdown margin, and transient and analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORl, including Any mid-cycle revisions or supplements
- thereto,
. hall be provided upon issuance, for each reload cycle,
~
to the NRC Do'cument Control Desk w'ith copies to the Regional Administrator and Resident Inspector.
PALO VERDE UNI'lI 2 6-20b Amendment No. M-,F9>99
\\ 'yR RE00
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 RIZONA PUBLIC SERVICE COMPANY ET AL.
DOCKET NO.
STN 50-530 PALO VERDE NUCLEAR GENERATING STATION UNIT NO.
3'MENDMENT TO FACILITY OPERATING LICENSE Amendment No.. 72 License No.
NPF-74 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.'he 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 Wat'er and.
- Power, and Southern California Public Power Authority dated
'August 3,
- 1995, 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.
D.
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; 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 2.
E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have'een 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:
0 4~
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~
C
3.
(2)
Technical S ecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment,No. '2, 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 to be implemented prior to startup from RF05.
FOR THE NUCLEAR REGULATORY COMMISSION Ch ries R.
- homas, Project Manager Project Directorate IV.-2 Division of Reactor Projects II.I/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
October 4, 1995
Cl P
TTACHMENT TO LICENSE AMENDMENT.
SE ET:
LI E
DOCKET NO.
STN 50-530 Replace the following page of the Appendix. A Technical Specifications with the enclosed page.
The revised page is identified by amendment number and contains marginal lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE 6-20b INSERT 6-'20b
~I
)
I P
~
~
p ~
1
\\
ADHINISTRAT V CONTRO 5
COR OP RATING HITS R
PORT 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 0 b.
c d.
e.f.
g.
h.
i ~j ~
Shutdown Margin K., - Any CEA Mithdrawn for Specification 3. 1.1.2 Moderator Temperature Coefficient BOL and EOL l.imits 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 Hargin for Specification 3.2.4 Axial Shape Index for Specification 3.2.7 6.9. 1. 10 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
a.
c.
d.
"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 (Hethodology for Specifications
- 3. 1. 1.2, Shutdown Margin K., - Any CEA Mithdrawn; 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 Mithdrawn;
- 3. 1.1.3, Moderator Temperature Coefficient BOL and EOL l'imits; 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 I-P to Enclosure 1-P to LD-82-054, February 1993 (Methodology for Specification 3.2.4, DNBR Hargin and 3.2.7 Axial Shape Index).
PALO VERDE - UNIT 3 6-20a AMENDMENT NO.~
48
ADMINISTRATIVE CONTROI S CORE OPERATING LIMITS REPORT (Continued) e.
"Calculative Methods for the CE -Large Break LOCA Evaluation Model for the Analysis of CE and M Designed NSSS;"
CENPD-132, Supple@'sent 3-P-A, June 1985 (Methodology for Specification 3.2. 1, Linear Heat Rate).
f.
"Calcu'lative. Hethods f'r the CE Small Break LOCA Evaluation Model,"
CENPD-137-P August 1974 (Method'ology'or Specification 3.2: 1,
'inear Heat Rate).
g.
"Calculative Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-137-P Supplement 1P, Janu'ary 1977 (Methodology for Specificati<)n 3.2.1,. Linear Heat~ Rate).
~
h.
Letter::
0.
D. Parr (NRC) to F.
M. Stern (CE), dated June 13, 1975 (NRC Staff Review of the Combustion Engineering ECCS Evaluathonl Model),.
NRC approval for:
6.9. 1.10f.,
i.
Letter::
K. Kniel (NRC) to A. E. Scherer (CE), dated September
'27,',
1977 (Evaluation of Topical Reports CENPD-133',
Supplement 3-P and'ENPD-137, Supplement 1-P).
NRC approval f'r 6i,9.1.10.g.
J.
"Fuel Rod Maximum A'llowable Pressure,~
GEN-37'2-P-A, Hay 1990'Methodology for Specification 3.2.1, Li'near Heat Rate).
k.
Letter;.
A. C. Thadani (NRC) to A.,E. Scherer (CE), dated Aplril ll),
1990; ("Acceptance. i'or.Reference'f Tbpica'll Report CEN-372-P"').
NRC approval for 6.9.1.10.j.
The"core..operating limits shall be determined sb that all applicable 1/mits (e.g., fuel thermal-mechanical limits, cor'e t,hermal-hydraulic. limits, ECCS limits, nuclear limits such as, shutdown margin, and transient and.analysis limits) of the safety analysi.
are met.
The CORE OPERATING LIflITS REPORT, including any mid-cycle revisions. or~
supplements
- thereto, shall be provided upoh iss)san'ce,',
f'or each reload cycle to the NRC Document Control Desk wiith copiihs to the f<egional Administrator and Resident Inspector.
PALO VERDE UNI1 3 6-20b Amendment No. 4MDS,72