ML17310A801
| ML17310A801 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 11/19/1993 |
| From: | Quay T Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML17310A803 | List: |
| References | |
| NUDOCS 9311300052 | |
| Download: ML17310A801 (8) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 RIZON UB IC S
R ICE CO A
DOCKET NO.
STN 50-528 PALO VERDE NUCLEAR GENERATING STATION UNIT NO. I AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.
72 License No. NPF-41 The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by 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 Cali,fornia Edison
- Company, Public Service Company of New Mexico, Los Angeles Department of Water and-
- Power, and Southern California Public Power Authority, dated September 8,
1993, 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 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.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated'n 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:
9311300052 93k'I29 T
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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. 72, and the Environmental Protection Plan contained in Appendix B,. are hereby incorporated into this license.
APS shall operate the facili.ty in accordance with the Technical Specifications and the Environmental Protection 'Plan,.
except where otherwise stated in speci.fic,license.conditions.
This license amendment is effective as: o'f 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 Theodore R. quay, Director Project.Directorate V
Division of Reactor Projects III/IV/V Office of Nuclear Reactor 'Regulation Date of Issuance:
November 19, 1993
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TTACHMEN 0
S D
N M ND NT NO. 72 F
C TY OP NG ICENSE NO.
NP -4 DOCKE 0;
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 vertical lines indicating the areas of change.
The corresponding overleaf page is also provided to maintain document completeness.
REMOVE'-20a INSERT 6-20a
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11
DM NISTRATIVE CON S
OP RATING IMITS REP 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 ~
b.
c ~
d.
e.,f.
9, h.
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 Specificltion 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 (Methodology for Specifications
- 3. 1.1'.2, Shutdown Margin K., - Any CEA Withdrawn; 3.1.1.3, Moderator Temperature Coefficient BhL 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 1 6-20a AMENDMENT ND.
!$ 7E
ADMINISTRATIVE CONTROLS
(~
CORE OPERATING LIMITS.REPORT (Contiriued) e.
"Calculationail Methods for the CE Large Break LOCA IEvailuation Model,",
CENPD-132-IP, August 1974 (Me'thodologiy for Specifi'ca'tion 3'.2.l, Linear Heat Rate);
f.
"Calculationail Methods foz 'tlhe CE Large Break LOCA Evaluation Model,"'ENPD-132-IP, Supplement 1February 1975 (Methodology for'pecification 3,.2.1, Lineair Heat Rate)..
"Calculationail Methods for tlhe CE Large Break LOCA Evaluation Model,"
CENPD-132-IP, Supplement 2-P, July'975 (Methodology for Specification 3.2.1, Linear -Heat Rate).
h.
"Calculative Methods for the CE Small Break LOCA'valuation Model,"
CENPD-137-P, August 1974 (Methodo'logy foz Specification 3.2.1 OncLar Heat Rate),.
"Calculative Methods for the CE Smal~l Break LOCA Evaluation Model,"
CENPD-137-P, Supplement 1P,- January 1977 (Hethodology for Specification
~
3.2.1, Linear Heat Rate).
j.
Letter:
0,.
D. Parr (NRC) to F.
M.. Stern (CE), darted June 13, 1975'(NRC'taff Review of the Comlbustion Engineering ECCS Evaluation Model'. 'RC approval for:
6.9.1.10e, 6.9.1.1Of,','9.1.10h'.
k.
Letter:
0.,
D. Parr (NRIC) to A. EScherer (CE), da'tedl December 9, 1975 (NRC Staff Review of thie P'roposed Comb6stlion Engineering ECCS Evaluation Model Changes).
NRC aplpraiva') for.'.9>1.10g.
Letter:
K,. Kniel (NRC) to A,.
E. Scherer (CE), darted September 27',
1977 (Evaluation of Topicail Reports CENPDi133, Supplement 3-P and CENPD-137, Supp'Iement 1-P).
NRC app'roval'ear 6.9.1.1O. i.
The. core operating 1 imits shall be dletermined 'so'that'all applicable limits (e.g., fuel thermal-mechanical limits, core'hermalihydraulic limits, ECCS 'limits, nuclear'.limits such as shutdown margin, and tr'ansient'and analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any hidl-cycle revisions or supplements
- thereto, shal'I be providled upon is'suance,,'foz'ach reload cycle,
'o the NRC Document Control Desk with copies to thei Regional Administrator'rid Resident Inspector.
PALO VERDE - UNIT 1 6-2Ob AMENDMENT NO.
69