ML17311A217
| ML17311A217 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde  |
| Issue date: | 08/18/1994 |
| From: | ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR |
| To: | |
| Shared Package | |
| ML17311A216 | List: |
| References | |
| NUDOCS 9408250011 | |
| Download: ML17311A217 (6) | |
Text
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 4o v 4 4 C, Paair ly <I'S Cf 4 QE'<
d 4l DeSi i9c,d
. Vc-e.
"CalculatieRa-'I'ethods for the CE Large reak LOCA Evaluation Model,"
CENPD-132 (Methodology for Specification 3.2. 1, Lin ar Heat Rate).
5vpp Je ianna~ J-3-P-4
~ Rural, l98S'Calculative Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-l37-P, August 1974 (Methodology for Specification 3.2.1, Linear Heat Rate).
"Calculative Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-137-P, Supplement 1P, January 1977 (Methodology forSpecification 3.2. 1, Linear Heat Rate).
4~
Letter:
O.
D. Parr (NRC) to F.
M. Stern (CE), dated June 13, 1975 (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model).
NRC approva1 for:...,..., 6.9.1.10+
< Ã Letter:
K. Kniel (NRC) to A.
E. Scherer (CE), dated September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P).
NRC approval for 6.9.1.10.I, The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and analysis limits) of the safety analysis 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 Control Desk with copies to the Regional Administrator and Resident Inspector.
PALO VERDE - UNIT 1 9<082500>l ee08lS PDR ADOCK 05000528 r
p PDR 6"20b AMENDMENT NO.
69
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CORE OPERATING LIMITS REPORT (Continued) a.~ J W
Dc@i ne. ol A ~58 e.
"Calculatiea& Methods for the CE Large Break LOCA Evaluation Model,"
22323 332~
211 Il 2 1
33 f 13 lfl 1
- 321, di Heat Rate).
5crpp ja+e~4 8-P-4~ 'Pote
/9ES 4P'.
"Calculative Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-137-P, August 1974 (Methodolo+ for Specification 3.2.1, Linear Heat Rate).
"Calculative Hethods for the CE Small 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, 1975 (NRC Staff Review of the Combustion Engineering ECCS Evaluation Model).
NRC approval for:
, 6. 9. 1. 10P'. g Letter:
K. Kniel (NRC) to A. E. Scherer (CE), dated September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENP0-137, Supplement 1-P).
NRC approval for 6.9.1.10.f~
The core operating limits shall be determined so that all applicable limits (e. g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and analysis limits) of the safety analysis 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 Control Desk with copies to the Regional Administrator and Resident Inspector.
PALO VERDE - UNIT 2 6-20b AMENDMENT NO. 55
lq
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It It I
P I
4 I
t I
P
ADHINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
+
~" ~
P'l Dcs) g 4.d'V S 5
. Vc e.
"Calculatioaak Methods for the CE Large Break LOCA Evaluation Model,"
222323232~2N 1 1 1
Nf f PP fff 1
3.2.1, 11 Heat Rate).
5upp(in g~Q 3,p-g 3 v~a I9$%
"Calculative Methods for the CE Small Break LOCA Evaluation Hodel,"
CENPD-137-P, August 1974 (Methodology for Specification 3.2.1, Linear Heat Rate).
"Calculative Methods for the CE Small Break LOCA Evaluation Model,"
CENPD-137-P, Supplement 1P, January 1977 (Methodology for Specification 3.2.1, Linear Heat Rate).
Letter:
0.
D. Parr (NRC) to F.
M. Stern (CE), dated June 13, 1975 (NRC Staff Review of the Combustion Engineering ECC$ Evaluation Hodel).
NRC approval for:...,...,
6.9.1310P'.
J.
Letter:
K. Kniel (NRC) to A.
E. Scherer (CE), dated September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1"P).
NRC approval for 6.9. l.10./. ~
The core operating limits shall be determined so that all applicable limits (e. g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and analysis limits) of the safety analysis are met.
The CORE OPERATING LIMITS REPORT, including any mid-cycle
) evisions 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 3 6"20b AMENDMENT NO. "2
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