ML17311A217

Proposed Tech Specs Adding Analytical Method Suppl Entitled, Calculative Methods for CE Large Break LOCA Evaluation Model for Analysis of CE & W Designed Nsss.

ML17311A217
Person / Time
Site:	Palo Verde
Issue date:	08/18/1994
From:	ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
Shared Package
ML17311A216	List: ML17311A217
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'<

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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 to Staff Review of the approva1 for: ..., ...,

(NRC) F. M. Stern (CE), dated June 13, 1975 Combustion Engineering ECCS Evaluation Model).

6.9.1.10+

(NRC NRC

< 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 6"20b AMENDMENT NO. 69 9<082500>l ee08lS PDR ADOCK 05000528 r

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CORE OPERATING LIMITS REPORT (Continued) a.~ J W Dc@i ne. ol A ~58 e.

22323 332~

"Calculatiea&

Heat Rate).

Methods for the 5crpp ja+e~4 211 CE Il 2 1 Large Break LOCA Evaluation Model,"

33 f 8-P-4~ 'Pote /9ES 13 lfl 1 321, di 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

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ADHINISTRATI VE CONTROLS CORE OPERATING LIMITS REPORT (Continued) + ~" ~

Dcs) g 4.d'V S 5

. P'l

. Vc

e. "Calculatioaak Methods for the CE Large Break LOCA Evaluation Model,"

222323232~2N Heat Rate).

1 1 1 Nf f PP fff 1 3.2.1, 11 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.

- 6" 20b AMENDMENT NO. "2 PALO VERDE UNIT 3

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