ML042160408

Tech Spec Pages for Amendment No. 217 Regarding the Relocating of the Primary Coolant System Pressure, Cold-Leg Temperature and Flow Departure from Nucleate Boiling Limits to the Core Operating Limits Report

ML042160408
Person / Time
Site:	Palisades
Issue date:	08/02/2004
From:	NRC/NRR/DLPM/LPD3
To:
Stang J, NRR/DLPM, 415-1345
Shared Package
ML042160428	List: ML042160408
References
TAC MC0804
Download: ML042160408 (4)

Text

PCS Pressure, Temperature, and Flow DNB Limits 3.4.1 3.4 PRIMARY COOLANT SYSTEM (PCS) 3.4.1 PCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) Limits LCO 3.4.1 PCS DNB parameters for pressurizer pressure, cold leg temperature, and PCS total flow rate shall be within the limits specified in the COLR.

APPLICABILITY: MODE 1.

I ACTIONS CONDITION . REQUIRED ACTION COMPLETION TIME A. Pressurizer pressure, PCS A.1 Restore parameter(s) to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> cold leg temperature, or within limit.

PCS total flow rate not within limits.

B. Required Action and B.1 Be in MODE 2. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met.

Palisades Nuclear Plant 3.4.1 -1 Amendment No. 489, 217

PCS Pressure, Temperature, and Flow DNB Limits 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1 Verify pressurizer pressure within the limits 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> specified in the COLR. 1, SR 3.4.1.2 Verify PCS cold leg temperature within the limit 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> specified in the COLR. i SR 3.4.1.3 ------------------------------NOTE-----------------------

Not required to be performed until 31 EFPD after THERMAL POWER is Ž 90% RTP.

Verify PCS total flow rate within the limit specified 18 months in the COLR.

AND I After each plugging of 10 or more steam generator tubes Palisades Nuclear Plant 3.4.1 -2 Amendment No. A89, 217

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.4 MonthlV Operating Report Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the NRC no later than the fifteenth of each month following the calendar month covered by the report.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a. Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

3.1.1 Shutdown Margin 3.1.6 Regulating Rod Group Position Limits 3.2.1 Linear Heat Rate Limits 3.2.2 Radial Peaking Factor Limits 3.2.4 ASI Limits 3.4.1 DNB Limits

b. The analytical methods used to determine the core operating limits shall be those approved by the NRC, specifically those described in the latest approved revision of the following documents:

1. EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs," Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

2. ANF-84-73 Appendix B (P)(A), "Advanced Nuclear Fuels Methodology for Pressurized Water Reactors: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. (Bases report not approved) (LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

3. XN-NF-82-21 (P)(A), "Application of Exxon Nuclear Company PWR Thermal Margin Methodology to Mixed Core Configurations,"

Exxon Nuclear Company. (LCOs 3.2.1, 3.2.2, & 3.2.4)

4. EMF-84-093(P)(A), "Steam Line Break Methodology for PWRs, "Siemens Power Corporation.

(LCOs 3.1.1, 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

5. XN-75-32(P)(A) Supplements 1 through 4, "Computational Procedure for Evaluating Fuel Rod Bowing," Exxon Nuclear Company. (Bases document not approved)

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

Palisades Nuclear Plant 5.0-25 Amendment No. 489, 217

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 COLR (continued)

14. EMF-92-116(P)(A), 'Generic Mechanical Design Criteria for PWR Fuel Designs," Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, 3.2.2, & 3.2.4)

15. EMF-2087(P)(A), "SEM/PWR-98: ECCS Evaluation Model for PWR LBLOCA Applications," Siemens Power Corporation.

(LCOs 3.1.6, 3.2.1, & 3.2.2)

16. ANF-87-150 Volume 2, "Palisades Modified Reactor Protection System Report: Analysis of Chapter 15 Events," Advanced Nuclear Fuels Corporation. [Approved for use in the Palisades design during the NRC review of license Amendment 118, November 15, 1988] (LCOs 3.1.6, 3.2.1, 3.2.2, & 3.4.1)

17. EMF-1 961 (P)(A), Revision 0, Siemens Power Corporation, July 2000, "Statistical SetpointlTransient Methodology for Combustion Engineering Type Reactors." (LCOs 3.1.6, 3.2.1, 3.2.2, 3.2.4, &

3.4.1)

18. EMF-2328 (P)(A), Revision 0, Framatome ANP, Inc., March 2001, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based."

(LCOs 3.1.6, 3.2.1, & 3.2.2)

c. The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems limits, nuclear limits such as shutdown margin, transient analysis limits, and accident analysis limits) of the safety analysis are met.

d. The COLR, including any mid cycle revisions or supplements, shall be provided, upon issuance for each reload cycle, to the NRC.

Palisades Plant 5.0-27 Amendment No. 189, 4-9,209, 217