ML17332A231
| ML17332A231 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 07/26/1994 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17332A230 | List: |
| References | |
| NUDOCS 9408010238 | |
| Download: ML17332A231 (15) | |
Text
REACTZVITY CONTROL SYS~S SURVEILLANCE RE UI~ENTS 4.1.1.4 The MTC shall b'e determined to be within its limits during each fuel cycle as follows:
a) The ETC shall be measured and compared to the'OL limit specified in the COIR prior to initial operation abave 54 of RATED TH R~ POKER, after each fuel loading.
b) The MTC shall be measured at any TH~&L PO~ within 7 E:PD after reaching an equilibrium boron concentration of 300 ppm+
The measured value shall be compared to the 300 ppm surveillance limit specified in the COLR. In.the event this comparison indicates that the MTC will be more negative than the EOL limit, the MTC shall be remeasured at least once per 14 EZPD during the remainder of the fuel cycle and the MTC value compared to the EOL limit.
Measurement of the MTC in accordance to 4.1.1.4.b. may be suspended provided the benchmark criteria and the revised prediction as documented in the COLR are satisfied. Data required for the calculation of the revised prediction is provided in the "Most Negative Moderator Temperature Coefficient Limit Report," per Specification 6.9.1.12.
COOK NUCLEAR PLANT 9408010238 '&0726
- UNIT 1 3/4 1-5a AMENDMENT NO. flan, ~
(1 t
~ ~
~ ADMINISTRATIVE CONTR CORE OPERATING LIMITS REPOR (Continued)
- b. WCAP-8385, "Power Distribution Control and Load Following Procedures Topical Report," September 1974 (Westinghouse Proprietary),
WCAP-10216-P-A, Part B, "Relaxation of Constant Axial Offset Control/F Surveillance Technical Specification," June 1983 (Westinghouse Proprietary),
<<Qgg(6 WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
6.9.1.11.3 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 accident analysis limits) of the safety analysis are met.
6.9.1.11.4 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.
f~siQT SPECIA REPORTS 6
pygmy 6.9.2 Special reports shall be submitted to the attention of the document control desk - U.S. Nuclear Regulatory Commission (Washington, D.C. 20555), with copies to the Region III Administrator and the Resident Inspector at the Cook Nuclear'lant within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
a ~ Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
- b. Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.
C. Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
- d. High Specific Activity in RCS Coolant, Specification 3.4.8.
Specification 3.4.9.3.
Moderator Temperature Coefficient, Specification 3.1.1.4.
COOK NUCLEAR PLANT - UNIT 1 6-18 AMENDMENT NO ~
Insert A
- e. WCAP-13749-P, "Safety Evaluation Supporting The Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," May, 1993 (Westinghouse Proprietary).
Insert B 6.9.1.12 The "Most Negative Moderator Temperature Coefficient Limit Report" shall be prepared prior to each cycle startup and maintained on file. This report'ill have data to be used for the determination of the revised prediction of the 300 ppm/ARO/RTP MTC, per WCAP-13749-P.
~vCT~'.TT COHTROL SYSTEMS SOZVZIIJ~CE RZ UIRWKNTS 4.1.1.4 The K'C shall be determined to be rithin iw limits du=ing each fuel cyc1e as fo13,ors:
.a) The EEC ahaU. be measured and compared to. the BOL limit specified in the COIR prior to initial operation above 5% of RATED THE22fAL POWER, after each fuel loading.
b) The EZC shall be measured at any THERMAL POWER vt.thin 7 EFPD after reaching an equilibrium boron concentration of 300 ppm.
The measured value shall be compared to the 300 ppm surveillance limit specified in the COLR. In the event this comparison indicates that the ETC vi).1 be more negative than the EOL limit, the HTC shall be remeasured at least once per 14 EFPD during the remainder of the fuel cycle and the EZC value compared to the EOL limit.
Measurement of the MTC in accordance to provided thee bene 4.1.1.4.b. may ma b e suspended in the COLR areenchmark criteria and the revised prediction as documented satisfied. Data required for the calculation revised prediction is provided in the "Most Negative Moderator of the Temperature Coefficient Limit Report," per Specification 6.9.1.12-COOK NC I2ME PLANT - UNIT 2 3/4 1-6 ~ND~ HO~ ggf,
ADMINISTRATI ONTROLS CORE OPERATING LIMITS REPORT (Continued)
- a. WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"
July 1985 (Westinghouse Proprietary).
- b. WCAP-8385, "Power Distribution Control and Load Pollowing Procedures - Topical Report," September 1974 (Westinghouse Propr'etary),
- c. WCAP-10216-P-A, Part B, "Relaxati.on of Constant Axial Offset Control/P Surveillance Technical Specification," June 1983 (Westingh8use Proprietary)f R,l d. WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation A,
Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
plE <x 6.9.1.11.3 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 acci.dent analysis limits) of the safety analysis are met.
6.9.1.11.4 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 contxol desk with copies to the Regional Administrator and Resident Inspector.
jN'5C V SP CIAL REPORTS 5 6.9.2 Special reports shall be submitted to the attention of the document gpgE control desk - U.S. Nuclear Regulatory Commission (Washington, D.C. 20555),
with copies to the Region IIZ Administ ator and the Resident Inspector at the Cook Nuclear Plant within the time period specified for each xeport. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable refexence specificat'on:
a Inoperable Seismic Moni.toring Instrumentation, Specification 0
3.3 '.3.
Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.
C Inoperable Meteorological Monitoring Instrumentation, Specification
~
3.3 '.4.
- d. High Specific Activity in RCS Coolant, Specification 3.4.8.
Moderator Temperature Coefficient, Specification 3.1.1.4.
COOK NUCLEAR PLANT - UNIT 2 6-18 AMENDMENT NO. ~, 3r36
Insert A A
- e. WCAP-13749-P, "Safety Evaluation Supporting The Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," May, 1993 (Westinghouse Proprietary).
Insert B 6.9.1.12 The "Most Negative Moderator Temperature Coefficient Limit Report" file. This shall be prepared prior to each cycle startup and maintained onrevised report will have data to be used for the determination of the prediction of the 300 ppm/ARO/RTP MTC, per WCAP-13749-P.
ATTACHMENT 3 TO AEP:NRC:1028A PROPOSED TECHNICAL SPECIFICATION PAGES
4 REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE UIREMENTS 4.1.1.4 The MTC shall be determined to be within its limits during each fuel cycle as follows:
a) The MTC shall be measured and compared to the BOL limit specified in the COLR prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
b) The MTC shall be measured at any THERMAL POWER within 7 EFPD after reaching an equilibrium boron concentration of 300 ppm.
The measured value shall be compared to the 300 ppm surveillance limit specified in the COLR. In the event this comparison indicates that the MTC will be more negative than the EOL limit, the MTC shall be remeasured at least once per 14 EFPD during the remainder of the fuel cycle and the MTC value compared to the EOL limit.
Measurement of the MTC in accordance to 4. 1. 1.4.b. may be suspended provided the benchmark criteria and the revised prediction as documented in the COLR are satisfied. Data required for the calculation of the revised prediction is provided in the "Most Negative Moderator Temperature Coefficient Limit Report," per Specification 6.9.1.12.
COOK NUCLEAR PLANT UNIT 1 3/4 1-5a AMENDMENT NO. 4k', 446
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued)
- b. WCAP-8385, "Power Distribution Control and Load Following Procedures Topical Report," September, 1974 (Westinghouse Proprietary),
C~ WCAP-10216-P-A, Part B, "Relaxation of Constant Axial Offset Control/F~
Surveillance Technical Specification," June, 1983 (Westinghouse Proprietary),
- d. WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March, 1987 (Westinghouse Proprietary).
- e. WCAP-13749-P, "Safety Evaluation Supporting The Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," May, 1993 (Westinghouse Proprietary).
6.9.1.11.3 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 accident analysis limits) of the safety analysis are met.
6.9.1.11.4 The CORE OPERATING LZMITS REPORT, including any mid-cycle revisionsto or supplements thereto, shall be provided upon issuance, for each reload cycle, the NRC document control desk with copies to the Regional Administrator and Resident Inspector.
6.9.1.12 The "Most Negative Moderator Temperature Coefficient Limit Report" shall be prepared prior to each cycle startup and maintained on file. prediction This report will have data to be used for the determination of the revised of the 300 ppm/ARO/RTP MTC, per WCAP-13749-P.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the attention of the document control desk U. S. Nuclear Regulatory Commission (Washington, D.C. 20555), with copies to the Region III Administrator and the Resident Inspector at the Cook Nuclear Plant within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
a ~ Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
- b. Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.
C ~ Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
High Specific Activity in RCS Coolant, Specification 3.4.8.
Specification 3.4.9.3.
Moderator Temperature Coefficient, Specification 3.1.1.4.
COOK NUCLEAR PLANT UNIT 1 6-18 AMENDMENT NO. &7, 454
REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE UIREMENTS
- 4. 1. 1.4 The MTC shall be determined to be within its limits during each fuel cycle as follows:
a) The MTC shall be measured and compared to the BOL limit specified in the COLR prior to initial operation above 5% of RATED THERMAL POWER, after each fuel loading.
b) The MTC shall be measured at any THERMAL POWER within 7 EFPD after xeaching an equilibrium boron concentration of 300 ppm.
The measured value shall be compared to the 300 ppm surveillance limit specified in the COLR. In the event this comparison indicates that the MTC will be more negative than the EOL limit, the MTC shall be remeasured at least once per 14 EFPD during the remainder of the fuel cycle and the MTC value compared to the EOL limit.
Measurement of the MTC in accordance to 4.1.1.4.b. may be suspended provided the benchmark criteria and the revised prediction as documented in the COLR are satisfied. Data required for the calculation of the revised prediction is provided in the "Most Negative Moderator Temperature Coefficient Limit Report," per Specification 6.9.1.12.
COOK NUCLEAR PLANT - UNIT 2 3/4 1-6 AMENDMENT NO. &%g ~g kQ8~ 438
ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) a ~ WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology,"
July, 1985 (Westinghouse Proprietary).
- b. WCAP-8385, "Power Distribution Control and Load Following Procedures Topical Report," September, 1974 (Westinghouse Proprietary),
c ~ WCAP-10216-P-Ai Part Bg Relaxation of Constant Axial Of fset Control/F< Surveillance Technical Specification," June, 1983 (Westinghouse Proprietary),
d0 WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March, 1987 (Westinghouse Proprietary).
- e. WCAP-13749-P, "Safety Evaluation Supporting The Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," May, 1993 (Westinghouse Proprietary).
6.9.1.11.3 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 accident analysis limits) of the safety analysis are met.
6.9.1.11.4 The CORE OPERATING LIMITS REPORT, including any mid-cycle revisionsto or supplements thereto, shall be provided upon issuance, for each reload cycle, the NRC document control desk with copies to the Regional Administrator and Resident Inspector.
6.9.1.12 The "Most Negative Moderator Temperature Coefficient Limit Report" shall be prepared prior to each cycle startup and maintained on file. prediction This report will have data to be used for the determination of the revised of the 300 ppm/ARO/RTP MTC, per WCAP-13749-P.
SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the attention of the document with control desk U.S. Nuclear Regulatory Commission (Washington, D.C. 20555),
copies to the Region III Administrator and the Resident Inspector at the Cook Nuclear Plant within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
a ~ Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
- b. Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.
C ~ Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
- d. High Specific Activity in RCS Coolant, Specification 3.4.8.
Specification 3.4.9.3.
Moderator Temperature Coefficient, Specification 3.1.1.4.
COOK NUCLEAR PLANT UNZT 2 6-18 AMENDMENT NO. ~g 488
f e<r