ML17333A989
| ML17333A989 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/11/1997 |
| From: | INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17333A987 | List: |
| References | |
| NUDOCS 9708180246 | |
| Download: ML17333A989 (18) | |
Text
ATTACHMENT 2 TO AEP:NRC:1028B EXISTING TECHNICAL SPECIFICATION PAGES MARKED TO REFLECT PROPOSED CHANGES 9708i80246 9708%i PDR ADQCK 050003i5 P PDR
REACTZVIXY CONTROL SYSTEMS SURVEILLANCE UIREMENTS 4,1.1.4 Tho MXC shall be dotermined to bo within its limits during each fuel cyclo as follovs: .
a) The ETC shall bo measured and compared to the'OL limit specified in tho COLE prior to initial operation above 50 of RATED TH LML PO'ER, after each fuel loading.
b) The MTC sha11 be measured at any THERMAL PO~ 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 vt.ll be more negative than the EOL limit, the MTC shall be remeasured at least once per 14 EPPD during the remainder of tho fuel cycle and the MTC value compared to the EOL limit.
gNs ePT.
COOK NUCLEAR PLQiT - UNIT 1 3/4 1-5a AMENDMENT NO. fff, 146
6.0 ADMINISTRATIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.
Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than th. 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
- a. Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4,
- b. Rod Drop Time Limits for Specification 3/4.1.3.3,
- c. Shutdown Rod Insertion Limits for Specification 3/4.1.3.4,
- d. Control Rod Insertion Limits for Specification 3/4.1.3.5,
- e. Axial Flux Difference for Specification 3/4.2.1,
- f. Heat Flux Hot Channel Factor for Specification 3/4.2.2,
- g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and
- h. Allowable Power Level for Specification 3/4.2.6.
6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary),
WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Report," September 1974 (Westinghouse Proprietary),
WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control/F~
Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),
WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
~SER7 H COOK NUCLEAR PLANT-UNIT 1 Page 6-17 AMENDMENT69, 4$ 4, ~, 489, 206
DM NISTRATIVE CONTROLS CORE OPERATING L MITS REPORT (Continuedj 6.9.1.9.3 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.
6.9.1.9.4 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.
SPECIAL EPORTS 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.
- d. High Specific Activity.in RCS Coolant, Specification 3.4.8.
- f. Moderator Temperature Coefficient, Specification 3.1.1.4.
- g. Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3.
- h. ECCS Actuation, Specifications 3.5.2 and 3.5.3.
- i. Violation of Safety Limit, Specification 6.7.1.
COOK NUCLEAR PLANT - UNIT 1 6-18 AMENDMENT NO. W, 444, 189
INSERT A Measurement of the MTC in accordance with 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 are provided in the HOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT, per specification 6.9.1.9.5.
INSERT B
- e. WCAP-13749-P-A, "Safety Evaluation Supporting The Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement,"
March, 1997 (Westinghouse Proprietary).
INSERT C 6.9.1.9.5 The MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT shall be prepared prior to each cycle startup and maintained on file. This report will have data to be used for the determination of the revised prediction of the 300 ppm/ARO/RTP MTC, per WCAP-13749-P"A.
~ ~
REACT~[TV CONTROL SYSTEMS SURVEILLANCE RE UIEEMENTS 4.1.1.4 Tho MTC shall bo dotezminod to bo crithin its limits during each fuol cyclo as follovs:
a) Tho ETC sho11 bo moasurod end comparod to. tho BOL limit specified in tho COLE prior to initial operation above 5% of RATED THERMAL POVER, after each fuel loading.
b) The MTC shall be measured at any THERKLL POWER vithin 7 EFPD aftez 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 "his comparison indicates that the MTC vi.ll be more negative than the EOL limit, tho MTC shall bo remeasured at least once p~c 14 EFPD during tho remaindor of the fuol cyclo and tho MTC value compared to the EOL limit.
COOK NVCIKlR PLANT - UNIT 2 3/4 1-6 AMENDMENT NO.
g7 )bi F08, l33
6.0 ADMINISTRATIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each montti following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
- a. Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4,
- b. Rod Drop Time Limits for Specification 3/4.1.3.4,
- c. Shutdown Rod Insertion Limits for Specification 3/4.1.3.5,
- d. Control Rod Insertion Limits for Specification 3/4.1.3.6,
- e. Axial Flux Difference for Specification 3/4.2.1,
- f. Heat Flux Hot Channel Factor for Specification 3/4.2.2,
- g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and
- h. Allowable Power Level for Specification 3/4.2.6.
6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
- 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-A, Revision IA, "Relaxation of Constant Axial Offset Control/F~ Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),
- d. WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
TWs E tt,7 COOK NUCLEAR PLANT-UNIT2 Page 6-17 AMENDMENTSk, 438, 4', 47$ , 190
MINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 6.9.1.9.3 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.
6.9.1.9.4 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.
(
Z~sc RT C 6 '.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.
- d. High Specific Activity.in RCS Coolant,,Specification 3.4.8.
- f. Moderator Temperature Coefficient, Specification 3 '.1.4.
- g. Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1 3.
~
- h. ECCS Actuation, Specifications 3.5.2 and 3.5.3.
- i. Violation of Safety Limit, Specification 6.7.1.
COOK NUCLEAR PLANT - UNIT 2 6-18 AMENDMENT NO. M, ~, 175
INSERT A Measurement of the MTC in accordance with 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 are provided in the MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT, per specification 6 '.1.9.5.
INSERT B
- e. WCAP-13749-P-A, "Safety Evaluation Supporting The Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement,"
March, 1997 (Westinghouse Proprietary).
INSERT C
- 6. 9. 1. 9.5 The MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT shall be prepared prior to each cycle startup and maintained on file. This report will have data to be used for the of the revised prediction of the 300 ppm/ARO/RTP HTC, determination per WCAP-13749-P-A.
ATTACHMENT 3 TO AEP:NRC: 1028B PROPOSED TECHNICAL SPECIFICATION PAGES
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.1 REACTIVITYCONTROL 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 THERMALPOWER, 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 pcr 14 EFPD during the remainder of the fuel cycle and the MTC value compared to the EOL limit.
Measurement of the MTC in accordance with 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 LIMITREPORT, pcr Specification 6.9.1.9.5.
COOK NUCLEAR PLANT-UNIT 1 Page 3/4 1-5a AMENDMENT444, 446,
6.0 ADMINISTRATIVECONTROLS MONTHLYREACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S.
Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4, Rod Drop Time Limits for Specification 3/4.1.3.3, Shutdown Rod Insertion Limits for Specification 3/4.1.3.4, Control Rod Insertion Limits for Specification 3/4.1.3.5,
- e. Axial Flux Difference for Specification 3/4.2.1, Heat Flux Hot Channel Factor for Specification 3/4.2.2,
- g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and
- h. Allowable Power Level for Specification 3/4.2.6.
6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
WCAP-9272-P-A, "Westinghouse Reload Safety Evaluation Methodology," July 1985 (Westinghouse Proprietary),
WCAP-8385, "Power Distribution Control and Load Following Procedures - Topical Rcport," September 1974 (Westinghouse Proprietary),
WCAP-10216-P-A, Revision IA, "Relaxation of Constant Axial Offset Control/F<
Surveillance Technical Specification," February 1994 (Westinghouse Proprietary),
WCAP-10266-P-A Rev. 2, "The 1981 Version of Westinghouse Evaluation Mode Using BASH Code," March 1987 (Westinghouse Proprietary).
WCAP-13749-P-A, "Safety Evaluation Supporting The Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Meaurement," March 1997 (Westinghouse Proprietaiy).
COOK NUCLEAR PLANT-UNIT 1 Page 6-17 AMENDMENT69, 484, 474) 4SQ, A4)
6.0 ADMINISTRATIVECONTROLS CORE OPERATING LIMITS REPORT Continued 6.9.1.9.3 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.
6.9.1.9.4 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.
6.9.1.9.5 The MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT shall be prepared prior to each cycle startup and maintained on file. This report will have data to be used for the determination of the revised prediction of the 300 ppm/ARO/RTP MTC, per WCAP-13749-P-A.
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:
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
- b. Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.
Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
High Specific Activity in RCS Coolant, Specification 3.4.8.
RCS Pressure Transient Mitigated By RHR Safety Valve or RCS Vent(s), Specification 3.4.9.3.
Moderator Temperature Coefficient, Specification 3.1.1.4.
Sealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3.
ECCS Actuation, Specifications 3.5.2 and 3.5.3.
Violation of Safety Limit, Specification 6.7.1.
COOK NUCLEAR PLANT-UNIT 1 Page 6-18 AMENDMENTS7, 4$ 4, 489,
3/4 LIMITINGCONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.1 REACTIVITYCONTROL 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.
Measuremcnt of the MTC in accordance with 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 LIMITREPORT, per Specification 6.9.1.9.5.
COOK NUCLEAR PLANT-UNIT2 Page 3/4 1-6 AMENDMENT&, 4P, 408, 43$ ,
Il 6.0 ADMINISTRATIVECONTROLS MONTHLY REACTOR OPERATING REPORT 6.9.1.8 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, shall be submitted on a monthly basis to the U.S. Nuclear Regulatory Commission (Attn: Document Control Desk), Washington, D.C. 20555, with a copy to the Regional Office no later than the 15th of each month following the calendar month covered by the report.
CORE OPERATING LIMITS REPORT 6.9.1.9.1 Core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT before each reload cycle or any remaining part of a reload cycle for the following:
- a. Moderator Temperature Coefficient Limits for Specification 3/4.1.1.4,
- b. Rod Drop Time Limits for Specification 3/4.1.3.4,
- c. Shutdown Rod Insertion Limits for Specification 3/4.1.3.5,
- d. Control Rod Insertion Limits for Specification 3/4.1.3.6,
- e. Axial Flux Difference for Specification 3/4.2.1,
- f. Heat Flux Hot Channel Factor for Specification 3/4.2.2,
- g. Nuclear Enthalpy Rise Hot Channel Factor for Specification 3/4.2.3, and
- h. Allowable Power Level for Specification 3/4.2.6.
6.9.1.9.2 The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in:
- 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-A, Revision 1A, "Relaxation of Constant Axial Offset Control/Fz Surveillance Technical Specification," February 1994 (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-A, "Safety Evaluation Supporting The Conditional Exemption of the Most Negative EOL Moderator Temperature Coefficient Measurement," March, 1997 (Westinghouse Proprietary).
COOK NUCLEAR PLANT-UNIT2 Page 6-17 AMENDMENT54, 438) 457, 4')
490,
6.0 ADMINISTRATIVECONTROLS CORE OPERATING LIMITS REPORT Continued 6.9.1.9.3 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.
6.9.1.9.4 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.
6.9.1.9.5 The MOST NEGATIVE MODERATOR TEMPERATURE COEFFICIENT LIMIT REPORT shall be prepared prior to each cycle startup and maintained on file. This report will have data to be used for the determination of the revised prediction of the 300 ppm/ARO/RTP MTC, per WCAP-13749-P-A.
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.
- d. High Specific Activity in RCS Coolant, Specification 3.4.8.
- f. Moderator Temperature Cocfficicnt, Specification 3.1.1.4.
- g. 'ealed Source Leakage in Excess of Limits, Specification 4.7.7.1.3.
- h. ECCS Actuation, Specifications 3.5.2 and 3.5.3.
- i. Violation of Safety Limit, Specification 6.7.1.
COOK NUCLEAR PLANT-UNIT2 Page 6-18 AMENDMENT&, 438, 47$ ,
li k