ML17335A444
| ML17335A444 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 12/28/1998 |
| From: | Stang J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17335A445 | List: |
| References | |
| NUDOCS 9901050217 | |
| Download: ML17335A444 (48) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 INDIANAMICHIGANPOWER COMPANY DOCKET NO. 50-315 DONALDC. COOK NUCLEAR PLANT UNIT 1 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 226 License No. DPR-58 1.
The U.S. Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Indiana Michigan Power Company (the licensee) dated June 11, 1996, and supplemented March 26, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment willnot be inimical to the common defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 of the "Commission's regulations and all applicable requirements have been satisfied.
990i0502i7 98i228 PDR ADGCK 050003i5 P
PDR Accordingly, Facility Operating License No. DPR-58 is hereby amended to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's application dated June 11, 1996, as supplemented March 26, 1997, and evaluated in the staffs safety evaluation dated December @ 1998. This license is also hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-58 is hereby amended to read as follows;.
B.
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No.226, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of issuance, with full implementation within 120 days.
Implementation shall include the relocation of Technical Specification requirements to the appropriate licensee-controlled document as identiTied in the licensee's submittal dated June 11, 1996, as supplemented March 26, 1997, and reviewed in the staffs safety evaluation dated December 28, 1998.
FOR THE NUCLEAR REGULATORYCOMMISSION Jo n F. Stang, S nior Project-Manager Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 28, 1998
ATTACHMENTTO LICENSE AMENDMENTNO. 226 TO FACILITYOPERATING LICENSE NO. DPR-58 DOCKET NO. 50-315 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT XVI XVII 6P 6-5 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6-13 6-13a 6-13b 6-13c 6-14 6-15 16 6-17 6-18 6-19 6-20 6-21 6-22 64 6-5 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6-13 6-14 6-15
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INDEX ADMINISTRATIVECONTROLS
'SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organization
. 6-1 Facility Staff........................ ~...... ~....................
6-1 6.3 FACILITYSTAFF UALIFICATIONS
..... 64 6.4 TRAINING 6.5 DELETED 6.6 REPORTABLE EVENT ACTION....
6.7 SAFETY LIMITVIOLATION.
6-5 6-5 6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING RE UIREMENTS
... 6-6 6.9.1 ROUTINE REPORTS 6-9 6.9.2 SPECIAL REPORTS..
. 6-13 6.10 DELETED 6.11 RADIATIONPROTECTION PROGRAM 6.12 HIGH RADIATIONAREA 6-14
... 6-14 6.13 PROCESS CONTROL PROGRAM PCP 6-15 6.14 OFFSITE DOSE CALCULATIONMANUAL ODCM 6-15 COOK NUCLEARPLANT-UNIT1 XVI AMENDMENT69) ~s ~~
489, 226
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6.0 ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (I) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant
- design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must hold or have held a Senior Operator License as specified in Section 6.2.2.h.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facilitystaff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
6.5 DELETED COOK NUCLEARPLANT-UNIT1 Page 6Q AMENDMENT49) 63) 483) 454)
))), ))), ))), 225
6.0 ADMINISTRATIVECONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken forgEPORTABLE EVENTS:
The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73.
Each REPORTABLE EVENT shall be reviewed by the PNSRC, and the results of this review shall be submitted to the NSDRC and the Senior Vice President Nuclear Generation.
6.7 SAFETY LIMITVIOLATION 6.7.1 The following actions shall be taken in the event 'a safety limitis violated:
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. The Chairman ofthe NSDRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A Safety LimitViolation Report shall be prepared.
This report shall be reviewed by the PNSRC.
This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence.
C.
The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the NSDRC and the Senior Vice President - Nuclear Generation within 14 days of the violation.
Operation of the unit shall not be resumed until authorized by the Commission.
COOK NUCLEAR PLANT-UMT1 Page 6-5 AMENDMENTSV, m, ae, m, 226
0 6.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.
Deleted.
Deleted.
PROCESS CONTROL PROGRAM implementation.
OFFSITE DOSE CALCULATIONMANUALimplementation.
Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and Regulatory Guide 4.1, Rev. 1, April 1975.
Component Cyclic or Transient Limits program, which provides controls to track the UFSAR, Section 4.1, cyclic and transient occurrences to ensure that components are maintained within the limits.
h.
Fire Protection Program implementation.
6.8.2 Each procedure and administrative policy of Specification 6.8.1
- above, and changes
- thereto, including temporary changes, shall be reviewed prior to implementation as set forth in Quality Assurance Program Description, Appendix C, Section 6.5.
6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas
- samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions.
The program willinclude the following:
Training ofpersonnel, Procedures for sampling and analysis, Provisions for maintenance of sampling and analysis equipment.
COOK NUCLEAR PLANT-UNITI Page 6-6 AMENDMENTV2 454, 489, kgb, SS, o08 226
4 6.0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued I
6.8.4 The following programs shall be established, implemented, and maintained:
Radioactive Effluent Controls Pro ram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program (I) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
I)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use ofthe liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, COOK NUCLEAR PLANT-UNIT1 Page 6-7 AMENDMENTZe, 226
6.0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARYconforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARYconforming to Appendix I to 10 CFR Part 50, 9) 10)
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARYconforming to Appendix I to 10 CFR Part 50, and Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
b.
Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radionuclides in the environs of the.
plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure
- pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
The program shall (1) be contained in the ODCM, (2) conform to the guidance ofAppendix I to 10 CFR Part 50, and (3) include the following:
Monitoring, sampling,
- analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, I
, 2)
A Land Use Census to ensure that changes in the use of areas at and beyond. the SITE BOUNDARYare identified and that modifications to the monitoring program are made ifrequired by the results of this census, and 3)
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
COOK NUCLEAR PLANT-UNIT1 Page 6-8 AMENDMENT489, 226
0 6.0 ADMINISTRATIVECONTROLS 6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements ofTitle 10, Code ofFederal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summaty report of plant startup and power escalation testing shall be submitted following (1) receipt ofan operating license, (2) amendment Io the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the-measured values of the operating conditions or characteristics obtained during the test program and a comparison ofthese values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
COOK NUCLEAR PLANT-UNIT1 Page 6-9 AMENDMENTm, ~, 4', 226
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6.0 ADMINISTRATIVECONTROLS 6.9 STARTUP REPORT Continued 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. Ifthe Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementaty reports shall be submitted at least every three months until all three events have been completed.
ANNUALREPORTS1 6.9.1.4 Annual reports covering the activities ofthe unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March 1 of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functions2, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),
waste processing and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% 'of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
The complete results ofsteam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).
Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.
Information regarding any instances when the I-131 specific activity limitwas exceeded.
A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
COOK NUCLEAR PLANT-UNIT1 Page 6-10 AMENDMENT$7, 434, F4, 489) 226
6.0 ADMINISTRATIVECONTROLS ANNUALRADIOLOGICALENVIRONMENTALOPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.
The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.
The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT3 6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January 1 of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.I of Appendix I to 10 CFR Part 50.
A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material for each unit.
COOK NUCLEAR PLANT-UNIT1 Page 6-11 AMENDMENT&, 442, 484, m,ue, 226
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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 LIMITSREPORT 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, 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 1A, "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).
COOK NUCLEAR PLANT-UNIT1 Page 6-12 AMENDMENT69, 4$4g 474>
ae, m, 226
h 6.0 ADMINISTRATIVECONTROLS CORE OPERATING LIMITSREPORT 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 OPEKATING LIMITSREPORT, 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 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 IIIAdministrator 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:
b.
Inoperable Seismic Monitoring Instrumentation, Specification 3.3.3.3.
Seismic Monitoring Instrumentation Actuated, Specification 4.3.3.3.2.
Inoperable Meteorological Monitoring Instrumentation, Specification 3.3.3.4.
High Specific Activityin 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.
6.10 DELETED COOK NUCLEAR PLANT-UNIT1 F
Page 6-13 AMKNDMKNTaV, 464, ee, 226
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6.0 ADMINISTRATIVECONTROLS 6.11 RADIATIONPROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel radiation exposure.
6.12 HIGH RADIATIONAREA In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*.
Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device. This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.
6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr. When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).
Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas.
In the event that it is not possible or practicable to provide locked doors due to area size or configuration, the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.
Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
COOK NUCLEAR PLANT-UNIT1 Page 6-14 AMENDMENT94, 480, 484, 48, 226
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'.0 ADMINISTRATIVECONTROLS 6.13 PROCESS CONTROL PROGRAM PCP 6.13.1 Changes to the PCP:
Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description, Appendix C, Section 6.10.2.n.
This documentation shall contain:
1.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2.
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the PNSRC and the approval of the Plant Manager.
6.14 OFFSITE DOSE CALCULATIONMANUAL ODC 6.14.1 Changes to the ODCM:
Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description, Appendix C, Section 6.10.2.n..
This documentation shall contain:
1.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
Shall become effective after review and acceptance by the PNSRC and the approval of the Plant Manager.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
COOK NUCLEAR PLANT-UNIT1 Page 6-15 AMENDMENTSV, 454, 489 226
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055&4001 INDIANAMICHIGANPOWER COMPANY DOCKET NO. 50-316 DONALDC. COOK NUCLEAR PLANT UNIT2 AMENDMENTTO FACILITYOPERATING LICENSE Amendment No. 210 License No. DPR-74 The U.S. Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by Indiana Michigan Power Company (the licensee) dated June 11, 1996, and supplemented March 26, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facilitywilloperate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities willbe conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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~ Accordingly, Facility Operating License No. DPR-74 is hereby amended to approve the relocation of certain Technical Specification requirements to licensee-controlled documents, as described in the licensee's application dated June 11, 1996, as supplemented March 26, 1997, and evaluated in the staffs safety evaluation dated December 28, 1998. This license is also hereby amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-74 is hereby amended to read as follows:
B.
Technical S ecifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 210, are hereby incorporated in the license.
The licensee shall operate the facility in accordance with the Technical Specifications.
This license amendment is effective as of the date of issuance,'with full implementation within 120 days.
Implementation shall include the relocation of Technical Specification requirements to the appropriate licensee-controlled document as identified in the licensee's submittal dated June 11, 1996, as supplemented March 26, 1997, and reviewed in the staffs safety evaluation dated December 28, 1998.
FOR THE NUCLEAR REGULATORY COMMISSION
-J hn F. Stang, Senior Project Manager=
Project Directorate III-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
December 28, 1998
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ATTACHMENTTO LICENSE AMENDMENTNO. 210 FACILITYOPERATING LICENSE NO. DPR-74 DOCKET NO. 50-316 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the attached pages.
The revised pages are identified by amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT XVI XVII 64 6-5 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6-13 6-13a 6-13b 6-13c 6-14 6-15 6-16 6-17 6-18 6-19 6-20 6-21 6-22 XVI 6-4 6-5 6-6 6-7 6-8 6-9 6-10 6-11 6-12 6-13 6-14 6-15
0 INDEX ADMINISTRATIVECONTROLS
~ SECTION PAGE 6.1 RESPONSIBILITY 6-1 6.2 ORGANIZATION Onsite and Offsite Organization Facility Staff.
6.3 FACILITYSTAFF UALIFICATIONS 6-1 64 6.4 TRAINING 6.5 DELETED 6.6 REPORTABLE EVENT ACTION.......
6-5 6.7 SAFETY LIMITVIOLATION 6-5 6.8 PROCEDURES AND PROGRAMS 6.9 REPORTING RE UIREMENTS 6-6 6.9.1 ROUTINE REPORTS....
6-9 6.9.2 SPECIAL REPORTS.....
6.10 DELETED 6-13 6.11 RADIATIONPROTECTION PROGRAM 6-14 6.12 HIGH RADIATIONAREA 6.13 PROCESS CONTROL PROGRAM PCP 6-14 6-15 6.14 OFFSITE DOSE CALCULATIONMANUAL ODCM 6-15 COOK NUCLEARPLANT-UNIT2 AMENDMENTV4, 407, 488, 47$, 210
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, 6.0 ADMINISTRATIVECONTROLS 6.3 FACILITYSTAFF UALIFICATIONS 6.3.1 Each member of the facility staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for (1) the Plant Radiation Protection Manager, who shall meet or exceed qualifications of Regulatory Guide 1.8, September 1975, (2) the Shift Technical Advisor, who shall have a bachelor's degree or equivalent in a scientific or engineering discipline with specific training in plant
- design, and response and analysis of the plant for transients and accidents and, (3) the Operations Superintendent, who must hold or have held a Senior Operator License as specified in Section 6.2.2.h.
6.4 TRAINING 6.4.1 A retraining and replacement training program for the facilitystaff shall be maintained under the direction of the Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971 and 10 CFR Part 55.
6.5 DELETED COOK NUCLEAR PLANT-UNIT2 Page 64 AMENDMENT34, 447, AS, IVAN, 478,407, P)Q
0 6.0 ADMINISTRATIVECONTROLS 6.6 REPORTABLE EVENT ACTION 6.6.1 The followingactions shall be taken for REPORTABLE EVENTS:
a.
The Commission shall be notified and a report submitted pursuant to the requirements of 10 CFR 50.73.
b.
Each REPORTABLE EVENT shall be reviewed by the PNSRC, and the results of this review shall be submitted to the NSDRC and the Senior Vice President - Nuclear Generation.
6.7 SAFETY LIMITVIOLATION 6.7.1 The followingactions shall be taken in the event a safety limit,is violated:
The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The Chairman of the NSDRC shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
A Safety LimitViolation Report shall be prepared.
The report shall be reviewed by the PNSRC.
This report shall describe (1) applicable circumstances preceding the violation; (2) effects of the violation upon facility components, systems or structures; and (3) corrective action taken to prevent recurrence.
C.
The Safety Limit Violation Report shall be submitted to the Commission, the Chairman of the NSDRC and the Senior Vice President - Nuclear Generation within 14 days of the violation.
Operation of the unit shall not be resumed until authorized by the Commission.
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'.0 ADMINISTRATIVECONTROLS 6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures shall be established, implemented and maintained covering the activities referenced below:
The applicable procedures recommended in Appendix "A" of Regulatory Guide 1.33, Rev. 2, February 1978.
b.
Deleted.
c..
Deleted.
d.
PROCESS CONTROL PROGRAM implementation.
e.
OFFSITE DOSE CALCULATIONMANUALimplementation.
f.
Quality Assurance Program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Rev. 1, June 1974, and Regulatory Guide 4.1, Rev. I, April 1975.
g.
Component Cyclic or Transient Limits program, which provides controls to track the UFSAR, Section 4.1, cyclic and transient occurrences to ensure that components are maintained with the limits.
h.
Fire Protection Program implementation.
6.8.2 Each procedure and administrative policy of Specification 6.8.1
- above, and changes
- thereto, including temporary
- changes, shall be reviewed prior to implementation as set forth in Qualification Assurance Program Description, Appendix C, Section 6.5.
6.8.3 A plant program for post-accident sampling shall be established, implemented, and maintained which will ensure the capability to obtain and analyze reactor coolant samples, containment atmosphere noble gas
- samples, and unit vent gaseous effluent samples for iodines and particulates under accident conditions.
The
. program willinclude the following:
a.
Training of personnel, C.
Procedures for sampling and analysis, Provisions for maintenance of sampling and analysis equipment.
COOK NUCLEAR PLANT-UNIT2 Page 64 AMENDMENT5k, 488, 475, %8,486, 493 210
0 6.0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued 6.8.4 The following programs shall be established, implemented, and maintained:
Radioactive Effluent Controls Pro ram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable.
The program (1) shall be contained in the ODCM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded.
The program shall include the following elements:
1)
Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 2)
Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to 10 CFR Part 20, Appendix B, Table II, Column 2, 3)
Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.106 and with the methodology and parameters in the ODCM, 4)
Limitations on the annual and quarterly doses or dose commitment to a MEMBER OF=
THE PUBLIC from radioactive materials in liquid effluents released from each unit to UNRESTRICTED AREAS conforming to Appendix I to 10 CFR Part 50, 5)
Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the ODCM at least every 31 days, 6)
Limitations on the operability and use ofthe liquid and gaseous effluent treatment systems to ensure that the appropriate portions of these systems are used to reduce releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix I to 10 CFR Part 50, COOK NUCLEAR PLANT-UNIT2 Page 6-7 AMENDMENT~, 21 0
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6.0 ADMINISTRATIVECONTROLS PROCEDURES AND PROGRAMS Continued 7)
Limitations on the dose rate resulting from radioactive material released in gaseous effluents to areas beyond the SITE BOUNDARYconforming to the dose associated with 10 CFR Part 20, Appendix B, Table II, Column 1, 8) 9)
Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous effluents from each unit to areas beyond the SITE BOUNDARYconforming to Appendix I to 10 CFR Part 50, Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released from each unit to areas beyond the SITE BOUNDARYconforming to Appendix I to 10 CFR Part 50, and 10)
Limitations on the annual dose or dose commitment to any MEMBEROF THE PUBLIC due to releases of radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.
b.
Radiolo ical Environmental Monitorin Pro ram A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure
- pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways.
The program shall (1) be contained in the ODCM, (2) conform to the guidance ofAppendix I to 10 CFR Part 50, and (3) include the following:
Monitoring, sampling,
- analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, A Land Use Census to ensure that changes in the use of areas at and beyond the SITE-BOUNDARYare identified and that modifications to the monitoring program are made ifrequired by the results of this census, and 3)
Participation in a Interlaboratory Comparison Program to ensure that independent checks on the precision and accuracy of the measurements
-of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
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0 6.0 ADMINISTRATIVECONTROLS 6.9 REPORTING RE UIREMENTS ROUTINE REPORTS 6.9.1 In addition to the applicable reporting requirements ofTitle 10, Code ofFederal Regulations, the following reports shall be submitted to the Regional Administrator unless otherwise noted.
STARTUP REPORT 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (I) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.
6.9.1.2 The stanup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison ofthese values with design predictions and specifications.
Any corrective actions that were required to obtain satisfactory operation shall also be described.
Any additional specific details required in license conditions based on other commitments shall be included in this report.
COOK NUCLEARPLANT-UNIT2 Page 6-9 AMENDMENTa, ~, uS, 21 0
6.0 ADMINISTRATIVECONTROLS STARTUP REPORT Continued 6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. Ifthe Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.
ANNUALREPORTS1 6.9.1.4 Annual reports covering the activities ofthe unit as described below for the previous calendar year shall be submitted prior to March 1 of each year.
The initial report shall be submitted prior to March I of the year following initial criticality.
6.9.1.5 Reports required on an annual basis shall include:
A tabulation on an annual basis of the number of station, utility and other personnel (including contractors) receiving exposures greater than 100 mrem/yr and their associated man rem exposure according to work and job functions2, e.g., reactor operations and surveillance, in-service inspection, routine maintenance, special maintenance (describe maintenance),
waste processing and refueling.
The dose assignment to various duty functions may be estimates based on pocket dosimeter, TLD, or film badge measurements.
Small exposures totalling less than 20% of the individual total dose need not be accounted for.
In the aggregate, at least 80% of the total whole body dose received from external sources shall be assigned to specific major work functions.
The complete results of steam generator tube in-service inspections performed during the report period (reference Specification 4.4.5.5.b).
Documentation of all challenges to the pressurizer power operated relief valves (PORVs) or safety valves.
Information regarding any instances when the I-131 specific activity limitwas exceeded.
A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station.
This tabulation supplements the requirements of 20.407 of 10 CFR Part 20.
COOK NUCLEARPLANT-UNIT2 Page 6-10 AMENDMENTm, uO, uS, 210
6.0 ADMINISTRATIVECONTROLS ANNUALRADIOLOGICALENVIRONMENTALOPERATING REPORT 6.9.1.6 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period.
The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2, IV.B.3, and IV.Cof Appendix I to 10 CFR Part 50.
ANNUALRADIOACTIVEEFFLUENT RELEASE REPORT 6.9.1.7 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted within 90 days after January I of each year.
The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.
The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.
A single submittal may be made for a multiple unit station.
The submittal should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material for each unit.
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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 LIMITSREPORT 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/Fq 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).
COOK NUCLEARPLANT-UNIT2 Page 6-12 AMENDMENTSk, 488, 487, kVS,
- 490, 210
6.0 ADMINISTRATIVECONTROLS CORE OPERATING LIMITSREPORT 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 midwycle 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 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:
'I 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 Activityin RCS Coolant, Specification 3.4.8.
e.
RCS Pressure Transient Mitigated By RHR Safety Valve or RCS Vent(s), Specification 3.4.9.3.
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.
6.10 DELETED COOK NUCLEAR PLANT-UNIT2 Page 6-13 AMENDMENTm, m, uS, 210
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6.0 ADMINISTRATIVECONTROLS 6.11 RADIATIONPROTECTION PROGRAM Procedures for personnel radiation protection shall be prepared consistent with the requirements of 10 CFR Part 20 and shall be approved, maintained and adhered to for all operations involving personnel. radiation exposure.
6.12 HIGH RADIATIONAREA 6.12.1 In lieu of the "control device" or "alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is 1000 mrem/hr or less shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:
a.
A radiation monitoring device which continuously indicates the radiation dose rate in the area.
A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received.
Entry into such areas with this monitoring device may be made after the dose rate level in the area has been established and personnel have been made aware of it.
c.
An individual qualified in radiation protection procedures who is equipped with a radiation dose rate monitoring device.
This individual shall be responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility Health Physicist in the Radiation Work Permit.
6.12.2 The requirements of 6.12.1 shall also apply to each high radiation area in which the intensity of radiation is greater than 1000 mrem/hr.
When possible, locked doors shall be provided to prevent unauthorized entry into such areas, and the keys shall be maintained under the administrative control of the Shift Supervisor on duty and/or the Plant Health Physicist (Plant Radiation Protection Supervisor).
Doors shall remain locked except during periods of access by personnel under an approved RWP which shall specify the dose rate levels in the immediate work areas.
In the event that it is not possible or practicable to provide locked doors due to area size or configuration," the area shall be roped off, conspicuously posted and a flashing light shall be activated as a warning device.
Health Physics (Radiation Protection) personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they comply with approved radiation protection procedures for entry into high radiation areas.
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6.0 ADMINISTRATIVECONTROLS 6.13 PROCESS CONTROL PROGRAM PCP 6.13.1 Changes to the PCP:
Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description, Appendix C, Section 6.10.2.n.
This documentation shall contain:
1 ~
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change(s) and 2.
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
b.
Shall become effective after review and acceptance by the PNSRC and the approval of the Plant Manager.
6.14 OFFSITE DOSE CALCULATIONMANUALODCM
- 6. 14.1 Changes to the ODCM:
a.
Shall be documented and records of reviews performed shall be retained as required by the Quality Assurance Program Description, Appendix C, Section 6.10.2.n.
This documentation shall contain:
1.
Sufficient information to support the change
'together with the appropriate analyses or evaluations justifying the change(s) and A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20. 106, 40 CFR Pan
- 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
b.
Shall become effective after review and acceptance by the PNSRC and the approval of the Plant Manager.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to t'ie ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g., month/year) the change was implemented.
COOK NUCLEAR PLANT-UNIT2 Page 6-15 AMENDMENTV4, AS, %5,210
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