ML023540419

Technical Specifications Pages for Amendment 235 Administrative Controls to Reflect Site Integration

ML023540419
Person / Time
Site:	Indian Point
Issue date:	12/17/2002
From:	NRC/NRR/DLPM
To:
References
TAC MB5256
Download: ML023540419 (9)

Text

TABLE OF CONTENTS (Cont'd)

Section Title Paqe 6.5 DELETED 6-3 6.6 Reportable Event Action 6-3 6.7 Safety Limit Violation 6-4 6.8 Procedures and Programs 6-4 6.9 Reporting Requirements 6-5 6.10 Record Retention 6-11 6.11 Radiation Protection Program 6-12 6.12 DELETED 6.13 Environmental Qualification 6-12 6.14 Process Control Program (PCP) 6-13 6.15 Offsite Dose Calculation Manual (ODCM) 6-13 6.16 Major Changes to Radioactive Liquid, Gaseous and Solid Waste 6-14 Systems Amendment No. 235 vi

6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The corporate officer with direct responsibility for the plant shall be responsible for overall facility activities and shall delegate in writing the succession to this responsibility during his absence.

6.1.2 The plant manager shall be responsible for facility operations and shall delegate in writing the succession to this responsibility during his absence.

6.2 ORGANIZATION 6.2.1 Facility Management and Technical Support Onsite and offsite organizations shall be established for unit operation and corporate management, respectively. The onsite and offsite organizations shall include the positions for activities affecting the safety of the nuclear power plant.

a. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through intermediate levels to and including all operating organization positions. These relationships shall be documented and updated, as appropriate, in the form of organization charts, functional descriptions of departmental responsibilities and relationships, and job descriptions for key personnel positions, or in equivalent forms of documentation.

These requirements shall be documented in the quality assurance program described or referenced in the Updated FSAR.

b. The plant manager shall be responsible for overall safe operation of the plant and shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

c. The corporate officer with direct responsibility for the plant shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, maintaining, and providing technical support to the plant to ensure nuclear safety.

d. The individuals who train the operating staff and those who carry out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

Amendment No. 235 6-1

6.2.2 Facility Staff

a. Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2-1.

b. At least one licensed Operator shall be in the control room when fuel is in the reactor.

c. At least two licensed Operators shall be present in the control room during reactor startup, scheduled reactor shutdown, and during recovery from reactor trips.

d. An individual qualified in radiation protection procedures shall be onsite when fuel is in the reactor.

e. All core alterations after the initial fuel loading shall be directly supervised by either a licensed Senior Reactor Operator or Senior Reactor Operator Limited to Fuel Handling. This individual shall have no other concurrent responsibilities during this operation.

f. DELETED

g. Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions (e.g., licensed Senior Operators, licensed Operators, health physicists, auxiliary operators, and key maintenance personnel).

The amount of overtime worked by unit staff members performing safety-related functions shall be limited in accordance with the NRC Policy Statement on working hours (Generic Letter No. 82-12).

h. The operations manager or assistant operations manager shall hold a senior reactor operator license.

AmendmentNo. 235 6-2

6.3 FACILITY STAFF QUALIFICATIONS 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 operation manager's and the assistant operation manager's SRO license requirement which shall be in accordance with Technical Specification 6.2.2.h, and, (2) the radiation protection manager who shall meet or exceed the minimum qualifications of Regulatory Guide 1.8, September 1975.

6.3.2 The plant manager shall meet or exceed the minimum qualifications specified for Plant Manager in ANSI N18.1-1971.

6.3.3 The Watch Engineer 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 6.4 TRAINING 6.4.1 A retraining and replacement training program for the facility staff shall be maintained under the direction of the Nuclear Training Manager and shall meet or exceed the requirements and recommendations of Section 5.5 of ANSI N18.1-1971.

6.4.2 DELETED 6.5 DELETED 6.6 REPORTABLE EVENT ACTION 6.6.0 A Reportable Event is defined as any of the conditions specified in 10 CFR 50.73a(2).

6.6.1 In the event of a Reportable Event, a report shall be submitted to the Commission pursuant to the requirements of 10 CFR 50.73.

Amendment No. 235 6-3

I 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is violated:

a. The provisions of 10 CFR 50.36(c)(1)(i) shall be complied with immediately.

b. The Safety Limit Violation shall be reported to the Commission immediately.

c. The Safety Limit Violation Report shall be prepared. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon facility components, systems or structures, and (3) correctiive action taken to prevent recurrence.

d. The Safety Limit Violation Report shall be submitted to the Commission within 10 days of the violation.

6.8 PROCEDURES AND PROGRAMS 6.8.1 Written procedures and administrative policies shall be established, implemented and maintained covering the activities referenced below:

a. The requirements and recommendations of Sections 5.2 and 5.3 of ANSI N18.7-1976 and Appendix A of Regulatory Guide 1.33, Revision 2 except as provided in the quality assurance program described or referenced in the Updated FSAR.

b. Process Control Program implementation.

c. Offsite Dose Calculation Manual implementation.

Amendment No. 235 6-4

d. Quality assurance program for effluent and environmental monitoring using the guidance in Regulatory Guide 1.21, Revision 1, April 1974 and Regulatory Guide 4.1, Revision 1, April 1975.

e. Fire Protection Program implementation.

6.8.2 Each procedure and administrative policy of Specification 6.8.1 above, and any changes to them shall be reviewed and approved for implementation in accordance with the quality assurance program described or referenced in the Updated FSAR.

6.8.3 The quality assurance program described or referenced in the Updated FSAR shall address making temporary changes.

6.8.4 The following programs shall be established, implemented, and maintained:

a. A program which will ensure the capability to obtain and analyze samples of radioactive iodines and particulates in plant gaseous effluents under accident conditions. The program shall include the following:

(i) training of personnel, (ii) procedures for sampling and analysis, and (iii) provisions for maintenance of sampling and analysis equipment.

6.9 REPORTING REQUIREMENTS Routine Reports and Reportable Occurrences 6.9.1. In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Regional Administrator, Region I unless otherwise noted.

Amendment No. 235 6-5

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

Special Reports 6.9.2 Special reports shall be submitted to the NRC Regional Administrator of the Region I Office 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. DELETED

b. DELETED

c. Sealed source leakage in excess of limits (Specification 4.15).

d. The complete results of the steam generator tube inservice inspection (Specification 4.13.C.).

e. Radioactive effluents (Specification 3.9).

f. Radiological environmental monitoring (Specification 4.11).

g. Meteorological monitoring instrumentation (Specification 3.15).

h. Inoperable radiation and hydrogen monitoring instrumentation (Specification 3.5) outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status

i. Operation of overpressure protection system (Specification 3.1 .A.4).

6.10 RECORD RETENTION 6.10.1 The types of plant records required to be maintained are addressed in the quality assurance program described or referenced in the Updated FSAR.

6.10.2 The minimum retention periods for plant records are addressed in the quality assurance program described or referenced in the Updated FSAR.

Amendment No. 235 6-11

6.14 PROCESS CONTROL PROGRAM (PCP) 6.14.1 Licensee initiated changes to the PCP:

1. Shall be submitted to the Commission in the Annual Radioactive Effluent Release Report for the period in which the change(s) was made. This submittal shall contain:

a. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information,

b. a determination that the change did not reduce the overall conformance of the solidified waste product to existing criteria for solid wastes, and

c. documentation of the fact that the change has been reviewed and found acceptable.

2. Shall become effective upon review and acceptance.

6.15 OFFSITE DOSE CALCULATION MANUAL (ODCM) 6.15.1 The ODCM shall be approved by the Commission prior to implementation.

6.15.2 Licensee initiated changes to the ODCM:

1. Shall be submitted to the Commission in the Radioactive Effluent Release Report for the period in which the change(s) was made effective. This submittal shall contain:

a. sufficiently detailed information to totally support the rationale for the change without benefit of additional or supplemental information.

Information submitted should consist of those pages of the ODCM to be changed with each page numbered and provided with an approval and date box, together with appropriate analyses or evaluation justifying the change(s),

b. a determination that the change will not reduce the accuracy or reliability of dose calculations or setpoint determinations, and

c. documentation of the fact the change has been revised and found acceptable.

Amendment No. 235 6-13

2. Shall become effective upon review and acceptance. I 6.16 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE SYSTEMS 6.16.1 Licensee initiated major changes to the radioactive waste systems (liquid, gaseous and solid) shall be reported to the Commission in the Radioactive Effluent Release Report for the period in which the change was made. The discussion of each change shall contain:

a. a summary of the evaluation that led to the determination that the change could be made in accordance with 10 CFR Part 50.59,

b. sufficient detailed information to totally support the reason for the change without benefit of additional or supplemental information,

c. a detailed description of the equipment, components and processes involved and the interfaces with other plant systems,

d. an evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto,

e. an evaluation of the change, which shows the expected maximum exposures to individuals in the Unrestricted Area and to the general population that differ from those previously estimated in the license application and amendments thereto,

f. a comparison of the predicted releases of radioactive materials in liquid and gaseous effluents and in solid waste to the actual releases for the period in which the changes are to be made;

g. an estimate of the exposure to plant operating personnel as a result of the change, and

h. documentation of the fact that the change was reviewed and found acceptable.

Amendment No. 235 6-14