ML20044G460

Proposed Tech Specs Re Administrative Controls

ML20044G460
Person / Time
Site:	Fermi
Issue date:	05/24/1993
From:	DETROIT EDISON CO.
To:
Shared Package
ML20044G458	List: ML20044G460 NRC-93-0062, Application for Amend to License NPF-43,changing Tech Specs Include Modification to Job Titles Following Mgt Reorganization,Changes to Onsite Review Organization Membership Description & Change to Overtime Requirements
References
NUDOCS 9306030138
Download: ML20044G460 (12)

Text

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ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY 6.1.1 The Plant Manager

• shall be responsible for overall unit safe operation l and shall delegate in writing the succession to this responsibility during his-absence. The Plant Manager shall have control over those onsite activities necessary for safe operation and maintenance of the plant.

6.1.2 The Nuclear Shift Supervisor or, during his absence.from the control room, a designated individual shall be responsible for the control room command function. A management directive to this effect, signed by the Senior l Vice President - Nuclear Generation

• shall be reissued to all station l personnel on an annual ba is.

4 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS 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 i 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 Updated Final Safety Analysis Report.  ;

b. The Senior Vice President - Nuclear Generation shall have l 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 of the plant to ensure nuclear safety, i

c. 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.

• An alternative title may be designated for this position. All requirements i of these Technical Specifications apply to the position with the alternative  ;

title as apply with the specified title. Alternative titles shall be ,

specified in the Updated Final Safety Analysis Report. l FERMI - UNIT 2 .

6-1 Amendment No. JJ, E , EJ, EJ 9306030138 930524 PDR ADOCK 05000341 ,

P PDR

ADMINISTRATIVE CONTROLS ,

6.2.2 UNIT STAFF

a. Each on duty shift shall be composed of at least the minimum shift-crew composition shown in Table 6.2.2-1;

b. At least one licensed Operator shall be in the control room when  :

fuel is in the reactor. In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior .

Operator shall be in the control room;

c. A Radiation Protection Technician

• shall be on site when fuel is in l the reactor. The Radiation Protection Technician position may be .

unfilled for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to

^

accommodate unexpected absence, provided immediate action is taken to fill the required positions;

d. All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;

e. DELETED

f. Administrative procedures shall be developed and implemented.to limit the working hours of unit staff who work on safety-related' equipment (e.g., licensed Senior Operators, licensed Operators, non-licensed Operators, Nuclear Maintenance Journeymen, and Nuclear I&C Repairmen).

Adequate shift coverage shall be maintained without routine heavy use of overtime. The objective shall be to have the personnel work l a nominal 40-hour week while the unit is operating. However, in the event that unforeseen problems require substantial amounts of overtime to be used, or during extended periods of shutdown for refueling, major maintenance, or major unit modifications, on a temporary basis the following guidelines shall be followed:

1. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> in any 24-hour period, nor more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inany' 48-hour period, nor more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in any 7 day period, all excluding shift turnover time.

• An alternative title may be designated for this position. All requirements of I these Technical Specifications apply to the position with the alternative title as '

apply with the specified title. Alternative titles shall be specified in the Updated Final Safety Analysis Report.

FERMI - UNIT 2 6-2 Amendment No. JJ, 79, A4,EE '

J ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

3. If an individual works 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> or more continuously (including shift turn-over) a break of at least 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> should be allowed before returning to work.

4. Except during extended shutdown periods, the use of overtime should be considered on an individual basis and not for the entire staff on a shift.

Any deviation from the above guidelines shall be authorized by the Plant Manager or his designee, in accordance with l established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the .

procedures such that overtime should be reviewed monthly by l the Plant Manager or his designee to assure that excessive l hours have not been assigned. Routine deviation from the above guidelines is not authorized. '

g. The Operations Superintendent *, Nuclear Shift Supervisor, and l .

Nuclear Assistant Shift Supervisor shall hold a Senior Reactor Operator license. The Nuclear Supervising Operator shall hold a Reactor Operator or Senior Reactor Operator license.

l l

1 i

• An alternative title may be designated for this position. All requirements of these Technical Specifications apply to the position with the alternative title as apply with the specified title. Alternative titles shall be specified in the Updated Final Safety Analysis Report. l l

FERMI - UNIT 2 6-2a Amendment No. 79 l

ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

[ UNCTION 6.2.3.I The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources of plant ,

design and operating experience information, including plants of similar design, which may indicate areas for improving unit safety.

COMPOSITION 6.2.3.2 The ISEG shall be composed of at least five dedicated, full-time engineers located onsite, each with a bachelor's degree in engineering or related science and at least two years professional level experience in his field, at least one year of which experience shall be in the nuclear field.

RESPONSIBILITIES 6.2.3.3 The ISEG shall be responsible for maintaining surveillance of unit activities to provide independent verification

• that these activities are performed correctly and that human errors are reduced'as much as practical.

i AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, .

equipment modifications, maintenance activities, operations activities or other means of improving unit safety to Nuclear Generation Management. l 6.2.4 SHIFT TECHNICAL ADVISOR The Shift Technical Advisor shall provide advisory technical support 'to 6.2.4.1 the Nuclear Shift Supervisor in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to safe operation of the unit. The Shift Technical Advisor shall have a bachelor's degree or equivalent in a scientific or engineering discipline and shall have received specific training in the response and analysis of the unit for transients and accidents, and in unit design and layout, including the capabilities of instrumentation and controls in the control room.

• Not responsible for sign-off' function.  :

FERMI - UNIT 2 6-6 Amendment No. J/, 79, Ef, EE  ;

a 4 .

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF OVALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Superintendent - Radiation Protection

• or his designee who shall meet or exceed l the qualifications of Regulatory Guide 1.8, September 1975. The licensed Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 29, 1980 NRC letter to all licensees.

6.4 TRAINING 6.4.1 A retraining and replacement training program for the unit staff shall be maintained under the direction of the Director, Nuclear Training,* shall meet or l .

exceed the requirements and recommendations of Section 5 of ANSI N18.1-1971 and Appendix A of 10 CFR Part 55 and the supplemental requirements.specified in Sections A and C of Enclosure 1 of the March 29, 1980 NRC letter to all licensees, and shall include familiarization with relevant industry operational experience. 1 6.5 REVIEW AND AUDIT ,

6.5.1 ONSITE REVIEW ORGANIZATION (OSR0)

FUNCTION 6.5.1.1 The OSR0 shall function to advise the Plant Manager on all matters related to nuclear safety as described in Specification 6.5.1.6 COMPOSITION t

6.5.1.2 The OSR0 chairman shall be the Plant Manager and the membership shall be composed of a minimum of 6 but not more than 11 plant management representatives whose responsibilities include the functional areas of: operations, maintenance, 1 radiation protection, engineering / technical support and quality assurance. All members shall be appointed in writing by the OSR0 Chairman. The qualifications of each OSR0 member shall meet or exceed the requirements and recommendations of Section 4.2 or 4.3 of ANSI N18.1-1971.

ALTERNATES 4

6.5.1.3 The Chairman may designate in writing other members who may serve as the-Vice Chairman of the OSR0. Alternates may be designated for specific OSR0 i members. No more than two alternates shall participate as voting members in OSR0 activities at any one time. All alternate members shall be appointed in writing I

by the OSR0 Chairman.

• An alternative title may be designated for this position. All requirements of these Technical Specifications apply to the position with the alternative title as apply with the specified title. Alternative titles shall be specified in the Updated Final Safety Analysis Report.

I FERMI UNIT 2 6-7 Amendment No. JJ,'JE, E4 j l

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ADMINISTRATIVE-CONTROLS MEETING FRE0VENCY 6.5.1.4 The OSR0 shall meet at least once per calenda month and as convened by the OSR0 Chairman or a Vice Chairman. l ,

OV0 RUM t 6.5.1.5 The quorum of the OSR0 necessary for the performance of the OSR0 responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or Vice Chairman and four members including alternates. i RESPONSIBILITIES ,

6.5.1.6 The OSRr shall be responsible for:

a. Review of all Plant Administrative Procedures and changes thereto;

b. Review of all proposed tests and experiments that affect nuclear safety;

c. Review of all proposed changes to Appendix A Technical Specifications;

d. Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety;

e. Review of the safety evaluations for plant procedures and changes thereto completed under the provisions of 10 CFR 50.59;

f. Investigation of all violations of the Technical Specifications, including .

the preparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the Senior Vice President - l Nuclear Generation and to the Nuclear Safety Review Group; -l

g. Review of all REPORTABLE EVENTS;

h. Review of unit operations to detect potential hazards to nuclear safety;

i. Performance of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Nuclear Safety Review -

Group; i

j. Review of the Security Plan;

k. Review of the Emergency Plan;  :

l FERMI - UNIT 2 6-8 Amendment No.-JJ, EJ l

ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued)

1. Review of every unplanned onsite release of radioactive material to the environs including the preparation and forwarding of reports covering .

evaluation, recommendations and disposition of the corrective action to  :

prevent recurrence to the Senior Vice President - Nuclear Generation and l to the Nuclear Safety Review Group; and l

m. Review of changes to the PROCESS CONTROL PROGRAM, the 0FFSITE DOSE CALCULATION MANUAL, and major modifications to the Radwaste Treatment Systems.

n. Review of the Fire Protection Program.

6.5.1.7 The OSR0 shall: -

a. Recommend in writing to the Plant Manager approval or disapproval of items considered under Specification 6.5.1.6a. through d. prior to their implementation.

b. Render determinations in writing to the Nuclear Safety Review Group with regard to whether or not each item considered under Specification 6.5.1.6a. through f. constitutes an unreviewed safety question.

c. Provide written notification within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the Senior'Vice' l President -' Nuclear Generation and the Nuclear Safety Review Group of l disagreement between the OSR0 and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements'  ;

pursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The OSR0 shall maintain written minutes of each OSR0 meeting that, at a  ;

minimum, document the results of all OSR0 activities performed under the responsibility provisions of these Technical Specifications. Copies shall be provided to the Senior Vice President - Nuclear Generation and the Nuclear Safety Review Group.

6.5.2 NUCLEAR SAFETY REVIEW GROUP (NSRG) l FUNCTION 6.5.2.1 The NSRG shall function to provide independent review and audit of designated activities in the areas of:

a. Nuclear power plant operations,

b. Nuclear engineering,

c. Chemistry and radiochemistry, .

d. Metallurgy, l

e. Instrumentation and control,  :

f. Radiological controls,

g. Mechanical and electrical engineering, and

h. Quality assurance practices.

The NSRG shall report to and advise the Senior Vice President - Nuclear .

l Generation on those areas of responsibility in Specifications 6.5.2.7 and 5.5.2.8. l ).

FERMI - UNIT 2 6-9 Amendment No. JJ, Ep, EZ, EJ

' ADMIN'ISTRATIVE CONTROLS COMPOSITION 6.5.2.2 The Senior Vice President - Nuclear Generation shall appoint at least nine j members to the NSRG and shall designate from this members'. iip a Chairman and at least one Vice Chairman. The membership shall collectively possess experience and competence to provide independent review and audit in the areas listed in Section 6.5.2.1. The Chairman and Vice Chairman shall have nuclear background in engineering or operations and shall be capable of determining when to call in experts to assist the NSRG review of complex problems. All members shall have at least a bachelor's degree in engineering or related sciences or at least 10 years of responsible power plant experience of which a minimum of 3 years shall be nuclear power plant experience. The Chairman shall have at least 10 years of professional level management experience in the power field and each of the other members shall have at least 5 years of cumulative professional level experience in one or more of the fields listed in Section 6.5.2.1.

ALTERNATES 6.5.2.3 All alternate members shall be appointed in writing by the NSRG Chairman to serve on a temporary basis; however, no more than two alternates shall participate as voting members in NSRG activities at any one time.

CONSULTANTS 6.5.2.4 Consultants shall be utilized as determined by the NSRG Chairman to provide expert advice to the NSRG.

MEETING FRE0VENCY 6.5.2.5 The NSRG shall meet at least once per 6 months.

OVORUM 6.5.2.6 The quorum of the NSRG necessary for the performance of the NSRG review and audit functions of these Technical Specifications shall consist of the Chairman or his designated alternate and at least one half of the remaining NSRG members of whom two may be alternates. No more than a minority of the quorum shall have line responsibility for operation of the unit.

REVIEW 6.5.2.7 The NSRG shall be responsible for the review of 6.5.2.7.a and shall review

, 6.5.2.7.b through i:

a. The safety evaluations for (1) changes to procedures, equipment, facilities or systems and (2) tests or experiments completed under the provision of 10 CFR 50.59 to verify that such actions did not constitute an unreviewed safety question;

b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59; FERMI - UNIT 2 6-10 Amendment No. JJ, 79, Ef, %)

.i ADMIN'ISTRATIVE CONTROLS AUDITS (Continued) .

g. Any other area of unit operation considered appropriate by the NSRG or the Senior Vice President - Nuclear Generation.

h. The radiological environmental monitoring program and the results thereof at least once per 12 months;

i. The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months;

j. The PROCESS CONTROL PROGRAM and implementing procedures for processing and packaging of radioactive wastes at least once per 24 months; and

k. The performance of activities required by the Quality Assurance Program to meet the provisions of Regulatory Guide 1.21, Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975 at least once per 12 months.

RECORDS 6.5.2.9 Records of NSRG activities shall be prepared, approved, and distributed as indicated below:

a. Minutes of each NSRG meeting shall be prepared, approved, and forwarded to the Senior Vice President - Nuclear Generation within 14 days following each j meeting.

b. Reports of reviews encompassed by Specification 6.5.2.7 shall be prepared, approved, and forwarded to the Senior Vice President - Nuclear Generation within 14 days following completion of the review.

c. Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to the Senior Vice President - Nuclear Generation and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.5.3 TECHNICAL REVIEW AND CONTROL ACTIVITIES 6.5.3.1 Procedures required by Technical Specification 6.8, and other procedures which affect plant nuclear safety as determined by the Plant Manager, and changes thereto, shall be prepared by a qualified individual / organization.

l FERMI - UNIT 2 6-12 Amendment No. JJ, JE l

7 ADMINISTRATIVE CONTROLS REVIEW 6.5.3.2 Each procedure or procedure change prepared in accordance with 6.5.3.1 above and not reviewed in accordance with Section 6.5.1.6 shall be reviewed for technical adequacy by a qualified individual other than the individual that prepared the procedure or change thereto. Each such review shall include a determination of whether or not additional, cross-disciplinary review is necessary. If deemed necessary, such review (s) shall be performed by personnel of the appropriate discipline.

6.5.3.3 Each procedure required by Specification 6.8.1.h through j, or changes thereto, shall be reviewed by the Superintendent-Radiation Protection or his I designee. The Environmental Program Coordinator

• will review any changes l pertaining to 6.8.1.J. These reviews may be performed in lieu of, or in addition l to, those required by item 6.5.3.2 above.

SAFETY EVALUATIONS 6.5.3.4 When required by 10 CFR 50.59, a safety evaluation to determine whether or not an unreviewed safety question is involved shall be included. in the review.

Pursuant to 10 CFR 50.59, NRC approval of items involving unreviewed safety questions shall be obtained prior to approval of the procedure or procedure change. .

OVALIFICATIONS 6.5.3.5 Individuals performing the reviews and evaluations in accordance with 6.5.3.2 through 6.5.3.4 above shall meet or exceed the qualifications stated in Sections 4.2 or 4.4 of ANSI N18.1-1971 for the appropriate discipline, and shall be members of the plant staff previously designated in writing by the Plant Manager.

RECORDS 6.5.3.6 Written records of reviews and evaluations performed in accordance with items 6.5.3.2 through 6.5.3.4 above, including recommendations for approval or disapproval, shall be prepared and maintained.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABLE EVENTS:

a. The Commission shall be notified and a report submitted pursuant to the requirements of Section 50.73 to 10 CFR Part 50, and P

b. Each REPORTABLE EVENT shall be reviewed by the OSR0, and the results of this review shall be submitted to the NSRG and the Senior Vice President -

Nuclear Generation.

• An alternative title may be designated for this position. All requirements of of these Technical Specifications apply to the position with the alternative title -

as apply with the specified title. Alternative titles shall be specified in the Updated Final Safety Analysis Report.

i FERMI - UNIT _2 6-13 Amendment No. JJ, 79, EJ ,

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

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. The Senior Vice President - Nuclear i Generation and the NSRG shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. l l

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the OSR0. This report shall describe (1) applicable circumstances preceding the violation, (2) effects of the violation upon unit 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 NSRG, and the Senior Vice President - Nuclear Generation within 14 days of the violation.

d. Critical operation of the unit shall not be resumed until authorized by the Commission.

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

a. The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.

b. The applicable procedures required to implement the Fermi 2 commitments made in response to the requirements of NUREG-0737.

c. Refueling operations.

d. Surveillance and test activities of safety-related equipment.

e. Security Plan implementation. l

f. Emergeacy Plan implementation,

g. Fire Protection Program implementation.

h. PROCESS CONTROL PROGRAM implementation.

i. OFFSITE DOSE CALCULATION MANUAL implementation.

j. Quality Assurance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide 1.21 Revision 1, June 1974 and Regulatory Guide 4.1, Revision 1, April 1975.

FERMI - UNIT 2 6-14 Amendment No. JJ, %)

y--+

ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. 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 levels. in the area have been established and personnel have been made knowledgeable of them.

c. A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive e control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the '

Radiation Protection Technician ** in the RWP. l 6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to personnel with radiation levels such that a major portion of the body could receive in I hour a dose greater than 1000 mrems shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Nuclear Shift Supervisor on i duty and/ or the radiation protection supervision. 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 area and the maximum allowable stay time for individuals in that area. For individual areas ,

accessible to personnel with radiation levels such that a major portion of .the body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000'mrems* that are located within large areas, such as the containment, where no enclosure exists 'for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be roped off, conspicuously posted, and a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, continuous surveillance, direct or remote (such.

as use of closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.

6.13.2 Changes to the PCP:

a. Shall be documented and records of reviews performed.shall be retained as required by Specification 6.10.3n. This documentation shall contain:

• Measurement made at 18 inches from source of radioactivity.

• • An alternative title may be designated for this position. All requirements of these Technical Specifications apply to the position with the alternative title as apply with the specified title. Alternative titles shall be specified in the Updated Final Safety Analysis Report. 3 ,

FERMI - UNIT 2 6-23 Amendment No. JJ, 82 f