ML20070J673
| ML20070J673 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 07/18/1994 |
| From: | Marsh L Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20070J676 | List: |
| References | |
| NUDOCS 9407250261 | |
| Download: ML20070J673 (14) | |
Text
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( sgjg[f f UNITED STATES NUCLEAR REGULATORY COMMISSION 4 ?
W ASHINGTON, D C. 20555-0001 DETROLT EDISON COMPANY POCKET NO. 50-341 FERMI-2 AMENDMENT 10 FAClllTY OPERATING LICENSE Amendment No. 101 License No. NPF-43 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by the Detroit Edison C,ompany (the licensee) dated May 24, 1993 and July 7, 1994, 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 facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (t) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be 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.
9407250261 94071e PDR ADOCK 05000341 P
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. 2.
Accordingly, the license is 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. NPF-43 is hereby amended to read as follows:
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No.101, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
Deco shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of the date of its issuance with full implementation within 45 days.
FOR THE NUCLEAR REGULATORY COMMISSION Ledyard B. Marsh, Director Project Directorate 111-1 Division of Reactor Projects - III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
July 18, 1994
ATTACHMENT TO LICENSE AMENDMENT N0.101 FACIllTY OPERATING LICENSE N0 NPF-43 1
DOCKET NO. 50-341 i
Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.
The rivised pages are identified by amendment number and contain vertical lines insicating the area of change.
REMOVE INSERT 6-1 6-1 6-2 6-2 6 - 2a 6 - 2a 6-7 6-7 6-8 6-8 6-9 6-9 6 - 10 6 - 10 6 - 11 6 - 11*
6 - 12 6 - 12 6 - 13 6 - 13 6 - 14 6 - 14
- 0verleaf page provided to maintain document completeness.
No changes contained on these pages.
ADMINISTRATIVE CONTROLS 6,1 RESPONSIBILITY 6.1.1 The Plant Manager
- shall be responsible for overall unit safe operation I
and shall delegate in writing the succession to this responsibility during his aLence.
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 basis.
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. Lines of authority, responsibility, and communication shall be a.
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 Updated Final Safety Analysis Report.
b.
The Senior Vice President - Nuclear Generation shall have I
corporate responsibility for overall plant nuclear safety and shall take any measures needed tc ensure acceptable performance of the staff in operating, maintaining, and providing technical support of the plant to ensure nuclear safety, 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 alternatise 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 FERMI - UNIT 2 6-1 Amendment No. JJ, Jp, S, SE 101
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 OPERAT'ONAL 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 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 responsib11ities during this operation; e.
DELETED f.
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 physics personnel, auxiliary operators, and key maintenance personnel).
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 shif t 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 /> in any 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 shif t turnover time.
- 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.
FERM1 - UN]T 2 6-2 Amendment No. 54, 62, 101 1
[.
1
' ADMIN!STRATIVE CONTROLS UNIT STAFF (Continued) 3.
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 between work periods, including shift turnover time.
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 individual overtime should be reviewed monthly by the Plant Manager or his designee to assure that l
l excessive hours have not been assigned.
Routine deviation from the above guidelines is not authorized.
g.
The Operations Engineer, Nuclear Shift Supervisor, and Nuclear Assistant Shift Supervisor shall hold a Senior Reactor Operator license.
The Nuclear Supervising Operator shall hold a l
Reactor Operator or Senior Reactor Operator license.
l l
i
l' ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF OVALIFICATIONS Each member of the unit staff shall meet or exceed the minimum 6.3.1 for comparable positions, except for the qualifications of ANSI N18.1-1971 l
Superintendent - Radiation Protection
- or his designee who shall meet or exceed The licensed the qualifications of Regulatory Guide 1.8, September 1975.
Operators and Senior Operators shall also meet or exceed the minimum qualifications of the supplemental requirements specified in Sections A and C of of the March 29, 1980 NRC letter to all licensees.
f 6.4 TRAINING 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
l 6.4.1 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 29, 1980 NRC letter to all licensees, Sections A and C of Enclosure 1 of the March l
and shall include familiarization with relevant industry operational experience.
6.5 REVIEW AND AUDIT 6.5.1 ONSITE REVIEW ORGANIZATION (0SRO)
LQNCTION The OSR0 shall function to advise the Plant Manager on all matters 6.5.1.1 related to nuclear safety as described in Specification 6.5.1.6 COMPOSITION The OSR0 chairman shall be the Plant Manager and the membership shall be l
)
6.5.1.2 l
composed of a minimum of 6 but not more than 11 plant management representatives l
operations, maintenance, whose responsibilities include the functional areas of:
All l
radiation protection, engineering / technical support and quality assurance.
The qualifications of l
members shall be appointed in writing by the OSR0 Chairman.
l each OSR0 member shall meet or exceed the requirements and recommendations of l
Section 4.2 or 4.3 of ANSI N18.1-1971.
etTERNATES The Chairman may designate in writing other members who may serve as the l
6.5.1.3 Alternates may be designated for specific OSR0
)
Vice Chairman of the OSR0.
No more than two alternates shall participate as voting members in OSR0 l
members.
activities at any one time.
All alternate members shall be appointed in writing l
j by the OSR0 Chairman, l
- An alternative title may be designated for this position.
All requirements of l
l these Technical Specifications apply to the position with the alternative title as apply with the specified title. Alternative titles shall be specified in the l
1 Updated Final Safety Analysis Report.
Amendment No. JJ, 79, Ef 6-7 FERMI - UNIT 2 101
ADMINISTRATIVE CONTROLS MEETING FRE0VENCY 6.5.1.4 The OSRO shall meet at least once per calendar month and as convened by
}
the OSR0 Chairman or a Vice Chairman.
DUORUM The quorum of the OSRO necessary for the performance of the OSRO 6.5.1.5 responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or Vice Chairman and four members including alternates.
l RESPONS181LITIES 6.5.1.6 The OSR0 shall be responsible for:
Review of all Plant Administrative Procedures and changes thereto; a.
b.
Review of all proposed tests and experiments that affect nuclear safety;-
Review of all proposed changes to Appendix A Technical Specifications; c.
d.
Review of all proposed changes or modifications to unit systems or equipment that affect nuclear safety; l
Review of the safety evaluations for plant procedures and changes thereto l
e.
l 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
Review of all REPORTABLE EVENTS; g.
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
f j.
Review of the Security Plan; k.
Review 'of the Emergency Plan; 1
l 1
i FERMI - UNIT 2 6-8 Amendment No JJ, JJ.101 L
ADMINISTRATTVE CONTROL 5 RESPONSIBIL TIES (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
Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE DOSE m.
CALCULATION MANUAL, and major modifications to the Radwaste Treatment Syst ems.
Review of the Fire Protection Program.
n.
6.5.1.7 The OSR0 shall:
Recommend in writing to the Plant Manager approval or disapproval of items a.
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, 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
c.
President - Nuclear Generation and the Nuclear Safety Review Group of l
l disagreement between the OSRO and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagreements pursuant to Specification 6.1.1.
RECOPDS 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 l
provided to the Senior Vice President Nuclear Generation and the Nuclear Safety l
Review Group.
6.5.2 NUCLEAR SAFETY REVIEW GROUP (NSRG)
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, e.
Instrumentation and control, f.
Radiological controls, Mechanical and electrical engineering, and l
9 h.
Quality assurance practices.
The NSRG shall report to and advise the Senior Vice President - Nuclear i
Generation on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.
I FERMI - UNIT 2 6-9 Amendment No. JJ, 30, $2, $$
101
ADMINISTRATIVE CONTROLS COMPOSITION The Senior Vice President - Nuclear Generation shall appoint at least nine j
6.5.2.2 members to the NSRG and shall designate from this membership a Chairman and at least ene Vice Chairman.
The membership shall collectively possess experience and independent review and audit in the areas listed in provide competence to The Chairman and Vice Chairman shall have nuclear background in Section 6.5.2.1.
er,gineering or operations and shall be capable of determining when to call in experts to assist the MSRG review of complex problems.
All members shall have at least a in engineering or related sciences or at least 10 years of bachelor's degree responsible power plant experience of which a minimum of 3 years shall be nuclear The Chairman shall have at least 10 years of professional power plant experience.
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.
ALT ERN ATES All alternate members shall be appointed in writing by the NSRG Chairman to 6.5.2.3 serve on a temporary basis; however, no more than two alternates shall participate as voting members in NSRG activities at any one time.
CONSULTANTS Consultants shall be utilized as determined by the NSRG Chairman to provide 6.5.2.4 expert advice to the NSRG.
(
MEETING FREQUENCY 6.5.2.5 The NSRG shall meet at least once per 6 months.
OUORUM 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 ca. um shall have line i
responsibility for operation of the unit.
l 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.h through 1:
The safety evaluations for (1) changes to procedures, equipment, facilities or systems and (2) tests or experiments completed under the provision of 10 a.
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; 6-10 Amendment No. JJ, JS, M, #
FERMI - tmIT 2 101
ACMIN: ST0ATIVE CONTROLS REi1E4 (Cent'nued) c.
Proposed tests or exoeriments which involve an unreviewed sa'etj cuestion as cefinea in 10 CFR 50.59; d.
Procesed changes.to Technical Specifications or this Operating License; Violations of codes, regulations, orders, Technical Specifications, e.
license requirements, or of internal procedures or instructions having nuclear safety significance; f
Significant operating abnormalities or deviations from normal are expected performance of unit equipment that affect nuclear safety; g.
All REPORTABLE EVENTS; n.
All recognized indications of an unanticipated deficiency in sc*e aspect of design or operation of structures, systems, or comocnerts that could affect nuclear safety; and i.
Recorts and meeting minutes of the OSRO.
AUO:~5
- 6. 5. 2. 8 Audits of unit activities shall be performed under the cognizance :'
tre NSR3.
These aucits shall encompass:
a.
The conformance of unit operation to. provisions contained within t*e Technical Specifications and applicable license concitions at least once per 12 months; 5.
The performance, training and qualifications of the entire unit i
staff at least once per 12 months; c.
The results of actions taken to correct deficiencies occurring in unit equipment, structures, systems, or method of operation that affect nuclear safety, at least once per 6 months; d.
The performance of activities required by the Operational Quality Assurance Program to meet the criteria of Appendix 8, 10 CFR Part 50, at least once per 24 months; e.
The fire protection programmatic controls including the implementing procedures at least once per 24 months by qualified licensee QA personnel; f.
The fire protection equipment and program implementation, at least once per 12 months utilizing either a qualified offsite licensee fire protection engineer (s) or an outside independent fire protection con-
- sultant, An outside independent fire protection consultant shall be utilized at least every third year; FERMI - f) NIT 2 6-11
ADMINISTRATIVE CONTROLS I
AUDITS (Continued) 9 Any other area of unit operation considered appropriate by the NSRG or the
[
Senior Vice President - Nuclear Generation.
l h.
The radiological environmental monitoring program and the results thereof at i
least.once per 12 months; j
i.
The OFFSITE DOSE CALCULATION MANUAL and implementing procedures at least once per 24 months; i
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 15.5.2.9 Records of NSRG activities shall be prepared, approved, and distributed as l
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' l
- 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 l
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.
b i
FERMI - UNIT 2 6-12 Amendment No. JJ, JS 101 t
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ADMlHISTRATIVE 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 If deemed necessary, such review (s) shall be performed by personnel of necessary.
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 l
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 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.
QUALIFICATIONS 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 staf f 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:
The Commission shall be notified and a report submitted pursuant to the a.
requirements of Section 50.73 to 10 CFR Part 50, and b.
Each REPORTABLE EVENT shall be reviewed by the OSRO, 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 I
Updated Final Safety Analysis Report.
1 FERMI - UNIT 2 6-13 Amendment No. JJ, JS, EJ 101
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 Certer shall be notified by telephone as soon as possible and in all cases within I hour.
The Senior Vice President - Nuclear 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 />.
i b.
A Safety Limit Violation Report shall be prepared.
The report shall be revtewed by the OSRO.
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 HSRG, 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:
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, a.
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.
f.
Emergency Plan implementation.
g.
Fire Protection Program implementation.
h.
PROCESS CONTROL PROGRAM implementation.
1.
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 4.3, Revision 1, April 1975.
fERMJ - UNIT 2 6-14 Amendment No. JJ, #
101