ML20028G885

Amend 54 to License NPF-43,changing Tech Specs Re Various Staff Items,Including Stated Group Meeting Frequency

ML20028G885
Person / Time
Site:	Fermi
Issue date:	08/27/1990
From:	Pierson R Office of Nuclear Reactor Regulation
To:
Shared Package
ML20028G886	List: ML20028G885 ML20028G887
References
NUDOCS 9009050341
Download: ML20028G885 (13)

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. f..g'b, UNITED STATES

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g NUCLEAR REGULATORY COMMISSION

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l DETROIT EDISON COMPANY DOCKET NO. 50-341 FERMI-2' AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 54 License No. NPF-43 1.

The Nuclear Regulatory Commission-(the Commission) has found that:

A.

The application for t.mendment by the Detroit Edison Company (the i

licensee) dated July 24, 1989, complies with the standards and requirements of the Atomic _ Energy Act of 1954, as amended (the Act),

l and the Commission's rules and regulations sct 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; i

l C.

There is reasonable assurance (i) that the act'ivities authorized by i

p this amendment can be conducted without end6ngering the health and j

safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; I

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-1:

E.

The issuance of this amendment is in accordance'with 10 CFR Part 51 ef 4

the Commission's regulations and all applicable' requirements have bean satisfied.

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2.

Accordingly, the license is amended by changes to the Technical Specifica-tions 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:

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Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 54, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.

DECO t'1all operate the facility in accordance with the Technical Specificatir.s and the Environmental Protection Plan.

9009050341 900827 PDR ADOCK 05000341 P

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This license an.endirent is effective as of the date of its issuance.

FOR.THE NUCLEAR REGULATORY COMMISSION.

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Robert C..Pierson, Director Project Directorate 111-1 Division of Reactor Projects - III.

-IV, V & Special Projects Office of Nuclear Reactor-Regulation Attachnent:

Charges to the Technical Specificaticns-

,Date of Issuance: August 27, 1990

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ATTACHMENT-TO LICENSE AMENDMENT NO. 54

. FACILITY OPERATING LICENSE NO. NPF-43

-DOCKET NO._,50:3a1 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Anendment number and

-contain a vertical.line indicating the area of change.1 REMOVE INSERT i

6-1 6-1*

6-2 6-2 6-5 6-5*

6-6 6-6 6-7 6-7 i

6-8 6-8*

i 6-9 6-9*

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• 0verleaf page provided to maintain com'pleteness.

No changes contained on this.page.

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i 6.0 ADMINJ,ST,R,ATJVE CONTROLS 6.1 Resp 0NSIBILITY 6.1.1 The Plant' Manager shall be responsible for overall unit safe operation 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 Vice President-Nuclear Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION 6.2.1,,,0Ff,S1,TE_ AND ONSITE ORGANIZATION 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 i.pdated, as appropriate, in the form of organization charts, functlonal 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 l

Updated Final Safety Analysis Report.

b.

The Senior Vice President shall have corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of the staff in operating, l

maintaining, and providing technical support of the plant to ensure l

nuclear safety.

l 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.

6.2.2 UNIT STAFF l

a.

Each on duty shift shall be composed of at least the minimum shift crew corrposition 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; FER111 - UNIT 2 6-1 Amendment No. II, g, 54

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' ADMINISTRATIVE' CONTROLS

.x RN,1,TSTAFF(Continued) c.

A Health Physics Technician

• shall be on site when fuel is in the reactor; d.

All CORE ALTERATIONS shall be observed and directly supervised by either a licensed Senior 0>erator or licensed Senior Operator Limited to Fuel Handling w1o has no other concurrent responsibilities during this operation; e.

A site fire brigade of at least five members shall be maintained on site at all times *. The fire brigade shall not include the Nuclear-Shift Supervisor, the Shift Technical Advisor, nor the two other members of the minimum shift crew necessary for safe shutdown of the unit and any personnel required for.Other essential functions during a fire emergency; and f.

Administrative procedures shall be developed and implemented to limit the working hours of unit staff who perform safety-related functions;(e.g.,licensedSeniorOperators,licensedOperators, 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 operating personnel-work 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 ir.dividual 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 zore than-16 hours 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 exclud-ing shift turnover time.

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 snutdown 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 a Section Superintendent or higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that individual overtime shall be reviewed monthly by the Plant Manager or a Section Super-intendent to assure that excessive hours have not been assi p d.

Routine deviation from the above guidelines is not authorized.

• The Health Physics Technician and fire brigade composition may be less than the minimum requirements 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 acconcodate unexpected absence, provided immediate action is taken to fill the required pusitions.

FEPJ41 - UNIT 2 6-2 Amendment No. II, 79, 54

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TABLE 6.2.2-1 MINIMUM SHIFT CREW COMPOSITION NUMBEROFINDIVhDUALSREQUIREDTOFILLPOSITION POSITION CONDITION 1, 2, or 3 CONDITION 4 or 5 NSS 1

1 NASS 1

None NSO 2

1 NPP0/NAPP0 2

1 STA 1

None-TABLE NOTATION NSS. -

Nuclear Shift Supervisor with a Senior Operator. license NASS -

Nuclear Assistant Shift Supervisor with-a Senior Operator license NSO z--

Nuclear Supervising Operator with an Operator license 3

NPP0/NAPP0 - Nuclear Power Plant Operator'or Nuclear Assistant Power Plant Operator Shift Technical Advisor STA Except for the Nuclear Shift Supervisor, the shift crew composition may be one-less.than the minimum requirements of Table 6.2.2-1 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 acconnodate unexpected absence of on-duty shift _ crew members provided immediate action'is taken to restore the shift crew composi-tion to within the minimum requirements of-Table 6.2.2-1.

This provisio

.does not permit any shif t crew position to be' unmanned upon shif t change due to an-oncoming shift crewman being late or absent.

During any absence of the Nuclear Shift Supervisor from the control room while the unit is in OPERATIONAL CONDITION I, 2 or 3, an individual (other than the

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i Shif t Technical Advisor) with a valid Senior Operator license shall be desig-nated to assume the control room command function. During any absence of the Nuclear Shif t Supervisor from the control room while the unit is in OPERATIONAL

.1 CONDITION 4 or 5, an individual with a valid Senior 0perator license or Operator y'

. license shall be designated to assume the control room command function.

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.x FERMI - UNIT 2 6-5

J ADMINISTRATIVE' CONTROLS

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t 6.2.3 INDEPENDENT SAFETY ENGlHEERING GROUP (ISEG)

FUNCTl0N'

6. 2. 3.1 The ISEG shall function to examine unit operating characteristics, NRC issuances, industry advisories, Licensee Event Reports, and other sources 6

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

COMPOSITION 6.2.3 ? 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 ve'ification* that these activities are perforned correctly and that human errors are reduced as much as practical.

AUTHORITY L

l 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, l-equipment modifications, maintenance activities, operations activities or other means of improving unit safety to the Vice President Nuclear Engineering and Services.

6.2.4 SHIFT TECHNICAL ADVISOR 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to 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 i

controls in the control room, t

• Not responsible for sign-off function.

FERMI - UNIT 2 6-6 Amendment No. II, 66, 54 i

' ADikINISTRATI'VE CONTROLS 6.3 UNITSTAFFQUALIFICATIONS 6.3 d _Each.. ember of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, except for the Superintendent - Radiation Protection or his designee who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed Operators'and Senior Operators shall.also meet or exceed the minimum qualifica-

-tions of the supplemental requirements specified in Sections A and C of of-the March 29, 1980 NRC letter to all. licensees.

6,.,4,, TRAI N I NG 6.4.1 A retraining and replacement training program for the unit staff shall bemaintainedunderthedirectionoftheDirector(s),NuclearTraining,shall meet or 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.

6.5 REVIEW AND AUDIT

6. 5. I' ONSITEREVIEWORGANIZAT!0 DOS,RO)

R 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 h

COMPOSITION 6.5.1.? The OSR0 shall be composed of the:

Chairman Plant Manager Vice-Chairman / Member

• Director, Plant Safety l

Vice-Chairman / Member

• Superintendent-Operations L

Member Operations Engineer lienber Superintendent-Technical Member Superintendent-Radiation Protection i

Member Superintendent-Maintenance-Member Reacttr Engineer I

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• May not act as Chairman and member at the same time.

FERMI - UNIT 2 6-7 Amendment No. II,if, 54

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c, ADMINISTRAyVECONTROLS' ALTERNAT,ES 6.5.1.3 All alternate members shall be appointed in writing by the OSR0 Chairman to. serve on a temporary basis; however, no more than two alternates shall participate as. voting members in OSR0. activities at any one time,

, MEETING FREQUENCY-

-6.5.1.4 The OSR0 shall meet at least once per calendar month and as conver,'ed by the OSR0 Chairman or a Vice Chairman.

QUORUh 6.5.1.5 The quorum of the OSR0 necessary for the performance of the OSR0 re-spensibility and authority provisions of these Technical Specifications shall consist of the Chairman or a Vice Chairman and four members including alternates.

RESPONSIBIL,ITIES

'ne OSR0 shall be responsible.for:

6.5.1.6 i

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 sval-uation and recommendations to prevent recurrence, to the Vice President-Nuclear Operations and to the Nuclear Safety Review Group; g.

Review of all REPORTABLE EVENTS; h.

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

Perform:nce of special reviews, investigations, or analyses and reports thereon as requested by the Plant Manager or the Nuclear Safety Review Group; j.

Review of the Security Plan; k.

Review of the Emergency Plan; FERMI - UNIT 2 6-8 Amendment No. II, 29, 54

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^ A_DMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) 1.

' Review of every unplant ed onsite release of radioactive material'to the environs including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the correc-tive action to prevent recurrence to the Vice President-Nuclear-Operations and to the Nuclear S*.fety Review Group; and m.

Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE l

DOSE CALCULATION MANilAL, and major modifications to the Radwaste Treatment Systems.

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Review of the Fire Protection Program.

6.5.1.7 The OSRO 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 Specifica-tion 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 Vice President-Nuclear Operations and the Nuclear Safety Review Group of disagree-ment between the OSR0 and the Plant Manager; however, the Plant Manager shall have responsibility for resolution of such disagree-ments 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 OSRO activities performed under the t1 responsibility provisions of these Technical Specifications.

Copies shall be provided to'the Vice President-Nuclear Operations and the Nuclear Safety Review Group.

6.5.2 NUCLEAR SAFETY REVIEW GROUP (NSRG).

FUNCTION h

6.5.2.1 The NSRG shall function to provide independent review and audit of designated activities in the areas of:

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Nuclear power plant operations, b.

Nuclear engineering, L

c.

Chemistry and radiochemistry,

. d.

Metallurgy, 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 on those areas I

of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

FERMI - UNIT 2 6-9 Amendment No. ZZ, E9, 54

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n AbMIN,ISTRATIVECONTROLS COMPOSITION w

6.5.2.2. The Senior Vice President shall appoint at least nine members'to the NSRG and shall designate from this membership 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.

t 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 bache-lor's. degree in engineering cr related sciences.

The Chairman shall have at l

1 east 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 profes-sional 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 y

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.

l MEETING' FREQUENCY.

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

QUORUM 6.5.2.6 The quorum of the NSRG necessary for the performance of the NSRG l

review and audit functions of these Technical Specifications.shall consist of I

the Chairman or his designated alternate and at least one half-of the remain-ing NSRG members of which two may be alternates.

No more than a minority of

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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 50.5is to verify that such actions did not constitute an unreviewed safety question; b.

Proposed changes to procedures, equipment, or systems which invcive an unreviewed safety question as defined in 10 CFR 50.59; FERMI - UNIT 2 6-10 Amendment No. II, M, 54

./hililSTRATIVEC0!GROLS

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_ COMPOS _ITE 6.5.2.P. The Senior Vice President shall anoint at least nine n.ec.bers to the 1

tiSRG and stall designate fror.i this nien.bership a Chairman ard at least one Vice l

Chairo.an. The trernbership shall-collectively possess experience and conpetence to provide independent review and audit in the artes listed in Section 6.5.P.1.

The Chairman ar,d Vice Chairraan shall have nuclear background in engineering or operations and shall be capable of determining when to call in experts to assist the !!SRG review of con: plex problems. All roernbers shall have at least a beche-

' lor's degree in er.gineering or related sciences. The Chairnen shall have at ler.st 10 years of professior.a1 level menagenent experier.ce in the power field and each of the other rnembers shall have at least 5 years of cun.ulative profes-sional level experience in one or more of the fields listed in Section 6.5.2.1.

Al.T ERNATES.

6.5.2.3 ' All; alternate men 4bers shall be appointed in writing by the fiSRG Chairnan to serve cn a ten.porary basis; however, no n. ore than two alternates shall participete as voting menbers in I:SRG activities at any one time.

EPh.5,U,L,TANTS 6.5.P.4 Censultants shall be utilized as determined by the I:SRG Chairn.an to N

. pr ovidt expert acM oe to the NSRG.

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6.5.2.5 The 11SRG shall n.eet at least once per 6 months.

gUORUM

6. 5. P. f.

The quorum of the liSRG necessary for the performance of the t:SPC review ar.c audit functions of these Technical Specifications shall censist of the Cheirnan or his designated alternate and at least one half of the ren.ain-ir.g iSPG c.er.bers cf which two rray be alternates. tio more than a niinority of 3

the quorunfshall have lir.e responsibility for operation of the unit.

REVIEW 6.5.P.7 The hSRG shall be responsible for the review of 6.5.2.7.a and shall review 6.5.2.7.b through 1:

a.

The safety evelvetions for (1) chariges to procedures, equipirent, facilities or systen.s ar.d (2) tests or experirnents completed under the provisior, cf 10 CFR 50.59 to verify that such actions did not cctsiitute an unreviewed safety question; b.

Proposed changes to procedures, equipnent, or systems whici, involve

- an unrevined safety question as defit.ed in 10 CFR 50.59; FEPl'I - l!t:lT P 6-10 Arrendo.ent fio. II, If, 54

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