ML20058M842

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Proposed Tech Specs Changing Title of Vice President - Nuclear Operations to Assistant Vice President & Manager - Nuclear Operation, to Reflect Util New Onsite Nuclear Operation
ML20058M842
Person / Time
Site: Fermi DTE Energy icon.png
Issue date: 08/01/1990
From:
DETROIT EDISON CO.
To:
Shared Package
ML20058M840 List:
References
NUDOCS 9008130087
Download: ML20058M842 (8)
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6.0 ADNINISTRATIVE CONTROLS 61 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-V49e-

- M 94 C ,t t : h;r ^;;r;t hr.; shall be reissued to all station personnel on an annual basis. Q sres/ani Vac frenhostand knq r - Nuclea r frufciwr,

(. /l 6.2 ORGANIZATION 6.2.1 0FFSITE AND ONSITE ORGANIZATION

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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,

s. Lines of authority, responsibility, and communication shall be established and defined for the highest management levels through l intermediate levels to and including all operating organization l 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 l i Updated Final Safety Analysis Report. i

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, maintaining' nuclear sa e,ty.and providing technical support of the plant to ensure
c. The individuals who train the operating staff and those who carry I out health physics and quality assurance functions may report to the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure thtjr independence from operating pressures.

( 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; l
b. At least one licensed Operator shall be in the control room when I o fuel is in the reactor. In addition, while the unit is in 1 OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Operator shall be in the control room; I

FERMI - UNIT 2 6-1 Amendment No. ZZ,30 l

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llIFORWiAT10iV CiilLY I

'ADi!NISTRATIVECONTROLS l

5.3 UNIT $TAFF QUALIFICATIONS

, 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-l cations of ANSI N18.1-1971 for comparable positions, except for the i

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 qualifica-tions 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 (s), Nuclear Training, 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 l to all licensees, and shall include familiarization with relevant industry operational experience.

6.5 REVIEW AND AUDIT 6.5.1 ONSITE REVIEW ORGANIZATION (OSR0)

FUNCTION l 4

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 I COMPOSITION

6. 5.1. 2 The OSR0 shall be composed of the: l Chaiman Plant Manager ,

Vice-Chairman / Member

  • Director, Plant Safety l Vice-Chairman / Member
  • Superintendent-0perations Member Operations Engineer  :

Member Superintendent-Technical Member Superintendent-Radiation Protection Member Superintendent-Maintenance and Modifications Member Reactor Engineer

  • May not act as Chaiman and member at the same time. l FERMI - UNIT 2 6-7 Amendment No.11.30

, ADN!il!$TRAT!vt CONTROLS .

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l ALTERNATES 1

6.5.1.3 All alternate seabers shall be appointed in writing by the 0$to i Chairman to serve en a paperary basis however ne more than two alternates shall participate es voting enabers in;0$R0 activities at any one time.

fEITING FREQUENCY ,

6.5.1.4 The 0$00 shall meet at least once per calender month and as ' convened i

, by the 0$00 Chairman er a Vice Chairman.

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6.5.1.5 The quorum of the 0$R0 necessary for the performance of the 0$R0 re-spensibility and authority provistens of these Technical Specifications shall 1

, consist of the Chairman er a Vice Chairman and four enebers including alternates. ,

RESPON5101 LIT]E$

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6.5.1.6 W 0$R0 shall be responsible for:

! a. Review of all Plant Administrative procedures and changes thereto; l-l l b. Review of all proposed tests and experiments that affect nuclear safety; I L

c. Review of all proposed changes to Appendix A Technical Specifications;
d. Review of all proposed changes or as  :,stions to unit systems or equipment that affect nuclear safety;
e. Review of the safety evaluations for plant precedures and changes therete completed under the provisions of 10 CFR 50.59;
f. Investigation of all violations ofthe Technical Specifications.  :

including the preparation and forwarding of reports covering eval-

, untion and receanendations to prevent recurrence to the #4ee ope 46 ens-and to the Nuclear defety Review Group; l GArv sn v.c e, tre r de a.st meg e r-uut<a v enkw

g. Review of all REPORTABLE EVENT $;
h. Review of unit operations to detect potential hazards to nuclear safety; -

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1. Performance of special reviews, investigations, or analyses and  ;

reports thereen as requested by the Plant Manager er the Nuclear l Safety Review Group;

j. Review of the Security Plan; I
k. Review of the Emergency Plan; i

FEIMI - UNIT 2 6-3 Amendment No.11 ,

& 1 ADMINISTRATIVE CONTROLS i

i RESPONSIBILITIES (Continued)

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

covering evaluation, recessendations and disposition of the correc- .l tive action to prevent recurrence to the "i;e ?.eeitat %.;1eer,  ;

C :r;ti;n and to the Nuclear Safety Review Group; and l

m. Review of changes to the PROCESS CONTROL PROGRAM, the OFFSITE -

DOSE CALCULATION MANUAL, and major modifications to the Radwaste Treatment Systen. g,5fJ V<e fma/eded honap -l(sulove fridun 6.5.1.7 The OSR0 t ialb  ;

a. Recommeno in writing to the Plant Manager approval or disapproval of items coniidered under Specification 6.5.1.6a. through d. prior to their implementation.
b. Render determinations in writing to the Nuclear Safety Review Group l with regard to whether or not each item considered under Specifica-tion 6.5.1.6a. through f. constitutes an unreviewed safety question. l
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 WhefreeWe*

%.;1;;r 4:7;ti;n 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 " I ""~ O "M "'# " "*/" ~ M" "

6.5.1.8 The OSR0 shall maintain written minutes of each OSR0 meeting that, at a minimum document the results of all 0$RO activities performed under the .

l rssponsibl11typrovisionsoftheseTechnicalSpecifications. Copies shall be provided to the R . ?ceei c at " ni;;r 3 :r;ti;= and the Nuclear Safety Review Group. C Anir/noif Ha fren/ erd el Jimyer-kin r Parda/ren .

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6.5.2 NUCLEAR SAFETY REVIEW GROUP (NSRG) l- FUNCTION . ,

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

a. Nuclear p9wer plant operations,
b. Nuclear engineering, - .
c. Chemistry and radiochemistry, q
d. Metallurgy,
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 on those areas l of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

6-9 Amendment No.11,30

' FERMI - UNIT 2 E_.

A IIN'ISTRATIVE CONTROLS - - C#

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COMPOSITION , , , , , ,

3 ycgrf ,y/w// Je uc/ cur facer pl,4 6.5.2.2 The 3enior Vice PbeM appoint at least nine members to the 1 I NSRG and shall designate from this membership a Ch rean and at least one Vice Chairman. _ The membership shall collectively posse s experience and competence to provide independent review and audit in the a s 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 n to call in experts to assist the NSRG review of complex problems. All membe shall have at least a bache-lor's degree in engineerire or related sciences 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 profes- )

sional level experience in one or more of the fields listed in Section 6.5.2.1. J 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 j

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shallparticipateasvotingmembersinNSRGactivit(tsatanyonetime.

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

1 MEETING FREQUENCY )

6.5.2.5 The NSRG shall meet at least once per calendar quarter during the l initial year of unit operation following fuel loading and at ? east once per l

6 months thereafter. )

i 000 RUM .

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 remain-i ing NSRG members including 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 J review 6.5.2.7.b through 1:

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; 6-10 Amendment No.11,30 l FERMI - UNIT 2 l

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. ADMINISTRATIVE CONTROLS REVIEW 6.5.3.2 Each procedure or procedure ch'ange 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 indi-vidual that prt$ured 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 per-sonnel 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 designee. The Environmental Program Coordinator will review l any changes pertaining to G.8.1.j. These reviews may be performed in lieu of, (

or in addition to, those required by item 6.5.3.2 above. j 1

SAFETY EVALUATIONS j 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 an..coval 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 i shall be members of the plant staff previously designated in writing by the i Plant Manager. l 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 re b nendations 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
b. Each REPORTABLE EVENT shall be reviewed by the 0$R0, and the results of this review n----a ...

shall be submitted to the NSRG and the W ee-President-

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-FERNI - UNIT 2 6-13 Amendment No. ZZ, 30 i

ADMINISTRATIVE CONTROLS 6.7 5AFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is vi01sted: gg f.e (,eydo,f,,j ga,,afer-Maine fwk/w

a. 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 44 ."+;;it:t ";:1::.

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^4 ::::- and the N5RG shall be notified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed by the 0$R0. This report shall describe (1) applicable circumstances proceding 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 "i;; ".e;i " -^ "-- '-- ^-------

7 l within 14 days of the violation'f j)ssis/en/ Vice Andol e d OQ "ftr - W"dc

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d. Critical operation of the unit shall not be resumed until authorized j 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 J Guide 1.33, Revision 2, February 1978.  ;
b. The applicable procedures required to implement the Fermi 2 commit-ments made in response to,the requireisents of NUREG 0737.
c. Refueling operations.

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

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e. Security Plan implementation. . .

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f. Emergency Plan implementation; .

l g. Fire Protection Program implementatiert

h. PROCESS CONTROL PROGRAM implementation.
1. OFFSITE DOSE CALCULATION MANUAL implementation.
j. Quality Assurance Program for effluent and environenntal sonitoring, using the guidance in Regulatory Guide 1.21 Revision 1. June 1974 and Regulatory Guide 4.1, Revision 1. April 1975.

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1 FERMI - UNIT 2 6-14 Amendment No. 11 l

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