ML20212C013

Proposed Tech Specs Reflecting Reorganization of Nuclear Operations Organization to Incorporate Group Vice President & Strengthen Plant Manager Position

ML20212C013
Person / Time
Site:	Fermi
Issue date:	08/05/1986
From:	DETROIT EDISON CO.
To:
Shared Package
ML20212C011	List: ML20212C006 ML20212C013
References
NUDOCS 8608070299
Download: ML20212C013 (15)

Text

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6.0 ADMINISTRATIVE CONTROLS 6.1 RESPONSIBILITY f%t M6nc[<

6.1.1 The i ;' 1 ..^. [..._,,.. __'__.7.__'_ . - . shall be responsible for overall

"' I unit operation and shall delegate in writing the succession to this responsibility during his absence.

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 Operrtions shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION  ;

0FFSITE 6.2.1 The offsite organization for unit management and technical support shall be as shown on Figure 6.2.1-1.

UNIT STAFF 6.2.2 The unit organization shall be as shown on Figure 6.2.2-1 and: l

) 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 v 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 Health Physics Technician

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

d. All CORE ALTIERATIONS shall be observed and dimctly 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. A site fire brigade of at least five meubers 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 i members of the minimum shift cmw necessary for safe shutdown of the unit and any personnel requited for other essential functions during a fire emergency; and "The Health Physics Technician and fire brigade composition may be less thin the minimum mquirements 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 inmediate action is taken to fill the required positions.

FERMI - UNIT 2 6-1

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8600070299 860805 PDR ADOCK 05000341 P PDR N

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ADMINISTRATIVE CONTROLS UNIT STAFF (Continued)

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f. A[ministrativeproced es shall be developed and implemented to ~

limit the working h rs of unit staff who perform safety related functions (e.g., 1 ensed Senior Operators, licensed Operators, health ;t:':':t:, 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 normal 8-hour day, 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 shut-

. down for refueling, major maintenance, on 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 kurs 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 /> 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 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. J' ,

s

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

l Any deviation from the above guidelines shall be authorized by the ,

'N ".;.% _c.; T._. _,_. ::__h. Tc:1:tt.. or his deputy, or higher levels of l management, in accordance with established procedures and with docu-mentation of the basis for granting the deviation. Controls shall be ,

included in the procedures such that individual overtime shall be re- I viewed monthly by the t.ht. .; 7._c._;;; ::_:h_: "::izth; or his designee to assure that excessife hours have not been assigned.

Routine deviation from the abovo guidelines is not authorized.

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FERMI - UNIT 2 6-2

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$ GROUP 3 INDEPENDENT DIRECTOR VICE i SAFETY _

NUCLEAR _ PRESIDENT c ENGINEERING OUALITY g GROUP ASSURANCE

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VICE j PRESIDENT

NUCLEAR OPERATIONS I

I i 1 DIRECTOR GENERAL

! REGULATORY DIRECTOR PLANT AFFAIRS NUCLEAR MANAGER j ENGINEERING i

m ,...... l l l a l l l l FIGURE NUCLEAR SUPERVISOR 6.2.2-1 i

RADIOLOGICAL DIRECTOR SAFETY SUPERVISOR ARCHITECT /

EMERGENCY LEAR j REVIEW LICENSING ENGINEER

RESPONSE

GROUP ENGINEERING PREPAREDNESS l

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I I GENERAL GENERAL SUPERVISOR SUPERVISOR GENERAL NUCLEAR SYSTEMS OF PROJECTS SWERVISOR

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INTERFACE RELATIONSHIP

& QUALIFICATION AND PLANT I ENGINEERING ENGINEERING FUEL 1

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FIGURE 6.2.1-1 OFFSITE ORGANIZATION i

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FERMI - UNIT 2 6.4

ADMINISTRATIVE CONTROLS 6.2.3 INDEPENDENT SAFETY ENGINEER,ilG GROUP (ISEG)

FUNCTION r T 6.2.3.1 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 auch as practical.

AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for mvised procedures, equipment modifications, maintenance activities, operations activities or other means of improving unit safety to the a

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6.2.4 SHIFT TECHNICAL ADVISOR A Direcht - Nuclear 006N}! 0""

l 6.2.4.1 The Shift Technical Advisor shall provide advisory technical support to the Nuclear Shift Supervisor in the areas of thermal fqydraulics, mactar engineering, and plant analysis with regard to safe opemtion 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 instnanentation and controls in the control room.

• Not responsible for sign-off function. .

FEitMI - UNIT 2 6-6 r-

ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Eacli member of the unit staff shall .eet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, except for the General 7 Supervisor-Health Physics who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975. The licensed Operators and Senior Opera-tors shall also meet or exceed the minimun 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 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 6.5.1 Onsite Review Organization (OSRD)

FUNCTION

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6.5.1.1 The OSRO shall function to advise the f.::'":t "; --- "r'er-

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doodeeMea.on all matters related to nuclear safety.

JJ/8,,f Yc7/ic7' er COMPOSITION 6.5.1.2 The OSR0 shall be composed of the: y l Chaiman ?z:'-t -?_  :^_.___ "M :: " : f " ' - -

Vice-Chairman Superintendent-40se$sup ope rations l Vice-Chairman Superintendent-Maintenance and Modification Member Operations Engineer Member Technical Engineer Member Maintenance Engineer Member Radiation Protection-themical Engineer Member Supervisor Operational Assurance Member Reactor Engineer q.

9 FERMI - UNIT 2 6-7 l

l l

ADMINISTRATIVE C0KTROLS ALTERNATES '

6.5.1.3 Afi_ alternate members shall be appointed in writing by the OSR0 --

Chairman to serve on a temporari 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 convened by the DSRO Chairman or his designated alternate. -

000 RUM 6.5.2.5 The quorm of the OSR0 necessary fcr the performance of the OSR0 responsibility ar.d authority provisions of these Technical Specifications shall consist of the Chairman or his designated alternate and four members including up to two alternates.

RESPONSIBILITIES 6.5.1.6 The OSRO shall be responsible for:

a. Review of (1) all procedures required by Specification 6.8 and changes thereto, (2) all programs required by Specification 6.8 and changes thereto, and (3) any other procedures or changes thereto as

• rt r: r- S:1: r "r:fr tic: to affect detemined nuclear safety;by the Plcu2:!:d Mamge;r-

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

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

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

e. Investigation of all violations of the Technical Specifications, including the pmparation and forwarding of reports covering evaluation and recommendations to prevent recurrence, to the i-.:;r-Nuclear

@erations and to the Nuclear Safety Review Group; .

f. Review of all REPORTABLE EVENTS; Y'l* '

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g. Review of unit cperations to detect potential hazards to nuclear safety;

h. Perfomance of special reviews, investigations, or analyses " '

and reports thereon as requested by the or the Nuclear Safety Review Group; ^

i. Review of the Security Plan and implementing procedures;

j. Review of the Emergency Plan and implementing procedures; FERMI - UNIT 2 6-8 l

ADMINISTRATIVE CONTROLS x

RESPONSIBILITIES (Continued)

k. Review of any accidental, unplanned or uncontrolled radioactive release-- Q 16cluding the preparation and forwarding of reports covering evaluationi recommendations and disposition of the corrective action to prevent g recurrence to the Vice President-Nuclear Operations and tc the o Nuclear Safety Review Group; and 1

1. Review of changes to the PROCESS CONTROL PROGRAM and the DFFSITE DOSE CALCULATION MANUAL. i P/an 'e Mav?ayr ,

6.5.1.7 The OSRO shall: - = - - - - -

a. Recommend in writing b the t ' 1 "_- g . M__L _ . 7. l _ ^.L..

4 1'

approval or disapp al of it s considered under Specifica-tion 6.5.1.6a. th ugh d. pr r to their implementation. T

b. Render deterni ions in Sr ing to the Nuclear Safety Review Group 8 with regard $4 whether or t each item considered under Specifica- 3 tion 6.5.1/a.throughe. onstitutes an unreviewed safety question.

c.

6,Provide w

'ritten notificat and on within the Nucle r Safety 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Review Group to the6 4 of disagreement betwe'en the OSRO and the p;however, the" shall have respons' bility for resolution of such disagreements pursuant to Specification 6.31. -

RECORDS

6. 5.1. 8 The 05R0 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 nnd the Nuclear Safety Review Group. e\ j 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 6 <. Cons

g. Mechanical and electrical engineering, and

h. - Quality assurance practices. G, The NSRG shall report to and advise the Vice President 6 on those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.8.

FERMI - UNIT 2 6-9

ADMINISTRATIVE CONTROLS COMPOSITION C,WP) 6.5.2.2 The ice-Presiden+ 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 expe.-ience i 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 i

in experts to assist the NSRG review of complex problems. Air members shall have at least a bachelor's degree in engineering or related sciences. The Chairman shall-have at least 10 years of professional level management experi-ence 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 utifized4as determined by the NSRG Chairman to provide expert advice to the NSRG. **

MEETING FREQUENCY 6.5.2.5 The NSRG shall meet at least once per calendar quarter during the '

initial year of unit operation following fuel loading and at least once per 6 months thereafter.

QUORUM 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-1 ing NSRG members including alternates. No more than a minority of the quarten 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 1:

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

b. ~

Proposed thanges to procedures, equipment, or systems which involve an unruviewed safety question as defined in 10 CFR 50.59;

. .. <r FERMJ - UNIT 2 6-10

.me.

ADMINISTRATIVE CONTROLS AUDITS (Continued)

g. Any other area of unit operation considered appropriate by the NSRG or the4(Vice 6mp) President-N.ci r Op;r:ti:n:;

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 Vice President-N;;1: r Op;r:ti:n: within 14 days (f- )

following each m in ,

h p- 6rco -

b. ReportsofreviewsencompassedbySpeciffcation6.5.2.7shallbe prepared, approved, and forwarded to theAVice President-N;;icer Ope :tfer: within 14 days following completion of the review.

c.

M Audit reports e ompassed by Specification 6.5.2.8 shall be forwarded to the Vice President-M;;?::r Op r: tier and to the management positions responsible for the areas audited within 30 days after completion of the audit by the auditing organization.

6.6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for RE URTABLE 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 OSRO, and the results M

of this review shall be submitted to the NSRG and theg eneger-Nuclear Operations. ice. Pnestclen{,)

S FERMI - UNIT 2 6-12 .

I

Nuce frwY ADMINISTRATIVE CONTROLS  ;

6.7 SAFETY LIMIT tidLATIDW ,,

6.7.1 The following actions shall be taken in t event Safety Limit is y violated.

a. The NRC Operations Center shall be no ified b telephone as soon as possible and 4 all cases within I )

ur. The t-Nuclear ,

Operations and the MSRG shall be no fled within 24 1ours. j

b. A Safety Limit Violation Report sh 11 be prepared. The report shall be reviewed by the OSRO. This te ort shall describe (1) applicable ,

circumstances preceding the viol ion, (2) effects of the violation 1 upon unit components, systems, or structures, and (3) corrective action taken to prevent recurre/re.

c. The Safsty Limit Violation R ort shall be submitted to the l Commission, the NSRG, and the Nuclear Operations within l 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:

I 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. Secu.-ity plan implementation.

f. Emergency Plan implementation.

g. Fire Protection Program implementation.

h. PRDCESS CDNTROL PROGRAM iglementation.

1. OFFSITE D05E CALCULATIDN MANUAL implementation.

j. Quality Aswrance Program for effluent and environmental monitoring, using the guidance in Regulatory Guide I.21 Revision 1. June 1974

~ and Regulatory Guide 4.1, Revision 1, April 1975.

FE'RMI - UNIT 2 6-13

+

ADMINISTRATIVE CONTROLS PRDCEDURES AND PROGRAMS (Continued)

L 6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be r reviewed by the OSR0 and shall be approved by the M P k 6g prior to implementation and reviewed periodical'y as se amin'strative procedures.

orth <n 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

N a. The intent of the original procedure is not altered;

) R

)Q 3

b. The change is approved by two members of the unit management staff, at least one of whom holds a Senior Operator license on Fermi 2; and

c. The change is documented, reviewed the OSRO, and approved by the within 14 days of implementation.

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

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the HPCI, CS, RHR, RCIC, reactor water sampling, containment sampling, reactor water cleanup, combustible gas control, control red drive discharge headers, and standby gas treatment )

systems. The program shall include the following:

i

. 2. Preventive maintenance and periodic visual inspection requirements, and

2. Integrated leak test requirements for each system at refueling cycle intervals or less.

b. In-Plant Radiation Monitorina A program which will ensure the capaoility to accurately determine the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

2. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

c. Post-accident San 611ng* ..

. A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous efflu-ents, and containment atmosphere samples under accident conditions.

"Not required until prior to exceeding 5% of RATED THERMAL POWER.

FEIMI - UNIT 2 6-14

ADMINISTRATIVE CONTROLS AUDITS (Continued)

g. Any other area of unit operation considered appropriate by the NSRG or the ice President-N.ci:27 0;;r:ti:n:;

A-

h. The radiologica 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 thejVice President-N.1: r Optrati: : within 14 days ig_)

following each

b. ReportsofreviewsencompassedbySpeciffcation6.5.2.7shallbe prepared, approved, and forwarded to theAVice President-N. i r Oper: tier: within da s following completion of the review.

6HME

c. Audit reports e ompassed by Specification 6.5.2.8 shall be forwarded to the ice President-9 :1::r Oper tfen: and to the management r :itions responsible for the areas audited within 30 days afte. :ompletion of the audit by the auditing organization.

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 OSRO, and the results M

of this review shall be submitted to the NSRG and theg eneger-Nuclear

~

Operations.

ce. P.vstanG FERMI - UNIT 2 6-12

• No ce fro YI' &

ADMINISTRATIVE CONTROLS I I 6.7 SAFETY LIMIT VIOLATIDW ,,

6.7.1 The following actions shall be taken in i event Safety Limit is 7 violated:

a. The NRC Operations Center shall be no ified b telephone as soon as possible and in all cases within I h ur. The t-Nuclear Operations and the NSRG shall be no fled within 24 iours.

b. A Safety Limit Violation Report sh 11 be prepared. The report shall be reviewed by the OSRO. This te ort shall describe (1) applicable circumstances preceding the viol ion, (2) effects of the violation upon unit components, systems, structures, and (3) corrective action taken to prevent recu .

c. The Safety Limit Violation R shall be submitted to the Commission, the NSRG, and th Nuclear Operations 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:

m

') 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 responst to the requirements of NUREG-0737.

c. Refueling operatinens.

d. Surveillance and test 3ctivities of safety-related equipment.

e. Sacurity Plan implementation.

f. Emergency Plan iglementation.

g. Fire Protection Program iglementation.

h. PROCESS CDNTROL PROGRAM iglementation.

1. OFFSITE DDSE CALCULATIDN MANUAL implementation.

i

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 6-13

ALY.INISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

L 6.8.2 Each procedure of Specification 6.8.1, and changes thereto, shall be --

reviewed by the OSR0 and shall be approved by the 4 [

k gg prior to implementation and reviewed periodical y as se admin'strative procedures.

orth 'n 6.8.3 Temporary changes to procedures of Specification 6.8.1 may be made provided:

N a. The intent of the original procedure is not altered;

) R 3 D b. The change is 9pproved by two members of the unit management staff,

( at least one of whom holds a Senior Operator license on Femi 2; and

c. The change is documented, reviewed by the OSRO, and approved by the within 14 days of implementation.

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

a. Primary Coolant Sources Outside Containment A program to reduce leakage from those portions of systems outside containment that could contain highly radioactive fluids during a serious transient or accident to as low as practical levels. The systems include the HPCI, CS, RHR, RCIC, reactor water sampling, containment sampling, reactor water cleanup, combustible gas control, -

tontrol red drive discharge headers, and standby gas treatment i systems. The program shall include the following:

i

. 1. Preventive maintenance and periodic visual inspection requirements, and

2. Integrated leak test requirements for each system at mfueling cycle intervals or less.

b. In-Plant Radiation Monitorina i A program which will ensure the capability to accurately detemine l the airborne iodine concentration in vital areas under accident ronditions. This program shall include the following:

3. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

c. Post-accident Sam 611n=* ..

. A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates 'n plant gaseous efflu-ents, and containment atmosphere samples under accident conditions.

• Not required until prior to exceeding 5% of RATED THERMAL POWER.

FERMI - UNIT 2 6-14 L ________ _. __ _

_ _ _ _ . - _ . _ .. . .. .. .