Text

Proposed Tech Specs Re Administrative Controls for Onsite Review Organization
	ML20207L039
Person / Time
Site:	Fermi
Issue date:	01/07/1987
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20207L014	List: ML20207L010; ML20207L039;
References
	NUDOCS 8701090600
	Download: ML20207L039 (21)
	v • d • e

._

Markup of 01 apter 6.0 "Adninistrative Controls" Technical Specifications

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( INDEX ADMINISTRATIVE CONTROLS .

PAGE SECTION 6-1 6.1 RESPONSIBILITY............................................

6-1 6.2 ORGANIZATION..............................................

6-1 6.2.1 0FFSITE..............................................

6-1 6.2.2 UNIT STAFF...........................................

3 6-6 ,b' 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP.................

6-6 \{ q J2 /3' ,M FUNCTION.............................................

COMPOSITION..........................................

6-6 bo#/ .~<,

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RESP 0NSIBILITIES..................................... 6-6 [gp .

AUTHORITY............................................

6-6 j)r'kJ 6-6 6.2.4 SHIFT TECHNICAL ADVIS0R.............................. .

6-7 6.3 UNIT STAFF QUALIFICATIONS................................. ,

6-7 6.4 TRAINING..................................................

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6.5 REVIEW AND AU0IT..........................................

6-7 6.5.1 ONSITE REVIEW ORGANIZATION (OSRO) 6-7 FUNCTION.............................................

6-7 COMPOSITION..........................................

6-8 A LT E RN AT E S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6-8 MEETING FREQUENCY....................................

6-8 QU 0 R UM . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

6-8 RESP 0NSIBILITIES..................................... #

6-9 REC 0RDS..............................................

(NSRG)................... 6-9 6.5.2 NUCLEAR SAFETY REVIEW GROUP 6-9 FUNCTION.............................................

6-10 COMPOSITION..........................................

6-10 ALTERNATES...........................................

6-10 CONSULTANTS..........................................

6-10 MEETING FREQUENCY....................................

6-10 QU0 RUM..............................................

xix FERMI - UNIT 2

INDEX ADMINISTRATIVE CONTROLS PAGE SECTION REVIEW............................................. 6-10 AUDITS............................................... 6-11 6-12 u REC 0RDS.............................................. a G.s. 3 fe'tamure- ofcouw s-cwrw p 4 6.6 REPORTABLE EVENT ACTION...................................

6-12I gl 6-13 [

6.7 SAFETY LIMIT VIOLATION....................................

6-13 6' 6.8 PROCEDURES AND PR0 GRAMS...................................

6.9 REPORTING REQUIREMENTS.................................... 6-15 6.9.1 ROUTINE REP 0RTS...................................... 6-15 STARTUP REP 0RT....................................... 6-15 ANNUAL REP 0RTS....................................... 6-15 MONTHLY OPERATING REP 0RTS............................ 6-16 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT...

6-16 SEMIANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT.......

6-17 SPECIAL REP 0RTS...................................... 6-19 6.9.2 ,

6-19 6.10 RECORD RETENTION.........................................

6-20 6.11 RADIATION PROTECTION PR0 GRAM.............................

6-20 6.12 HIGH RADIATION AREA......................................

6-21 6.13 PROCESS CONTROL PR0 GRAM..................................

6-22 s 6.14 0FFSITE DOSE CALCULATION MANUAL.......................... 4 6.15 MAJOR CHANGES TO RADI0 ACTIVE LIQUID. GASEOUS. AND 6-22 ,

SOLID WASTE TREATNENT SYSTENS............................

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I FERMI - UNIT 2 xx

t INDEX

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s LIST OF FIGURES

, FIGURE PAGE 3.1.5-1 SODIUM PENTABORATE VOLUME / CONCENTRATION REQUIREMENTS ................................... 3/4 1-21 3.2.1-1 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VS. AVERAGE PLANAR EXPOSURE, INITIAL CORE FUEL TYPE 8CR183 .................. 3/4 2-2 3.2.1-2 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VS. AVERAGE PLANAR EXPOSURE, INITI AL CORE FUEL TYPE SCR233 . . . . . . . . . . . . . . . . . . 3/4 2-3 3.2.1-3 MAXIMUM AVERAGE PLANAR LINEAR HEAT GENERATION RATE (MAPLHGR) VS. AVERAGE PLANAR EXPOSURE, INITI AL CORE FUEL TYPE SCR071. . . . . . . . . . . . . . . . . . 3/4 2-4 3.2.3-1 MINIMUM CRITICAL POWER RATIO (MCPR) VERSUS t AT RATED FLOW ................................ 3/4 2-8 3.2.3-2 (LOW CORRECTION g (K ) FACTOR .................... 3/4 2-9 g 3.4.1.1-1 3.4.6.1-1 THERMAL POWER VS CORE FLOW ..................... 3/4 4-3 MINIMUM REACTOR PRESSURE VESSEL METAL TEMPERATURE VS. REACTOR VESSEL *RESSURE .................... 3/4 4-21 4.7.5-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST ..... 3/4 7-21 8 3/4 3-1 REACTOR VESSEL WATER LEVEL ...................... B 3/4 37 8 3/4.4.6-1 FAST NEUTRON FLUENCE (E>1MeV) AT 1/4 T AS A FUNCTION OF SERVICE LIFE . . . . . . . . . . . . . . . . . . . . . . . . B 3/4 4-7 8 3/4.,6.2-1 LOCAL POOL TEMPERATURE LIMIT .................... B 3/4 6-5 8 3/4.7.3-1 ARRANGEMENT OF SHORE BARRIER SURVEY POINTS ...... B 3/4 7-6 5.1.1-1 EXCLUSION AREA ................................. 5-2 5.1.2-1 LOW POPULATION ZONE ............................ 5-3 5.1.3-1 MAP DEFINING UNRESTRICTED AREAS AND SITE BOUNDARY FOR RADI0 ACTIVE GASEOUS AND LIQUID EFFLUENTS ...................................... 5-4

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6.0 ADMINISTRATIVE CONTROLS

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6.1 RESPONSIBILITY "

y The M :5:t: PkAMT t t r:nThennAc c " :t:ti:n shall be responsible for overall

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6.1.1 unit operation and shall delegate in writing the succession to this responsibility l' 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 Operations shall be reissued to all station personnel on an annual basis.

6.2 ORGANIZATION OFFSITE 6.2.1 The offsite organization for unit management and technical support shall be as ihn: : "!;;r: 5. 2. '-1. Ma*% 4 (.ppn. a op N f*M(L. ,

UNIT STAFF CEM.msce m 6myran. 0 or % , F 5 AE.

6.2.2 The unit organization shall be as% hun :n figur: 5.2.2-1 and:

a. Each on duty shift shall be composed of at least the minimum shift

- crew composition shown in Table 6.2.2-1;

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

c. A 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 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 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 "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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , in order to accommodate unexpected absence, provided immediate action is taken to fill j the required positions.

FERMI - UNIT 2 6-1 l

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ADMINISTRATIVE CONTROLS )

UNIT STAFF (Continued)

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 ;2pic'N;, auxiliary operators, and key maintenance personnel). gg pan 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- i

- down for refueling, major maintenance, major unit modifications, j ,

on a temporary basis the following guidel es shall be followed:

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1. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ,

straight, excluding shift turnover time.

2. An individual should not be permitted to work more than 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months -

in any 24-hour period, nor more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months in any 48-hour

period, nor more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months in any 7 day period, all excluding shift turnover time.

3. A break of at least 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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. m seg Q,aw .n.me Am W bra.%nc.wunugg.negg %

orued by the h.ncrr manmMar. Any deviation "esia;;nt from

";n.;;r the above m.;h;r guidelines Pr:ictha or 5': t r_shall _ bef;, or higher levels of 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-q viewed monthly by the "..ht;..t "x:;;r " :hrr "r:t:thn or his

a. b m e htr.s m d;;ign;; to assure at excessive hours have not been assigned.

u. w c N . % b e e,jtoutine deviation rom the above guidelines is not authorized.

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i ADMINISTRATIVE CONTROLS )

i 6.2.3 INDEPENDENT SAFETY ENGINEERING GROUP (ISEG)

FUNCTION i

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 much as practical.

AUTHORITY 6.2.3.4 The ISEG shall make detailed recommendations for revised procedures, l())

equipment modifications, maintenance activities, operations activities or

other means of imorovino unit safety to the M c "-- &tmp Vic P.tWer. ;a 6.2.4 SHIFT TECHNICAL ADVISOR j 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 o 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 l

unit design and layout, including the capabilities of instrumentation and controls in the control room.

l j *Not resp'onsible for sign-off function.

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FERMI - UNIT 2 6-6 -

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i ADMINISTRATIVE CONTROLS 4 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifi-cations of ANSI N18.1-1971 for comparable positions, except for the General 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 minimum qualifications of the supplemental requirements specified in Sections A and C of Enclosure 1 of the March 29, 1980 NRC letter to all licensees.

6.4 TRAINING g 6.4.1 A retraining and replacement training prog am for the unit staff shall be maintained under the direction of the Director Nuclear Training, shall meet or exceed the requiremerits 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 &p p\

6.5.1 Onsite Review Organization (OSRO)

FUNCTION PLarrr man %3-6.5.1.1 The OSR0 shall function to advise the A;;i;t:nt M:n:;i:r- S ci::r "c;i;ti:n on all matters related to nuclear safetyAt Ocw.mgco z.n Spcovscnion COMPOSITION O'b'O 6.5.1.2 The OSRO shall be composed of the:

Chairman A;;iet; .t M;n:;;;r-5:!::r "-^&ctica PLany hnagst, Vice-Chairman Superintendent L uleer Operations Vice-Chairman Superintendent-Maintenance and Modification

'. Member Operations Engineer -

Member Technical Engineer Member Maintenance Engineer Member Radiation Protection-Chemical Engineer Member Supervisor Operational Assurance Member Reactor Engineer FERMI - UNIT 2 6-7

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ADMINISTRATIVE CONTROLS y ALTERNATES 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 OSRO 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 OSRO Chairman or 'f e de:f; :t:d :Meenek

a. vicei couremu QUORUM

_6.5.1.5 The quorum of the OSRO necessary for the performance of the OSRO

responsibility and authority provisions of these Technical Specifications shall consist of the Chairman or 5.i: d= f :=ted :lt:rn:te and four members including i g t: tr: alternates. % " * "' "S*n RESPONSIBILITIES ,

6.5.1.6 The OSRO shall be responsible for: I ra. "=':r :" ('.) :" ;r:::d: = =;;'r:d by 5;;;f'ic:ti:n S.S : d th r ;n th: = t:, (2) :!! pr:; n:: nz i n d by S;;;f't::ti:n*k---+a 5.9 :nd ch= ;= th: = te, :.d (?) ry Other ; ecr e ee" e- c'e ;e= se [w )

t m n d by tha A:: hts t " =;;r " d u r . a d = ti= t: :ff::t

-"c're !!'e*y: j

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

c. Review of all proposed changes to Appendix A Technical Specifications; 3

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

g. Investigation of all violations of the Technical Specifications,

, including the preparation and forwarding of reports covering evaluation -

andrecommendationstopreventrecurrence,tothe.".;m\;;r-Nuclear Operations and to the Nuclear Safety Review Group; wur. MnecnT

$ f. Review of all REPORTABLE EVENTS; l h g. Review of unit operations to detect potential hazards to nuclear safety; j i. )(. Performance of special reviews, investigations, "

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

'-t A::\xt Pi .;x;n "Ghz nd=th or the am Mages, j f. Review of the Security Plan = d t ; h n at h; ; n n dun:; ,

K f. Review of the Emergency Plan = d 5; h: = t h; prece t ree; x I

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FERMI - UNIT 2 6-8 l _ . , _ . . _ , , - _ , _ , _ _ , _ . , _ , , - . . . . . - _ . , _ _ , . . . , _ _ _ , , _ . . , _ . . , . _ - , _ _ _ . , _ . . _ _ _ _ _ . . _ _

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h ADMINISTRATIVE CONTROLS RESPONSIBILITIES (Continued) onsive nu:-%c er inmounu ,d h__

!X.,ReviewofthIcident: 1, ur. planned I er an ;r.trolud radioactive r:h:::

F enydtens _ , including the preparation and forwarding of reports covering evaluation, recommendations and disposition of the corrective action to prevent recurrence to the Vice President-Nuclear Operations and to the Nuclear Safety Review Group; and m J. Review of changes to the PROCESS CONTROL PROGRAM,and the OFFSITE

_ DOSE CALCULATION MANUAL,, ano maiot moordarb% T. wc Raowavre

.. e m errr swrems.

6.5.1.7 The OSRO shall: ,

a. Recommend in writing to the- Assister.t Nn;;;r ch:r PrWtien approval or disapproval of items considered under Specifica-tion 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. throughj . constitutes an unreviewed w.c safety question.

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c. Provide written notification within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to the Mew ger- leer l Operations and the Nuclear Safety Review Group of disagreement between the OSRO and thepshtent ".:n;;;r-N:h;r Preducthn; however, the es .;ger N ;,c - Preduction shall have responsibility for resolution W ursuant to Specification 6.1.1.

RECORDS 6.5.1.8 The OSRO shall maintain written minutes of each OSR0 meeting that, at a mi'nimum, document the results of all OSRO activities performed under the responsibility provisions of these Technical Specifications. Copies shall be provided to the -Nuclear Operations and the Nuclear Safety Review '

Group. h % cnt

(' 6.5.2 NUCLEAR SAFETY REVIEW GROUP (NSRG)

FUNCTION s'

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, l b. Nuclear engineering,

c. Chemistry and radiochemistry,

d. Metallurgy,

e. Instrumentation and control,

f. Radiologicai ;;fety, c.onynog

g. Mechanical and electrical engineering, and l h. Quality assurance practices.

Gacup The NSRG shall report to and advise the*Vice President-Scher Operatient on l

( those areas of responsibility in Specifications 6.5.2.7 and 6.5.2.0.

FERMI - UNIT 2 6-9 y . . _ _ _ . _ . . . _ . _ . _ _ _

F u_____ _ _ _ _ _ _ _ . . _ _ . _ _ _ _ . . _ _ _ _ _ _ _ . , _ . _ . _ , , _ _ _ _ , . . _ _ _ _ _ . _

~ . . _ _ _. _ _ _ _

ADMINISTRATIVE CONTROLS ;

COMPOSITION ,

> 6.5.2.2 The Vice/ President L. clear Oi;ereth;n shall appoint at least nine l 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 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 problens. All 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 utilized as 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 p

review and audit functions of these Technical Specifications shall consist of ji the Chairman or his designated alternate and at least one half of the remain-

! 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 review 6.5.2.7.b through i:

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

b. Proposed changes to procedures, equipment, or systems which involve an unreviewed safety question as defined in 10 CFR 50.59;

)

FERMI - UNIT 2 6-10 i , . - := . .. - - - _ - -

ADMINISTPATIVE CDN1MLS 6.5.3 . TIXIINICAL RWIN AND CONIML ACPIVITIES 6.5.3.1 Procedures required by Technical Specification 6.8, and other procedures which affect plant nuclear safety as &termined by the Plant Manager, and danges thereto, shall be prepred by a qualified individual / organization.

REVIN 6.5.3.2 Each procedure or procedure change preparal in accordance with 6.5.3.1 above and not reviewed in accordance with Section 6.5.1.C shall be reviewed for technical adequacy by a qualified individual other than the individual that gepred the procedure or change thereto. Each sud review shall include a determination of whether or not additional, cross-disciplinary review is necessary.

, If desned necessary, su& review (s) shall be performed by personnel of the appropriate discipline.

6.5.3.3 Each procedure required by Specification 6.8.l(h) through (j), or danges thereto, shall be reviewed by the General Supervisor-Health Physics or designated alternate. %e Environnental Program (bordinator will review any danges pertaining to 6.8.l(j) .

%ese reviews may be performed in lieu of, or in addition to, those required by item 6.5.3.2 above.

SAFE'IY EVALIATIONS 6.5.3.4 When required by 10 CFR 59.59, a safety evaluation to determine whether or not an unreviewed safety question is involved shall be included in the review. Pursuant to 10CFR50.59, NIC approval of items involving unreviewed safety questions shall be obtained prior to approval of the procedure or procedure change.

00ALIFICATIWS 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 4.3 or 4.4 of ANSI N18.1-1971 for the appropriate discipline, and shall be members of the plant staff previously designated in writing by the Plant Manager.

REODRDS 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 preparal and maintained.

)

ADMINISTRATIVE CONTROLS I l

AUDITS (Continued)

g. Any other area of unit operation considered appropriate by the NSRG or theyVice President N.;ie.c Op;c;ti;n;;

Gimp

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 e President-Mu;l;;r 0;;r;ti;r.: within 14 days

( h following each meet Group ,

b. Reports of reviews encompassed by Sp fication 6.5.2.7 shall be prepared, approved, and forwarded to the ice President N. l...

Oe:ceti;;; within 14 days following comp 1,etion of the review.

c. Audit reports encompassed by Specification 6.5.2.8 shall be forwarded to theoVice President N;;?:;r 0;:r:t'rn: and to the management positi ons responsible for the areas audited within Av?O Inhener 30 days af ter con pletion of the audit by the auditing organization.

le.0 % y -Onn u p 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 of this review shall be submitted to the NSRG and the ";c.;;;r-Nuclear Operations, g

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FERMI - UNIT 2 6-12

. . ADMINISTRATIVE CONTROLS 6.7 SAFETY LIMIT VIOLATION 6.7.1 The following actions shall be taken in the event a Safety Limit is 3- violated:

- a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months . The " c.;;;r- clear l Operations and the NSRG shall be notified within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . q's hscseceiT l

b. A Safety Limit Violation Report shall be prepared. The report shall be reviewed 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 NSRG, and the " c.;;;;-Nuclear Operations within 14 days of the violation. N gg g iggwy

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

6.8 PROCEDURES.AND PROGRAMS i

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

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

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

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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.

i. OFFSITE DOSE CALCULATION MANUAL implementation.

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

FERMI - UNIT 2 6-13

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1 ADMINISTRATIVE CONTROLS )

PROCEDURES AND PROGRAMS (Continued)

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DW 6 @ ~.C. prF adure of Specification 6.8.1, and changes ths ant Manager-Nuclear

v. epproved.by-t roduction prior by the lesentatT6h~ and reviewed per16dits11y :: ==t forth in Leviewed inistra ve-proceduces. OSRO and sfFali 6.8.fTemporarychangestoproceduresofSpecification6.8.1maybemade provided:

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

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 he_DSRn. =4 eppr:=d by-the 9 ine on nv e is du m ted,_rayiewed b ~

~l I.nu ex L.B 4. c. Assistant E.ge. hitar PF5Hiicii tliih 14 days vi kplementation.

6.8.$' The following programs shall be established, implemented, and maintained:

s. 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 rod drive discharge headers, and standby gas treatment "

systems. The program shall include the following:

1. Preventive maintenance and periodic visual inspection requirements, and

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

i' b. In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine i'

the airborne iodine concentration in vital areas under accident conditions. This program shall include the following:

1. Training of personnel,

2. Procedures for monitoring, and

3. Provisions for maintenance of sampling and analysis equipment.

c. Post-accident Sampling

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.

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

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6.8.2 Each plant adninistrative procedure, and dianges thereto, shall be reviewed in accordance with Specifimtion 6.5.1.6, and approved by the Plant Manager prior to implementation, and shall be reviewed periodically thereafter as set forth in adninistrative procedures.

6.8.3 Each plant procedure required by Specific .icn 6.8.1, other than adninistrative procedures, and dianges thereto, shall be reviewed in accordance with 6.5.3, and approved by the Plant Manager prior to implenentation and shall be reviewed periodically thereafter as set forth in adninistrative procedures. 'Ihe Plant Manager may delegate approval authority in writing for specific types of procedures to the Superintendent-Operations, the Superintendent-Maintenance and Modification, the Superintendent-Services, or the Radiation Protection-Olenical Engineer. .

(6.8.4)

c. The change is documented, and reviewed and approved in accordance with either 6.8.2 or 6.8.3 above, as approgiate, within 14 days of inplementation.

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ML20207L039

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