ML20078R731

Proposed Tech Specs Section 6.0, Administrative Controls

ML20078R731
Person / Time
Site:	Fermi
Issue date:	12/15/1994
From:	DETROIT EDISON CO.
To:
Shared Package
ML20078R718	List: ML20078R731 NRC-94-0107, Application for Amend to License NPF-43,proposing Changes to Administrative Controls Section of Ts,Consistent W/Guidance in NUREG-1433 & GL 93-07, Mod of Ts...For Emergency & Security Plans
References
NUDOCS 9412270183
Download: ML20078R731 (62)

Text

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ATTACIIMENT 2 PROIOSFE TECIINICAL SPECIFICATION CIIANGES i

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ADMINISTRATIVE CONTROLS EGIl0N f.aK 6.1 RESPONSIBILITY...........................................

6-F 6.2 ORGANIZATION.............................................

6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS..................

6-1 l

6.2.2 UNIT STAFF......................_..................

6-1 92LETED INDEPEn..__.._

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6-6 6.2.3 vi.n i w r. i i

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6-6 60MPo nT40 6.....................................

6-6

-RES PON S I B I L-!T1 ES*..................................

6-6 6-6 UTHORIYv-6.2.4 SHIFT TECHNICAL ADVIS0R...........................

6-6

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C0HPOSiH ONc......................................

6-10

--ALT ERNAT ES........................................

6-10

-C0NSUET AN TS.......................................

6-10 MEETING-fREQ"""0W................................

6-10 6-10 4tGGiuin...........................................g FERMI - UNIT 2 xix Amendment No. 82

IlE.G ADMINISTRATIVE CONTROLS 9

SECTION E&E

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DELE cRtVitW...........TGD 6-10 AW9tTS;.............................................

6-11 AG66R06:............................................

6-12 6.5.3 n61acw anu-sunTROL........................

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6-13 RE90R95............................................j 6-13 6.6 REPORTABLE EVENT ACTI0N....................................

6-13 1

6.7 SAFETY LIMIT VIOLAT10N.....................................

6-14 6.8 PROCEDUP,ES AND PR0 GRAMS....................................

6-14 l

1,.1 REPORTING RE0VIREMENTS.....................................

6-16b

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l 6.9.1 ROUTINE REP 0RTS.....................................

6-16b STARTUP REP 0RT......................................

6-16b ANNUAL REP 0RTS......................................

6-17 MONTHLY OPERATING REP 0RTS...........................

6-18 i

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT., 6-18 ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT......

6-18 l

6.9.2 SPECIAL REP 0RTS.....................................

6-21 6.9.3 C036OPERATINGLIMITSREP0RT........................

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6.14 0FFSITE DOSE CALCULATION MANUAL.......................... 6-24 FERMI - UNIT 2 xx AmendmentNo.JJ.Jf.77,91

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t nrr1miTinut TREQUENCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of Surveilleace Requirements shall correspond to the intervals defined in Table '..l.

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IDENTIFIED LEAKAGE i

1.15 3DENTIFIED LEAKAGE shall be:

5 l

a.

Leakage into collection systems, such as pump seal or valve packing i

leaks, that is captured and conducted to a sump or collecting tank, or.

i b.

Leakage into the containment atmos >here from sources that are both specifically located and known ettser not to interfere with the operation of the leakage detection systems or not to be PRESSURE BOUNDARY LEAKAGE.

ISOLAT10N SYSTEM RESPONSE TIME i

1.16 The ISOLATION SYSTEM RESPONSE TIME shall be that time interval from I

when the monitored parameter exceeds its isolation actuation setpoint I

at the channel sensor untti the isolation valves travel to their recuired positions. Times shall include diesel generator starting i

anc sequence loading delays where applicable. The response time may be measured by any series of sequential, overlapping or total steps j

such that the entire response time is measured.

LIMITING CONTROL ROD PATTERN l

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l.17 A LIMITING CONTROL ROD PATTERN shall be a pattern which results in the core being on a thermal hydraulic limit, i.e., operating on a l.

limiting value for APLHGR, LHGR, or MCPR.

1 LINEAR HEAT" GENERATION RATE l

1.18 LINEAR HEAT GENERATION RATE (LHGR) shall be the heat generation per unit length of fuel rod. It is the integral of the heat flux over the heat transfer area associated with the unit length.

LOGIC SYSTEM FUNCTIONAL TEST 3.19 A LOGIC SYSTEM FUNCTIONAL TEST shall be a test of all logic components, i.e., all relays and contacts, all trip units, solid state logic elements, etc., of a logic circuit, from sensor through and including the actuated device, to verify OPERABILITY. The LOGIC.

SYSTEM FUNCTIONAL TEST may be performed by any series of sequential, overlapping or total system steps such that the entire logic system is tested.

MAXIMUM FRACTION OF LIMITING POWER DENSITY 1.20 The MAXIMUM FRACTION OF LIMITING POWER DENSITY (MFLPD) shall be the highest value of the FLPD which exists in the core.

NEMBER($) 0F THE PUBLlg 1.21 MEMBER (S) 0F THE PUBLIC shall be an individual in a controlled or UNRESTRICTED AREA. However, an individual is not a MEMBER OF THE PUBLIC during any period in which the individual receives an

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occupational dose.

FERMI - UNIT 2 1-3 Amendment No. g3

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DEFIN1TIONS MINIMUM CRITICAL POWER RATIO 1.22 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be the smallest CPR which exists

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in the core.

0FF-GAS TREATMENT SYSTEM 1.23 An 0FF-GAS TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting reactor coolant system offgases from the reactor coolant and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

0FFSITE DOSE CALCULATION MANUAL 1.24 The OFFSITE DOSE CALCULATION MANUAL (00CM) shall contain the methodology and.

parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, tr. the calculation of gaseous and liquid effluent monitoring Alars/ Trip Setpoints, and in the conduct of the Radiolcgical Environmental Monitoring Program. The 00CM sh01 also contain (1) the Radioactive Effluent Controls # and Radiolo Monitoring Programs deoutred by section 6.8.S/ and (2) giv En. 'ranmental descripti m of the information that s 1d be included in the Annual RadioWical En Wretal l

Operating an nual Radioactive Effluent Release Rep %',s r weire: by Specifications 1.7 and 6.9.1.8.

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OPERABLE - OPERABILITY 1.25 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of perform %g its specified function (s) and when all necessary attendant instrumentation, controls, electrical power.

cooling or seal water, lubrication or other auxiliary equipment that-are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

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OPERATIONAL CONDITIDN - CONDITION 1.26 An OPERATIONAL CONDITION, i.e., CONDIi!ON, r, hall be any one inclusive combination of mode switch position and average reactor coolant temperature

.as specified in Table 1.2.

PHYSICS TESTS 1.27 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 14 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

PRESSURE BOUNDARY LEAKAGE 1.28 PRESSURE BOUNDARY LEAKAGE shall be leakage through a nonisolable fault in a reactor coolant system component body, pipe wall, or vessel wall.

Eg1 MARY CONTAINMENT INTEGRITY 1.29 PRIMARY CONTAINMENT INTEGRITY shall exist when:

a.

All primary containment penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an OPERABLE primary containment autcmatic isolation system, or

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FERMI - UNIT 2 1-4 Amendment No. 82

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Na Change to'tMspage.

Pwridedf:r W:nnaden only.

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~ PLANT SYSTEMS'

Q SURVEILLANCE REQUIREMENTS (Continued) j pictted using an " Accept" line which follows the equation N = 55(1 + C/2).

Each snubber point should be plotted as soon as the snubber is tested.

If the point plotted falls on or below the " Accept" line, testing of that type of snubber may be terminated.

If the point plotted falls above the " Accept" line, testing must continue until the point falls in the

" Accept" region or all the snubbers of that type have been

. test.ed.

l The representative sample selected for the functional test sample plans shall be randomly selected from the snubbers of each type and reviewed before beginning the testing. The review shall' ensure as far as practical that they are repre-sentative of the various configurations, operating environments, i

range of size, and capacity of snubbers of each type. Snubbers placed in the same locations as snubbers which failed the previous functional test shall be ratested at the time of the-next functional test but shall not be included in the sample plan.

If during the functional testing, additional sampling is required due to failure of only one type of snubber, the func-tional testing results shall be reviewed at the time to deter-mine if additional samples should be limited to the type of snubber which has failed the functional testing.

i f.

Functional Test Acceptance Criteria The snubber functional test shall verify that:

1)

Activation (restraining action) is a:.hieved within the specified range in both tension and compression; i

2)

Snubber bleed, or release rate where required, is present 3

in both tension and compression, within the specified

range, i

3)

For mechanical snubbers, the force required to initiate or maintain motion of the snubber is within the specified range l

in both directions of travel; and 4)

For snubbers specifically required not to displace under continuous load, the ability of the snubber to withstand i

i load without displacement.

Testing methods may be used to measure parameters indirectly or parameters other than those specified if those results can be correlated to the specified parameters through established methods.

4

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FERMI - UNIT 2 3/4 7-19

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

)

I g.

Functional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers irrespective of type which may be subject to the same failure mode.

For the snubbers found inoperable, an engineering evaluation shall be performed on the components to which the inoperable snubbers are attached. The purpose of this engineering evalu-ation shall be to determine if the components to which the inoperable snubbers are attt t d were adversely affected by the inoperability of the snubbers in order to ensure that the i

component remains capable of meeting the designed service.

If any snubber selected for functional testing either fails to lock up or fails to move, i.e., frozen-in place, the cause will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same type subject to the same defect shall be functionally tested. This testing requirement shall be inde-pendent of the requirements stated in Specification 4.7.fe.

for snubbers not meeting the functional test acceptance criteria.

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h.

Functional Testina of Repaired and Replaced Snubbers Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacsment snubbers and snubbers which have repairs which might affect the functional test result shall be tested to meet the functional test criteria before installation in the unit. Mechanical snubbers shall have met the acceptance criteria subsequent to their most recent service, and the freedom-of-motion test must have been performed within 12 months before being installed in t

l the unit.

1.

Snubber Seal Replacement Program The service life of hydraulic and mechanical snubbers shall be monitored to enaure that the service life is not exceeded between surveillance inspections. The ma::imum expected service life for various seals, springs, and other critical parts shall be determined and established based on engineering information and shall be extended or shortened based on monitored test results and failure history. Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replace-mentsshall.bedocumentedandthedocumentationshallbereta g e w m,,s w e; g ; g m n w g re g

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FERMI - UNIT 2 3/4 7-20 l

1 NJ Change to thispage.

ProvidedforIr@mation cnly.

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SECTION 6.0 ADMINISTRATIVE CONTROLS J

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84 4

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ProvidedforhVonnation only.

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ADMINISTRATIVE CONTROLS 6.1 RESP 0NSIBILITY The Plant Manager

• shall be responsible for overall unit safe operation l

6.1.1 and shall dele ate in writing the succession to this responsibility during his l

absence. The lant Manager shall have control over those onsite activities necessary for safe operation and maintenance of the plant..

6.3.2 The Nuclear Shift Supervisor or, during his absence from the control room, a designated individual shall be responsible for the control roon A management directive to this effect, signed by the Senior command function.

Vice President. Nuclear Generation

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

6.2 ORGANf7ATf0N 6.2.1 0FFSITE AND ONSITE ORGAN 17ATIONS Onsite and offsite organizations shall be established for unit operation and The onsite and offsite organintions corporate management, respe...Waly.

shall include the positions.*or activities affecting the safety of the nuclear power plant. Lines of authority, responsibility, and communication shall be

(

a.

established and defined for the highest management levels through

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intermediate levels to and including all operating organization These relationships shall be documented and updated.

positions.

as appropriale, in the form of organization charts, functional descriptions of departmental responsibilities and relationshi s, i

7 and job descriptions for key personnel positions, or in equiv lent forms of documentation. These requirements shall be documented in i

the Updated Final Safety Analysis Report.

I The Senior Vice Pr.esident - Nuclear Generation shall have l

corporate responsibility for overall plant nuclear safety and

-l b.

l shall take any measures needed to ensure acceptable performance of l

the staff in operating, maintaining, and providing technical support of the plant to ensure nuclear safety.

The individuals who train the operating staff and those who carry l

c.

out health physics and quality assurance functions may report to l

the appropriate onsite manager; however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

cy.

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• An alternative title may be designated for this position. All requirements of these Technical Specifications apply to the position with the alternative title as apply with the specified title. Alternative titles shall be specified in the Updated Final Safety Analysis R'eport.

i 6-1 Amendment No. II JJ, JJ. #1 101 FERMI - UNIT 2

I ADMINISTRATIVE CONTROI5 6.2.2 UNIT STAFF Each on duty shift shall be composed of at least the minimum shift a.

crew composition shown in Table 6.2.2-1; At least one licensed Operator shall be in the control room when b.

fuel is in the reactor. In addition, while the unit is in 0PERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior j

Operator shall be in the control room, i

J A Radiation Protection Technician

• shall be on site when fuel is in c.

the reactor. The Radiation Protection Technician position may be unfilled for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to accommodate unexpected absence, provided imediate action is taken to fill the required positions 1

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.

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Admini e

oce es s 11 be ele and lemented to limi t or ng urs o nit s f

perf safety-related Knc s

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icon Seni Ope

ors, consed Operators, h

p si perso el, a iar opera rs, and ke aintenance so 1

h qu; e shi cover e sh be ntained1 out to e heavy seg ov, ime, eo etive all be aave th ersonnel work l ajfomt f 40-h r we while e unit operati However, in the prob as requi substa a amounts of f

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d. or dG) ring ex even hatynfores ded pe s of shutdo r

overtime 10 be

, refuel)fi,g, ma main, nance, major u i modificati on a temporaryb is th allowin guidelin shall be fo hfwed:

al shou)d not be reitted to e ce tbafi l

1.

A ndi.straig, excludt shift tu er tist. /

ho 2.

A divid should be pers ited to wo e than an 24 hoyrt'in any I hours n any 24-ur period or more 48-hou period, n morethg72 hours any 7 day period.,

all e ciuding ft turnov(r time.

4&*:

• An alternative title may be designated for this position. All requirements of these Technical Specifications apply to the position with the alternative title as apply with the specified title. Alternative. titles shall be specified in the Updated Final Safety Analysis Report.

6-2 Amendment No. )(, $2.101 FERMI - UN]T 2 r -.

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ADMINISTRATIVE CONTROL 5 UNIT STAFF (Continued) bydk at 1 t8 ur oul a,16Iwedbetweenwork peft

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the above gui eline is not auth 12e.

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The Operations Engineer, Nuclear Shift Supervisor, and Nuclear Assistant Shift Suprvisor shall hold a Senior Reactor Operator license. The Nuclear Supervising Operator shall hold a Reactor Operator or Senior Reactor Operator license.

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FERMI - UNIT 2 6-Za Amendment No. H.101

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FERMI - UNIT 2 6-3 Amendment No. 30 1,-

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TABL,E 6.2.2-1 1

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HINIMUK SHIFT CREW COP. POSITION POSITION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION l

' CONDITION 1, 2, or 3 CONDITION 4 or 5 NSS 1

1 NASS 1

None NS0' 2

1 NPP0/NAPP0 2

1 STA 1

None j

TABLE NOTATION Nuclear Shift Supervisor with a Senior Operator license NSS NASS -

Nuclear Assistant Shift Supervisor with a Senior Operator license j

Nuclear Supervising Operator with an Operator license NSO

'NPP0/NAPP0 - Nuclear Power Plant Operator or Nuclear Assistant Power Plant

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STA Operator l

Shift Technical Advisor 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 acconsnodate 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' provision does not permit any shift crew position to be unmanned upon shift 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 1, 2 or 3, an individual (other than the Shift 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 CONDITI0n 4 or S an individual with a valid Senior Operator license or Operator license shall be designated to assume the control room command function.

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TERMI - UNIT 2 6-5 J

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A0"b;1STRATIVECONTROLS 3]

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DELETED 6.2.3 / INOJPtNDERT/S AFETV -EtlG11&EERINGIROFf5SEG )

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on t[exa idunit o ng ch3r(cteri c[

issuarleb,5 G shall Th 1 indus.tr dyi nsee Even rtynnd ot,h3 urces plapt' design and'operatin,sef'ies, L N

g exp ence info

'lon a(udin Mnts of I

simi)c: desigr)/which y indi e areas fo mprov unit s ty.

,, COMPOSITION

/

The ISEG sh' 11 be composed of a least fi dedicated,fpt-time 6.2.3'.2 engineersdocated'onsite, e3cti with Vlischelor'ydegree in en rience in hjs / -

Mering or

" related' science' and at least two yefrs professional level field', at,1eist one yeaf of whjch experience'shall be in t e nuclear fierd.

Sp0NSIBILITIES

/

/

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l 6f2.3.3 The ISEG sha'11 be respof(Ible for majntaining survef11ance of urtit

'activitie's to provide independent verification

• that these' activities a(e perforined correctly and that4uman errors'~are reduced as much as pre k

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AUTHORITY' 6.2.3'.4 The ISEG s' hall make Ntailed recoigmendations f revised,p'roceduyes,

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i equipment trodific'ations, mair. enance actjdties, oper34 ons actWities orsafety gnd Services,of improviny6 nit other means 6.2.4 SHIFT TECHNICAL ADi SOR 6.2.4.1 The Shift Teche cal Advisor shall provide advisory technical support

• 'f to the Nuclear Shif t St :rvisor in the areas of thermal hydraulics, reactor engineering, and plar* analysis with regard to safe operation of the unit.

The Shift Technical

• wisor shall have a bachelor's degree or equivalent in a I

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 controls in the control room.

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• Notrreislpon s ib~liii;f eresign%iCiviidi on.

FERMI - UNIT 2 6-6 Amendment No. II, 86. 54 i

ADMINISTRATIVE CONTROLS 6.3 MS"*? S"eM"=R;G J)gLe,. JEp 1

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c ( es, Mh N w-6.4 @ M 5 gyg eak a n r

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he Nu of Section 5 of JW31 N18,1 97 R Pact'55 and the sppfilementaPrequire!pents spe s anddecome on e

d ar ire f

App ix f1 ees f

dt_,,fatniliaritation With releva)nt industfy operational (xperfe of Epflosurfd of the March Se ion an Land sh ljn 3

6.5, b Z WJ01T D6L ETED

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1' ONSIT REdEW N17(T10N(0SRO)

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NCT 6.5.}d T OSR hall f etion advis e Plant nager on matter rela'ted t nue ar saf

,as d cribed Specift ion 6.5.1 g

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Th_e,0 RO c rman 1 be th lantManap and the ember ip shal e

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sed ova minim)um of ut not e than 11 lant mana ent r resenta ves se rJH5onsifflitie lude th unctional as of: o ratio, maint ance, com fadi4 tion pr,stectio gineer.1

/ technical pport and unlity ssuran All w

ointed i OSRO Chyttman.

e qual ications r'shall meet /n writing by J membfers s'il be y r exceed ts and commen tions of 4.3 of AN l'N18.1-1971.)he requirem p(ch 0 mem

/Secti 4.2 At NAT 6.

The Ch man may desfgnate in ting other embers who may erve as Vi e Chairma f the OSRO,/ Alternate ay be desi atedf6rspecif 0$RO

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ipate as votingonembers' in OSRO more than two alternate shall part M

rs shall be appointed in dritin'g members.

All 3 ernate mem at any one, time.

activiti$ROChairman.

y the E

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,pefibn.

A Pt rementbef '

Abtect[ atty 4tT1[nisyr,bsQ ig iMtit IA i n vith,t W }alternettp title as,

Tech JyecJfidtions gW So th titles pa-bt_specif A th g A i

y th pet %ed tJtif Alt

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Up ed Final afety Anatysis Repor s

s Amendment No. JJ, 77. JJ 6-7 FERMI - UNIT 2 101

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ADMINISTRATIVE CONTROLS

)

NG ENCY alendar month and as convened by i

6

.4 The 05 shall meet at ast once pe e 05R0 Cha an or a Vice iman.

985 6

.1.5 The quor of the 05 ocessary for th rfomance of the 0$R0 esponsibility d authorit revisions of th schnical Specifications shall consist of Chaiman o ice Chairman a our members including alternates.

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1 RESPONS18'It1 TIES 6

6 The 05 shall be resp ible for:

Re kiw of all Pla Administrative cedures and ges thereto; l

a.

b.

eview of al proposed tests experiments t affect nucle w

all proposed nges to Appe A Technical ifications; Revie/p d.

Rev4w of all prop ed changes or difications t it systems or r

uipment that ect nuclear ety; e.

Review of safety eval ions for plany rocedures and ch thereto

~

completed under the 'r, sions of 20 C B0.59; p

r

/

violations e Technical 5 fications, inc ding

..~

4 In(vestigation of gecomendation[and forwardingto pre f.

e preparation reports cover]

~ evaluation and t-I NuclearGep6ationandto ffe Nuclear Saf,tf Review Group; V

,1

[

all REPORT E EVENTS; g.

Revi j h.

Review of unit

~ rations to dp ct potential hgz

to nucleardifety; erfomanc34f special rp

, investigati or analyse and reports Group [/gs requested by the Plant Manage /6r the N i

thereon J

~

j.

w of the curity Plan; k.

Review of e Emergency Plan.

R;:

l t

.)

58 Amendment No. JJ. M.101 FERN! - UNIT 2

.- - ~

(.

$a@M3 Rev o

ery u lanh nsite re ease of radioactive terfiltothe.

vi clu the preparaj.te nd fotyarding of ts coverjng' comendations,4fid dispos rrective 3ction to. -

currence tcJWSenior VJoe'ition of t eyaluation Preside Nuclear G ration and' prevent-tc)he' Nuclear tf Review G,roup; and r

m.

Review of chehges to thpM0 CESS CQN OL PROG he 0FF T 003E CALCULAJION MANUAL, ad ma,jor a 1Yication the Ra te Treatment Systems.

/

n. / Review of he Fire Prote tion Program.

i

~

/

/

6<5,.1.7 TheA RO shall;/

/

/

Recommend in writin,g to the Pjant Manager approval or disappre al of items a.

considered under Specification 6.5.1.6a. th ugfi d. pr or'to their implementation!

\\

/

7eview Gro th b,l Render determin3ti ns in writing,to" he NucJear Saf.V t

/

regarll to whether or not each, item considered under.,,Secific n

an unfaviewed safety qu s on.

ttfrough f. conspthtes/

- / roy.1.6a 6'5

/

/

t e written nptificationytthin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to the enior Vice

(

P of l

/c.

disagreement 4etween the'tSRO and the Plapt 14anager;y R resident - Nyclear Generation and the NuclearAafet howev he Plant Manager,fstiall have refponsibility for Tolution of such isagreements p- /.-

pur s'nt to Speciffcation 6.1.1.

/

RECORDS 0 shall maintain 4,ritten minufte of each OSRO meeting that,,at a The 0 6). 4.8 ity provisions of these Tochtiical Specifit, performed under ent the resujts'of all OSRO, activities Aninimum, do l

ations. Copies shall be-

/responsi provi to the Senior"Vice Pres,jden't - Nuclear 4eneration and*the Nuclear Safety Re Group. f '

/-

g/

^

/

NUCLEb SAFETY Jtt W GROUP (NsRG)

.S.2 fUNCT10N

/

/

/

/

./,

/

The"HSRG shalbfu/

/

/

nction to, provide f

7 nated activitjes*in the areas'of: j/jndependent r/evisiand aud "6.5.2.1 t

f f'

desig/ Nuclenopower plant, operations,

,s s.

/

b' Nuclear engineer,ing,

/

1. c,./ Metallurgy /. Chemistry and, radiochemistry, /,

/.

d.

/

/

/

/

l J.c'

.e' Instrumentation and control,

/

/

Radio 1' gical,cointrols,

/

/

/

iihanicapand electrical gineering, and /

/

/

0-f.

o Quali Assurance prac es.

j

f I

The NSRG shall report to advise the Senior Vic'e President -

clear

/ /

(Generation on those areas of responsibility in Specifications 6 6g Amendment No. JI, Jp, $J. $7 FERMI - UNIT 2 101

- ~ ~ ~ ~

ADMIN 15TRATIVE CONTROLS COMP 051 TIM dent - Nuc M ane ifn'shalla t at 1past nine

]

6.5.2.

e Seni ice P memb s to th RG an all design rom _thi mbership airman 8 at least o

Vice irman.

The memb.

p sh ycollectivej possess perience and ompete to vide ind ent w and a dK in th reas listed in f a Chairna all hay clear background in an and)be capabl Secti 6.5.2 The Ch ir deterni when to call in experts e

eart operati n nd s assi the MSRG view o lex pro s.

All ers shall have ata)efst a bache r's degr in engi ering or ated se ces or at least Xyears of nsible poder plant 4xperience which nimum of 3 years > hat 1 be nuclear ave at least 10 y,eefs of professional res r plagvexpertenes. The citatruan shal is1d and each of tffe other members shall ifthe pow ye dgement Afperience)lativeyrofes sional level ferienceinoneor H of evel least Fyears of sumu have the telds M,sted in Sociton 6.5 2 'I.

ALTERNA rna members shall inted in r4 ng by the HSRG Chairta o

serve oWT,1tempoyafy) basis; howeyer), no me,re thp t o alternates sh 6.

.3 A1 e

as voting me.efs in NSRG activities at pay ont time.

C b UlitJfT

/

Consul ad shall be uti d as determined 4 e NSRG Chairman to provide g '~

6..

ek art advica;t the NSR /

MEETIN UENCY [

6 5 The NSR shall meet at e st once per 6 months

~

/

000RUti,

~

,/

2.6 The quorum of the NSRG nece.ssary for the performance of the.NSRG' rev 6.5'./

audit functions *6f these Technical

• Specifications shall consist'of the Chairman or i

his design 3 tad alternate and,at1 east one half of the remairfihg NSRG members r

two may-be alternates.pW5 more than a minority #of"the quorum shall have line responsibility for operation of the unit.

/

RtY EV 6.5.2.7/ihe MSRG shall be rpsp6nsible for the review 1ff 6.5.2.7.a and shall review 6.5,2.7.h through i pment, facilities The safety evaluations for (IVehanges to procedures or systems and (2) tests-or' experiments completed.,urder the provision a.

ifghat such actions did no coffstitute an untytowed'iafety j/,CFR 50.5g to ver question;

/

gcc Proposed changes to procedures, equipment, o[r sTstems which involve

' b.

4 unreviewed safety question as defined in 10 CF 50.5g;

}

6-10 AmendmentNo.JJ,JJ,Jf.JJ 1

~

FERMI - WIT 2 101

(

ADMINISTRATIVE CONTROLS s

RkVIEw M tinu c.

omosed ts or ex iments whi nvolve an reviewed safety

~

cuesti as defi in 10 CFR

. 9; i

d.

posed c ges.to Tec al Specifi ions or this nating License-e.

Vi ations of es, regula s, orders, Jac%nical Specifications, Aicense re ements, orj internal prpc'edures or instructJerfs having n ear safetyjfgnificance:

f.

Si icant ope tdgabnorm es or deviati # Nom normal and a eted perf r nce of ur quipment that,af act nuclear safety;,

I All REPO TABLE EVE I

/y

/

h.

All cogni23p " ndications of aff unanticipated deJJc'iency in some J

f that cou15 af fect nucleaf',$oh of structures,,sydems, or components s ect of j esign or operatsafety; and i

A and meeti,n utes of the,,0 0.

(

AUDITS g

E.,5 8 Audi ts,.

unitactivjtiesshallbeper refd under the cognizance,,of -

Tpefse audits s,hp1 encompass:

g" the N54G.

a.f The confor,mah"ce of unit operstTon to provisions contained within tne

~~

f Technical' Specifications,.afia applicable license #fonditions at least d

/

onc;,per 12 month g.

/c'gThe performanca,*' training and qual)f.ications of t b.

staff at least once per:12 months;

,r*

f

[ c.

The 'resIlts of actionsjaKSN to correct)'sethod of operation that7 tencies occurring in l

utgit equipment, structures, systems p

. cit per 6 months;

/pffect nuclear syfdy, at least

/~

r A.

The performance of activi required by the Operf ional Quality

{

j

/

Assurance # Program to see the criteria of Apppffdix 0,10 CFR Pap 5[

at 1,ealit once per donths;

[

fT$efirepro.e ion programmatic co 1sincludingAK implementi e.

procedure t least once per

dienths by qualif ad Itcensee Q

,g person fire protectionj ipment and progr implementa J

nce per 12 months' utilizing either a'oualified op(g n, at least

~

f.

T te licensee fire J

-[

protection en3fff6er(s) or an outgitfe indep'endent fire protection con-

)

sultant.

An"outside independ9nf fire protection consultant sna11 be 1

utilized at least every third year; FERMI - UNIT 2 6-11

AOMINISTRaTIVE CONTROLS y

N k ontin.ued)

,[.

y other of unit o tion considered riate by th JSRG or the t

Senior President uclear Generati Th adiologic vironmental ing program d he results thereof at ast once 12 months;

.c The 0F E DOSE CALCULAT MANUAL and 1 nting proceduresit least once p

months; 24 months; andf~ g and l;

es for processin j.

e PROCESS C PROGRAM an splementing-pr packaging of dioactive st'es at least once.

k.

The per ance of a ities required.

the Quality Assur e Program to i

e provisiop Regulatory de 1.21. Revisioff 1, June 1974 and i

meet atory Guid 4.1, Revision p 'ril 1975 at leasC'once per 12 months.

R RECOR

/

r 6.5.2.9 Rec s of NSRG acti its shall be r(pared, approved..an 1stributed as f'

indicated ow:

11beprepared.,ap/

proved, and forwarded"to a.

Minutes of e NSRG meetin the Seni ice President uclear Generatiopilthin 14 days follo. wing each l

/

l meeti l

ts of revieys-ncompassed by M be prepared, pproved, and forwarded to the,Sn. cification 6.5.2.7..sh J

b.

R ior Vice President eNuclear Generation l

f Intionofthereview,/

.s*

within 14 days following c 2.8 shall be forwa(de,d to the Nuclear Generation)and to the manage 6ent positionsl y Specification c.

Audit r,e rts encompas Sen / Vice Preside res nsible for areas audited in 30 days after ompletion of the dit by the av ting organizatio

1. [

6.5 TECHNICAL RE EW AND CONTROL/

ACTIVITIES 6.5.3.1 racedures requ d by Technical 5 fication 6.8, an otherproce(u which fact plant nuc ar safety as date ned by the Plant' Manager, and' changes thereto, shall be p ed by a qualifie ndividual/orgapitation.

i S

FERMI - UNIT 2 6-12 Amendment No. JJ #

101

('ADMINISTRATIVECONTR0tS Epch dure proced_ure change' prepared in accordance with 6.5.3.1 a

and no evie n accordanceytth Section 6.5;1.6 shall be reviewed for ni' cal y a gyntffied 3tfdividual othef than the individual that tii pared,,a equa dure er change,,thereto.

et3rdiinatiperof whether or n6t additipnel'EstEh such review'sha the py f

cross disciplinaryJaview is y

hall be pe formed by personnel of Mhe app'roprpte' deemed necv,,sary, such review (s) necessary '. If s

disc pilne.

,8 3.3 'Each pr cedure uired by Jpecification'6.8.1.h ugh j or changes

~

~ thereto, shall be re d by theEperintendefit-Radiaf,A Protectiop-or his des'ignee/The Env nmental,P,rofram Coordfnatort yHT review any-changes Tjas reviews eiay be perMrmed in 1 au'if or in addition h

/pertainingto6

.1.j.

to, those re red by sin 6.5.3 2'above.

IATETY, ATION

/

50.59 evaluat' on to determ hether questionA[einfeinvolved_ shat 1 be included in the'feview 4

en re uit by 10 n unrevi wed safe f

dfft or n questions,tp40 CFR 50, 9, NRC appr6 val of items" involving,un aviewe P

uant shall be nined Her to approval' of the recedure procedure chapg(

/

(

OUALIFICAM NS

,p 6

In y duals perf6rm ng the.,re' vie s a evaluations ibatcordance withations theappropriate).ifdiscipline('and shall xceed the qua

.3.2 the ugh 6.5.3s4 above shall meet o f

Sectins'4.2or$4'ofANSIN18'.1-1971J mbers of the plant staff previ usly designated. n' writing by tfie Plant' nager.

/

/

~ /e'/

I be RECORD

/

/

6.5.3.6 Written reto s of reviews an evaluatiop performe n accordance with items 6.5.3.2 thro 6.5.3.4 above' including ricommendations for approval or disapproval, sha be prepared and maintained.

6.'6 REPORTABLE EVENT ACTION 6.6.1 The following actions shall be taken for REPORTABl.E EVENTS:

The Comission shall be notified and a report submitted pursuant to 'the a.

requirements of Section 50.73 to 10 CFR Part 50, and h'ehufts

[achp0RA5f.E EffT sh'adebe reYewedstbhe,dSR f

) ;

~

h cer nr op Ap alternatsye-tipahay be'designafe'd,for,hi-sIosit[of6'A11Iequ t

offhese'Tych'ni'caJspecj5pe'cif i

alysis 'Re,#.Alterpative, tit 1'es'sha11 be'specified' tit 1 with th&

hs applyfinalAlafety, port.

pdated

(

FERMI - UNIT 2 6-13 Amendment No. JJ, 7#, JJ 101

~... __._._.__ _

w

=,w w

vr

e l

ADMINISTRATIVE CONTROLS uche Seb/1 fm*{6N/

6.7 SAFETY LIMIT VIOLATION The following actions shall be taken in the event a safety Limit is violated:

6.7.1 The NRC Operations Center hall be notified by telephone as soon as possible and in all cases withi 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

The Senior Vice President - Nuclear a.

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

A Safety Limit Violation Report shall be prepared.

The report shall be Od b.

reviewed by the W.

This report shall describe

1) applicable circumstances preceding the violation, (2) effects of the viol (

p Rd orq# g,,b -

3 (o@

components, systems, or structures, and (3) corrective action taken to prevent recurrence.

The Safety Limit Violation Report shall be submitted to the Comission, the I

i NSRG, and the Senior Vice President - Nuclear Generation within 14 days of c.

I the violation.

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

C T.i ssion.

6.8 PROCEDURES AND PROGRAMS Written procedures shall be established, implemented, and maintained cowwring 6.8.1 the activities referenced below:

The applicable procedures recomended in Appendix A of Regulatory Guide 1.33, a.

Revision 2. February 1978.

/;..

The applicable procedures required to implement the Fermi 2 comitments made b.

in response to the requirements of NUREG 0737.

c.

Refueling operations.

SurveillanceandtesEactivitiesofsafety-relatedequipment.

d.

J.G.9WAL x_

- s x,-

. e.

, y_,,...v.,. a-

,-a

(- idl YOb :_7b.'_b=.

[

f.

Fire Protection Program implementation.

g.

h.

PROCESS CONTROL PROGRAM implementation.

1.

OFF5ITE D0SE CALCULATION MANUAL implementation.

using Quality Assurance Program for effluent and environmental monitoring,latory S

.j.

the guidance in Regulatory Guide 1.21 Revision 1 June 1974 and Regu Guide 4.1, Revision 1. April 1975.

i 6-14 Amendment No. JJ, #

TERMI - UNIT 2 101 z.-. -

J

l s

(',

ADMINISTRATIVE CONTROL $

PROCEDURES AND PROGRAMS (Continued) ge a

er tan==t 'arth t a ad=4 Ki tt raftwa near-d===

j Jach plank robre re ed Specif tion 6

..other an r admipistr ve e

res, cha s the

, sh a revi in aycer ce w tfi 3,

appr d by Plan anager pr to Imp ent op d i be iew riodi y there er as ort a ini at A p ures The t Man r may del ate app 1a ity I in wrt ing for s cific ypes 9 proced_ures to a management represen tive l

]

\\ aspons.ibla t

fa-th-functional area./,

i 6.8.4[mpo ' yih nkek to p' roc duresMf Spe kica n 6.8c1 may'bef$ade' r

fprovid

/

/

/

1, eyed t,he ori na

.ec no e nte o

e an

)

p p, ve y

o me ers o he unit manag,ement j fw m h ids a $ ior 0 efator license h st'a

/pleast one F

and c

The cKang is cu nted and viewe nd aparoved in acc dance

(

j tt)impi men ati orJtt.3apve,a ppropr. tite, within 4da}s 4

'ei er

.8.

of 6.8.5 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 rod drive discharge headers, and standby gas treatment systems. The program shall include the following:

'4.

Preventive maintenance and periodic visual inspection requirements, and 2.

Integrated leak test requirements for each system at refuelingJy11Lintaryals or less.

ta@1adt l3 ELE TEDtadiatin# Morfit/rish b.

c[ 11 sd{e capdt y [ac delhed.ne r

ai gne i ip( con' cept atisfi i itaVares d(r 3cci t'

(condi ons.,A is pr,ogram shall in uderthe following:/,f FERMI - UNIT 2 6-15 Amendment No. JJ, M, 91

i s

ADMINISTRATIVE CONTROLS N

I PROCEDURES AND PROGRAMS (Continued)

(~

DELETED o

Ah uh.

c.

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

The program shall include the following:

1.

Training of personnel, 2.

Procedures for sampling and analysis, and j

3.

Provisions for maintenance of sampling and analysis equipment.

d.

Hioh Density Seent Fuel Racks A program which will assure that any unanticipated degradation of the high density spent fuel racks will be detected and will not compromise the integrity of the racks.

Radioactive Effluent Controls Proaram e.

i A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to MEMBERS OF THE PUBLIC from radioactive affluents as low as reasonably achievable. The program (1) shall be contained in the 00CM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program limits are exceeded. The program shall include the following elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including surveillance tests and setpoint determination in accordance with the methodology in the ODCM, 4

2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to ten times the concentration values in 10 CFR Part 20.1001-20.2402, Appendix 8 Table 2. Column 2 sampling, and analysis of radioactive liquid and Monitoring,luents in accordance with 10 CFR 20.1302 3) and with l

gaseous eff 8'l the methodology and parameters in the ODCM.

.)

~

FERMI - UNIT 2 6-16 Amendment No. $, JJ, JJ, pg,93 '

• w

+w

N3 Change to thispage.

ProvidedforInfonnation only.

i ADMINISTRATIVE C0tT20i$

i PROCEDURESANDPROGRAMS(Continued)

~

4)

Limitations on the annual and quarterly doses or dose comitment to a MEMBER OF THE PUBLIC from radioactive materials in liquid effluents releas.ed from each unit to UNRESTRICTED AREAS conforming to Appendix ! to 10 CFR Part 50, 5)

Determination of cumulative and projected dose contributions from radioactive effluents for the current calendar quarter and current calendar year in accordance with the methodology and parameters in the 00CM at least every 31 days, 6)

Limitations on the operability and use of the liquid and gaseous affluent treatment systems to ensure that the appropriate portions of these systems are used to reduce l

releases of radioactivity when the projected doses in a 31-day period would exceed 2 percent of the guidelines for the annual dose or dose commitment conforming to Appendix ! to 10 CFR Part 50, 7)

Limitations on the dose rate resulting from radioactive material released in gaseous affluents from the site to areas at or beyond the SITE BOUNDARY -to the following:

I, s.

For noble gases: less than or equal to 500 mrea/yr to the total body and less than or equal to 3000 mram/yr to the skin and b.

For Iodine-131, for Iodine-133, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days: less than or equal to 1500 mrem /yr to any organ.

8)

Limitations on the annual and quarterly air doses resulting from noble gases released in gaseous affluents from each unit to areas beyond the SITE BOUNDARY conforming to Appendix ! to 10 CFR Part 50, 9)

Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from Iodine-131, lodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous affluents released from each unit to areas beyond the SITE B0UNDARY conforming to Appendix I to 10 CFR Part 50,

10) Limitations on venting and purging of the Mark I containment through the Standby Gas Treatment System or the Reactor

.j$

Butiding Ventilation System to maintain releases as low as f.

reasonably achievable.

11) Limitations on the annual dose or dose comitment to any MEMBER OF THE PUBLIC due to releases of' radioactivity and to radiation from uranium fuel cycle sources conforming to 40 CFR Part 190.

FERill - UNIT 2 6-16a Amendment No. AI,93

ADMINISTRATIVE CONTROL $

~ '

t 1

o ro roer 1b rovided-or t adia an ra Wnust des the opv6o35 the nt.

pr sh F de (1) aprosp titj ( measu nts adi tvi the est p6tential e ure p ays (2

erif on of the e

ccuracy of tfie uent itor pro an deling of j

rogr shall 1

AonunedAft the ADCf.e athw environpeffla

- posur ppendix I foiguidance t,

1) onf to t owi

'g Part 50, a 3) ude nd Jacionyei' ides jMg.

ysis, repo g of radiat1%n Ttorj

, sampi n JJ Tse env men accordan ith the method 3cty and,ptramete nt CN,

^

r 3)

A't.and Use t6 ensu that s in us

/

at and"beyondA SI,TPBOUNDARy ideyt that / -

i modificatjeffs tophe monit hg p grain ar *(de if rd'qu by t desul s bf thi

nsus, 3) rti Spation n an I terlaboratory Co

' son,P ogr p aterjali 1 /isionandccura/cf thaJ d ndepepde t chec d on t p en 3

/

jf' th asure nts of yadioactiv 4

envirorwaantal mani+ ndna.the,/ ) I perf,ormed p part of

/ env ment sampig,sitrices

_/*

aua ty a rance, program f 6.9 REPORTING REOUIREMENTS ROUTINE REPORTS In addition to the applicable reporting requirements of Title 10. Code 6.9.1 of Federal Regulations, the following reports shall be submitted to the Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT A summary report of plant startup and power escalation testing shall 6.9.1.1 be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

The startup report shall address each of the tests identified in 6.9.1.2 Subsection 14.1.4.8 of the Final Safety Analysis Report and shall include. a description of the measured values of the operating conditions or d '.

characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to 6 16b Amendment No. 82 FERMI. UNIT 2 I

e---

a um

=m*e

---

er

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wa

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~

No Change o thispage.

Providedf:r kpnnation caly.

C *'

ADMINISTRATIVE CONTROLS STARTUP REPORT (Continued) obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other comitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of comercial power operation, or (3) 9 months following initial criticality, whichever is earliest.

If the startup report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of comercial operation) supplementary reports shall be submitted at least every 3 months until all three events have been completed.

ANNUAL REPORTS 6.9.1.4 Annual reports covering the activities of the unit as described below l

for the previous calendar year shall be submitted prior to March 1 of each year.

The initial report shall be submitted prior to March 1 of the year following initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

a.

A tabulation on an annual basis of the number of plant, utt11ty, and

{.

other personnel (including contractors), for whom monitoring was required, receiving exposures greater than 100 arems/yr and their associated man rem exposure according to work and job functions.*

(e.g., reactor operations and surveillance, inservice inspection, 1

routine maintenance, special maintenance (describe maintenance), waste processing, and refueling). The dose assignments to various dirty functions may be estimated based on pocket or thermoluminescent dosimeters (TLD) dosimeters or film badge measurements. Small exposures totalling less than 20% of the individual total dose need not be accounted for. In the aggregate, at least 80% of the total whole-body dose received from external sources should be assigned to specific major work functions; and b.

Documentation of all challenges to main steam line safety / relief valves, and c.

A summary of ECCS outage data including:

1.

ECCS outage dates and duration of outages, 2.

Cause of each ECCS outage, 3.

ECCS systems and compontnts in the outage, and 4.

Corrective action taken.

d.

The reports shall also include t% results of specific activity analysis in which the primary coolant exceeded the limits of Specification 3.4.5.

The following 1,nformation shall be included:

(

'This tabulation supplements the requircments of $20.2206 of 10 CFR Part 20.

[

4 FERMI - UNIT 2 6-17 Amendment No. JJ. 93

4 A IN15TRaTIVECONTR0tS ANNUAL REPORTS (Continued)

(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first' sample in which the limit was exceeded; (2) results of the last isotopic analysis for radiotodine performed prior to exceeding the limit, results of analysis l

while limit was exceeded and results of one analysis after the radiciodin6 activity was reduced to less than limit (each result should include date and time of sampling and the radiciodine concentrations);

I (3) clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; l

(4) graph of the I-131 and one other radiciodine isotope concentrations in microcuries per gram as a fenction of time s

for the duration of the specific. activity above the steady-state level; and i

(5) the time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

MONTHtY OPERATING REPORTS 6.9.1.6 Routine reports of operating statistics and shutdown experience shall be submitted on a monthly basis to the Director, Office of Resource N

copy to the Regional Administrator of the Regionril Office of the NRC, no later

'J Management, U.S. Nuclear Regulatory Commission, Washington 0.C. 20555, with a than the 15th of each month following the calendar month covered by the' report.

t':':UAL RADIOLOGICAL ENVIRONf4 ENTAL OPERATING REPORT 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radichgical The material Environmental Monitoring Program for the reporting period.

provided shall be consistent with the objectives outlined in (1) the 00CM and (2) Sections IV.B.2. IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

yd ANNUAL RADIDACTIVE EFFLUENT RELEASE REPORT

{

td 6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted weitt." r ty: :'tr 2rry

• of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the 00CM and PCP and (2) in

.py conformance with 10 CFR 50.36a and Section IV.BT of Appendix I to 10 CFR Part 50.

S FERMI - UNIT 2 6-18 Amendment No. JJ. Af,.91 j

NnChange to thispage.

Providedf;rInf nnation caly.

ADMINISTRATIVE CONTROLS THIS PAGE HAS BEEN INTENTIONALLY DELETED i

l E.

-J:

(...-

FERMI - UNIT 2 6-19 Amendment No. JJ, 81

E N) Change to thispage.

Providedf;rinformation cnly.

ADMINISTRATIVE CONTROLS

.)I P

THIS PAGE HAS BEEN INTENTIONALLY DELETED l

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J FERM1 - UNIT 2 6-20 Amendment No. JJ JJ, 82

(,'

ADMINISTRATIVE CONTR0tS SPEC 1Al REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

CORE OPERATING LIMITS REPORT 6.9.3 Selected cycle specific core operating Ilmits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Company reports NEDE 24011-P A and NEDE-23785-1-PA.The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core themal-hydraulic limits, ECC$ limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The COLR, including any mid cycle revisions or supplement thereto, shall be submitted upon issuance to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector prior to use.

6.10 Od Edd

'/ /ff etentMnre frements of Title a

ti o the' appl dble ecor 7 7 o

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,t foi ng rec'ords all ife ptained for

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1 st' e i imu pari ind-ted.

( The fo)1ow g records s be ained or a en 5 ye s:

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p/. R1tcor,d anf/logso uni erat n cov r'ln me i erval each

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power Itv61.

a ' logs of pr c' pal it net a t' viti

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Mcem3n of i di items fe ment r ated to air,fa r

uclear safe)..j/

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LL REP RTABLE. EVENTS rye 1 ance/activi iss, nspections rations'~

Technical)p cifjestions./, and ca

( Records f thes riquired by /

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'"'f val physica1' inventory,of all sealed s9u'rce mateItal l g.

Regards of Q.,

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FERMI - UNIT 2 6 21 Amendment No. JJ, JJ, 37,93

ADMIN 1sTRAT1VE CONTROL 5

[s.10 REGORD RETElpt0N. (mmlinued) 3 fo1 g records s be retained f r tN'e' duration of the unit Oper ng Li se:

Records an awing chang flecting un sign modific [

made i stems and e ent describ n the F nal 5 y Analysis Re b

Records of and irradi fuel invento

, fuel transfers, and I

assemb1 rnup histo c.

rds of dos eceived by al dividuals for whom oring was

equired, j

d.

Recor of gaseous a iquid radioactive arial released to the en ons.

I e.

Records of nsient or opera cycles for those components identif in Table 5.7.1-f.

R rds of reactor ts and experimen Records o ning and quali on for current me.

of the i

unit I

h.

Rec'6 ds of inservi nspections per y pursuant to these f ations.

j/' Technical Spec j

/1.

Records quality assu pp tivities required by t tional Qual Assurance Ma

)

J.

• ecords of r v4f s performed for chanet.

e to procedures or equipment reviews of tests and.expfriments pursuant to 10 CFV 50.59 k.

R cords of meeting OSR0 and the NSRG.

Recordsofthe vice 1tves of all aulic and mechanical theserficelifecommencesnubbers required by Spscific (a.tt

. 5 including the dAWit,.7 which n associated install Vand f

mainfenance records cords of es required by the ogical environment monitoringeho.1 the anpfysis at a later date edThis should includA+/ol:.ac6 racy of gram that would pe__p aluation of the edures effective at specified t and QA records ing that these

1. r

,p'rocedures were fell gestothe0FFSITf.r.D85 RecordsofgUALandPROCESSws performed for.

CALCULATI TROL PROGRAM.

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's of radioactive s ments.

m Amendment No. JJ. JJ, AI,93 j FERMI - UNIT 2 6 22 u..

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ADMIN 15TRAT1VE CONTROL $

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FERMI - UNIT 2 6 22a Amendment No. JJ. JJ,93

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ADMINISTRATIVE CONTROLS j

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may4e had' calved / Entry e aftfr thg,(ose r evels he area e been estab i hed4nd pa sonnel we been a knowled le of I

A radi ion protectjoffqualified ndividual

.e., qu 1 led in c-

/m',adt ion protection procedurps with a p 1ation d ' rate torin~g devjef who is resfon)sible fsf providiWpositive f

t er..the activities with n', tie area ahd shall pe'rfom e

1c,e radiation s'urvat11 nce. 'the fr ency specified by Radittion'

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6.13 Mi-5N6idurrNIdT 6[mplemen'tati 6f13'.VT$e sfi'11 Wa e4 d'C ission 2

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pec FERMI - UNIT 2 6-23 Amendment No. JJ JJ, g3

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ADMINISTRATIVE CONTROLS 6.13 /boCISv[6Hina MIEi 4 A?C?; l0..Mx:S -.

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~n he pprova of the lant name.

6.14 0FFSITE DOSE CALCULATION MANUAL f0DCM) 6.14.1 The ODCM shall be approved by the Connission prior to implementation.

6.14.2 Changes to the ODCM:

a.

Shall be documented and records of reviews performed shall be This documentation shall contain:

s 1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s) and 2)

A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. ~

Shall become effective af terC-

-m---

- --- Z Z )

@ approval of the Plant Manager.

Stall be submitted to the Commission in the form of a complete, c.

leyible copy of the entire ODCM as part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.

Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,

month / year) the change was implemented.

l TERMI - UNIT 2 6 24 Amendment No. JJ, pf, H,93,

N3 Change to thispage.

Providedf:rIn(;rnsation cn!y.

ADMINISTRATIVE CONTROLS THIS PAGE HAS BEEN INTENTIONALLY DELETED

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1 FERMI - UNIT 2 6-25 Amendment No. JJ, 82

............ : = - - : = :.

=:

i i

EEEd ADMINISTRATIVE CONTROLS i

SECTION PJMif 6.1 RESPONSIBILITY...........................................

6-1 I

6.2 ORGANIZATION.............................................

6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS..................

6-1 l

6.2.2 UNIT STAFF........................................

6-1 6.2.3 DELETED...........................................

6-6 l

6.2.4 SHIFT TECHNICAL ADVIS0R...........................

6-6 6.3 DELETED..................................................

6-7 6.4 DELETED..................................................

6-7 6.5 DELETED..................................................

6-7 6.5.1 DELETED 6-7 6.5.2 DELETED 6-9 FERMI - UNIT 2 xix Amendment No. #2,

llf.fd ADMINISTRATIVE CONTROLS SECTION PAGE 6.5.3 DELETED 6-12 l

6.6 REPORTABLE EVENT ACTI0N....................................

6-13 6.7 SAFETY LIMIT VIOLATION.....................................

6-14 6.8 PROCEDURES AND PR0 GRAMS....................................

6-14 6.9 REPORTING RE0VIREMENTS.....................................

6-16b 6.9.1 ROUTINE REP 0RTS.....................................

6-16b STARTUP REP 0RT......................................

6-16b i

ANNUAL REP 0RTS......................................

6-17 MONTHLY OPERATING REP 0RTS...........................

6-18

~

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT..

6-18 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT..........

6-18 6.9.2 SPECIAL REP 0RTS.....................................

6-21 6.9.3 CORE OPERATING LIMITS REP 0RT........................

6-21 6.10 DELETED 6-21 6.11 DELETED 6-22a 6.12 DELETED 6-22a 6.13 DELETED 6-23 6.14 0FFSITE DOSE CALCULATION MANUAL...........................

6-24 1

FERMI - UNIT 2 xx Amendment No JJ, JA, SJ, SJ,

i DEFINITIONS' MINIMUM CRITICAL POWER RATIO I

1.22 The MINIMUM CRITICAL' POWER RATIO (MCPR) shall be the smallest CPR which exists in the core.

4 0FF-GAS TREATMENT SYSTEM 1.23 An 0FF-GAS TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous affluents by collecting reactor coolant system i

offgases from the reactor coolant and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

OFFSITE DOSE CALCULATION MANUAL i

1.24 The OFFSITE DOSE CALCULATION MANUAL (DDCM) shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous j

and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program.. The ODCM shall also i

contain (1) the Radioactive Effluent Controls required by Section 6.8.5 and Radiological Environmental Monitoring Programs and (2) descriptions of the information that should be included in the Annual Radiological-i Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.7 and 6.9.1.8.

OPERABLE - OPERABILITY 1.25 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s) and 1

when all necessary attendant instrumentation, controls, electrical power, l

cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, component or device to perform its function (s) are also capable of performing their related support function (s).

i i

QPERATIONAL CONDITION - CONDITION 1.26 An OPERATIONAL CONDITION, i.e., CONDITION, shall be any one inclusive combination of mode switch position and average reactor coolant temperature as specified in Table 1.2.

i PHYSICS TESTS i

1.27 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation and (1) described in Chapter 14 of the FSAR, (2) authorized under the provisions of 10 CFR 50.59, or (3) otherwise approved by the Commission.

t PRESSURE BOUNDARY LEAKAGE l.28 PRESSURE BOUNDARY LEAKAGE shall be leakage through a nonisolable fault in l

a reactor coolant system component body, pipe wall, or vessel wall.

i PRIMARY CONTAINMENT INTEGRITY l.29 PRIMARY CONTAINMENT INTEGRITY shall exist when:

a.

All primary containment penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an OPERA 3LE primary containment automatic isolation system, or FERMI - UNIT 2 1-4 Amendment No. SJ, m

e

.w.

,.-w-

,.7 y.

y w..,

9 a

m

)

PLANT SYSTEMS r9

. SURVEILLANCE REQUIREMENTS (Continued) i i

g.

D;pctional Test Failure Analysis An engineering evaluation shall be made of each failure to meet the functional test acceptance criteria to determine the cause of the failure. The results of this evaluation shall be used, if applicable, in selecting snubbers to be tested in an effort to determine the OPERABILITY of other snubbers'

)

irrespective of type which may be subject to the same failure

mode, i

For the snubbers found inoperable, an engineering evaluation I

shall be performed on the components to which the inoperable snubbers are attached. The purpose of this engineering l

evaluation shall be to determine if the components to which the inoperable snubbers are attached were adversely affected by the inoperability of the snubbers in order to ensure that the component remains capable of meeting the. designed service.

If any snubber selected for functional testing either fails to i

lock up or fails to move, i.e., frozen-in-place, the cause i

will be evaluated and if caused by manufacturer or design deficiency all snubbers of the same type subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated in i

Specification 4.7.5e.lfor snubbers not meeting the functional test acceptance criteria.

h.

FunctionalTestinaofRepairedandReplacedSnu5bers i

i Snubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced.

Replacement snubbers and snubbers which have repairs which might affect the functional test result shall be tested to j

meet the functional test criteria before installation in the l

unit. Mechanical snubbers shall have met the acceptance l

criteria subsequent to their most recent service, and the freedom-of-motion test must have been performed within 12 months before being installed in the unit.

1.

Snubber Seal Reolacement Proaram The service life of hydraulic and mechanical snubbers shall be monitored to ensure that the service life is not exceeded

.}

between surveillance inspections. The maximum expected service life for various seals, springs, and other critical i

parts shall be determined and established based on engineering l

information and shall be extended or shortened based on monitored test results and failure history.

Critical parts shall be replaced so that the maximum service life will not be exceeded during a period when the snubber is required to be OPERABLE.

The parts replacements shall be documented and the documentation shall be retained.

FERMI - UNIT 2 3/4 7-20 Amendment No.

U

, ADMINISTRATIVE CONTROLS 6.2.2 UNIT STAFF a.

Each on duty shift shall be composed of at least the minimum shift crew composition shown in Table 6.2.2-1; b.

At least one licensed Operator shall be in the control room when fuel is in the reactor.

In addition, while the unit is in OPERATIONAL CONDITION 1, 2 or 3, at least one licensed Senior Operator shi11 be in the control room; c.

A Radiation Protection Technician

• shall be on site when fuel is in the reactor. The Radiation Protection Technician position may be unfilled for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to

/

accommodate unexpected absence, provided immediate action is taken to fill the required positions; d.

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

DELETED f.

DELETED l

• An alternative title may Le designated for this position. All requirements of these Technical Specificationc apply to the position with the alternative title as apply with the specified title. Alternative titles shall be specified in the Updated Final Safety Analysis Report.

j FERMI - UNIT 2 6-2 Amendment No. JJ, Jp, Jf, JE, JpJ

ADMINISTRATIVE CONTROLS UNIT STAFF (Continued) l g.

The Operations Engineer, Nuclear Shift Supervisor, and Nuclear Assistant Shift Supervisor, shall hold a Senior Reactor Operator license. The Nuclear Supervising Operator shall hold a Reactor Operator or Senior Reactor Operator license.

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FERMI - UNIT 2 6-2a Amendment No. 59, JJJ, 1

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ADMINISTRATIVE CONTR0ts 6.2.3 DELETED

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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 controls in the control room.

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l FERMI - UNIT 2 6-6 Amendment No. y, y, y,

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ADMINISTRATIVE CONTROLS 4-6.3 DELETED l

6.4 DELETED l

6.5 DELETED l

L FERMI - UNIT 2 6-7 Amendment No. JJ, 79, S, Jp/

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FERMI - UNIT 2 6-8 Amendment No. JJ, JJ, JpJ

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ADMINISTRATIVE CONTROLS l

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FERMI - UNIT 2 6-10 Amendment No. JJ, Jp, pp, pp, Jpy

ADMINISTRATIVE CONTROLS F

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FERMI - UNIT 2 6-11 Amendment No.

ADNINISTRATIVE CONTROLS

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FERMI - UNIT 2 6-12 Amendment No. JJ, 75, JJJ

,q,

.J s

a-ADMINISTRATIVE CONTROLS 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.

i I

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FERMI - UNIT 2 6-13 Amendment No. JJ, 79, JJ, JpJ r

p

]

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

a.

The NRC Operations 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 Senior Vice President -

Nuclear Generation and the Nuclear Safety Review Group (NSRG) shall be l

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 Onsite Review Organization (OSR0). This report shall l

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 Senior Vice President - Nuclear Generation within 14 days of the violation.

d.

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

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

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.

DELETED f.

DELETED l

g.

Fire Protection Program implementation, h.

PROCESS CONTROL PROGRAM implementation.

i.

0FFSITE 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 6-14 Amendment No. JJ, JJ, JSJ

1 iu ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) l 6.8.5 The following programs shall be established, imolemented, 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 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.

b.

DELETED l

l 1

l FERMI - UNIT 2 6-15 Amendment No. JJ, Jf, JJ u

I ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) l c.

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

The program shall include the following:

1.

Training of personnel, 2.

Procedures for sampling and analysis, and 3.

Provisions for maintenance of sampling and analysis equipment.

d.

Hiah Density Soent Fuel Racks I

A program which will assure that any unanticipated degradation of the high density spent fuel racks will be detected and will not compromise the integrity of the racks.

e.

Radioactive Effluent Controls Proaram A program shall be provided conforming with 10 CFR 50.36a for the control of radioactive effluents and for maintaining the doses to

-l MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program (1) shall be contained in the 00CM, (2) shall be implemented by operating procedures, and (3) shall include remedial actions to be taken whenever the program i

limits are exceeded. The program shall include the following r

elements:

1)

Limitations on the operability of radioactive liquid and gaseous monitoring instrumentation including' surveillance l

tests and setpoint determination in accordance with the i

methodology in the 00CM, i

2)

Limitations on the concentrations of radioactive material released in liquid effluents to UNRESTRICTED AREAS conforming to ten times the concentration values in 10 CFR Part 20.1001-20.2402, Appendix B, Table 2, Column 2, 3)

Monitoring, sampling, and analysis of radioactive liquid and gaseous effluents in accordance with 10 CFR 20.1302 and with the methodology and parameters in the 00CM.

FERMI - UNIT 2 6-16 Amendment No. %, JJ, Jp, SJ,SJ

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) f.

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ROUTINE REPORTS l

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the l

Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT j

6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (1) receipt of an Operating License, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the unit.

6.9.1.2 The startup report shall address each of the tests identified in l

Subsection 14.1.4.8 of the Final Safety Analysis Report and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to l

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FERMI - UNIT 2 6-16b Amendment No. E

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued)

(1) reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (2) results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results' of one analysis after-the radiciodine activity was reduced to less than limit (each result should include date and time of, sampling and the radiciodine concentrations);

(3) clean-up system flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; r

(4) graph of~the I-131 and one other radiciodine isotope i

concentrations in microcuries per gram as a function of time for the duration of the specific activity above the steady-state level; and (5) the time duration when the specific activity of the primary' coolant exceeded the radiotodine limit.

MQHIHLY OPERATING REP'"LS 6.9.1.6 Routine reports of operating statistics and shutdown experience 'shall be submitted on a monthly basis to the Director, Office of Resource Management, U.S. Nuclear Regult W y Commission, Washington, D.C. 20555, with a copy to the Regional Administrator of the Regional Office of the NRC, no later than the 15th of each month following the calendar month covered by the report.

ANNUAL RADIOLOGICAL ENVIRONMENTAL'0PERATING REPORT l

6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year.

The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological i

Environmental Monitoring Program for the reporting period.

The material provided shall be consistent with the objectives outlined in (1) the ODCM and (2) Sections IV.B.2. IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.

ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 The Annual Radioactive Effluent Release Report covering the operation of the unit during the previous 12 months of operation shall be submitted prior to May 1 of each year. The report shall include a summary of the l

quantities of radioactive liquid and gaseous effluents and solid waste released from the unit.

The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50.

FERMI - UNIT 2 6-18 Amendment No. JJ, SJ, #J

ADMINISTRATIVE CONTROLS SPECIAL REPORTS 6.9.2 Special reports shall be submitted to the Regional Administrator of the Regional Office of the NRC within the time period specified for each report.

CORE OPERATING LIMITS REPORT 6.9.3 Selected cycle specific core operating limits shall be established and documented in the CORE OPERATING LIMITS REPORT (COLR) before each reload cycle or any remaining part of a reload cycle. The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Company reports NEDE-240ll-P-A and NEDE-23785-1-PA. The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-i hydraulic limits, ECCS limits, nuclear limits such as shutdown margin, and transient and accident analysis limits) of the safety analysis are met. The COLR, including any mid-cycle revisions or supplement thereto, shall be submitted upon issuance to the NRC Document Control Desk, with copies to the Regional Administrator and Resident Inspector prior to use.

6.10 DELETED l

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1 FERMI - UNIT 2 6-21 Amendment No. JJ, #, S/, #

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ADMINISTRATIVE CONTROLS' l

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FERMI - UNIT 2 6-22a Amendment No. JJ, Ef, SJ j

ADMINISTRATIVE CONTROLS 6.13 DELETED l

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i FERMI - UNIT 2 6-23 Amendment No. JJ, EJ, JJ

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l ADMINISTRATIVE CONTROLS l

i 6.14' 0FFSITE DOSE CALCULATION MANUAL (ODClu l

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6.14.1 The 00CM shall be approved by the Commission prior to implementation.

6.14.2 Changes to'the ODCM:

a.

Shall be documented and records of reviews performed shall be retained. This documentation shall contain:

l i

1)

Sufficient information to support the change together with the appropriate analyses or evaluations justifying the changes (s) and 2)

A determination that the change will maintain the level of I

radioactive effluent. control required by 10 CFR 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of i

effluent, dose, or setpoint calculations.

b.

Shall become effective after approval of the Plant Manager.

l 4

i c.

Shall be submitted to the Commission in the form of a complete,

)

legible copy of the entire ODCM as part of or concurrent with the l

Annual Radioactive Effluent Release Report for the period of the report in which any change to the 00CM was made.

Each change shall be identified by markins in'the margin of the affected pages, clearly indicating tl> r ea of the page that was changed, i

and shall indicate the date g.g., month / year) the change was implemented.

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l FERMI - UNIT 2 6-24 Amendment No. JJ, pf, pf, py

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