ML20116F306

Proposed Tech Specs Re License Amend to Change Adminstrative Controls Section 6.0 of Fermi 2 TS Per Nrc'S Issued Generic Guidance in Form of AL 95-06,dtd 951212

ML20116F306
Person / Time
Site:	Fermi
Issue date:	07/25/1996
From:	DETROIT EDISON CO.
To:
Shared Package
ML20116F273	List: ML20116F306 NRC-96-0064, Submits Rev to Proposed TS Change (License Amend) for Administrative Controls (TAC M91189) to Be Consistent W/Al 95-06,Improved Standard TS & Pending Changes to Improved Standard Ts,Per Discussions W/Nrc
References
AL-95-06, AL-95-6, NUDOCS 9608060309
Download: ML20116F306 (63)

Text

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A'ITACIIMENT 2 1 PROPOSED TECIINICAL SPECIFICATION CIIANGES l

9608060309 960725 PDR ADOCK 05000341 P PDR l

B.D.fl ADMINISTRATIVE CONTROLS SECTION f.AG.f.

6.1 RESPONSIBILITY........................................... 6-t 6.2 ORGANIZATION............................................. 6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS.................. 6-1 j 6.2.2 UNIT STAFF........................................ 6-1 l 6.2.3 .

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6.2.4 SHIFT TECHNICAL ADVIS0R........................... 6-6 6.3 UNIT STAFF 00ALIFICATIONS................................ 6-7 6.4 t N'

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xix Amendment No. 82 FERMI - UNIT 2

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ADMINISTRATIVE CONTROLS F

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' . ,. .__...................................... 6,13 6.7 SAFETY LIMIT VIOLATION..................................... 6-14 ..

6.8 PROCEDURES AND PR0 GRAMS.................................... 6 6.9 REPORTING RE00fREMENTS.'................................... 6-16b 6.9.1 ROUTINE REP 0RTS.........../......................... '6-16b i STARTUP REP 0RT............

ANNUAL REP 0RTS ....................... . . . . . . . . . . . .//. . . . . .6-16b 6-17.................

MONTHLY OPERATING REP 0RTS........................ .. 6-18 ..

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT., 6-18 ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT...... 6-18 1 6.9.2 SPECIAL REP 0RTS..................................... 6-21 6.9.3 CORE OPERATING LIMITS REP 0RT........................ .

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~__n.-. ................................... 1 1 6,23 6.14 0FFSITE DOSE CALCULATION MANUAL........................... 6-24 FERMI - UNIT 2 xx '

Amendment No. JJ Jf $$,91

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, No Change to thispage. ,

Proyidedforinformation only. - l mertutvinue -

TRIOUCHCY NOTATION 1.14 The FREQUENCY NOTATION specified for the performance of. Surveillance

., Requirements shall correspond to the intervals defined in Table 1.1.

IntNTtr1to ttAct

. 1.15 10EH11FIED LEAKAGE ahall be:

a. Leakage into collection systems, such as pump seal or valve packing leaks, that is captured and conducted to a sump or collecting tank, a r. -

b teakage into the containment atmosshere from sources that are both specifically located and known either not to interfere with the operation of the leakage detection systems or not to be PRESSURE SOUNDARY LEAKAGE.

J1QtAT10N SYSTEM RtsPOWst TIMt - -

3.16 The L50LA110N SYSTEM RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its isolation actuation setpoint

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at the channel sensor until the isolation valves travel to their required positions. Times shall include diesel eenerator starting and sequence loading delays where applicable. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

LIMITING CONTROL ROD PATTERN -

I a.17 A LIM 111NG CONTROL R0D PATTERN shall be a pattern which results in the core being on a therm1 3 hydraulic limit i.e., operating on a

, Itatting value for APLHGRI LNGR, . or MCPR.

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11Ntat HEAT GENERATION RATE .

3.38 LINEAR HEAT GENERAi!0N RATE (LNGR) shall be the heat generation per unit length of fuel rod. It is the intepral of the heat flux over '

the heat transfer area associated with, tas unit length. -

LOGIC SYSTEM FUNCTIONAL Ttr' 1.19 A LOGIC SYSTEM FUNCLIONAL TEST shall be a test of all logic

. components i.e., all relays and contacts, all trip units, solid state logic elements, and includinn the actuatedetc., device to verify CPERABILITY.of The LOGIC.

a logic circ

. SYSTEM FUNC1, DNAL 1EST may be performed by any series of sequential.

overlapping or total system steps such that the entire logic system is tested. *

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MA11 MUM TRACTION OF L1MITING POWER DEN 11TY -

3.20 The MAXIMUM FRACTION 0F LIMillNG POWER DENSITY

• highest value of, the FLPD which exists in the co(MFLPD) re. , . shall be the MEMBERf 510F THE MJBlic

• 3.11

• MEMBER (5) 0F THE PUBLIC shall be an individual in a controlled or

, UNRE51RICIED AREA. However, an individual is not a MEMBER 0F THE PUBLIC during ary i /. occupational dose. period in which the individual receives an -

FERMI - UNIT 2 . 1-3 -

Amendment No. 33 ..

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M10fMUM CRITICAL POWER RATIO 1.22

{t - The MINIMUM CR111 CAL POWER RATIO (MEPR) shall be the smallest CPR which exists

. in the core. .- -

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l 0FF CAS TREATMENT SYSTEM -

j 1.13 An 0Ff-GAS TREATMENT SYSTEN is any system designed and installed to reduce i

radioactive gaseous effluents by collecting reactor coolant systes offgases j- .

from the reactor coolant and providing fordelay or holdup for the purpose of

. reducing the total radioactivity prior to release to the environment. -

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OFFSITE D0$f CALCULATION MANUAL . ~

! shall contain the methodology and -

i 1.14 . parameters The 0Ff51TE usedDOSE CALCULATION in the calculation of offsi MANUAL (00CN)te doses resulting fr gase6us and liquid effluents, in the calculation of gaseous and liquid offluent monitoring Alars/ Trip Set oints, and in the conduct of the Radiological Environmental Monitorin Program. The ODCN sh611 also contain (1) the Radioactive Iffluent to rols# and Radiological Environmental -

descriptions of the

- Monitoring Programs information that sh 16 be crecutred included by section in the Annual 6.8.D Radio and (2) logical Environmental Operating an nual Radioactive E,ffluent Release Reports required by

. Specificatto .7 and 6.9.1.8. -

-- OPERAstt - OPERAgit1TY 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 when all necessary attendant instrumentation, controls, electrical (p)ower, cooling or seal water, lubrication or other auxiliary equipment that are train, com)onent er device to perfom its required function (s)for the are alsosystem, capablesubs f per stem, forming the4r related support function (

I OPERAT10Nat CONDITION - COND1T10N

)

1.16 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.

. PHYSICS TESTS 1.17 PHYSICS 1ESTS shall be those tests performid to measure the fundamental nuclear characteristics of the reactor core and related. instrumentation and (1 described in Chapter 14 of the FSAR, of)10 CFR 50.59, or (3) otherwise approve (d by the Comission.2) authortred un PRE 55URE BOUNDARY ttAKAGE 1.14 PRESSURE BOUNDARY LEAXAGE shall be leaka

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reactor coolant system component body, pe wall, p'le through or vessela wall.

monisolable fault in a PRIMARY CONTAINMENT INTEGRITY

• 1.19 PRIMARY CONTAINMENT INTEGRITY shall exist when: ,

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. a. All primary containment penetrations required to be closed during

, accident conditions are eithers

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1. Capable of being closed by an OPERABLE primary containment .

automatic isolation system, or .

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FERMI - UNIT 1 AmendmentNo.82-]

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No Change to thispageo Providedforinformation only. .

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PLANT $YSTEMS .

$URVElll&NCE REQUIREMENTS (Continued)

' plotted using an " Accept" line which follows the equation ,

N as =the 55(1 + C/2)is tested.Each snubber If thesnubber point should point plotted falls onbeorplotted as soon below the " Accept" line, testing of that type of snubber may be terminated. If the point plotted falls above the " Accept" o line testino must continue untti the point falls in the .

"Acce,pt" region or all the snubbers of that type have been

. tested. ,

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, 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 1

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-eine if additional samples should be limited to the type of j , snubber which has failed the functional testing.

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f. Functional Test Acceptance Criteria , ,

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The snubber functional bst shall verify that:

1) Activation (restrainingaction)isachievedwithinthe

, specified range in both tension and compression; 1 2) Snubber bleed, or release rate where required, is present -

in both tension and compression, within the specified .-

' range;

~ 3) For mechanical snubbers, the force required to initiate or j eatntain motion of the snubber is within the specified range 1 In both directions of travel; and l l

4) For snubbers specifically reqvfred not to displace under l continuous load, the ability of the snubber to withstand load without displacement.

Testing methods may be used to measure parameters indirectly or l parameters other than those specified if those results can be  !

correlated to the 'specified parameters through established

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3/4 7-19

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i PLANT $YSTEMS s

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j~ $URVE1LLANCE REQUIREMENTS (Continued) y t .

! g. Functional Test Failure Analysis ,

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' An engineering evaluation shall be made of each failure to meet )

the. functional test acceptance criteria to determine the cause I

! of the failure. The results of this evaluation shall be used.

l 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 evalv-stion 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 lock up or fails to move 1.s., froten-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 4.7.5e. .

I for snubbers not meeting the functional test acceptance criteria. a

h. Functional Testing of to aired and Replaced Snubbers )

$nubbers which fail the visual inspection or the functional test acceptance criteria shall be repaired or replaced. Replacement snubbers and snubbers which have repairs which alght 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 the unit.

i. $nubber Seal Replacement Procrea The service 1(fe of hydraulic and mechanical snubbers shall be 8 monitored to ensure that the service 1tfa is not exceeded between curveillance inspections. The maximum expected service life for various seals, springs, and other critical parts shall be -

determined and estabitshed 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 saxteum service 1tfe will not be exceeded during a period when the snubber is required to be OPERABLE. The parts replacer t cents shall A

. Semwgocumented w *caand m the ~ documentation ixtT5 LM shall be retained, FERN! - UNIT 2 3/4 7*20

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ADMIN 1$TRAT1VT CONTE 0LS

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. s .1 afsP0Nsts1ttTy . .

I 5.1.1 The Plant Manager

• shall be responsible for overall unit safe operation. I

! and shall delegate in writing the succession to this responsibility during his

- absence. The Plant Manager shall have control over those onsite activities j -

accessary for safe operation and maintenance of the plant.. ,

I 5.1.1 The Nuclear shift Supervisor or, during his' absence from the control i room, a designated individual shall be responsible for the control room connand function. A annagement directive to this effect, signed by the Senior Vice President . Nuclear Generation

• ahall be reissued to 41, station , ,

personnel on an . annual basis. )

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! 8.7 ORCaN17aTf0N '

j g1 0Frs1Tt AND ogs1TE ORGAN 17AT1DNs Onsi?e and offsite organizations shall be established for unit operation and ..

. corpetse e:,nagement, respe.?.1741y. The onsite and offsite organizations l i shall include the positions for activities affecting the safety of the nuclear power plant.

1( a. responsibility, and comunication shall be

! Lines of authority,ined established and def for the highest management levels through

! intersediate levels to positions. These relaionships {and including all operating shall be documented organization and updated.

as appropriate. in the form of organization charts, functional i [J,. descriptions of departmental responsibilities and relationships.

! and job descriptions for key personnel positions, or in equivalent i forms of documentation. These requirements shall be documented in j the Updated Final safety Analysis Report.

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b. The Senior Vice Pr.esident - Nuclear Centration shall have I corporate responsibility for overall plant nuclear safety and shall take any measures needed to ensure acceptable performance of -

the staff in operating, maintaintne and providing technical

. support of the plant to ensure nuclear safety.

c. The individuals who train the operating staff and those who carry out health physics an.d stuality assurance functions may report to the appropriate onsite managers however, they shall have sufficient organizational freedom to ensure their independence from operating pressures.

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• An alternative title any be des'fgnated f'or this position. All requirements i of these Technical specifications apply to the position with the alternative.  ;

f. title as apply specified in thewith the specified Updated inal Safetytitle. Alternative Analysis feport. titles shall

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. i ggang . UNIT g 61 Amendment No. JJ. 77. $7. pp.101 l

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I ADP.lNISTRATIVE CONTROLS 3l

. s 4.1.2 pH1T3TMJ l -

a. Each on duty shift shall be composed of at least the minimum shift j trew composition shown in Table 4.1.1-1; .

! . 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 0PERATIONAL CONDITION 1. I or 3, at least one Itcensed Senior i Operator _shall be in the control room;

! c. A Radiation protection Technician

• shall .be on site when fuel 'is in '

I the reactor. The Radiation protection Technician position say be unfilled for a period of time not to exceed I hours, in order to accomodate unexpected absence, provided innediate action is taken to fill the required positions; -

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. DELITED -

f. bAdmin a e oce es s 11 be ele and lemented to }

J t wer ng use nit f perf a safety-related .s

, et s .g. icen Seni Ope ors, consed Operators.

sv he si perso el, a iar opera rs, and ke nintenance rso . 1 A' qui e shi cover e sh be ntained out r heavy .

se ' ov ime. eo etive all be have th rsonnel work l l 4 mi 40- r we while e unit operati owever, in the e en hat ores probjems requir substari amounts of be d. or Gring exte6ded perJ(cs of shutdo or f-ovJtttime ptfuel g. ma main nance, gr' major unit modificatio , on a tem ary b is th allowin duidelin (shall be fo ved:

2. ndiv al sh.ov not be rattted to y more hou straig ,excludt shift tur o9er time

2. An ndivid should be pers tred to more than I hours n any 24- ur perto nor more n 24 hoyr(in any, 48-hou period, a more th 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> arny 7)af period, all cluding ft turno r time. -

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• An alternative title may be designated fo'r this position. All requirements of these Technical Specifications app y to the position with the alternative title as apply with the specified title. Alternative. titles shall be specified in the 3 Updated Final safety Analysis Report. >j

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FERM1 - UNIT 2 6-2 Amendment No. H. H.101

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• j' W.!NISTRATIVE CONTROLS j'* .

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~ tm1T 1114. (Continued) 6 k at 1 t8 ur ou a owed between work j i , Inc in ift rno 11 .

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ept ing ten s d riod soul e sid he ed vertime.

o ai vide asts d ,for t j ,

ont as e s t, y la n th abov idel es 1 be her d by.

la Ma er is igne in orda l th',ab s' sh proc < res ut doc tati of uit basis

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} r in he dit,att . Coe 1s all inc ed in e l

! p ce as s M5i th indi dual erti 'sh be fewejl

! n y by nt Na ser o his si to e essivp/sep j ure kit j

our ave tbegesstJ ed. outi devif* t}ien fadin4, the above out eline is not auth C ae .

g. The Operations Engineer. Nuclear Shift Supervisor, and l I

Nuclear Assistant Shift Superv4er shall hold a Senior Reactor i Operator license. The Nuclear Supervising Operator shall hold a j Reactor Operator or Senior Reactor Operator license.

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l FERK! - Let!T 1 5-ta Acendment No. 39.101

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& Chxnge to tMtpag;.

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hMforWo%n only.

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FIGURE PAGE DELETED FEW - WIT 2 6-3 Ameni~.ent No. in

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. No Gange to thispage, j havidedforWomation only.

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FERMI - UNIT 2 6-4 k ndment No. 30 f

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Providedforinfonnation any.

T,A,B,L,E 6.2.2 1

MINIMUM $HIFT CREW COMP 051T10N

. P0$1 TION NUMBER OF INDIVIDUALS REQUIRED TO FILL POSITION

{. -_...- . . _ . . - -

CONDITION 1,2 or 3 CONDITION 4 or 5

. MS 1 -

1 l NASS -

1 . None

! N$0' 2 1 i NPP0/NAPP0 2 1 l STA 1 None l TABLE NOTATION I NSS .

Nuclear Shift Supervisor with a Senior Operator license

! MASS . Nuclear Assistant Shift Supervisor with a Senior Operator 1

license -

N50 - Nuclear Supervising Operator with an Operator license i NPPD/NAPP0 - Nuclear Power Plant Operator or Nuclear Assistant Power Plant Operator STA - Shift Technical Adviso , '

Except for the Nuclear shift Supervi or the shift crew composition may be one less than the minimum requirements of Table 6.2.21 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 acconmodate unexpected absence of on-duty shift crew merbers provided irmediate action is taken to restore the shift crew compost.

tion to within the minimum requirements of Table 6.2.21. 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 0PERATIONAL CONDITION 1 2 or 3. an individual Shift Technical Advisor) with a valid Ienfor Operator license (other than shall be the desij.

cat'e d to assume the control room command function. During any absence of tse Nuclear Shift Supervisor from the control room while the unit is in OPERATIONAL CONDITION 4 or 5. an individual with a valid senior Operator license or Operator license shall be designated to assume the control room consnand function.

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. The G shall nctic o exa e unit oper ng th eteris s, ssua s .1.idu adv tes, ensee Even" eport ad oth sources la design oper g exp ence info son, udin nts of si r desig hich y indi e areas f sprov unit s ty.

A PO$1T1 6.1.SI T 15EG 11 be com ed of least ft dedicated f . time en ineer oca schelor' erin or

're at; scienc[td'onsite and at It twoeJan rs profess with enal egree level in a engrience !n hjs/-

ft 14 at least one ypa of wi}. experier M shall be in a nuclear f Td.

A ESPONS181LITIES 5.2.3.3 1 be resp ble for ma inin s e Isace of up -

"activitie,T,heiSEG kh s to prov de independeht verificatio,ian*thatkhe[u activities fe l parfarined cor.rectly and th tiuman error ' ire reduced 1 much as pa tical. '

{UTHORITY" 6.2.1.4 The 15EG.S all make tailed r connendat sf revisc 'r"oceduces[

eqbipment modif4 cations, i tenance a j d ties, ons atti itiesJer other meanspf improvinpnit safety to/the Vice PrMident Ngclear Epg1neering and services. - _

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I 6.2.4 SHIFT TECHk! Cat ADV150R 6.2.4.1 The Shift Technical A(visor shall provide advisory technical support to the Nuclear $hift Supervisor in the artas of thermal hydravites, 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 engineerin discipline and shall have received specific training in the response and anal sis of the unit for transients and accidents, and in ur.it fesign and layout nelu cen'cols in the control room. ding the capabilities of instrumentation and .

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• N ,

FERK! *Ut:1T 2 6-6 Amendment No. II,1/.s. 54

ADMIN 1STRAT1VE CONTROLS 6.3 UNIT STAFF OUALIFICATIONS f 6.3.1 Each member of the unit staff shall meet or exceed the minimum l qualifications of ANSI N18.1-1971 for comparable positions, except for the l l Superintendent - Radiation Protection

• or his designee who shall meet or exceed '

the cualifications of Regulatory Guide 1.8, September 19752 i

NIETEl> {

a

~

6.4 3RDf(MV 1)GLET* ED \

'/'/ u a in g d ce n aini o m t r io o t Di ec r, uc ar' i g sh mee r ui m ts d e nda o o Se ion of N18 f d (re n

/

/nd / .'f A f t 5 n he up e nt 2, 86 N 1t -

se ns o su of he ar s 1 e de ia z io wi r ev s y e /

i 6.5 IREffD/MFAMDIT 10

' NLEYE~ p

/

4Mt' //

T a fn to t vi th Pa n er on al m r d c fe s s ed n5 i o 6. .I ,

e l $ '. .

P O

/ e SR ai al be n Ma g a e m e s'ni al b I p nt an e n r pre e a ve 1.

ed of a u 6 u not e h i e nc , l oe s ons i e i lu t t nal ar as : per t ,

/

o, gi er g h cal s or a qu iy ss a ce 1 r i i s

p 1

c p nte i w n by e SR Ch irm . T al fi at ns of ,

e e qu em ts re o n ti ns f l c 05 m rs 1 e o e d e S ti .2 r 4. of N .- 7.

E AT

/ T Ca a es na i wr ing the mb s o ay er e a th ,

t na s yb des n ed or p if 0 RO i ha ma t ,

rn es all ar rcishatIb as t 9 mb rs' n0 0 e or t n w al a 01 ed in rit ng All alt nat me ti i y n ti e. .

e S C ai .

I All requirements of l

• An alternative title may be designated for this position. l these Technical Specifications apply to the position with the alternative title as I l

apply with the specified title. Alternative titles shall be specified in the l l

' Updated Final Safety Analysis Report.

6-7 Amendment No. JJ, 77, 55 l FERMI - UNIT 2 101 l

i ADM1Nif11ativt towt90ts 3 I

.. s Mfft1NC ENCY ,

ast once pe alendar month and as convened by 6 . 4 The 05 shall oest at 0$R0 Cha an er a Vice irman. .

BU0tDN 4 .1.5 The quer of the CSR etessary for th rformance o'f the 05R0 gesponsibility d authorit revisions of th echnical specifications shall Chairsan e ice Chairman a our members including alternates. [

consist of ttt90Nt131t1Titt 6 The 05 shall be res . ible for:

s. Re w of all Fla Administrative cedures and ges thereto; l

proposed tests experiments t affect n6cle afety

b. eview of al

• Review all proposed nges to Appe A Technical ificationst Rey w of all prop ed changes or difications t it systems or

d. sty; -

utpment that f ect abclear j e Review of a safety eval igns for n"e recedures and'ch es thereto {d '

i comple under the pr, sfont of 10 Mio.53;

!> f .

Inve igation of violations a Techn.ical 5,e fications, in ding l f.

- he preparation > d forwarding reports cover evaluation and

= l

! recomendationf to prevent C rrence,Saf tt Review Group,to th$rsensor Vice Nuclear G tion and Nuclear ,-

) . .

i g. Ravi all REPORT EVENTS:

Trations to dp ect potential h t ds to nucles afetys

h. Re w of unit

. Investigatto or analyse nd te orts l l t. erformanc pecial thereon requeste a Plant Manage Ifr the Nuclea . afety Rt few l Group

• sw of the . urity Plans l J. Je

k. Review of de Emergency F1 .

.XO ,

i l . . .

j .

8*8 A** " d** "* "'

• N ' *1 ftRK! - tmIT 1 i

l I

[ .* *

. 10 MIN 15TRaTIVE CONTR0t$ _

r_ = - . iL r.. ; =.,

l Rev try atite re Aase of radioactive agtefill to the vi inclu 7the prepara and fe afding of ris covering e at ation comendation a dispo n of t errective action to l revent currence to Senior V resid - Nuclear s' ration'.and' i

to uclear 5 t Review G and

a. eview of DCE55 C OL PROG he OFJF M DOSE CALCULAJM@i MANUAL.ges n5 major a to(cations th3 the Ra vnte Treatment j Systjat. .

/

l a. eview of a Fire Pr tion P .

J.4.1.7 Th .45RO ahall'

a. ecomend n writing o the Phn Manager approval' or disapproval of items considefed under-S~pecific sn 6.5.1.6a. throug'h d. pr pr'to their j 1ementat on!

1 i

Rende temin3ti s in writing he Nuclea Safn* r 7eview Gr3u tth

regafd to whether or not each 4t'em considef"ed under decific3141In -

l l . . '5.1.6a. firough f. consptutes an n(iviewed safety qu tTon.

tion I . . Prov(fe written apt 4

) (esidenttietween - Nuclear tjetSR0 Generettid.ithin and the Nuclear 4 fet14 hours to fhaienior Vi and the Plan 14anager;y Review Plant

. disagream howev'Jr ie Manag all havipeiponsibility for "clution of such'5(sagreements

! tid pur t to 5 .ification 5.1.1.

4 pfCORDV

! 6).t t The 0)R shall maintaja4rritten minu of each DSR meeting that, at a 1vities l

i Minimum, doJument the resv}ts'of all Copies'shall ations. 05RO.,atif,f be erespo

! provi e6 to the Senior"Vice Fra dent - Nuclear 1Ientration#pnd the Nucleft Safety Re w Group. _

! 6.5.7 WUttf AR SUETY.Jt 1EW CROUP R 1RC) '

/*

j FuwtTION .

! 4uncticathe vide to argar'ois ependent rey aw and audit of dt.1 natefactivities The1SRG shal)in -

desig/ Nucleac4iiwer plan pirati

! Nuclear engineerJn . .-

i c. Jh'e'mistry radi c si ry. . /'.

! d./ Neta11urgy 4 ,4,,-

. e; Instrument tion,a control. .

1 - T- ~ f. Radio 1'ogical entrols. -

I j g. Eechanica nd electrical and ssurance prac es. gineering,/,

{ [' *, 4.fQuallt '

advise the Sen'ior Yde President ' clear is Qeration1 report on tothose areas of responsibility in Spec 1

The NSRG s l

j TERK! - UNIT g 69 faendment No. JJ. JJ. ff. JJ

) 101 1

- ~~ -

ADMINISTRATTVE CONTR0t$

f [COMPD51I15 ice p dent - Nu Gener n shall a t at 1sant nine ]

I 5.5.2. e sen abership airman I at least memb stoth RG an all desi rom t possess pariance and Vice irman The me ,p sha collective orpete to vide inde av and a in th reas listed in all hay clear background in

! 5ect 6.5.2 . The Ch an and e Chairst when to call in expe.rts

{ operati and s be capab1 deterat

c eart

s. All ers shall have at assi he NSRG view tax pro l

i bache r's degr in enti ring er ated s nimum cesofor 3

.at leastM.Jerst years htl1 be ears of nuclear

• a res nsible r plant 4rperienc which

.s of professional i

expertenef. The truan shal ave at least 10

! j r 31 the pow teld and each o e other members shall

! level gement/fperience trience in ene or M of i hav sist # years of mulative s fassional level the telds fated in se ' ton 6.5 1.

l ALTftNaTt3 appointed in ing by the N5RG Chairma o

6. .3 11 alter members shall wo alternates shall par ici e serve e, temp basiss howeye no more pp ing in NSRG act rTttes at any time.

a CONSULT a NSRG Chairman to provide

$J. 4 Consulp s shall be ut ited as iletermined expert advic ;to the NSRG.

a MEET 1HrAttOUEHtY st once per 6 mont .

5 The NS G shall meet at

\

com

" for the performance of the.MSR6 view and 5.5.2.6 The que -of the NSRG necessa these Technica1'3pecifications shall consist 4f the Chattuan or a'udit fuection his design t3 t15 alternate and.at'least one half of Af the9heremahlhg quorumNSRG shall havemembers line of who K5 acre than a minorit two mayebe alternates.j~ tion of the unit. -.

resp rJibility for o era .

WIN 5.5.1.y NSRG shall be pensibla for the revia f 6.5.t.7.a and shall review '

5.5,2.7.6 through is .

pment,ision facilities of-IV

a. The si et evaluations for p)xp'tian!es to procedurekr er sys ams and ( tetts:4t e erim nts completeA e prov

$ hat such actions did,no orFstitute an unre fewed' safety CFR 50.59 to vert '

guestions 4 s stems which involve an

- b. Proposed chan es to procedures *, equipment, 50.59s .

gravi'twed sa ety question as defined in 10

-3 6 10 A,.4ndment No. JJ. 77. JJ. JJ FDDG - tEIT 2 tot

~

ADMINISTRATIVE CONTROLS .

REVIEW (Co M )

~

l c. ropose ests or e eriant quest ich invol an unreview safety as defin in 10 r 0.59;

d. P posed ch nical Spe icense; es to T ications or is Opera ng

e. Violat ns of c s, regulat s, orders, Tect lice e requir cal Speci cations, ha ng nucle nts, or internal pro ures or structions safety s ificance;

f. ignific t operati abnormalities deviatio from normal d expect perform e of unit equi t that af et nuclear s ety; Al REPORTAB EVENTS;

h. 11 reco zed indications an unan ipated defi aspect ency in some design or operat n of stru ures, syste , or components that uld affect nucle safety; d

1. Re rts and meeting nutes of e 0$RO.

DITS 6.5.2.8 udits of unit a ivities s 11 be perfo d under the cog zance of the NSRG. hese audits sh i encomp  :

a. Theco rmance o n t operati to provisions ntained with ~ the  !

Tech cal Spect cat ons and pplicable lice e conditi~ns- o '

b. T e perform ce, trainin and qualific ions of the tire unit '

taff; I

The re its of act ns taken to rrect deficie es occurrin in unit quipment, ructures, sy ems, or metho of operatio that I I aff ct nuclear faty; k d. he perform ce of activ tes required b the Operati al Quality Assurance rogram to et the criter a of Appen B, 10 CF Part 50-g

e. The re protect n programmatic c trols includ g the imple nting I pr edures by ualified license QA personnel-

f. he fire otection equipme and program plementati , utilizing I l(

either qualified offsi licensee. fir rotection ngineer(s)or !

an o ide independen fire protecti consulta . An outside ind endent fire pratiction consult ' hall be tilized at least-s

_ ev ry third yen I

i FERMI - UNIT 2 6-11 Amendment No. 104 l

l ADMINISTRAT E CONTROLS x

. AUDIJ[(C inued I

g. An ther a un oper on cons are ppropr o' by t NS nior e resid t-N ear G ati .

r e l T ra ologi env onmenta n ring pr ram an er uits ereof-

f

. he 0 ITE E CALC TI MANUAL d imple tin roc es;

)

.1 he CESS T PROG nd imp nti proc ures proce '

p ng and l l aging r loactive astes; d

, k. The fo ance of iviti requi d by e Qua y Assur ce Progr to i a t provisi of R ulator Guld .21, evision , June 1 and

] egu ory Guld 4.1, R ision , Apri 975. '

RE DS l S. . Recor of N activ its s 1 be repared, pproved, nd distrib ed s

! in cated w:

a. inut of each SRG m ing all be p pared, a roved, a fo arded  :

1

, th iorVi Presi nt - clear Ge ration w hin 14 da fo owing th j ing.

s i

b. Report of re ws e ompassed y Specif ation 6 . 7 all be re red appr ed. a forw ded to Senior ce Pres ent Nuclear e rat n I w in 14 ays f lowing c letion the rev w.

c. Audi eport encompas d by Spe fication .5.2. shall fo rde to he l Se or Vi Presiden - Nucle Generat n an to the nag ent s ton I sponsi e for t areas dited w in 3 days a er mple on f e audit y the a ting or ization

6. TEC' ICAL REV W AND C TROL T1V1 S

.1 P cedures quired y Tec cal S cifi tion 6 , nd her oced es ch af et plant uclear afety det ined y the a M ger, nd nges prepar by a ali.fi indiv ual/o an at n.

(heret , shall b -

N ~

FERMI - UNIT 2 6-12 Amendment No. JJ. H 1D1,104

. 1 I

ADW NISTRATIVE CONTR0tS rg

.TumfEdu l

6 . E oc ure r pr ch ge re red i acc an wt 6 .3.1 a no av ewe in a rd ce th oc on 6. 1.5 all i ed f l n 1 q y aq if di iv un other a he i tv1 al hat l ed e e re ch ge er o. ach ch view hal in ud's 6 at of et o no d to 1, e s- cip1 ary v is

' ec at If een ne ss , uc view s 11 pe me by rsonn of t ap pr ed cip ne

6. . 3 ac ro ur to tre by 5 if ion .S. .h t ug j, or anges are ,s 1I ew by he $ ri nden a tion to etion his 1 l de ne T Env o nta Progr Co ina r* 11 i any ses

6. 1. T se pe ormed n su of r la ddit n ria ng 1ews y '

i to os q ed i 6. . 2 ve.  !

AT EV ATI S

. W quir by CFR . .&s ety valu on tr et in e r o ta un vie saf y su ti is i olv sha ei u i e view ,

rsu t 10 50. . NR ap oval it s in , vin nr few sa y I que ton sha be sine pr r to pr 1 of he pr ed a pr du ng -

LIF1 10N ,

/ .

6 .5 divid perf in he view and al ti s in eco anc wi l

jM.:- Sect

.3.2 s 4.

hrou .

4.4 3.

ANS bov sha dee re se h ual 18 -197 for e r riat dis pli ce ns a

all be aber o the ant aff rev sly si d in it b nt nager i RE DS

3. Wr e e ds of ev s de un n e o ed i acc an em . . r gh 6. . . b .t udi r o en tio for ppr r i pp va , s 1 be rep ed nd ntai d 6 === =e ? = ~

f n et s ta for E AB S- g

. iss ott ed a epo  : it p s o e re s cti 50 3t 0 P ,a

. ac E T E NT al e vi d th a t t su s f t s vi sh b su tt t he RG th 5 o e e de -

en en t1 . . /

e y d gna is os o ,

r s of i

. p f tf sa y ep it n te 1 r t at f I ci edft1 a A er tiv ti es a bs e i g l

a y ay1 s .

j pf --

1 .

FERMI - UNIT 2 6-13 Amendment No. JJ. 75. JJ 101

~ -

. ADNTN15TRaT1vt covimots 5.7 1AFETY 11MIT V10LAT10N //blhet'Sec(c' 6N/M6[

6.7.1 The following actions shall be taken in the event a safety Limit is violated:

a. The NRC Operations Center hall be notified by telephone es soon es possible 1 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 Generation and the shall be notified within 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br />. ,

@p b. A safety Limit vi reytkwed by the n Report shall be prepared. The report shall be This report shall describe 1) applicable Re# .

circumstances pre the violation. (1) effects of the viol (ation upon unit 07 components, systems, er structures, and (3) corrective action taken to prevent recurrence.

c. The safety Limit Violation Report shall be submitted to the Comission, 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 -

C mission.

6.8 PRottDURES AND PROGRAMS 6.8.1 Written procedures shall be estab1tshe6 implemented, and maintained covering 3 the activities referenced below: /

-i

')

a. The applicable pbcedures r/ecomended in Appendix A of Regulator Revision 1. February 1978. .

6. The applicable procedures required to implement the Fermi 2 comitments made in response to the requirements of NUREG.0737. .

c. Refueling operations.

d. surveillance and test activities of safety related equipment.

F DWTe 0 . , a ~ h l

. . a. tW,%. srgs spenvn y... J

9. UE$ T$l-MA;d. :..

g. Fire Protection Program implementation. , ,

b. FRDCE55 CONTROL PROGRAM implementation.

1. OFF51TE D05E CALCULATION MANUAL {mplementation. , .

using

& ,1 Quality Assurance Frogram for effluent and environmental monitoring,latory the guidance in Regulatory Guide 1.11 Revision 1. June 1974 and Regu Guide 4.1, Revision 1. April 1975.

6 14 Amendment No. 11 77

.' TERMI - UNIT 2 101

1 l

.# ADMIN 15TUTfVE C0WTRots

~

ppottetters4WDpeocuMS(Continued) nt n a her chplanEr'oNa d pecif ion 6 .. ether an l ads tr ve ce res. cha  : the . sh a revie in 1 4 rd ce w . .3 appr d by Plan nager p te i

mp . ant a ds be fewe riod y there er as s rt a int at pr vre The P at Man r may del ate appre ity procedures to_a management represen tive Qinewri.i.ng or s cific ypes I

.- 5 sa. .6. sonetional 5.8.4[mphrhh nkekjto, proc dure 4f Spe kits n8.8.[may'bem'ade iprovid : / ,

/ 1

. e ate any jo 13 ori 4 app, ve y oc a me e-

,/ ,erge ers of, he unit manage $y-

. e ent 1 sta Aeast ne f a h Ms a 5 (for 0 etator icense /

/,and i

c Th e ang is cv nted and viewed ad a ed act dcnc/e jwity'ei er .8. orJtt.3a ve, a)4ppropr.pt14te, y( hin 4 days of im $ men ati /

. l

. /

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

8. primary teclant Sources outside Centainment .

A program to reduce leakage from those po'rtions 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 MPCI, CS, RHR, RCIC, reactor water samp1(ag, containment sampling, reactor water cleanup, combustible gas control, control rod drive discharge headers, and standby gas -

treatment systems. The progran shall include the following: .

1. Preventive maintenance and periodic visual inspection requirements, and

3. Integrated leak test requireme'nts for each system at refuelino Ivets intervals er less.

JELETE)

b. h@1Mt hadMw MtAstr ,

~

ra h a e e c pdf acc at e i ne l l t at o{f I cp tfat',a 1 it at u r ci at j

/* cond ion {. I p 9 shalN in ud , he ilo ngs f FERMI UNIT 2 6 15 Arnendment No. JJ. JJ. 91

. ADMINISTR&TIVE CONTROL 5

~

PR0tfDUtt'$ AND PROGRAMS (Continued) d r MLETED .

lift dont.

l C. Fest.necident tameline A program which will ensure the capability to obtain and analyze reactor coolant, radioactive iodines and particulates in plant gaseous affluents and sentainment atmosphere samples under accident conditions.

The program shalt include the following: ,

1. Training of personnel.

2. Procedures for sampling and analysis, and .

3. Provisions for maintenance of sampling and analysis equipment. 4 l

i g. Mieh Bensity teent Fuel Raeks .

1 l

! A program which will assure that any unanticipated degradation of

! the high density spent fuel racks will be detected and will not j compromise the integrity of the racks.

e. Radienettve Emuent Centrols preeram .

1

! A program shall be provided conforming with 10 CFR 30.36a for the i control of radioactiv.i effluents and for maintaining the doses to

! ttEMBERS OF THE PU8LIC from radioactive effluents as low as j reasonably achievable. The prosram ODCM, shall inc (t)lude remedial s taken actions whenever the toprogram b'perating e limits are exceeded. The program shall' include the following i

i elements:

1 i 1) Limitations on the operability of radienttive liquid and

' gaseous monitoring instrumentation including surveillance tests

} and setpoint deterstantion in accordance with the methodology in the CDCN. .

3) Limitations on the concentrations of radioactive asterial released in liquid affluents to UNRESTRICTED AREAS conforming l to ten times the concentration values in 10 CFR Part 10.1001..

10.1402. Appendix 8. Table 2. Column 2.

3) Monitoring,luents in accordance with 10 CFR 10.1301 and withsampling, caseous eff l 1 & {he methodology and parameters in the 00CN. .

j"~

]

l FERMI UNIT 1 .

5-15 Amendment No. J.11. JJ. JJ. SP j .

No Cknge so thispage.

Providedforhtformation cnly.

l l1 -

l. ADM1W1tinaT1vt toute011

} PeettDURttANDpeccaAMs(Continued)

Limitations on the annual and quarterly doses or dost #

' 4)

!~

• comitment to a MEM8ER OF THE PUBLIC free radioactive materials in liquid effluents releaspd from each unit to UNRESTRICTED j AREA 5 conforming to Appendix ! to le CFR Part 80 i .

5) Determination of cumulative and orojected dose contributtons

! from radienctive effluents for the current calendar quarter and current calendar year in accordance with the methodology and j parameters in the CDCN at least every 31 days, l 4). Liettations 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 Appendia I to 10 CFR Part j 50

7) Limitations on the dose rate resulting from radioactive

• material released in gaseous affluents from the site to areas et or beyond the $1TE SOUNDARY to the following: .

a. For noble gases: 1ess than or equal to 500 mram/yr to the total body any less than or equal to 3000 aree/yr to the sMn and i

b. for fodine 131. for fodine 133. for tritium, and for all

. radionuclides in particulate ' form with half lives greater than 8 days: less than or equal to 1500 ares /yr to any organ.

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

g) Limitations on the annual and quarterly doses to a MEMBER OF i THE PUBLIC from fodine-131. Iodine-133 tritium and all radionuclides in particulate form with half lives creater than 8 days in gaseous affluents released from each unit to areas beyond the SITE BOUNDARY conforming to Appendix I 1610 CFR Part 50 ,

10) Limitations on venting and purging of the Mark I containment throvnh the Standby Cas Treatment System er the Reactor

-. BuildLag Ventilation System to mainttin releases as low as

- 1<,2 reasonably achievable. . . .: . -

~

II) CF THE PUBLIC due to releases of

• radioactivity and to radiati

. from uranium fuel cycle sources conforming to 40 CFR Part 190.

FERMI - UNIT 2 6-18a Amendment No. M. 33

8 l

ADMIN 15TRATIVE CONTROLS

/

i PROCEDURES AND PROGRAMS (Continued)

A/ '

f. Radiole6icaY EMfirsdmental MonitorIaIro[am J)fM //

a h men he /diat n /

r o I s t yn ir of plan . T prog' ram hal //

sr d 1 ep s ntati s ement fr oactivi in //

j g t te a exp r a ways, nd(J)verift to f e /

a u yo tF eff e no torin prog a and eli o

! t on e

t nt 0 ex ur pa ways.

) co orm The ograin s the'gui ne of 1 )

pe x

[

/

/

l to P 5 , an (3) clu th foll i : /

\

it ing, amp g, alys s, d po n f lati

// /

1) nd adio cli si h m i ac da e wi th //

! m hod ogy dp amers[e 4nvir 0 t , /

/

) A nd eC sus o en r tha ch ges n th o a s//

an bey dt SIT B NDA a i ntif n //

mo ic ons ot ito n ro am a i e r /f th resy s t 's ce u,a , /f

/ gr

/4 1 3 P i ati i an t la rat o ar o t /

ns et dep ck o pr a ur j

/

j l

f o th ny onm t ea re n s p ma ad c

v m e o al s rt 7%

/,/

l %jh it a ur c ro a o e n n i f/ '

6.9 REPORTING REOUIREMENTS j -

ROUTINE REPORTS .

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

! STARTUP REPORT 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 i supplier, and (4) modifications that may have significantly altered the I nuclear, thermal, or hydraulic performance of the unit.

6.9.1.2 The startup report shall address each of the tests identified in 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 ccrrective actions that were required to 6-16b Amendment No. 82

! FERMI - UNIT 2

l i

l I

I l . .

i 1

i

! 6.8.6 Administrative controls shall be developed and implemented to limit the working hours of personnel who perform safety-related functions (e.g., senior j reactor operators, reactor operators, auxiliary operators, health physicists, i

and key maintenance personnel). The controls shall include guidelines on working hours that ensure that adequate shift coverage is maintained without i

routine heavy use c.f overtime for individuals.

i Any deviation from the working hour guidelines shall be authorized in advance l

by the Plant Manager or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting i

the deviation. . Controls shall be included in the procedures such that i

individual overtime shall be reviewed monthly by the Plant Manager or his j detignee to ensure that excessive hours have not been assigned. Routine j deviation Yrom the above guideljnes shall not be authorized.

l i

i i l 1

1 i

l 1 -

I i . .

4 h .

l .

No Change to thispage. .

ProvidedforWonnation only.

{[ -

ADM1W15ttaTfvt t0HTR0t5 l ITARTUP RfPbRT (Continued) obtain satisfactory operation shall also be described. Any additional specific details required in license conditions based on other connitaants shall be included in this report. ~

1 6.9.1.3 templetion Startup reports of the startup testshall be submitted program. (t) 90 days )within (followine 90 days following resumption

- comencement of comercial power operation or (3) 9 months following initial criticality, whichever is earliest. If the startup report does not cover all 1 three resumptionevents or (i.e.. initial criticalityl comencement of comercia completion operationofsupplementary startup test program, and reports shall be su mmitted at least every 3 months untti all thre)e events have been compl AWWat REPORTE 5.9.1.4 Annual reports covering the activities of the unit as' described below 4

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

The initial report shall be submitted prior to March I of the year following ~

initial criticality.

6.9.1.5 Reports required on an annual basis shall include:

i .

a. A tabulation on an annva) basis of the number of plant ett11ty and .

other personnel (including contractors). for whom monitoring was l required, receiving exp6sures greater than 100 arems/yr and their l associated man.res exposure accordine to work and job functions.*

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

routine maintenance, special maintenance (describe maintenance] wasta i

processing and refueling). The dose assignments to various duty functions may be estimated based on oocket or thermoluminescent -

dosimeters (TLD5 dosimeters or film badge measurements. Small exposures tota 1 Ling less than 30% of the individuni 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 j specific major work functions and

6. Documentation of all challenges to main steam line safety /relfaf valves, and

c. A sumary of ECCS outage data including:

3. ECCf outage dates and duration of outages.

2. Cause of each ECCf outage ,,

i 3. ECCS systems and componenIs in,the ou,tage, and l 4. Corrective action taken.

g.

The reports analysis shallthe in which also (nelude the results of :kecific activity i .- . specification 3.4.5. primary coolant exceeded ha limits ofThe following j AThis tabulation supplements the requirements of $20.2206 of 10 CFR Part 20. [

ftRMI - UNIT g 6 17 knendment No. JJ. 83 i --_

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,. ADu!N11TeTiVECONTeots ANWUAt RtPORTS (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 exceededi .

(1) results of the l'ast isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after

~

the radicindir.e activity was reduced to less than limit i (each result should include date and time of stapling and j . theradiotodineconcentrations): ,

(3) clean.up first sampsfe in which the limit was exceededstem flow history starting 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />

, . (4) graph of the 1131 and one other radiciodine isctope 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 i coolant exceeded the radiotodine limit. i j MONTWtY OPEtaTING REPORTS , l 6.9.1.5 Routine reports of operating statistics and shutdown experience shall be subattted on a monthly basis to th Director, Office of Resource g Management. U.S. Nuclear Regulatory C) omission. Washinrton. D.C. 20555, J w

, copy to the Regional Administrator of the Regional Offtce of the NRC. no later than the 15th of each month following the calendar month covered by the *

report. .

**??Jat rad 10l001C11 ENVIR0fMENTAL OPEtaTING REPORT .

l 6.9.1.7 The Annual Radiological Environmental OperatOg Report covering the i operation of the unit during the previous calendar year shall be subattted before May 1 of each year. The report shall include sumaries.

interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The mater < al provided shall be consistent with the objectives outlined in 1)the00CMand g 5 (1) Sections IV.S.I. IV.S.3, and IV.C of Appendix 1 to 10 CFR(Part I g r/ ANNUst RAD 10acT1VE EFFLUENT Rfttast REPORT d 8.9.1.5 The Annual Radienctive Effluent Release Report. covering the operation of m y unit a.the durin,g

__2_ . .. . . . the.

. . previous

• pfIt each months of operation year. The report shall beinclude shall submitted a i sumary of the guantities of radioactive liquid and gaseous affluents and solid waste released from the unit. The material 1rovided shall be f t) da i

'47 consistent conformance withwiththe10objectives CFR 50.36aoutlined in theIV.S.T and Section CDt1 of and PCP and Appkndix 1 to(t)10 CFR Part

. 50.

] ..

FERMI - UNIT t 4 18 Amendment No. JJ. S.91

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FERxt - UNIT 2 6-10 menhment No. JJ. K/. 81

',* A0w.1N1titaT1vt contaott -

17t' etat trpoRTs l

8.g.t Special reports shall be subattted to the Regional Administrator of the

! Regional Office of the NRC within the time perled specified for each report, tett opttaffMc t1M1Tt ttpoRT l~

• 6.9.3 Selected cycle specific core o tratin limits shall be esta611shed and documented in the CORE OPERATING LIM 1!$ REPokT (C LRb before each relo l er any remaining part of a reload cycle. The ana Scal methods used to

. determine the core operating limits shall be those previously reviewed and approved by the NRC in General Electric Company reports NEDE 14011 p.A and NEDE 237851.PA7he core operating limits shall be determined so that all i

applicable 1tatts fuel thermal mechanical limitsu core thema1 j hydraulic limits. CCS e.g. limits, nuclear limits such as shutdown margin. and transient and accident anal sis limits) of the safety analysis are met. The COLR, including any mid cyc e revisions or supplement thereto, shall be I submitted upon issuance to the NRC Document Control Desk, with copies to the l Regional Administrator and Resident Intpector prior to use.

I i.10 ftt(OWWEW1W U i r .f f// J j ad tion ot app 1 ble acer aten on re,RtHremefits of Title

. e of ede R ati .t fo1 ing r rds all 's r tained for i

1 e imu eri ind ted 0 7 lowi s sb be r aine o en E ye a:

l . eco d a ogs unit era cov' n me i erval t each

powe .

I

. e sa os3 pri nt nce ac vitte , inspej: ons, air d re Hcem at ofpal p he m)t il ite 'of a f'pment r Tated to ave a sa . .

i L1. R TABLE. VENTS f f rye activif es, pecti . and c 1 rations' l

Resquirdsd 'by th a andcical pecif c tions.

R rds o cha e r.ade

.8.1.

th . recedu required y S 1 (ca [ i

' l Re rds o taled urc nd fissi n detet teak ts a d sults /d-l

g. ds of val p stea) aventofy f all ge ed sg rce material

. h.- Re$ecord ef )l ' ,

TERMI - UNIT 2 6 11 Amendment No. JJ. ff. $7, g3 I

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ADMtwisitstivt cowinois l . fs.ie efFAD etTrg3+04 . f2enheued) 3 foi g records be retained f satre' duration of the unit

[, Oper ng Li se: ,

3

!' Records an swing thang aflecting vn sign modific n the F.nn) y Analysis t[

made t stems and a ment describ Re . .

l 1

l 6 Records of and irradt fuel invento , fuel transfers. and j assemb1 rnup histo . .

! c. rds of dos actived by al dividuals for,whos ' oring was '

equired. -

1

! d. Rece of gaseous iguid radienttive ertal released to the i j en ons. ,

l o. ecords of ansient er opera 1 tycles for those components identif

~

! in Table 5.7.1 l

l f. R res of reactor is and experine f Records of ning and quali on for curren of the unit sta .

I h. Rac1 of inser aspections perf pursuant to these

! /%chnical spec f ations.' -

1. Records quality as  ; ctivities required by t nal ,

i Qual y'AssuranceManhs )

,1.

• ecords of r v4f . e to procedures or

eeutoment rf reed fo'r thanhtments .xp pursuant to 10 CTV freviews of' test.s an m.ig .

j l k. K cords of meetin 0$RO and the NSRG.

! Records of the ice lives of all aulic and mechanical snubters ref;iuired by Specificat . 5 including the d Wifw/- hich the sedice life commence .ans associated install and r.afn~Gnance records.

]

al ses required by the o i Records tonitori g dof ah6eram that would evalva!tealenviron 1on of the acy of the anptysis at a late'r date is should includt g(6 edures

! [ e(fattive at specified recedures were fell .

e s and QA records ng that thess er..-

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! a. Records of re.v1 ws perferned for les to the CFFS

. CALCULATI W EANUAL and PROCESSTRO. PROGRAM.

.g e. Re s of radioactive a ments. .

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1, ftml - UNIT g Amendment No. JJ. Jf. JJ 83 - ) ,

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ADMINISTRATIVE CONTROLS

• i 6.11' '/ <NPA6fMtHiddd.-

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8.12 HICH RADIATION AREA

! 6.12.1 '

i paragraphIn lieu of the 'contro1 ~ device

• or 'alars signal" required by

20.1601 of 10 CFR Part to, each high radiation area in which the j

intensity of radiation is greater than 100 arer l shall be barricaded and conspicuously posted as/hr but less a high than 1000 radiation arem/hr area and

entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the followingi i

-) , /

l

' Radiation protection personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement during the l performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas. ,

.)

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

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. 4 FIRMI - UNIT t t 6 126 . * " Amendment No. f*

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[ . ADMINISTRATIVE CONTROLS HIGHRADIATIONAREA(Continued) ,.

1 4 a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the radiation dose rate in the area and alams when a preset integrated '

dose is received. Entry into such areas with this monitoring device may be made after the dose rate' levels in the area have been

, established and personnel have been made knowledgeable of them.

4 c. A radiation protection qualified individual (i.e., qualified in 1 i radiation protection procedures) with a radiation dose rate 1

monitoring device who is res >onsible for >roviding positive control over the activities within tie area and stall perform periodic radiation surveillance at the frequency specified by the Radiation i l Protection Supervisor ** in the RWP.

! 6.12,2 In addition to the requirements of Specification 6.12.1, areas l

! accessible to individuals with radiation levels such that an individual could l receive in I hour a dose equivalent greater than 1000 mrems but less than 500 l l rads at one meter from sources of radioactivity shall be provided with locked l  !

doors to prevent unauthorized entry, and the keys shall be maintained under l 4 the administrative control of the Nuclear Shift Supervisor on duty and/or the '

radiation protection supervision. Doors shall remain locked except during l l periods of access by individuals under an approved RWP which shall specify the l l j dose rate levels in the immediate work area and the maximum allowable stay I i time for individuals in that area. For individual areas accessible to i l

individuals with radiation levels such that a major portion of the i i i individual's body could receive in I hour a dose in excess of 1000 arems* but l I

! less than 500 rads at one meter from sources of radioactivity that are located l i within large areas, such as the containment, where no enclosure exists for i purposes of l'ocking, and no enclosure can be reasonably constructed around the ,

! individual areas, then that area shall be roped off, conspicuously posted, and j a flashing light shall be activated as a warning device. In lieu of the stay 1 i time specification of the RWP, continuous surveillance, direct or remote (such

! as use of closed circuit TV cameras) may be made by personnel qualified in i radiation protection procedures to provide positive exposure control over the j activities within the area. J 6.13 RRbC(SS'CDbWWGGWB4hCW .1kJA-rE' .D

//////

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p1(g fe',F[P f gall p

b6 r ed t ommis'sio,n r or i e ta o i p

. Chads P:

l/ ( Shal d ment a reco[d of e91e per o all i ret ed s re re y Sp6 on .10. .  ;

p/d ume att sh cogap)c(ic t

• Measurement made at 30 centimeters from source of radioactivity.  ;

• • 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.  ;

FERMI - UNIT 2 6-23 Amendment No. JJ, #2,93 l

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.: ADMIN 1sToativt towtRots E'N I OhiAOt' Mu A sn i ?[ 71 [ Con", I T.LT '". -- b 1 -

/ Su icle

, 1) ofo'rm o o su ort hechangetoejherwj,ththe j pro at,eFan ses r av unti sjust ying a ch tege(

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' ) de I i to the he e ge wl main in t av 11 c fff ae th solidi ed wa e pro et ti ris ng e ir n of ederal tate r et ap cab i s.

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N nd he pprova of the tant annen .

i-8.14 0FFstTr Dost cAttutAT10N MANUAL (00cm -

1 -

! 5.14.1 The ODCM shall be approved by the Coassission prior to implementation.

1 4.14.2 Changes to the ODCM: l

a. Shall be documented and records of reviews performed shall be i retained,62csnmuhdeg This s p ' documentation shall contain: ,

1

! 1) Sufficient information to support the change together with the j appropriate analyses or evaluations justifying the changes (s) and ,

! 2) A determination that the change will maintain the level of radioactive affluent control required by 10 CFR 20.1302, 40 CFR' l Part Igo,10 CFR 50.36a. and Appendix 1 to 10 CFR Part 50 and l

. not adversely impact the accuracy or reliability of affluent, dose, or setpoint (alculations.

6. * ' Shall become effective afterCi

! r -J-,1 ~ m. _ SS) l d29fEEEDapproval of the Plant Manager. -

c. Shall be submitted to the Commission.in the form of a complete, j legible copy of the entire CDCM as part of or concurrent with the Annual Radioactive Efluent Release Report for the

! period of the report in wsich any chance to the CDCM was r 's. -

Each change shall be identified by marungs in the margin '

i the affected pages, clearly indicating the area of the pt that was changed, and shall indicate the date (e.g.,

month / year)thechangewasimplemented.

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TERMI - UNIT 2 6 24 . Amendment No. JJ. M. M,g3,,,

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ADMINISTRATIVE CONTROLS i .

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FERMI - UNIT 2 6 15 Amendment No. fl. 32

4 INEX ADMINISTRATIVE CONTROLS SECTION PAGE 6.1 RESPONSIBILITY........................................... 6-1 6.2 ORGANIZATION............................................. 6-1 6.2.1 0FFSITE AND ONSITE ORGANIZATIONS.................. 6-1 6.2.2 UNIT STAFF........................................ 6-1 6.2.3 DELETED........................................... 6-6 l 6.2.4 SHIFT TECHNICAL ADVIS0R........................... 6-6 6.3 UNIT STAFF 0VALIFICATIONS............................... 6-7 6.4 DELETED.................................................. 6-7  !

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

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FERMI - UNIT 2 xix Amendment No. E/,

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-ADMINISTRATIVE CONTROLS SECTION PEE 6.6 DELETED................................................... 6-13 l 6.7 SAFETY-LIMIT VIOLATION..................................... 6-14

-6.8 PROCEDURES'AND PR0 GRAMS.................................... 6-14 6.9 REPORTING REQUIREMENTS..................................... 6-16b 6.9.1 ROUTINE REP 0RTS..................................... 6-16b STARTUP REP 0RT...................................... 6-16b 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 f 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 HIGH RADIATION AREA....................................... 6-22a 6.13 DELETED 6-23 j 6.14 0FFSITE DOSE CALCULATION MANUAL........................... 6-24 FERMI - UNIT 2 xx Amendment No. JJ, $f, SJ, JJ,

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

OFF-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.

OFFSITE DOSE CALCULATION MANUAL 1.24 The 0FFSITE DOSE CALCULATION MANUAL (0DCM) shall contain the methodology I and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring Alarm / Trip Setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also 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 Environmental Operating and Annual Radioactive Effluent Release Reports required by Specifications 6.9.1.7 and 6.9.1.8.

OPERABLE - OPERABILITY 1.2S 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, 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 capabit of performing their related support function (s).

OPERATIONAL CONDITION - CONDITION 1.26 An OPEPATIONAL 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.

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 B0UNDARY LEAKAGE 1.28 PRESSURE B0UNDARY LEAKAGE shall be leakage through a nonisolable fault in a reactor coolant system component body, pipe wall, or vessel wall.

PRIMARY 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 automatic isolation system, or FERMI - UNIT 2 1-4 Amendment No. E ,

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. PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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.

i 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 '

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. I 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 independent of the requirements stated in '

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

h. Functional Testina of Repaired and Replaced Snubbers  !

)

Snubbers which fail the visual inspection or the functional l test acceptance criteria shall be repaired or replaced. I Replacement 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 i 12 months before being installed in the unit.  ;

i. Snubber Seal Replacement 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 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 i exceeded during a period when the snubber is required to be OPERABLE. The parts replacements shall be documented and the i documentation shall be retained.

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

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ADMINISTRATIVE CONTROLS 6.2.2 ONIT 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 shall 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 Operator or licensed Senior Operator Limited to Fuel Handling who has no other concurrent responsibilities during this operation;

e. DELETED

f. DELETED 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.

• 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.

FERMI - UNIT 2 6-2 Amendment No. JJ, JE, M , g , JpJ J

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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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FERMI - UNIT 2 6-6 Amendment No. JJ, JS, Jf,

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. ADMINISTRATIVE CONTROLS 6.3 UNIT STAFF QUALIFICATIONS 6.3.1 Each member of the unit staff shall meet or exceed the minimum qualifications of ANSI N18.1-1971 for comparable positions, except for the Superintendent - Radiation Protection

• or his designee who shall meet or exceed the qualifications of Regulatory Guide 1.8, September 1975.

6.4 DELETED l 6.5 DELETED l l

• 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.

FERMI - UNIT 2 6-7 Amendment No. JJ, JS, Jf, JpJ

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FERMI - UNIT- 2 6-10 Amendment No. (J, JS, S . 5 , JSJ

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FERMI - UNIT 2 6-13 Amendment No. JJ, 79,5),

191,

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

a. The NRC Operations Center shall be notified by telephone as soon as possible and in all cases within I hour. 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 (OSRO). 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. i

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 J

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

g. Fire Protection Program implementation.

h. PROCESS CONTROL PROGRAM implementation.

1. 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 6-14 Amendment No. JJ, SJ, JSJ

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued) 6.8.2 DELETED 6.8.3 DELETED 6.8.4 DELETED 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:

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

FERMI - UNIT 2 6-15 Amendment No. JJ, JJ, SJ

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

c. Post-accident Samolino 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 A program which will assure that any unanticipated degradation of the high density apent 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 MEMBERS OF THE PUBLIC from radioactive effluents as low as reasonably achievable. The program'(1) shall be contained in the ODCM, (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 elenents:

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,

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 ODCM.

FERMI - UNIT 2 6-16 Amendment No. E, JJ, JS, SJ,JJ

ADMINISTRATIVE CONTROLS PROCEDURES AND PROGRAMS (Continued)

f. DELETED 6.8.6 Administrative contrnis shall be developed and implemented to limit the working hours of personnel who perform safety-related functions (e.g., senior reactor operators, reactor operators, auxiliary operators, health physicists, and key maintenance personnel). The controls shall include guidelines on working hours that ensure that adequate shift coverage is maintained without routine heavy use of overtime for individuals.

Any deviation from the working hour guidelines shall be authorized in advance by the Plant Manager or his designee, in accordance with approved administrative procedures, or by higher levels of management, in accordance with established procedures and with documentation of the basis for granting the deviation. Controls shall be included in the procedures such that  !

individual overtime shall be reviewed monthly by the Plant Manager or his designee to ensure that excessive hours have not been assigned. Routine l deviation from the above guidelines shall not be authorized. '

6.9 REPORTING RE0VIREMENTS ROUTINE REPORTS 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 Regional Administrator of the Regional Office of the NRC unless otherwise noted.

STARTUP REPORT I 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 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 FERMI - UNIT 2 6-16b Amendment No. EE

. 1 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 radioiodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the.radioiodine activity was reduced to less than limit 4 (each result should include date and time of sampling and  !

the radioiodine 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;  ;

(4) graph of the I-131 and one other radioiodine isotope 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 radiciodine limit. '

MONTHLY 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 Management, U.S. Nuclear Regulatory 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 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 Radiological 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 RADIOACTIVE 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, JJ

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-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 thermal-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 l

4 d

i FERMI - UNIT 2 6-21 Amendment No. JJ, Ef, E/, JJ

.- ADMINISTRATIVE CONTROLS 1

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THIS PAGE HAS BEEN DELETED l

- UNIT 2 6-22 Amendment No. JJ, M. Me N

. ADMINISTRATIVE CONTROLS 6.11 DELETED l 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20. 1601 of 10 CFR Part 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mrem /hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP)*. Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

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• Radiation Protection personnel or personnel escorted by radiation protection personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are otherwise following plant radiation protection procedures for entry into high radiation areas.

FERMI - UNIT 2 6-22a Amendment No. JJ, Jf, jl)

l I

. ADMINISTRATIVE CONTROLS HIGH RADIATION AREA (Continued)

a. A radiation monitoring device which continuously indicates the radiation dose rate in the area.

b. A radiation monitoring device which continuously integrates the  !

radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel have been made knowledgeable of them,

c. A radiation protection qualified individual (i.e., qualified in i radiation protection procedures) with a radiation dose rate l monitoring device who is responsible for providing positive control over the activities within the area and shall perform l periodic radiation surveillance at the frequency specified by the Radiation Protection Supervisor ** in the RWP.

6.12.2 In addition to the requirements of Specification 6.12.1, areas accessible to individuals with radiation levels such that an individual could '

receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose equivalent greater than 1000 mrems but less than 500  :

rads at one meter from sources of radioactivity shall be provided with locked doors to prevent unauthorized entry, and the keys shall be maintained under the administrative control of the Nuclear Shift Supervisor on duty and/or the radiation protection supervision. Doors shall remain locked except during .

periods of access by individuals under an approved RWP which shall specify the  !

dose rate levels in the immediate work area and the maximum allowable stay j time for individuals in that area. For individual areas accessible to  !

individuals with radiation levels such that a major portion of the individual's body could receive in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> a dose in excess of 1000 mrems* but less than 500 rads at one meter from sources of radioactivity that are located ,

within large areas, such as the containment, where no enclosure exists for l purposes of locking, and no enclosure can be reasonably constructed around the l individual areas, then that area shall be roped off, conspicuously posted, and i a flashing light shall be activated as a warning device. In lieu of the stay time specification of the RWP, continuous surveillance, direct or remote (such as use of closed circuit TV cameras) may be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

6.13 DELETED

• Measurement made at 30 centimeters from source of radioactivity.

• • 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.

FERMI - UNIT 2 6-23 Amendment No. JJ, EJ, 9)

- ADMINISTRATIVE CONTROLS l

6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 The ODCM 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

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 I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.

b. Shall become effective after approval of the Plant Manager. 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 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.

FERMI - UNIT 2 6-24 Amendment No. JJ, EJ, SJ, SJ

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