Text

Facility Tech Specs 3 & 4 Re Limiting Conditions for Operation & Surveillance Requirements,Respectively
	ML19326A126
Person / Time
Site:	Davis Besse
Issue date:	11/12/1975
From:	; TOLEDO EDISON CO.
To:	;
Shared Package
ML19326A125	List: ML19326A124; ML19326A126;
References
	NUDOCS 8002030003
	Download: ML19326A126 (33)
	v • d • e

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FROOF & liEViEW CUA 3/4.1 REACTIVITY CC:ITROL SYSTDIS g.y

'h 3 /4'.1.1 BORAT10:1 CD:tTROL m

:p S!!UT00'.l.l t!ARGI!!

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.,3 L1 tilt!::G CC::DIT10!! FOR OPERAT10tl 4f-

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Eih 3.1.1.1 The S!!UTD01ll1 MARGIrl shall be > 1% ak/k.

A APPLICASILITY: MODES 1, 2, 3, 4 and S.

4 4.-

ACTI0rt:

yO 13 MM s

M

/

liith the SHUTC.0'.!:1 MARGI!! < 1% ak/k, i=ediately initiate and continue boration ati

' gpm o f ( '

l J

required SliDIGC;;;;~MARGI:! is4 ppm boron, or'~itfequivalcrit

i r s t oi~e d '.-~~~ ~ ~ ' ~ ~ ~ ~ ~ ~ '

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y 9 7g SURVE!LLAt:CE REOUIREME!iTS 4.1.l'.l.i The Sl!UT00'.!!! MARGlii shall be deter:ainc;1 to be > 1% uk/k:

I When i.n MODES 1 or 2, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , by verifying a.

NU;i that control groups withdraual is within the limits of Specifi-l

.'d cation (3.1.3.6).

L.a.1 r

b.

Ilhen in MODES 3, 4 or 5, at least once per 24 hcurs by consideration of the : allowing factors:

9 1.

Reactor coolant system boron concentration, 2.

Control rod positinn, 3.

Reactor ccolant systc:. average temperature,

'fd.

4.

fuel burnup based on grcss thermal energy generation,

T;{j 5.

Xenon concentratica, and l

2 6.

Sam:.rium ccccentraticn.

.t c.

Imediately upon detection of an inmovable or untrippable inoparable centrol red, considering tne worth of the iiraovable or untrippable ir. operable control rod as well as assuaing that the single OFERACLE red of highest reactivity : orth is fully withdra.n.

dQd e;qg.q d.

Imediately upon detection of a meveable and assun'ed trippable v

"" I inoperable centrol rod, assuming that the single rod of highest reactivity t: Orth is fully withdrav,n.

e.

Prior to initial operation above 5", RATED Tl!ERMAL PC'!ER af ter q

each refcaling, with the control groups at the miniaum with-orwal limit of Specificatian (3.1.3.6).

l June 24,1975lut/-rs DAYlS-BESSE, U?;li 1 3/4 1-1 II v

800203000')

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PROOF & RtViEW COFY

$IE REACTIVITY CC:ITPCL SYSTEMS w

s 9

BORIC ACID PU. P - SHUTD0'ilii N3,h!

LIMITI!;G CO:DITIC:1 FOR OFERATIO!1

f.

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IV 3.1.2.6 At least one boric acid pump shall be OPERABLE and capable of being powered frca an OPERABLE essential bus if only the ficw path y'@".J.]

thrcugh the boric acid pump in Specification 3.1.2.la above, is CPERABLE.

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APPLICABILITY: MODES 5 and 6.

M ACTIOTO i

With no boric acid pump OPERABLE as required to ccanlete the flow path 1

of Specification 3.1.2.la, suspend all operations nyciving CORE ALTERATIC:iS

-$N ofej or positive reactivity changes until at least one boric acid pump is restored to CPEPABLE status.

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..c.:: 3 SURVEILLA:CE RECUIREMEilTS 4.1.2.6 One boric acid pump shall be deconstrated OPERABLE at least once per 7 days by:

.r....

c4 Starting (unless already operating) the pump frca the control M-M.k 4

a.

room.

^ t' l' b.

Verifying, that on-recir-cula-t4cn I' n, the pump develops a v;"-

D i.? ~5 c

a c ( c. - ' c:; n preuwri-w W C. '

D u rh h eo c/

CO y c J f Ve, %

Verifying /pumpcha>rationforatlead'ocl'.

~

i5 minutes, and c.

IN d.

Verifying that the pump is aligned to receive electrical power,

.E..w-W.,

irca an OPERAELE essential bus.

che;c ha ryc. f re:2 u re cS fo r cn

.2 G C / c,J -

v DAVIS-BESSE, UiiT 1 3/4 1-i3 April 23, 1975 kI I,/ i t

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&-.$..$.5..!5.b.$OhH.r. e*e$. k$.N$?OQ.$Wdk*4'.?A*W-

.M W M. S W AS*$ $

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REACTIVITY C0:ITROL SYSTEMS

- PROOF & RbViEW COPY Mi'l BORIC ACID PU".PS - OPERATit:G

.k d4 LIMITl!!G CC lDITIO t FOR OPERAT10tl

$.D..

.G1 At least one boric acid pump in the boron injection flow path

,M 3.1.2.7 required OPERABLE pursuant to 3pecificaticn 3.1.2.2a shall be OPERABLE and capable of being powered from an OPERABLE essential bus if the flow

'Q, -

path through the boric acid pump in Specification 3.1.2.2a is CPERABLE.

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E7.j APPLICABILITY: MODES 1, 2, 3 and 4.

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liith no boric acid pump OPERABLE, restore at least one beric acid pump to OPERABLE STATUS within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or make the reactor subcritical W

1 1l*ARGIN equivalent to within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and borate to a SHUTC0'.-l:

l's Ak/k at 200*F; restore at least one boric acid pump to CPERABLE i

j status within the next 7 days or be in COLD SHUTC0;.'N within the next 36 hcGrs.

pg0$ 0$$b SURV'!LLAtCE RECUIREMEilTS One boric acid pump shall be deconstrated OPERABLE at least a..3

%.jg;,?

4.1.2.7 once per 7 days by:

Starting (unless already operating) the pump from the control a.

rocm,

.. ~ _.

/*

Verifying, that omWet-ion " ~.- the pump develops a I ' '!'

b.

Tiischx9+-ferassure v. _,,-psig, y,</J gp p g a f,. -

OO t^C 9 Vm p head C,o p a c'7 Verifying pump operation for at least 15 minutes, andy C

+Q c.

.g; :..

-p;4.;g.

Verifying that the pump is aligned to receive electrical power d.

from an OPERABLE essential bus.

Ca i

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07, it Sups 13, DA"!S-DESS2. U.ilT 1 3/4 1-14 May 19, 1975 j

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c 3/4.1 REACTIVITY CONTROL SYSTEMS

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-M BASES 3/4.1.1 BORATIO1 CONTROL 3/4.1.1.1 SHUTD0i!N MARGIN A sufficient SHUT 00'.:N MARGIN ensures that 1) the reactor can be made subcritical from all operating conditions, 2) the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, and 3) the reactor will be maintained sufficiently suberitical to preclude inadvertent criticality in the shutdown condition.

During Modes 1 and 2 the SHUTDC'.lN MARGIN is known to be within limits if all control rods are OPERABLE and withdrawn to or beyond the minimum withdrawal limits.

The most restrictive condition occurs at EOL, with Tavg at no load operating temperature, and is associated with a postulated steam line braak_ accid 2nt-cnd-resulting uncontrolled RCS ccoldown.

In the analysis of this accident a minimum SHUTDC'.lN MARGIN of (0.30)5 ak/k is initially required to control the reactivity transient. Accordingly, the SHUTC7.lN MARGIN required is based upon this limiting. condition and is consistent with FSAR safety analysis assumptions.

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r 3/4.1.1.2 BORON DILUTION approe / <b/c/y /8 / M

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A minimum flow rate to the core of at least 2S00 GPM provides N

adequate mixing, prevents stratification and ensures that reactivity changes will be gradual during boren concentration reductions in the i

Reactor Coolant System. A flow rate of at least 2500 GPM ui1Lciccu- '

lata an equivalent Reactor Coolant System volume of 415252 cubic feet in tpproximately 30 minutes.

The reactivity change rate associated with boren concentration reduction will be within the capability ftr operator reccgnition and centrol.

3/4.1.1.3 M00ERATCR TEMPERATURE COEFFICIENT (MTC)

The limitations on MTC are provided to' ensure that the assumptiens used in the accident and transient analyses remain valid through each fuel cycle. The surveillance requirement for measurement of the MTC at the beginning middle and near the end of each fuel cycle is adecuate to confirm tha MTC value since this coefficient changes s10wly due princically to the r,eductica in RCS boron concentration associated with fuel burnu?.

The ccnfirmati n that the measured and appropriately compensated MTC value is within the allowable tolerance of the predicted value provides additional assurance that the coefficient will be maintained within its limits during intervals between measurement.

DAVIS-BESSE, UNIT 1 B 3/4 1-1 July 3, 1975 I

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5AREACTCR COOLA!!T SY_"._T_E._M.

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DESIG!! PPE..; '".C A!iD TEMPf RATURE aqlant system is desir.ud and shall be maintained:

5.4.1 The reactor i

_In accordance h the (de requirements specified in Sect on (5.2) of the FSAR,,w'r 41 allevance for normal degr.2dation a.

pursuant to th applicab.- Surveillince Requirement.

^

b.

For a e ssure of psig, and ror a temperature of F, except for thu *assur :er and i

c;

F.

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. pressurizer surga line.:nich is

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The tof.al *.nter and steam volume of the re cter ccolant systen is l

//2 4.<

5.4.2 cf 525 F.

in it. //o+ 2e cubic feet at a nominal T.lg a

)

.J 5.5 EMET.EEQ'Of. Gut.inG SYsrara metint systems are ' -igned u.d sin 11 be 5.5.1 The crcrgency cori.

riqinal design provisien'. cont:ined raaintained in acccrd;.:. wi th c...

' e for ncrmal de;;racation V

in Sect. ion ((6 A oi the FSAR, with al,t..the applicable Surveillance f:cquir.

pursuant t

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.UCL STO2 AGE 5.5 1

CRITICALITY F

The nert ar.d spent fuel storage racks are designed and shall be

!! j/g c:cintain.:d with suf fici:nt center w-center distance bet.een fuci 5.6.1 4

asse:r51ics placed in the storace rechs to ensure a k'Ur.quivalent to

..c ff

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The L - u?

/r'

~ 0.95 includes a cons;e prol fillc.!, tith ur,Nrated.dervativa

< 0.95 wi t.1 the stora:

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l p' l;;ME W g is Cesigned and shall to m.;ctiined.

a.o.2 The srens :nel to prevent

d-cent draining or

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TABLE 3.3-3 (continued)

SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM TMAL NO.

Clit.NNELS CllANNELS APPLICABLE FUIX;fiONAL LNTT OF CIIANNELS TO T111P OPERAllLE MODES ACTION 3.

CONTAINMEfE ISOLATION (Continued) c.

RCS Pressure Low-Low **

4 2

3 1, 2, 3 8

t

'l

[

4.

CorEAINMENT COOLING e

x a.

Containtnent Pressure -

Itigh 4

2 3

1, 2, 3, 8

i.

b.

Containtaent Pressure liigh-liigh 4

2 3

1,2,3 8

f c.

RCS Pressure Low

4 2

3 1, 2, 3 8

A rl0 / / FL V.A 7t A 5.

MAIN STEAM ^ ISOLATION a.

Containment Pressure -

Iligh-liigh 4

2 3

1,2,3 8

i 6.

COIRAINMEtU SUMP SUCTION N@

a.

Borated Water Storage Tank -

2 3

1,2,3 8

Low 4

7.

DECAY llEAT REMOVAL SYSTEM ISOLATION AND ItEERLOCK p,

b 1

1 1,2,3 10 M. it l/

1*'

a.

RCS Pressure as;

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.. j,.$ } 5 N

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TABLE 3.3-3 (Continued)

SAFETY FEATURES ACTUATION SYSTEM IllSTRUMENTATION

)-

!!INI!!UM TOTAL NO.

CllANNELS CIIANNELS

' APPLICABLE FUNCTIONAL UNIT OF CllANNELS TO TRIP OPERAfsLE M O'9,S _ _

ACTION g

o, -

~N N6

(. 8.

CORE FLOODING TANK ISOLATION VALVE INTERLOCK

'Y a.

RCS Pressure 2

2 2

1 11 s

l i f,;ryia, 9.

SFAS MANUAL ACTUATION

' '.v / CilANNEL A i 1

1 1

1,2,3,4 12

/

10.

SFAS MANUAL ACTUATION

,y,7,,,jCllANNEL M 2 1

1 1

1,2,3,4 12 11.

CO!UAINMENT SIRAY MANUAL

\\

ACTUATION CilANNEL 1

-1 1

1 1,'2, 3

' 12 12.

ColffAIN:1Etif. SPR AY MANUAL ACTUATION CilANNEI. 2 1

1 1

1,2,3 12 13.

COINCII)ENCE LOGIC CilANNELS 34 2***

2***

All Modes 13 14.

SEQUENCE LOGIC CilANNELS 4

2 3

1,2,3 8

l

@D 5 59 f

s-4%

TABLE 3.3-3 (Continued)

TABLE NGrATION

Trip function may be bypassed in this mode below 1800 psig.

Bypass shall be automatically removed when RC pressure exceeds 1800 psig.

- Trip function may be bypassed in this mode below 600 psig. Bypass shall be automatically recoved when RC pressure exceeds 600 psig.

- - Two output logic modules and associated relays per Coincidence Logic Channel.

ACTION STATEMENTS ACTION 8 - With the number of OPERABLE channels one less than the Total Number of Channels and wich RC system pressure:

4.1800 psig, restore the inoperable channel to OPERABLE a.

status prior to increasing the RCS pressure above 1800 psig.

b.

1 1S00 psig, operation may continue arovided that the minimum chant.els OPERABLE requirement is cet; however, one additiona: channel may be bypassed for up to six hours for survelliance testing per Specitication 4.3.1.2.

With less than the Mini =um Channels OPERABLE, operation may ACTION 9 continue provided the contain=ent purge and exhaust is,lation

,W' gf ekt J tvoet.J'/ *"" M9SM ##

valves are maintained closed.

M p

ACTION 10 - UithAanst oe-ense channel 4 inoperable,tand reactor coolant pressure >280 psig, both Decay Heat Isolation Valves (DH 11 and DH 12) shall be verified closed, gg g.%

k

~

- f 8 Min. ms jacs p5WLs With less than the '/1nimum Channels OPERAF'." and reactor coolant pressure 4 280 psig operatio1 of the Decay Heat System may con-tinue; however, boi.h channels shall be OPERABLE prior to increas-ing reactor coolint pressure above 280 psig.

ACTION 11 - With either or both channels inoperable and reactor coolant pressure:

(a) 2 830 psig immediately verify the Core Flood Tank Isolation valves (CF1A and CFIB) are epen.

(b) / 800 psig, re=ain in Mode 4, 5, or 6 and do not increase reactor coolant pressure above 700 psig until both channels are OPERABLE.

ACTION 12 - With less than the Mini =um Channels OPERABLE, be in COLD SHLT-DORN within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

I

'7

TAntd 4.3-2 (Continued)

SAFETY FEATIIRE ACTilATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIRE!ENTS Cit!.MNEL MODES IN WilICil C11ANf;EL CilAtINEL FUNCTIONAL SURVEI LLAliCE FUt1CTIONAL UNIT CllECK cal.IliR ATION TEST REOllT RCl) 4 CONTAlfelENT COOLI!!C a.

Containment Pressure-liigh S

R M

1, 2, 3, 4 b.

Containment Pressure--

11i gh -III gh S

R M

1,2,3

)

c.

RCS Pressure-Low S

R 1, 2, 3 5.

ItAI!1 STEAM ISOLATION t',

8.

Containment Pressure --

liigh-liigh S

R 1, 2, 3 fj 6.

CONTAINME!C SUMP SUCTION Borated Water Storage Tank-Low S

R M

1, 2, 3 7.

DECAY llEAT RDt0 VAL SYSTEM ISOLATION AND INTERLOCK b

RCS Pressure S

R M

1,2.3 g

a.

8.

CORE FLOODING TANK ISOLATION VALVE INTERLOCK M

a.

RCS !ressure S

R M

1 d

9.

SFAS MANilAL ACTUATION CilANNEL N.A.

N.A.

c= =3 R

1, 2, 3, 4 10.

SFAS }!Af;UAL ACIUATION CilANf7EL $12 N.A.

N.A.

c :23 R

1, 2, 3, 4 8

11.

CONTAINMEh*f SiW\\Y ACTUATION CllANNEL L N.A.

NA.A R

1,2,3 Y l.s,

/e y

e EliERGE!!CY CORE C00LT! G SYSTE!!S B0 RATED llATER STORAGE TA!!K Lil4TTI;:G CD::0ITIO:! FOR OPERATidtt 3.5.4 The borated water storage tank (CUST) shall be OPERACLE with:

U a c,le a.

A minimum centened volume of 360,000 gallons of borated

water, b.

A minimum boron concentration of 1800 pro, c.

A minimum water temperature of 35*F, and p b h A' maximum concentration of (y) ppm.

2.1 o o APPLICABILITY: P,0 DES 1, 2, 3 and 4.

ACT10!!:

!!ith the barated water storage tank inoperable, restore the tank to 02EPJ.0LE statu: within or.e hour or be in COLD SHUTCG'. t! within tha next (30) iiours.

d

k Ya SURV21LLAi1CE RECUIRE'4E!!TS The'BWST-shall be demonstrated CPERABLE:

4.5.4 a.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when ambient air temperature

<35*F by verifying the water temperature.

b.

At least once per 7 days by:

9 1.

Verifying the water icvel in the tank, 2.

Verifying the boron concentration of the water.

. DAVIS-BESSE. UillT 1 -

3/4 5-8 Ilay 19, 1975 q./

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EMERGEfiCY CORE C00LI!;G SYSTEMS e

i SURVEILLN:CE P.E0VIREMEl1TS (Continued) 72 5.

Verifying that a minicum total of fET cubic feet of solid granular trisodium phosphate dodecchydrate (TSP) is contained within the TSP storage baskets.

6.

Verifying that when a representative sample of 0.35 + 0.05 lbs of TSP from a TSP storage basket is submerged, witr.ou*

agitation, in (50 + 5) gallons of 180 + 10) F borated water from the P.';ST, the pH of the mixed solution is raised to > 6 wa thin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

d.

At least once per 18 months, during shutdown, by cycling each pcwer operated valve in the subsystem flow path not testable during plant operation through at least one complete cycle of i

full travel, i

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i DAVIS-BESSE,~ U'llT 1 3/4 5-6 June 4, 1975 l

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TABLE 3.6-2 CO:TrAT:02:.r ISOLATIO:7 VALVES

TESTABLE

~

PENETRATIO:t VALVE DURI!G PLRiT ISOLATIC:t

};U:GER NU:CER FII' CTIC:t OPERATIC::

TI!2 containment Su=p E=crgency Recirc Line No 7/6r sec

30 D119A 31 D119B Contain=cnt Sump E=ergency Recirc Line No

~//.61' see 32 RC 1773A RCS Drain to.RC Drain Tank Yes 10 3ee 32 RC1773B RCS Drain to RC Drain Tnk ~

Yes 10 see W 45

.s

,AF599

> Auxiliary Fcedwater I.ine Yes

'to see v

w v

.fs 36./

N AF603 Auxiliary Tecduater Line

. _,,,,.. Ye s-10 see 37 57601 11 sin Fecduater Line No 15

.sec 38' n:612 1!ain Fcedvater Line No 10 sec 39 15100 lbin Steam Linc No 10 sec 4:oJV:J 10 see 39 15107

!!ain Stea-A-.ine bb }O Y iN Yf) c, a S imj ",

y. ;

/.'--

39 1CS11A 1:ain Steam Line Ik, 10 sec

'39 ifs 375 lbin Steam Line N s, X Fe; 10 see i

39 11S100A

?!ain Steam Line ps-g 10 see 40 IIS101

!!ain S cas Line

/

No a

. 10 see w

m.-

,~7%

--er.-

1

. vw.,,.we%

.w>

w m e w y.m mi

.~~

40 1!S106

!!ain S ca= Line

.'10 sec

'.1:a f.

%a

' ' M.S IQb lr Jha;n &;ha t. i,,.

.; g p*7' M '"

,*0 ICS11B

! bin Seca:a Line f7 go 10 see 40 1:S394 lbin Secca Line -

grY l,

No' /c-10 sec

Y 40 11S101A

?!ain S ca= Line 7

1;,y-Y,7 10 sec 41 RC232 Pressuriser Quench Tank Circulating Yes 10 see Inlet Lin.

42A SA2010 Service Air Supply Line Yes 10 see 423 CV5010E Centainment Vessel Air Sam 10 sce

? t.~;,*v;W:gy.+.dq: i. r.= <.; s '; as. ;w.. * :pic 2eturn':; ;.:;;;;;p.<;q:p.Yes......:w;:;.:: ia : =w

".y::%,',?.:

. :-;~:'.

^

'4 3 A IA 2011 Instrument Air supply Line No 10 see D*

D YN

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C0!! TAI!:'EliT SYSTE!!S

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C0t:TAlf;4EllT CCCLli:G SYSTE!!

LI!41Tif G CC::DITIO:t FOR OPERATIC:1 Tw D n 'a ~ 1 3 3.6.2.2 gWe containment cooling units shall be OPERABLE.

f APPLICABILITY: !?00ES 1, 2 and 3.

A Mmegg.g.

ACTIO!!: Go t

With one' containment ccoling u' nit $ inoperable:

RestoreYh^eino'perableunittoOPERABLEstatuswithin48 a.

hours or be in HOT STA!:03Y within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; restore as lhe inoperable unit to CPERABLE status within.the next 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in COLD SHUTDC'.;;t within the next 35 hours4.050926e-4 days 0.00972 hours 5.787037e-5 weeks 1.33175e-5 months , and b.

If containment cooling unit 1-3 is OPERABLE, within (two) hours align unit 1-3 to the same essential bus as the inoperable unit unless that unit is inoperable as a result of an incperab!c essential bus, than align unit 1-3 to the 0FERABLE essential bus.

SURVEILLAt:CE RECUIREP.EilTS Eachcontain=cntcoolingunitshallbede.h.onstrated(PERABLE:

4.6.2.2 At least once per 12 hcurs, when unit 1-1 or 1-2 is inoperable, I a

ff by verifying that unit 1-3 is aligned to the specified essential bus, b.

At least once per 31 days-on a STAGGERED TEST BASIS by:

1.

Starting each unit frca the control room, 2.

Verifying that c:ch unit operates for at least 15 minutes,

-I k :

+.vo 3.

Verifying' that'. units J '

' 2 are aligned to receive-electrical pet;er frca separate OPERABLE emergency busses, and 1

cgk.$ O Vcrifying a ecoling water flow rate of >

gpm to cach N !/S g d / unit cooler. Q y,.,

3

.,3.g c, u f,,)

DAVIS-BESSE, Utili 1 3/4 G-13 1.tay 19, 1975

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PLANT SYSTEMS AUXILIARY FEECMATER SYSTEMS LIMITI;;G C0f DITIO!! FOR OPERATIOl!

3.7.1.2 At least two steam generator auxiliary feedwater subsysteins shall be OPERACLE with each subsysten comprised of:

a.

One OPERABLE auxiliary feedwater pump capable of being powered from an (dtr.notc.wyn 's'$0PERA3LE steam supplyk, b.

A separate and independent CPERa.BLE flow path capable of taking suctionfromthecondensatestoragetankgndtrapsferringcteL du suction to the (alternate water source).

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APPLICABILITY: MODES 1, 2 and 3.

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ACTION:

a.

With One auxilicry feediater subsystem inoperable, restore the inoper&ble subsystem to GFERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or

~.'.

be in HOT SHUTDC'.!N within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

} '.

l SURVEILLAt:CE RECUIREMENTS k

i 4.7.1.2 Each auxiliary feedwater subsystem shall be demonstra ted OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by:

1.

Starting each pump from the control room, t

2.

Verifying that each pump:

Develops a discharge pressure of > /c d _ic a) psig on recirculation flow, and b)

Operates for at least 15 minutes.

Si Verifying that the folicwing valves are open with ocuer j

'o',\\o_tJhc valve operator removed:

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V DAVIS-CESSt, Utr!T I 3/4 7 a.

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7 May 2,'I'

DtEP.GE CY CG2E C00tI!;G SYSTEMS SUP."EILLA' ICE REOUIRE!'EriTS 4.5.2 Each ECCS subsystem shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGEP.ED TEST BASIS by:

1.

Verifying that each HPI pump:

a)

Starts autcmatically on a test signal.

b)

Develops a discharge pressure of 1 1170 psig on recirculation flow, c)

Operates for at least 15 minutes.

2.

Verifying that each LPI pump:

a)

Starts automatically on a test ' signal, b)^

Develops a discharge pressure of 1150 psig on recirculation flow.

c)

Operates for at least 15 minutes.

T Verifying that the fellcwir.g valves are Open with pcuer r3 v

to the valve oper.:Ler disconnected by removal of the

'[*

breaker frca the circuit:

Valve Number Valve Function 0

h } '

a.

b.

c.

[O[. g C' locked, sealed ar otherwise secured in their throttle 4

Verifying that the LP injection cross-over valves are j

position.

5.

Cycling each testable remotely or automatically power operated valve through at least one complete cycle of full' travel.

6.

Verifying the correct position for each manual valve not locked, sealed or otherwise secured in position.

Yh D**}D *)D.S]ukm

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3/4.4 REACTOR C00LAtlT SYSTEM 4

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fi 3/4.4.1 REACTOR C00LA{T LOOPS t

i The plant is designed to operate with both reactor coolant loops in cperation, and maintain DliBR above (1.3?J.L30) during all normal operations cnd anticipated transients. With one reactor coolant pump not in cper-ation in one or both loops, THE?f'AL PCUER is restricted by the Nuclear Overpower Based on RCS Flow and AXIAL POWER IMSALAl ICE and the fluclear Overpower Based on Pump Monitors trip, ensuring that the 0iBR will be maintained above (1.32/J.30) 'at the maximum possible THEPJ%L POWER for the number of reactor ccolant pumps in operation or the local quality at the point of minimum D!iBR equal to (22 5)% whichever is more restrictive.

t A single reactor coolant loop provides sufficient heat removal capability for removing core decay heat while in MODE 3; however, single failure considerations require placing a DHR loop into operation I in the sh'itdcwn cooling mode if cocconent reoairs and/or corrective i

m actions cannot be made within the allowable out-of-service time.

l 1 l

3/4.4.2 and 3/4.4.3 SAFETY VALVES j

The pressurizer code safety valves operate to prevent the RCS from being pressurized above its Safety Limit of 2750 psig. Each safety valve is designed to relieve-lb Q e hour of saturated steam at the j

valve set point.

33, w j

~The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown In the I

event that no safety valves are OPERABLE, an operating DHR loop, con-

'l nected to the RCS, provides overpressure relief capability and will prevent RCS overpressurization.

During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS frcm being pressurized apove its safety limit of 2750 psig. The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from any transient.

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1f' 3/4.7.1.1'-SATETY VALVE",

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'The OPEPA",!LITY of tha ruin ste;m line code safety valve. ensures tha t the secoori1ry Sy*,te': pr:.'ure wi11 be 1imited to withinfits design pressure of /050 psig daring the mare severe anticipated system operational transient.

ine uaxir..um relieving capacity is associated with a turbine strip from IC07 PATED T!iG:9.L PO'.;ER coincident wi th an assumed loss of -

condenser heat sink (i.e., no steam bypass to the condenser).

I j

The specified valve lif t settings and relieving capacities are in accordance uith the require.:ents of Section III of the ASME Boiler and Pressure Code, 1971 Edition.

The total relieving capacity fcr all valves on all of the stean lines is/?.M,"* bs/hr '.hich is no parctn t j_

of the total secondary stea:n flow of v/m" lbs/hr at 100" RATED THE?>'AL 1

5 PO'<!ER. A mini..:U.: of 2 0?EPAGLE s. fety valves pn staan generator c tsures j

that sufficient relieving coa' city is available in the event of a single i

safety valve failure.

j.

STARTUP and/or PCUER OPERAT!01 is allouable with saf aty valves i

inoparable within the 1i, i:.otiods ai U.c ACTION raciairc:..nts en the 'cas.is

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of the reduction in secca 1ary sys tem s cam flou and _ne.....L r..w., it.uired

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.l lj-by tha' reduced reactor trip settings of ti.e ::nclear Overgn.;er channels.

.The reactor trip setpaint reduc 8.icn; arc deriv 2d en the follouing b350s:

.)

SP = (X). /Y)(V) x (105.5)

..=

R %y P%%j W D g

D g

g j

wheru

-l SP = redxed !Nelear Overpe.ier trip set;; int in cercent of i[

l RATED TiiEY:.*,l. PCUCR ( > r-: in n'.r ~::nk i.waror es a s:. r Amr.,..- a r - < ls.> i iscr, ra e era, e ;

+!..n

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V = r.'axi: un n:. Or of inoperabla. cafety valves ;;er stear: M r. G u h r:,L li (105.5) = thclear Over;u:uer trip set cint specified in Tcble 2.2.1 j

X = Total relinving c2pacity of all.nfety valves per steam 9,.,,...,,,

'si.a in i o5/Mur O.,e n nd mj,,,,)

LY ="'axi:=:n clievin.; capacity of any cnc safety valve in lbs/ hour

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f tilI10tl5 TPE0!!TriCY !!0 TAT.!.0ft

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The FREQt!!fiCY tiOIAT10r! specified for the performance of Surveillan

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Itequircire:nts shall corre", pond to the intervals defined in Table 1.2.

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1.2?

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' AX1 AL PC'.!ER llTA1.AT:CE AXIAL POWER !!;BALAl CE shall be the power in the _ top half of the c E

i s the power in the 1.23 expressed as a percentage of RATED T!!EfW.AL l'CU R m 51!! ELD BUILD 1 rig litTEGRITY SHIELD BUILD:!:G liiTEGRITY shall exist when:

1.24 Each door in each access opening is closed except when the access opening is being uscd for normal transit entry and 1.24.1 exit, then at laest one door shall be closed.

The shield building filtration systea is 0?ERABLE.

1.24.2 RDCTOR PROTECTIO:1 SYSTEM RESR!iSE Ti!'E F shall be the time interval The REACTC. TRIP SYSTElt P.ES?0:iSE T1!

,, ~.

fro':1 when the n:onitored para;ut v scads its trip se'. point at the 7

1.25 I

channel sensor until power f at r uptien at the control rod drive brenars.

V Ei4G!fiEERED SAFETY FEATt'IE repa:;sE TIME _

The E!;GI!;EEI!ED DFETY TEATU3E PESPC 'SE TIME s'1311 be that ti interval frem when the r.enitored garmater ex.ced; its ESF actuation 1.26 setpoint 2t the ch.mnel se.uor until the ESF equipmen

)

pasitions, pt.. p dischire pressaires rNch their required values, etc..

perfor.ni.19 Tiucs shall include diesel generator starting and sceaence loading delays where applicable.

M P!!YSTCS TESTS' PiiVSICS TESTS shall be ti.one tests performd to :.easure !be f of the reactar core and ralated ins.'runantnicn 1.27 nuclear characteric,:ce, TSAR, 2) authorizal under tha r'd 1) described in Ch.: +.- (14.0) of '.h.:

provisions of 10_Crd E0.59, or 3) othemise ap;: roved by the Comi,sio June 21, 1975 1-5 B!.;l-STS l/

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TNSi4WCC OWH M AI NH'* U ^

.,J. ' a ?.

il<N

...n.:*.

a,.

Nesse o

t A e.

d PRESSURE CO*.TAl*;iNG WE LDS IN PE ACTOR VES$f L BE LT LsNE REGtOne The areas si.b.ect to etahman..n shag.nsli te the riel.

De admimal easmaastase d the sang lengrtadttal and e

a lonpluJmal anJ circumferentul cM m ibe ec.ss.

sewel *arl 4 orcussferenttal weWa rne, he twrfmasd et or acar t me e a,. N -

~ - - - -

opposne e.e ier.;tn rf t'e rever seu.! term I sh e*.T**fiere

hJ"M'U* *' d #'

" " " "'" 7 I E

3

'uset!or*rfpor?F ele' effhti.e Iegth ef rew.,.t f ei ehere the lenge ed fash Wudinal med ad i wem M %

9.

j thermal $NelJ is not used.

f t.!

d...ca.s.a c..irc.u.m. feren.tta

.e!J equal to one ea.,1 th.l = eld e.t3 the m.astnant iesc The area to be eumined shi:1 inst Je abe metJ. net i and ic amess.

-j base metal for oce plate th.dnes bound tne e.fge.4 med

% hen e6.e 1..e.go:wJ,ns;.nd.rtc arrfe*cattal ee.J t'.e reten ed

' T _.,,, _ _.

2n,c,pmare tu neutron tfeeve in es.eu we we trvt s#, if a T

q In adJit.co. mater i *Nch nas been repaircJ by

\\fes ce aes,ses. the inngth.4 wou is tae hah fLa<* regnie au

i eelding be etamsned sP.fi he instrasad ta at icant. M pertens

,[13[,,,

Al se mi a de W inspe M $ M p.4 O

e no al. 1 h n,,

,g

'g, a.

area ts located so the vennej.413,.pp,,,,, g, g,9 og areas have recmved an espammes to ass sea s'ma se "

of

g reactor sessel thermal sNeld. *here

!.h8 effectase length of reactor fuel.h,re ice ihmnal aned. or.

este the

'* t##' ' # *

I " "

l'8 ' $'* *'

q {

u is aos used. De euminanno must cemp.etely en,,, i3,,q,,,; gg g3, inspa tsoe iminnal @ utest dWeupw WSM

. ', ;j locaboa of the repair se aos posataveto and act.rse Em rect-smed to et : cast 50,w tvat ed tar tmarsd arsas. I s a m. -s w then the tedmdual shel) p!. ate, fciga3,"at seO ecrane paarwW, stiaa he erweiru.J is a.fie wsmians.8s.erva.a a suce.'.ame *C j'.

k.nown to contata the repaar shad be @ to maam

- iH'i--

-- *d'# ' ' '

"p

~f~

c

^ 'n L.' ' ' * ~ ~ ~ ' '

} Al.~

i y

sie # / c s /c ( # f 7s saf,e a.)

... ~..;.

.,. w. :

_ pl o.,.,, _

4 1

P58E$$URE CONT As*.af4 v.t L05 'N VFSSE t S l

The areas suject to ciamir at n sha.!.nc!.Je the LinpivJ n.I:

The eumsmatms perferir.ed Jorine uc'. mMca, uiterval j

acd circumferenual setJ6.a :he ses.cl shell.sJ rnerid.onal and circamferent.al se!Js m seuel heaJs tha11 mwr at lease 10 percent of the ienata of each funpta tr:.:

saet! seu acJ merid. ara: head et.L a.J 5 pette =t of e..e The area to be esamined shall insi.Je meu met.! 49J hase

!<nnt of na.ctrcumfere inal sta'! *eaf aad bed =eu.

metal for one place nNancu bocnJ the che id meld Fa seida.oe the reactor wtsel the mJmdust "r' taata a-

,g may As prtconed as ce nea: the eved rf each t= p-r-g 9

s' munal.

~

f.

.s Al o n' <

C

~

^"

}

l PRESSURE CONTAINING WTLCS. VESSEL 70 FLANGE AND HEAD'TO-FLNeGE y

l The areas sdrect to cumiutien shau m.!ude the seuel to-flange and head to f!ange me!Js.

The inJrufaal eumina'twets performed Juttet eachi.:s.r.vctqn i

s mt.m.al-s!:ad cumularrvely l

The naminatio1 of tpe seuel.to Cange meu ma.s be conJucicJ ci rismferentral me,g

. co,cr.!00.r.ercent of cacti e-j from the bolt.rg ' ace of c:e flange The nurnber and cuent d aress etamined durice each

_md;ndual esammation of a circumferential weld M1 provi.fe a r

representause sampme cf the ectire wekL g9 p~

{

flepe D g

6:

UU U

PRESSURE.CONTAINING NOZAES IN VESSELS 1

The aree subject to summatwo shaft mitude the nonle

}

atracment old to swl at:J the mtwat estewon 4 nonte The cuent of eummatio, of each noza!c shau ceser 104 mue sewel I w!uded ttom thn c twty are the norrk.ti of the nou!e.t.scuel se!d. and 100 percent cf the percent inner radias section of the necie.h vessef ja.xture. At the cowstti: DN.tranderc*ttul wetJs and prewuresentammg sea! aetJ.

Moules of the seuel sh3!! be eu mced duttng eac1.nycta.e interval.

~7?.t" number of nor. ales eummed durmg each inverem interval shall be t.'e total number in a sessel sur rct 7.a uactmat.on JmJed approomarely equally arnune the.spected

'4 nureber of cummanens Jmng the msystert.oterval. De resu ur4 stamber sha21 tnelade a represenutive verphy amos*:

each jtroup of noffes of co-rparsele me.

i

,a

=

" :*:.. */q o r~cd. - Jn m.

- ;- r-~~ m. m m- ~y

,.i -

g' *

~

e. :. '.. '

.- / N C*.. e /a / A.,.g /,- 4

.. s;

..' -.cg w p.rxfme./q4 M

,,,,,g 1, e '.

i g <* ' < !1 Mee @ g /.

o

,,,,,f,y,,,

h/ 4 c.nc

,D A vi.s Be,sse,,

,. m,,

f,, 6,

.c,.d,,;l,j e

usn r

.1.

7 g3, y 3.,.. y c g,m a _ s,j. m,...-

e.

...rs.,

.e.

n -

. o.& s w..

1 g.~y-. -........ =w....\\ *.

z.. l A p t E 4.l.t-.4. &.? M*1...-

..7.,..,,

. y.,.g.,.

?

?-

.~.... :.. -

,r.:. G P..*.. :

f;LQ'?' A-Q'.- 2: ). Z N_sE g w ek ; 'ZK/spc rQ*}.:_

T s-

.: w.sd. : r..

s

+

.... m~,x.

EXTENT AND PREOUENCY OF EXAMINATIONS AREAS SUBJECT TO EXAMINATIONS I'f M

[!

.: 5 I I Nehr E.1 p

PRESSURE C04 tt.44iW/.E LO* a*4 VES5F t. 8't t.E irt a t:CNS

.i oon :n cr. 4 e.

The esarn n$.ons perf..smed Janng ca.h inspes c

4t suas 2' penent of it.e ve.d The areas sub ect to cuminauon hall insluJe ah..e pee..re.

sh41 cu:nu ai.ie5y weer a

[]

contaimeg meld. of textor.untral :.id Jrne peastrati. r.#.a pr.etrat.on

.a ush grup of penevausms el curaparabie.ize.

1, -

sessel hea.ts. in de cos. trol rod Jras bou..ags.

48

{

sessel instr'an entanon sonnecuena and as heater 6.inr.<stu o in reactot j

pressurizer sessets. among %h a dJ f. Jure m ar.y..eg e

[)

penetrauon resWts m ear.J.rsons than fad to meet the twin..n

'.. '. l criter Os of 15 121. 6-/See f.sw I"7,, t, A, fe n % t+ t' o *1/ ca..J

Ca 7 ro n/le.a'.)

5 4

fOt t

_C 2

? l PRESSURE CONT ALMf4G r: elf,5 s's VEOSEL Pe NE7R Af TONS t

I

{

'The curet of eu::u.atei >?.4! :sch.Je toestyJoe per.ent r

15128 *aII of 4.e penstrt ions e t'>e sesire si rmg ce saspectaos satend.

Pesetrations exclaJed froen the enammataan by j

f 5

be gtses a wsul eu:nsnataos for esalence of !raiseg at the i

tm:e ef the sp'em hydrc<taue test as reywred tr) la '.'O s.

'of Sr,c /..' 77*., J' h

s Fait d*N

,. 4,.

p e

e A, c..n can,s2.a t

i A;o H F 5

PRES $URE CO'4T AINING Di*.s;1MILAR ndETAL WELDS.~. -,.,'

s ; j, l..

~',

i *

The encbv>Jual essessations prioetneJ J:mng each innecuc t

,..s The areas sub;cci to esammatsoa sha!! ensla te J. sundae sha.1 ctver IJ) percees cf t%e ettrictere.cr cf the sa'e end

- y',

j-rnetal eclJs tsafe.enJ seedst bes.ces combinaunce.:( fcmt.c melJs All cf the ule-end eelds shad be eutumed Jurmg cc

}

ste Is (earbon. low alloy and hyh :enw;e steelte and austernta inspenon mienal i

stamless stech. nicLal.chrem.us.iren.' oy s. nnael-ston thrernaum J

9.}

aHoys and 'u kel cepper diop.

e

- :?

The area to be eummed shall mctuJe de base material for.

.j at ' east, one wall th:dnes beyenJ the edge of seid.

s

~

[*4 P # G1

.s g

PRESSURE. RETAINING SOLTING L:

rfort.ed.'funne cah ins ion interval

.: 1; The esaminations

-.n.e

.inshes and tar er m Jiameter sha!! be cumined sh4! eumdatsely cover er enure nEmber of tvits, snma and

.,i Solu :

~

. i,.

eitner m pb[u tJer wn ion.'or when the b40ng n removcJ.or auts.

in ba.c when the bolted can.csuon is JistwemMed.

Esarrunanons of bu hmgs. thresds and I.gamcit.

The bott:.g and arus to 'e cum:ned WI sactuJe the statenal of Ibnces mas be performed from a face of die Ihv r -

studs, nats. bush:a.;s..hreads in base mater ai and the flange and are required to be eumined only when trve svnne.uc.i a j

lipments between threaded st ad holes.

4:< assembled

.I -

4

'~#

~!

1 7.h.'C7.* *i'

-~,p-..

7,..

w e'.t:

.e.,

.. ~.,

[.....

[

.,..., '., '".. a ;,, ~ ;

y.. ;. -

, ! ". *yg-

.,g;.s,

s.

.. I,

e. - * +.

g,.

='

. ; 7 y.,,,.

.. g r

g

~~

. c' e.

8>-

g

$,A H,$

'ggSSg es

,1

,,,o

., 5

y,.

'. :.D.. ',,

' ~.

. - =

..i rf.

.o

- m_.,

,,.... s..

v.s.:......

p

..:.s.

s.

..t A 6 t E..

<f. 4 ~.f.' A/.. -

...a.

~

..e.

. ~.

i:.

1.,,...

^

p:r;..,.y

.'4, *qN s g a w. c e-ZNsHc ym g. pm..y y e

g..

e."c i

P**

3]

t; c

~L :

m.;, y

t

s..

..> h 2. - n...

t*

AREAS SUBJECT TO EX A'.tlN ATICNS EXTENT AND FREOtJENCY OF EX Ar.ttNATICNS g.

I s

7 s.

Nu t' e G2 PM.SamE pk ThM.G is0L f.r.G

{

' f.

e s erru

.t..,n ge r.~ a 'rJ s..-.e e 3 Bdting ><!..s 2 msres m Jurre*er.nat. '< u.a. fis es em nest T he e s 'er ' f usua:

a egher in p%e J the 5. sied..en'estavs as ri.

s. c=+.e4

'.* pest.un in:er.ai st !! c.m 'a tn e's (4., - " e s t tree

~.c:

4 Juring the mtpectu.nteruf. er w he.cssr the n..:t J.onnes u..a bo!rs. st.Js aJ wi.

.l j

is J e ertNed.

N The botting to be statnitied hn.n.: sc.a:. aad nat.

Excluded f.em enemmation is beu r.

..! 4..ne.e wnnei n t

a whose fa:Iare re ults it weditam %t ut f-ti c e s. W..+.

critenon vf 15121. c4.ai%. M p d E s "f2"~. [ d e f;Sm E 8*PV code M < el.b.e*>O

(.

)Y di f H

't VE S*.E L E xf E M4AL SwPPOR TS 4.e The areas sutwt to cu:nanation slullpduJe the internay..

TN etarr.ma'we perf.stred Jaring each taspect.cn.eterval it j

- mc!JeJ seswl esternal wpport atta.hmens avessel setenr1 startit t.9e case i f seuel surrect sorts sha41 N. at leaat.10 M* cent L.

g mhkh ind.4 des the wcids to the vev.1 arid vne e.aw rm tal

theh.stal feet of,ibe!Jief ses the seswL

. beneath inc scM rorte and alnne the supp.es atust.nwns in the tage of.scules wi'3 surt;cr's, a'l of the act:!n wi.h 4-

' nember for a Jistance or!*o bee metal thi knesses sup prts,tha.: Pt rumiscal.n acwrJance sah Categry D i

'la the case cf nen:e type supports ensating ei pa.h meegral wnh the nonJe. t'.e area to be tsarnineJ d.a.1 he the setJ

,cf connectwo between the neu!e acJ the seuel sheit as JessnbeJ in Eumination Categers D.

i

s l.

b 4:

j)C/ b? I1 INTERIOR CLAD SURF ACES Or RE ACTOR VESSELS

>~

-}.

In the case of the reactor ses e!. the areas to be esamancJ The currmations pearmed Jrrtre cach marect m etteru d

l shall melude at le.nt o vches. renh St. quare mshe t esenh sMI :rciude the patch areas ubject 'i cummatwn m $?

J distnbuted. :n the shre.1caJ. and 6 patshes seash o q uare reactor senet she.1 and in the sicure head.

inchest. esenly distr 52'eJ in acces..h:e etwns of sewel shell.

a ClaJJing eu'rmation pat 6he, ha;l be prepared to facihiste esammation. anJ.ha:1 he locat<J m areas with nientifiab e 5

D**}*

I mJnassarm i tvrar as prasitol.

3 i

,w w Ju o

I.

.3 i

1 7

((

J

.',7

/W r1 (12.

INTERIOR CLAD SURFACES CF VESSEL 3 OTHER THAN RE ACTOR VESSELS

.s

-3 In the case of other than res6 tor se..e!*. the areas to be ".

The eummatwn of the patches.mav S.e aed..rme_d 2. e se.s' g.

eumireJ shaJ.9c!aJ.? 4t feast I pat.h e.to weare msheu near the end of the inwestwn mimal.

ca.h mannay n t.'c pnmarv v4e et the.Me!.

~ ~ ~ '

~ ~ ~ ~ *'

CIaJJac eumma:4cn patchcs shall be preprcJ to tasihtate

,,,;N, tumsution. arJ tha!! be tessted ir. areas with iJcitifiable

-9 isJteat:Ons. mwfar u practical

.. ~., =

,,,,,...7,

*I

,,.. = * **

""*'a*

...\\

2.

~

~ '

.s

[

/

. ';2.d?

'~

~.

c.....

..i' :a a. ~.

W.-?.( w.

.....'....y..

m,..,..

....-e

,,....-s..,

e

.d, [

.. T,.

T A 8 L. E ~

4.. 4 - ;e c.w,.c).

[<.c.

.i~~

~

4:,

.. ~,. a..w..,.,,..;....,.....y..

La. ;_; 3.~:.

.. [N sg g w cg

. Z y y ;-(y.,o m..

r..

~

. g,

y.. p y, e

[. /.'. '

j.

..Pr.

y. '.).).

L..-

~

' c.L.

.s

~

.,:. x

. ;~ v..

'g?

.*--J"~*

......i p

r

., g(fv[, 5 ' ),

',,.~

AftEAS SUBJECT TO EXAMWATIONS EXTENT AND FREQUENCY OF EX AWNATION3 d *.. s. y h.&i:C.i Nofe J1 M..l.

Pene.mE cora A.iw.G v.ms.N Pmw 3,0*,.85*.*i ]

~

1 -

De area 6 subje. to cum;r.n s. sn 11 in.laar t..n.tt a eal The esam nota.fis perberned J.r.nc e e.nv :e s. wer..

. f.

7 M.f,, * 'j ar.d circumferenta.1 selJs in p p.ry enJ ihe her meid f..a.me s.*.ad s.afr.daine.v c. ser e as.! tcies:.J.r.c i.%: n a. c 3 11 th.dr.ess un bush edges.J ta.e c.e!.h l aw:aJer.. aslJs u'6 ar.fe'c'.t...ets t a nJ e.e.Ji. n r a,et: or..,f.mg : ;e

. y,t shall be esamired fer at sease a 'egeh..f..ne f.. e e see...arcJ m e.J se ntae:y J e n+.iec

,.he te.wem 4 tJ. sty n.'

h, ( r, '..I frcm the tatersection s.th :he 6 riumiesenuAl.vJ w:nte.1 f..t t ne !.* pe t e.at..f tr.e p.pe '.r ar h...nru u..'s a c'Jed,. ir.:s Yp'*

examination h.'..,.,,?

-%'4' Pipe bran $h connecnuns ha:1 he surwat t.. etar.%f.m.

, 7.. '

shish sh.ll in.luJe all the mcLi m.%i. at 6 ast 'Fe h.s u t.1 Mr W..

one pipe wall thidno. bcynd tr.e eder..a the e lJ e.n es.c d

- (,.7. '., *j!

rnain pipe runs. anJ at le.it she bec :: er.1 m tN. tr en.f. re,-e

('4..%.-

sithin the limat d.un pewta..o d.finsJ an Se bleas Pmt r g ;.:r.,!

Pipmg CuJe.

.a.

.. ['b'y

.6[ j.,

3

's hO $d.

N

},y,., A

t PRESSURE CONTA!'s NG AiLOS IN PIPINO

.s

@.,.{W "% a f.l WelJs us p.pi g fan.!wJm,: pips bransit ca.nne twnd =*.h h are '

7%g e s're t of etAenna:en sna') cu tulataciy coser ifs:

8 '.5,*.' *". ]

sulud.'d from the enammassorts by 15121 *N!! be vau. ally ; penent oi tu neida ta p.gvg.6r.c!u.' eg ;wpe branch ecanestros.

4

. ;. Q'[, : e cum.ncJ w?.erer the sesw. be.v..Jarv.

u.1 roeJ t.

ag stern tAe nr.spects ma mterut

.s...

s.. j hidio.:sts :.s1 prior ao sa n p.or n.rtup 8.4...%:. L.c.aq.

- rj*7*.', '.;

and at tla tame of t!w system hv trmtata test an ent.reeJ by

. P 4..

1s.5:o.

p;? }.'}'n 3 r1

^ /)c) M. K.1 a.

s.

, 2 '. e,.. e a.

.s "

SUPPORT VEYBERS ANO STRUCTURES FCA PIPtNG, VALVES AND PUWS t

..is s w

h De sup;crt fteT.bers and structures si.P;ect sa cummatmo Be easrumanor s requart'd to be p.rfortned 'du.rg eac't

',, p.

's '-

i, {,%,, j shall ine!ude the artegrslty me!JeJ esternal numet as*adments rnspectaon in:er al s!*.ajl cu:nutatn ty coser 2.5 grcer.t of t.5e i

.. Q (. '. t which inclu '.e the welds to the precurc<antamma twnJar) arkt total number of antera1).ne!Jed su; pet *.s withan the syste.

f.P.t.4 * ',.

2 the base :: etal beneath the meld une and alor.e LM suppnet bou';Jary.

attachmeet9 ember for s dntanse et t.o Nse rne'ai thidnesics.

' 9,'..;.b] . *I i

~'

( '? *.Q Eteluded frorn esamination are supports ahese fadute resuhs

<./ '

in cortditions that sataff the etslusmn cettena of 1%.l:1.

. $.%rs.'

y 4. $.,

,.Q*l']

/UMe K2

' G. 8

~ **, e.. / 4 SUPPORT YEIL1SE RS AND ST AUCTURE! FOR PtPING, VALVES AND PUVPS

' s t f'S[r

,, V.,. 7.{ 'j, -

The suppt'rt members anJ struttures s'at.pst in rummanon The esaminatico prfoer c.3 Junng cash m*pttica ;nte:v sha3 include thuse supparts fer ppng. uhes and purnps witnta shall cumdarnely ceser all suppert r.c.nners ar.J strut:u'es

, [' t ff;a tbe system Nu'tdary. whose str ;sturst integrity is rehed up m p.'.'< a=.4

' to withstand the Jests, toads and entmc.iriJuteJ ji'rt.aurnents.

'*3 3

..c-4:

ne support settags. f const. int and unWe pring type f;'M l M

,j. g hangers. snubters and she.k abs..rbers shd be mpe::ed in

, 4. f *{. ;

ve.fy proper Jistribution of Jeuen te2Js.irnong the sn..aated

, ' *,. *, ',)8 support ecmpenents.

': ~;

m

.c.

. ~ ~

w,,.

e MM

~4 8.7 all" MM/7,j.

f I

I DN$;ihg3Ma

~

r...

o

.........w,..

. w.

w.....

?.< :. -..:

2. ;.

. m

x. v...

..u.

..,. c... u

$.'. S f.&ld:

...~.A.,$

.('h.. ~, ; L

. -. h 8t. 6

.>i., j

~

4 2,y..,. ;.,C.. : *. -

'- ~~.' c....

~

.Z y p y yf g,...

y

}]y N.

' TN S E g w g

.h f.3..b ?,i, ;

f t-

.al.e.

NA

K 4

k. -

r Q

'*4'

=

3 s..

1,y, d.

g.

,)

.8*

.l, *,.

g.

g

.Mi*

%A

..T. *Q,,..a

,s.. s a. %

f1

(* hN AREAS SUBJECT TO EX AMINATIONS EXTENT AND FREOutNCY OF EXAMINATeONS

.tJ

.j s'

Ll

/Votf-

,.. )

L2 l'

PUY? f t.Si%S l.

, s The areas sah;cci to etartn atwn.m p*.mp s.wr.s J4i li.e sne.s:e 4 r: e c=..f

.sh. J.. am.s.tA J. u' 40.

h,,

, e I

mslude the mternal prewure N.cJ rs.u'f a.rs 3.t he.,u' prew..*es r.t.a.q m e.h w sad.J dc. w:*.

4l

-g purr.f.s p rf t.a m.ngt *. :. ar f ars to.n.

n me o s te n

.r.4..

muity raari.e.e4 Jart e e..h..%p.t.r. miend I r.c p**

- ae F d ~r.co m h. h p 2 r -<. c ; -

. e. -

caa nrar...s mas 6

tne...&.me% es.-i navr. ui p+...re t u. air g....

p

y

The v.amjna:wns i;f f.mp,w.p :r.a3 'e ;er!..:

<J..

/. 6

.near.-the end o.f :he r. p.u.*n ::. ers.4' yl' p

g_

.-l u

.J PRESLUH E CLN T O Ni%. M. OS t h V A L VE BOI;1F 5 TIE areas sub'p t tolut tu tion 441 ir. : Je tPe reci.wrc.

t he. e. utnation. : sri. am.J J.erme.4.% es.ra t,n irc.

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contamms welJn m utse b.sJacs ths.c inacs askt uses m n.mn,4 w :3 hsta.te less present ut

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p Ica.: .me sehs t e sit C'eS'are Wotamte "elJ'8 * *;13 J

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Si The area to be 'ummed Al m.tia.le the ne'J r eus and ine er. +.4 v.hes wh. '. 4. vi the same wastia.reu-J 4:.: -

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base c:esal fue one we th.sLnea tsessmJ ire eJ,e wf de es!J -

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The areas subject to ets:ninaten sha'l ir.stuJe the mteraal the m:ernal surfaces o's eme daassertt4ed *ahe i=:th pressure coundary surfaces, en salies three m.hes arid..cr.a

.ahout prevure contaming =eidse in cad i.! the e pc.r,

'f commal pipe stic.

sabes of t.'.e sa:ne ccnstr.ctenal druen. trunJasturi g -.et*.e man.fasturer and prt r-see s tcilar fuccnons m tre ost-

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sball be muacy etammed dur:n each insreenon m:end..N:

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sclested for the sol:stetris esaaunataan of the premresenras..,

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The esamination on salve booes nay te perfermJ a:

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y near the end,of,ca.h m ptisrs mienal.

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Mcd-d-N INTERIOR SURFACES AND INTERNAL COYPONEfsTS OF RE ACTC5R VESSELS

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The areas subjest to cummation shalt mslede thow areas The esaminatiotu of the mterme surfaces of tre sessel which are m.ade aceemble tur cummation bv the re noval of internal components asiJ the spa.e 'e'o=

the reaster 7'i componenti durma nonnal tetushqouta;;es..uch.ss the mtenor shall te perforfr.ed at me first refuehne outa[e r.J J4

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surfash of the rea. tor vewt. the internal coirp.ments, the subsequent refschng outJjes at appretMratch E.hree } ear t'f'%

meernal support.trashrnefits welJed to t'e seswl w.all. and the The esamination el.m. ternal erf. ort. sit.asame... *e!Jes ga.e Nl m the rea. tor. ore aaJ above the bett. m heaJ.

t the venel ms!! whs e 'at'ure may aJse.c:y affets crea i*.te

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shall be eummed at least onse Janeg cad m<rcettert ete.

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. Visual cuminat:vn shall cmer adJ.rmnai se!cced ;M i througrtout the sessel to provide a reawnaNy ret re cnt.:

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samphng of the conetton of the claJang.

Where secess to the space be!o= the reactee cure duem

'Q*j normal refuehng outages preclude > mstecen of t'us spass. -

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, least ene eurnmanos at or oc.ac the c:J of eacs -'P mienal, shall be conducted under sunJ2rioes stuch.rr'

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3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SCURCES OPERATI!:G LIMITI!:G C0!DITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
Two 345 KV transmission lines in service, and b.
One 345 KV - 13.8 KV startup transformer in service, and c.
One 13.8 KV bus energized, and d.
Two separate and independent diesel generators each with:
1.
A separate day tank containing a minimum of gallons of fuel
(
inches indicated), and 2.
A separate fuel oil transfer pump, and 3.
A com=on fuel oil storage system containing a minimum of
. gallons of tuel.
. APPLICABILITY: MODES 1,2,3, and 4 ACTION:
a.
With only one 345 KV transmission line in service or one diesel generator inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.la and 4.8.1.1.2a.5 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, unless the diesel generator (s) are already operating. Restore the requ!.rements of 3.8.1.la and d within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in COLD SHUTDOWN witnin the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months , b.
With only one 345 KV transmission line in service and one diesel genctator inoperable, demonstrate the OPERABILITY of the remaining A.C.
sources by performing Surveillance Requirements 4.8.1.1.la and 4.8.1.1.2a.5 within one hour and at 1 cast once per 3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months thereafter unless the diesel generator is already operating. Restore at least one of the inoperabic sources to OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in COLD SHL"IDU.C within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .
Restore the requirements of 3.8.1.la and b within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time of initial loss or be in COLD SHUTDCWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .
c.
With no 345 KV transmissien lines in service, de=onstrate the OPERASILITY of both diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.5 within one hour and at least once per S hours thereafter,
.unless the diesel generators are already operating. Restore at least one 345 KV transmission line to OPERAELE status withir. 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . With only one 345 KV transmisrion line resca red. restore - at icast two 345 KV transmission lines to OPERABLE status within-72 hours frem the time of initial loss or be in COLD SLUTDOWN p
///f2/7f within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months ,
.. ~ _ _. _ _,
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With tv) dies 21 gunsrators intparabic, drmonstrate th2 OPERABILITY of the transmission network by performing Surveillance Requirement 4.8.1.1.1.a within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable diesel generators to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in COLD SKUIDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .
Restore at icast two diesel generators to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the time of initial loss or be in COLD SHUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months , e.
With'no 345 KV - 13.8 startup transformer in service, demonstrate the OPERABILITY of both diesel generators by performing Surveillance Requirement 4.8.1.1.2.a.5 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thercafter, unless the diesel generators are already operating.
Restore at least one 345 KV - 13.8 KV startup transformer to OPERABLI status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and COLD 'S!IUTDOWN within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .
f.
With no 13.8 KV bus OPERA 3LE, be in COLD SHUTDOWN within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .
SURVEILLANCE RECUIREMESTS 4.8.1.1.1 The transmission networks into the station shall be demonstrated OPERABLE by:
a.
At least once per 7 days verifying correct breaker alignments, indicated power availability, and b.
At 1 cast once per 18 months, providing power to the station from cach of the individual transmission lines.
4.8.1.1.2 Each diesel generator shall be demonstrated OPERABLE:
a.
At 1 cast once per 31 days on a STAGGERED TEST BASIS by:
1.
Verifying the fuel level in the day fuel tank, 2.
Verifying the fuel icvel in the fuel oil storage tanh, 3.
Verifying that a sample of diesel fuel from the fuel oil storage tank is within the manufacturer's recommended limits for Cetane number and filtration cleanliness test, 4.
Verifying the fuel oil transfer pump can be started and transfers fuel oil from the fuel oil storage tank to the day tank, 5.
Verifying the diesel starts from ambient condition, 6.
Verifying the diesel generator is synchronized, loaded to 22000 EM, and operates for2:60 minutes, and 7.
Verifying the diesel generator is aligned to provide standby power to its associated essential busses.
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b.
At least once per 18 months during shutdown by:
1.
Subjecting the diesel to a thorough inspection in accordance with procedures prepared in conjunction with its manufacturer's recommendations for this class of standby service, to reject a load of Verifyingthegeneratorcapability/,d:e(.
2.
2 2000 kw without tripping 4 Ae c 3.
Each diesel generator shall be started automatically by a simulated loss of all normal AC power supplies coincident with a simulated safety actuation signal, and loaded sequentially with essential loads.
Proper operations shall be verified by bus load shedding and automatic starting of selected motors and equipment to establish that resotration with emergency power has been accomplished within 40 seconds and the diesel generator continues to operate for 15 minutes while its generator is loaded with the essential loads.
4.
Verifying that on the safety injection actuation signal, all diesel generator trips except engine overspeed and generator differential, are automatically bypassed.
5.
Verifying the diesel generator operates forz60 minutes while loaded to h2000 kw.
Verifying that the auto-connected loads to each diesel genera-tor do not exceed the 2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rating o kw.
2.4? 3 8
.4.5.1.1.3 Each 345 KV - 13.8 KV startup transformer shall be determined OPERABLE at least once per 7 days verifying correct breaker alignments from its power sources and indicated power availability.
4.8.1.1.4 Each 13.8 KV bus shall be determined OPERABLE and energized from normal AC sources at least once per 7 days by verifying correct breaker alignment and indicated power availability.
lllAl'75 9
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.., - - L ELECTRICAL POWFR SYSTEMS
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SHLTDOWN LTMITING CONDITION FO1 OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:
a.
One 345 KV transmission line in service, and b.
One 345 KV - 13.8 KV startup transformer in service, and c.
One 13.8 KV bus energized, and d.
One diesel generator with:
1.
A day tank containing a minimum of gallons of fuel (
inches indicated), and 2.
A fuel oil transfer pump, and 3.
A fuel oil storage system containing a minimum of gallons of fuel.
APPLICA3ILITY: MODES 5 and 6.
ACTION:
With less than the above minimum required A.C. electrical power sources OPERABLE, suspend _all operaticas involving CORE ALTERATIONS or positiv reactivity changes until the mini =um required A.C. electrical power sources are restored to OPERABLE status.
SURVEILLANCE RTOUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be demonstrated OPERABLE per Surveillance Requiremencs 4.8.1.1.1, 4.3.1.1.2, 4.8.1.1.3 and 4.8.1 1.4 h
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ML19326A126

Text

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