ML20078N661

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Proposed Tech Specs Supporting Performance of Drywell Bypass Leakage Rate Surveillance on Performance Based Interval
ML20078N661
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 02/10/1995
From:
ENTERGY OPERATIONS, INC.
To:
Shared Package
ML20078N651 List:
References
NUDOCS 9502160063
Download: ML20078N661 (55)
v • d • e


Text

' '

GNRO 95/00014 Enclosure 2 Page 1 Enclosure 2 Markup of Affected TS and Bases 9502160063 950210 PDR ADOCK 05000416 P PDR

l . LCO Aoplicability GNRO 95/00014 8 3.0 Enclosure 2 Page 2 BASES UC # or other specified _ conditions in the Applicability that LCO 3.0.4 (continued) result from O ., y shutdown.

Exceptions to LCO 3.0.4 are a ed n the individual Specifications. Exceptions may apply to all the ACTIONS or

[ to a specific Required Action of a Specification.

t gyg.g' ,

Surveillances do not have to be perfonned on the associated inoperable equipment (or on variables outside the specified limits), as pemitted by SR 3.0.1. Therefore, changing 3 ,0 N M00ES or other specified conditions while in an ACTIONS ggQl Condition, either in compliance with LCO 3.0.4, or where an exception to LC0 3.0.4 is stated, is not a violation of I SR 3.0.1 or SR 3.0.4 for those Surveillances that do not have to be perfomed due to the associated inoperable equipment. However, SRs must be met to ensure OPERA 81LITY prior to declaring the associated equipment OPERABLE (or variable within limits) and restoring compliance with the affected LCO.

LCO 3.0.5 LC0 3.0.5 establishes the allowance for restoring equipment to service under administrative controls when it has been i removed from service or declared inoperable to comply with i ACTIONS. The sole purpose of this Specification is to ,

provide an exception to LCO 3.0.2 (e.g., to not comply with the applicable Required Action (s)) to allow the perfomance ,

of SRs to demonstrate: )

I

a. The OPERASILITY of the equipment being returned to j service; or
b. The OPERABILITY of other equipment.

The a hinistrative controls ensure che time the equipment is returned to service in ccr.fitct with the requirements of the ACTIONS is limited to the time absolutely necessary to perfom the allowed SRs. This Specification does not provide time to perform any other preventive or corrective maintenance.

An example of demonstrating the OPERABILITY of the equipment j being returned to service is reopening a containment j (continued)

BWR/6 STS B 3.0-6 Rev. O, 09/28/92

-_ _ _ _ _ _ _ _ _ _ _ _ - _ - - _ _ _ _ . _ _ - _ _ _ _ - ' w, -

r- ,

GNRO 95/00014 1 Enclosure 2 Pags 3 INSERT B3.0-6A LCO 3.0.4 is only applicable when entering MODE 3 from MODE )

4, MODE 2 from MODE 3 or 4, or MODE 1 from MODE 2.

Furthermore, LCO 3.0.4 is applicable when entering any other specified condition in the Applicability only while operating in MODE 1, 2, or 3. The requirements of LCO 3.0.4 do not apply in MODES 4 and 5, or other specified conditions of the Applicability (unless in MODE 1, 2, or 3) because the ACTIONS of individual Specifications sufficiently define the remedial measure to be taken.

The ACTIONS for an inoperable required battery charger in LCO 3.8.4, "DC Sources - Operating," and LCO 3.8.5, "DC Sources - Shutdown," include a Note explicitly precluding entry into specific MODES or other specified conditions of the Applicability while relying on the ACTIONS. With an inoperable required battery charger this Note in LCO 3.8.4 prohibits entry in MODE 1, 2, or 3 except during power decreases and in LCO 3.8.5 prohibits starting movement of

/ irradiated fuel, entering MODE 4 from MODE 5, or loading

/ fuel 11 a, the vessel if the vessel is defueled .

\

s 13 t> I Con 1omeAh i

+

l l

l 4

I l

INSERT B 3.0-6  ;

GNRO 95/00014 Enclosure 2 Page 4 o

SR 3.1.3.2 -------.-----------NOTE----------- -------- - -

Notrequiredtobeperformeduntil($ days e i Lit_, _

, s after the control rod is3 withdrawn and 'I THERMAL POWER is greater than the LPSP of

/

the RPCS. ong 1 3.)

Insert each fully withdrawn control rod at 7 days C c,mM I least one notch.

I SR 3.1.3.3 ----.--.-..-------NOTE------.----

1 l

Not required to be perfonned until %c.---.. days *- l% l after the control rod is withdrawn and l THERMAL POWER is greater than the LPSP of the RPCS. )

Insert each partially withdrawn control rod 31 days at least one notch.

SR 3.1.3.4 Verify each control rod scram time from In accordance full with

@ M 7hwithdrawn seconds. to notch positionM 13 fis SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 l

(continued) i i

l BWR/6 STS 3.1-11 Rev. O, 09/28/92

l GNRO 95/00014 Enclosure 2 Page 5 Control Rod OPERA 8ILITY 8 3.1.3 g 8ASES ACTIONS k J (continued) inoperable control rods exist, the plant must be brought to a MODE in which the LCD does not apply. To achieve this status, the plant must be brought to M00E 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

This ensures all insertable control rods are inserted and places the reactor in a condition that does not re active function (i.e., scram) of the control rods. quire The the number of control rods permitted to be inoperable when operating above 10% RTP i.e., no CRDA considerations could be more than the value sp(ecified, but the occurrence o)f a large number of inoperable control rods could be indicative of a generic problem, aridinvestigation and resolution of I the potential problem should be undertaken. The allowed Completion Time of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is reasonable, based on operating experience, to reach MODE 3 from full power l conditions in an orderly manner and without challenging  ;

plant systems.  !

_ _ i 11 _

(pn%) cof i SURVEILLANCE SA 3.1.3.1 C*m"-*# l REQUIREMENTS "b

( The position of each control rod must be termined, to ,

ensure adequate information on control rod sition is '

available to the operator for determining 0PERASILITY 1 and controlling rod patterns. Control rod position may be j determined by the use of OPERABLE position indicators, by moving control rods to a position with an 0PERA8LE l indicator, or by the use of other appropriate methods. The l 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Frequency of this SA is based on operating  !

experience related to expected changes in control rod  ;

position and the availability of control rod position i indications in the control room.

SR 3.1.3.2 and SR 3.1.3.3 t omd 4 Control rod insertion capability is demonstrated by i

, w inserting each partially or fully withdrawn control rod at I Pubd least one notch and observing that the control rod moves.

s The control rod may then be returned to its original y position. This ensures the control rod is not stuck and is ImA / free to insert on a scram signal. These Surveillances are 8 7.l . ) se'mnot requireewhen 63Tsiikthe actual LPSP of the RPC since the ,

notch insertions may notpe compatible with the requirements 1

'- 7HERMAL PcWER s Im %

8WR/6 STS 8 3.1 18 Rev. 0, 09/28/92

GNRO 95/00014 Enclosure 2 Page 6 INSERT B 3.1-18A modified by Notes identifying that the Surveillances are 3,1 com med l

1 i

I INSERT B 3.1-18

GNRO 95/000%

4 Enclosure 2 Page 7 Control Rod OPERABILITY B 3.1.3 BASES k ,

I SURVEILLANCE SR 3.1.3.2 and SR 3.1.3.3  !

REQUIREMENTS (continued) of @ -iirrn -.a.y? (1C0 3.1.6) and the RPC 89u)5 (LCO3.3.2.1).3 The 7 day Frequency of SR 3.1.3.2 is based  :

i Gy_*A V( on operating experience related to the changes in CR0 performance and the ease of performin notch testing for fully withdrawn control rods. Partia l 03 3 3 - I T ft rods are tested at a 31 day Frequency,based y withdrawn on the control

' potential power reduction required to allow the control rod  ;

movement, and considering the large testing sample of 7'; SR 3.1.3.2. Furthermore, the 31 day Frequency takes into Cr M account operating experience related to chan es in CR0 performance. At any time, if a control rod s immovable, a determination of that control rod's trippability (OPERASILITY) must be made and appropriate action taken.

SR 3.1.3.4 Verifying the scram time for each control rod to notch position 13 is spPseconds provides reasonable assurance

- that the control rod will insert when required during a DBA or transient, thereby completing its shutdown function. ,

( " Reactor Drekee%b scramThis SR is performed in conjunction with the control rod J; time testin of SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4.

55 ## # (EEb he LOGIC SYSTEM FUNCTIONAL TEST in r

" LC0 3.3.1.14and the functional testing of SDV vent and drain i Lt trucACen,J complete testing of the assumed safety function.

The valves associated Frequencies are acceptable, considering the more h> > _ ""_" g' '('t Q""controlrodOPERA81LITYandoperatinfrequent testiex trience, which (SbV) Ved ad bsn shows scram times do not significant y c ange over an operating cycle.

%es,[_ ~

SA 3.1.3.5 Coupling verification is performed to ensure the control rod '

is connected to the CROM and will perform its intended function when necessary. The Surveillance requires verifying that a control rod does not i 1

overtravel position when it is fully w('tothdrawn.

to the withdrawn The  !

overtravel position feature provides a positive check on the coupling integrity, since only an uncoupled CRD can reach the overtrave position. The verification is required to be (continued)

BWR/6 STS B 3.1-19 Rev. O, 09/28/92

GNRO 95/00014 Enclosura 2 Page 8 INSERT B 3,1-19A i These Notes also provide a time allowance such that the Surveillances are not required to be performed until the next scheduled control rod testing for control rods of the same class (i.e., fully w-. thdrawn or partially withdrawn) These Notes provide this allowance to prevent unnecessary perturbations in i reactor operation to perform this testing on a control rod whose l surveillance class (i.e., fully withdrawn or partially withdrawn) J has changed.

3.I C o m m e. R t J

4 0

INSERT B 3.1-19

GNRO 95/00014 Encin .are 2 Page 9

. ~

Control Rod Siock Instrumentation 3.3.2.1 SURVEILLANCE REQUIRDIENTS

.....................................N0TES.-.-----.----..--..-

1. Refer to Table 3.3.2.1-1 to determine which SRs apply for each Centrol Rod Block Function. g
2. When b hannel is placed in an inoperable status solely far performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up t Gihours provided the associated Function maintains control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 -....-.---.-....--N0TE-------...-..---.--

Not required to be performed u__til n I hour y,3,7 , after THERMAL POWER is [ 7C"; 2 7 ___ -

    • - - - ~ _ [.... ----v- h- -a%

M. 3k}s-p . d $g+ p .'#

Perfom CHANNEL FUNCTIONAL 161. (Hf 50392[ days i

\

s SR 3.3.2.1.2 ----...---.-..--- N0TE.---.---.--------..

, M n'.c; Not required to be performed until I hour

, e.,J % % 35% RTP and a M RMAL POWER i >

t ga v u, m y.

weW ........................................-

Perfom CHANNEL FUNCTIONAL TEST. T92[ days SR 3.3.2.1.3 .-- ----...-----.-N0TE.-.------------..-.

ur A

Not required to be performed until 4 g,4 ATf after any control rod is withdrawn in r MODE 2. . 3. I

......................................... ' w4 Perform CHANNEL FUNCTIONAL TEST.

192fdaysh (continued)

BWR/6 STS 3.3 15 Rev. O, 09/28/92

GNRO 95/00014 Enclosure 2 Page 10 Control Rod Block Instrumentation 3.3.2.1 Table 3.3.2.1 1 (pose 1 of 1)

Centrol Rod Block Instrsmentation APPLICABLE MODES DE OTNER SPECIFIED RE0W!tED REVE!LLANCE FUNCTION COISITIONS CNANNEL5 REGUIREMENTS

1. Red Pettern Centret System 3.3.2 y
e. Red witteemet tietter N(e)F 2 SR 3.3.2.1.1 i SR 3.3.2.1.6 .,

S(b)@ 2 saj 3

b. Red pettom controtter 1(c),2(c) 2

_Q h th su s.s .2.l .3 c4 sa 3.3.2.1.6 #

SR 3.3.2.1 Ji _

kW,3r'

~

2. Remeter mees switch-Shutsam Peef tien (d) 2 3R 3.3.2.1.tp

.~~

jass %n u Qu%<~ %n % H P59 SR 3.3.2 (e) TWut4L MnER :

u_m e o.1gfgpto w (b) Tune 4L PetEn >%555 tTP andM 3.32.1

, 3.1 (c) WithTIEstALP0bERsN1tTESTP. h cemgM 4 (d) Reester made switch in the shutdem peeltien. N l5 BWR/6 STS 3.3-17 Rev. 0, 09/28/92

GNRO 95/00014 Enclosure 2 Page 11 PAM Instrumentation 3.3.3.1 femte 3.3.3.1 1 (sees 1 ef 1) peet Acttourit eenitertng inetrumentatien

]

CENSIf!CWS REFEREhCID Fe9E RSSJ! RED sEtuleED PLAICTION ChaceELS ACTION O.I 1 Reester Pressure 2 /E N

2. Soester Wesset Ideter Lowel - LJ A E. eta 2 /8'
3. Rest.%e Meusl L.lsbre Levef = f*msl Eont.o 2. f q J. Sweproosten Post laster Level 3.3,3 I. 2 f e*

8 /. DrywetL Pressure C## 2 s I

v. 1e,, . n va ee>+a z /e 12 f. Prisery Centairement Aree testation \ 2

^sef7-E g-

- s. - can ces woor&ee s z I , I I E. , _ ; . - __ - _ i Primar3 Mvipital A.*e 7 germ +. j 2 fg _p

/ 13 f. orymtt as533AEmeAliiilill Area Ra&V.e. gMs- 2 r 8.EPCiv Posttien (Psas4=6;a Elaw P*A 2 por /(

4 _i g QV (, sistammusammuseIFFRm apt.r12.J;a[em gl A p.* /h A'

{

N W. or,wtt u, 2 rg i e 4,a+rm4 A a J r%.

lI N.(Centei M Lyser r 2 ((

m 's 2 CI

+&w.

/ ,cieery Comei ereneure - e,* U:Je o.russ2.-ePe%

aJserm 4Ms ~*ta- c) /[t -

5,35. mapressian pesi isoter fassereture .1 f(

Sestoe)

I*I e _" $

$5 I.T )

e 1,e,1. ee. L, a =%.w.y9 @1 -

-(,Q Cah ens postIaw inad*ite.he=* chas e dl Is ry4alesd fes getralrl,a {\e.apalls wik enh 'enepi4ral c.,  ;# +:~t m et - -

eviamer u - .. e . a.a.a.i , i == - ___ rar eash ent se to Ust

1. Regutet

.itwe,ery

,a \.e . l er,ude 1.W ,ee fhinet..u r.,nd e s 2.

L wee t.pr see.tv ewmaien assert.

u . i. '

-e i,ie. - e pia is.te,,

\Q _

)

I in s%%.9 33 3.)

% n% '

l I

BWR/6 STS 3.3-21 Rev. O, 09/28/92

I. ,

GNRO 95/00014 Enclosure 2 Page 12

  • 09 SURVEILLANCE REQUIREMENTS *% 9'

)

.....................................N0TES.--------.....-..-----..............

1. Refer to Table 3.3.5.1 1 to determine which SRs apply for each ECCS Function.
2. . When a channel is placed in an inoperable status solely for performance of I required Surveillances, entry into associated Conditions and Required Actions may be delayed as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 3.c, 3.f 3.g, and 3.h; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 3.c, 3.f, 3.g and 3.h. provided the associated Function or the redundant Function maintains ECCS initiation capability.  !

SURVEILLANCE FREQUENCY SR 3.3.5.1.1 Perfom CHANNEL CHECK. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SR 3.3.5.1.2 Perfom CHANNEL FUNCTIONAL TEST.

h 2{ days l p 3.3.5.1.3 Calibrate the trip unit. [2[ days M SR 3.3.5.1.4 Perfom CHANNEL CALIBRATION. 92 days SR 3.3.5.1.5 Perfom CHANNEL CALIBRATION. [8[ months SR 3.3.5.1.6 Perfom LOGIC SYSTEM FUNCTIONAL [8{ monthsTEST. h a . ,

y SR .5.1.7 Ve the ECCS R E TINE is wit 418}' nths on limits. g a STAGG D

3. 3.5. I c o,-, J BWR/6 STS 3.3-38 Rev. O, 09/28/92

GNRO 95/00014 0

Enclosure 2 Page 13 ECCS Instrumentation 3.3.5.1 femte 3.3.5.1 1 (sese 3 of 5) teorgency Core Coeting Systee Instrumentation APetICASLE Coe!T10ms mots OR REFERENCED OfMER REGUIRED fetpl SPECIFIED CNAeNELS PER REGJIRED SURVEILLANCE ALLOWASLE RalCT10s Comit!Out PWCTION ACTIou A.1 ageUIREMEufs VALUE

3. Nigh Pressure Core M I sprey (IIPCs) system o T
e. Reacter Weeset 1,2,3, J4)(b) 8 sa 3.3.5.1.1 Water Levet - Low J.43.s> incnes Lou. Levet 2 6(e) 5(s)

Pf SR 3.3.5.1.2 Lgg 3,3,$,9,34 p f,

/' st 3.3.5.1.5

~ ~ - - ~

""' 3.3. f . /

b. Dryvett 1,2,3 J4)(#3 I st 3.3.5.1.1 s J1.44J pois camM Pressure - Nigh pp st 3.3.5.1.2 ja p pt s3.3.5.1.364 3.3.5.1.5 -

SR 3.3.5.1 4 '

~

=- '=_1.;.:.'.D-

c. Reacter Veneet 1,2,3, C st 3.3.5.1.1 s J55.7J inanes Weter st 3.3.5.1.2 # /*

Levet - Ogh, 4(a) $(e)

, 3.3.5.1.36 Lovet 8 st 3.3.5.1.5 a 3.3.5.1.6

d. Caniseneste 1,2,3, J27 9 a 3.3.5.1.1 t g 31 inehes storese Tent [r P e 3.3.5.1.3 r fe Levet - Lew 6(83,5(8I p 3.3.5.1.3F e 3.3.5.1.5 m 3J.5.1.6
e. segresalen poet 1,2,3 D st 3.3.5.1.1 s17.0[inehes Water Level - Nish a 3.3.5.1.2 A pM 3.3.5.1.3F 3.3.5.1.5 st 3.3.5.1.6 to3r f.hMPCS Pimp 1,2,3, I st 3.3.5.1.1 ab psie 3 3 6d Dtscheese a 3.3.5.1.2 %J) em,4 Pressure - Nish 4(a) 5(83 Asa 3.3.5.1.3 F i la 1'2 SJL (pypass>Q # SR 3.3.5.1.5 st 3.3.5.1.6 e2 *-
s. M system Flow 1,2,3, A18 E a 3.3.5.1.1 R$ P am one Sete - Law A a 3.3.5.1.2 s (typass>Q 6(e) 5(e)

A m 3.3.5.1. .la

  1. a 3.3.5.1.5 M 3.3.5.1.6 -

- h. limposet Inttietien 1,2,3, f1 C st 3.3.5.1.6 les g

-. 4(a)3(e)

(sentinues)

(e) een aseecteted enemystem(s) are resedired to be (PERA8LE.

(b) "i "" h-'-b . Sc\aewer p(c) menAloeecs reentfred is n. -to=initiate

_yOpennetthe esses ated_ 4 . m . %

e _=

'.. = 3.52; evec - shute . and sensensei. et.re.s ten t .,

levet le not within tWiletto of a 3. 2.2. 1 -

P (td N 5nk BWR/6 STS 3.3-41 Rev. O, 09/28/92

4 GNRO 95/00014 Enclosure 2 Page 14 i

', Primary Containment g lsolation Instrumentation 3.3.6.1 h J % e.j p

,r,.Cente,3.3.6hnsiet,.e6.*61 Tese

,e ,t i

.n i t _ t tion c.'h'gb o

APPL! CABLE CGSITI28 NEBES GR REFERENCID ofet REeJ!tED F40N SPECIFIED CNANNELS PER REeJIRED SERVE!LLANCE ALLOW 48LE FUNCTION CSSITICE gS8TSTEM ACTION C.1 REeJIRSENTS VALUE i._- C. _. , .vete 89RGs !.l d h ae.*

is.ietion 3

3.3.G.) e. Re E mismant mesa (1 per jF M 3.3.6.1.1 1 (1711*F yy = t.e . . ~.

! j;i!;ge

", b. Em E stpennt seen 2,3 Il por resel F SR 3.3.6.1.1 s (102]'F Differentist a 3.3.6.1.2

  1. femperature - uf sh et 3.3.6.1.5 p,j,. E 3.3.6.1 6 e. se =ter veneet water Lowel - Low, Level 3 3,4,5
  • E a

@y m 3.3.6.1.1 9e 3.3.6.1.2 i<<10.sr

m inohes y, gety J .3 ,L . ) a43 3.3.4.1.

CwdA E 336

  • P Il T8 M4 M _ m C . g.

. seester steau Dame 1,2,3 M

~~ %F W

M 3.3.6.1.1 stMysts Pressure - ulWi M 3.3.6.1.2 3.3.6.1. .

m 3.3.6.1 E 3.3.6.1 0 '4. Brymet t Preneure - nf sh 1,2,3 W F m 3.3.6.1.1 N 3.3.6.1.2

61. '

Is

(- ats 3.3.6.1.g

& L e.. p'.,..as l Zg :k dios I,2.5 S . M: iz., 7i!t Q irD --

ap

,i w_ -- _ -- -

- - - -- --- v- --_- _s  ;

c. # 4) only one trfp system rewired in IESES 6 and S with RM mutdown Casting System integrity esintefned.

y$ - v w-- , --v w. , ~. m.

(t. ) p,);+ k reaeL ow sdeu~ afo -g fc scure giw),er. flan oc e uc) da 4[e E R Cvt is perNssivt pre tsure .

( ' ' G ) tJi+ L rencko r- 54 w donc fessure less % 4Le rel4R.

W -k ?*M ssM f re ssa<c -

1 I

A-

.w .i

~

j 33  ?

st 3.3.r.. .1 ,a

~

' h _- se 3 . 3.G . I .1

- .sg. 3 3 . G . I . (a 52 0 '

~

J.3 4. \ ,.

yne a - - - -

3%

BWR/6 STS 3.3-58 Rev. O, 09/28/92

GNRO 95/00014

, Enclosure 2 Page 15 LOP Instrumentation 3.3.8.1 3.3 INSTRUMENTATION 3.3.8.1 Loss of Power (LOP) Instrumentation LCO 3.3.8.1 The LOP instrumentation for each Function in Table 3.3.8.1-1 shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, When the associated diesel generator (DG) is required to be OPERA 8LE by LCO 3.8.2, "AC Sources-Shutdown."

ACTIONS

.....................................N0TE-.-----.-----..-- -..---.............

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A. One or more channels A.1 Place channel in hhours inoperable. trip.

,p .

r-v 1 Required Action and l 11 Declare associated DG Immediately C associated Completion c. inoperable.

' Time not met. ,

I y- -

Tnuch 77 A 'h ~ C 5

1 BWR/5 STS 3.3-77 Rev. O, 09/28/92 i

- GNRO 95/00014 l Enclosure 2 Page 16 I 5

INSERT 77A i

t i

B. One or more B.1 Restore actuation 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Functions with capability. +

actuation I capability not maintained.  ;

i I

3.3. 't . \ l Co met.M l  !

5  !

F i i

. i i

)

1 i

?

~

i I

e i

I i

INSERT  !

GRAND GULF 3.3-77 [

4

, - . . , , , , , . , . - , - - - . . . - - , _ . . . . - _ . . . , . - - - - . - , . , - , - - . . . , . ,h

GNRO 95/00014 Enclosure 2 Page 17 Control Rod Block Instrumentation B 3.3.2.1 BASES APPLICABLE 1.a. Rod Withdrawal Limiter (continued)

SAFETY ANALYSES, ,

LCO, and The RWL satisfies Criterion 3 of the NRC Policy Statement. l APPLICABILITY Two channels of the RWL are available and are required to be l OPERABLE to ensure that no single instrument failure can

_ , preclude a rod block from this Function. f  ;

%ek  !

l 6 33-#) "*"i"*i 'P i"** ' "d i" *"* i"*

  • 'i'.The nominal setpoints are selected to ensure calculations that the setpoints do not exceed the Allowable Values between successive CHANNEL CALIBRATIONS. Operation with a 71M trip setpoint less conservative than the nominal trip Cwvwt\ setpoint, but within its Allowable Value, is acceptable.

Trip setpoints are those predetermined values of output at which an action should take place. The setpoints are compared to the actual process parameter (e.g., reactor power), and when the measured output value of the process parameter exceeds the setpoint, the associated device (e.g.,

trip unit) changes state. The analytic limits are derived from the limiting values of the process parameters obtained from the safety analysis. The Allowable Values are derived ,

from the analytic limits, corrected for calibration,  !

process, and some of the instrument errors. The trip setpoints are then detemined accounting for the remaining instrument errors (e.g., drift). The trip setpoints derived l in this manner provide adequate protection because I instrumentation uncertainties, process effects, calibration tolerances, instrument drive, and severe environment errors  !

(for channels that must function in harsh environments as defined by 10 CFR 50.49) are accounted for.

The RWL is assumed to mitigate the consequences of an RWE event when operating > 35% RTP. Below this power level, the consequences of an RWE event will not exceed the MCPR, and therefore the RWL is not required to be OPERABLE (Ref. 3).

1.b. Rod Pattern Controller The RPC enforces the banked position withdrawal sequence (BPWS) to ensure that the initial conditions of the CRDA analysis are not violated. The analytical methods and assumptions used in evaluating the CRDA are summarized in References 4, 5, and 6. The BPWS requires that control rods be moved in groups, with all control rods assigned to a specific group required to be within specified banked positions. Requirements that the control rod sequence is in (continued)

BWR/6 STS B 3.3-45 Rev. O, 09/28/92

~

s l GNRO 95/00014

  • Enclosure 2 Page 18 i

INSERT B 3.3-45A l The RWL high power function channels are OPERABLE when control l rod withdrawal is limited to no more than two notches. The RWL low power function channels are OPERABLE when control rod withdrawal is limited to no more than four notches.

3. ~3. D do m m s ett-0 1

l l

INSERT B 3.3-45 i

GNRO 95/00014 i Enclosure 2 Page 19 l Control Rod Block Instrumentation i B 3.3.2.1 BASES SURVEILLANCE o w associated lConditionsandRequiredActions may be delayed l

REQUIREMENTS for up to hours, provided the associate Function 4 (continued) maintains @controlrodblockcapability. Upon completion of  !

the Surveillance, or expiration of the hour allowance, the channel must be returned to OPERABLE s atus or the ,

33,g , l , applicable Condition entered and Required Actions taken.

Cow & l SR 3.3.2.1.1. SR 3.3.2.1.2. SR 3.3.2.1.3. and

) SR 3.3. W h The CHANNEL rUNCTIONAL TESTS for the RPC and RWL are i

8 3.3-W A J performed by attempting to withdraw a control rod not in v compliance with the orescribed sequence and verifyino that a i control rod block occurs.1/If t as found point is i (witnin it required owabl alue, th ant spec c setpoi methodo1 y may revised, s appropri , if

- CI ^

hi ry and al other pertinent infbmation indicate a eed]

f r the revi on. Thi setpointAshall be H M:EEP consistent ,

with tho assumptions of theJcurrent plant specific setpoint I h54*y methodo'ogy. As noted, the SRs are not required to be p(erfomed until e.g., after any 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> control rod after specified is withdrawn conditions in MODE 2). Thisare met allows entry into the appropriate conditions needed to perform the required SRs. The Frequencies are based on reliability analysis (Ref. 7).

SR 3.3.2.1.5 The LPSP is the point at which the RPCS askes the transition between the function of the RPC and the RWL. This transition point is automatically varied as a function of power. This power level is inferred from the first stage turbine pressure (one channel to each trip system). These power setpoints must be verified periodically to be within the Allowable Values. If any LPSP is nonconservative, then the affected Functions are considered inoperable. Since this channel has both upper and lower required limits, it is not allowed to be placed in a condition to enable either the RPC or RWL Function. Because main turbine bypass steam flow .

g p _- can affect the@ nonconservatively for the RWL, the RWL l is considered inoperable with any main turbine bypass valves l

/ open. The Frequency of days is based on the setpoint methodology utilized for these channels.

eO (continued)

B 3.3-49 Rev. O, 09/28/92 BWR/6 STS

s GNRO 95/00014

Enclosura 2 Pags 20 INSERT B 3.3-49A Proper operation of the RWL is verified by SR 3.3.2.1.1 which verifies proper operation of the two-notch withdrawal limit and SR 3.3.2.1.2 which verifies proper operation of the four-notch withdrawal limit. Proper operation of the RPC is verified by SR 3.3.2.1.3 and SR 3.3.1.4.
3. 3. a , i Comm wn i

a l

I l

INSERT B 3.3-49

s GNRO 95/00014 Enclosure 2 Page 21 ECCS Instrumentation B 3.3.5.1 BASES SURVEILLANCE SR 3.3.5.1.6 (continued)

REQUIREMENTS channel. The system functional testing performed in LCO 3.5.1, LCO 3.5.2, LCO 3.8.1, and LCO 3.8.2 overlaps this Surveillance to provide complete testing of the assumed safety function.

The[18fmonthFrequencyisbasedontheneedtoperform this Surveillance under the conditions that apply during a plant outag'e and the potential for unplanned transients if the Survei lance were performed with the reactor at power.

Operating experience has shown these e onents usually pass the Surveillance when perfonned at the 8[monthFrequency.

).3.5.( 3 . 3. 5.1.1 This R ensures at the indi dual channel r onse time CoM N are 1 than or al to the imum values as in th acciden analysis. sponse time esting accept a criteria inclu ed appfepic pMprea' der c et. - , Th i s I

CCS RESPONS TI ests onducted sont iJ/ anJ18)is g

ERED TES IS. F ency co istent with a typica ustry refue ng cycle and has upon plant rating ex ionce, which hows that rand failures of strumentati components using seriou response ti degradation, but not chan I failure, re inf quent.

REFERENCES 1. FSAR,Sectionh.2h

. 2. 14F5AR,Sectiong6.3[

3. (JFSAR, Chapter 15}(
4. NEDC-30936-P-A, '8WR Owners' Group Technical Specification Improvement Analyses for ECCS Actuation Instrumentation, Part 2," December 1988.

Q.- -- c . M m .. i: .:: , n :; h N T A ._, -

BWR/6 STS 8 3.3-128 Rev. O, 09/28/92 c

GNRO 95/00014

. Enclosure 2 Page 22 Primary Containment Isolation Instrumentation 3.34.I B 3.3.6.1 c .a -___.. h d brpell zs BASES SURVEILLANCE SR 3 . 3 . 6.1. F (c ued)

REQUIREMENTS Operating experience has shown these components usually pass the Surveillance when perfonned at the 18 month Frequency.

SR 3.3.6.1 Bi, hA C *

,3 - , --

(" 38

/ s This SR ensures that thl i ndividual channel response times i

~

fp , are less than or eq 'Jto' the - - -maximum values assumedg-* he ident ar =

" " " . - - - - SOLATION TINE fe a@ < acceptance criteria included in m- - -'r; :6 O'"" f l

Se_1g pmud>w, _

=_ _

l o to Surve11Tanh ates FhaY9t~PGiation 734 g det tors TI tes' ng.

y be e luded f Th Note i ISO necess 10N SYS RE beca e of <m}$0NSE e Q ;g

' ~~ di ficu :y of ge rating appro inte d ector nput 3.34.1 gna nd beca se the p inciple of det tor o ratio Co ed" irtu< ly ensu an ins antan s respo e t1 . Res onse 3g time 'or radi ion de tion annels hall measu d from det tor out t or th input f the f rst *_ trpnic c onent i the channel. g, -

V. Ns ISOf.ATION SY3 Tut RESPONSE TINE test onducted on an e * '_ge :e 18 month STAGGERED TEST BASIS. She-EmamWB test Frequency is consistent with the typical industry m fueling cycle and is based upon plant operating experience that shows that y, 3, c , , random failures of instrumentation components causing c ~,-= A serious response time degradation, but not channel failure, are infrequent.

REFERENCES Q chker

1. f tXSAR, C:.=i(6 .

2.(AFSAR, Chapter 915f

3. NED0-31466, " Technical Specification Screening Criteria Application and Risk Assessment,"

November 1987.

4. I)FSAR , Sectionh 9.3.5 f g

(continued)

BWR/6 STS B 3.3-176 Rev. O, 09/28/92

. - . . . . ~ - - - - - - . - . . . .- --- - .- --. -.. .-..

GNRO 95/00014

. Enclosure 2 Paga 23 INSERT B 3 . 3 --17 6 A

-- ' Testing is performed only on channels where the assumed l I.34.,

3 response time does not correspond to the diesel generator <

p (DG) start time. For channels assumed to respond within the (c D DG start time, sufficient margin exists in the 10 second N ,

start time svhen compared to the typical channel response time (milliceconds) so as to assure adecuate respon_se without a specific measurement __ test.f Testing of the closure  !

times of the MSIVs is not included in this Surveillance  !

since the closure time of the MSIVs is tested by SR 3.6.1.3.6.

-. / ,

.7. 3k . t  ;

Com ~< M  ;

I 1

l t

I i

i l

l f

i i

I

[

t 8

INSERT l B 3.3-176 1 i

. 1 GNRO 95/00014

I and R L3.L,.7.6 )

SURVEILLANCE SR 3.3.6.2.4 M n'tTnse~di REQUIREMENTS __

,be revised, appropr1 , if thefdstory and othe -

g ..ipertine formatio ndicate p need for th evision. he- l Iset shall b eft set consistent wit he assu. on lo he current n1 ant eaari ffe s.tnaint ==+hadalog ~ ~ 'g The Frequency [is Dased upon the assumption ofe? c c 3.3 6.t.4;

'n ctiib :- ;; nt: n : n C: ::::. . ::::: :y the magnitude I

of equipment arift in the setpoint analysis.

SR 3.3.6.

i The LOGIC SYSTEM FUNCTIONAL TEST demonstrates the OPERABILITY of the required isolation logic for a specific l channel. The system functional testing, performed on SCIVs -

and the SGT System in LC0 3.6.4.2 and LC0 3.6.4.3, respectively, overlaps this Surveillance to provide complete I testing of the assumed safety function. j The 18 month Frequency is based on the need to perfom this 3,3 , L, .Q Surveillance under the conditions that apply during a plant outage and the potential for an unplanned transient if the C=ea m Surveillance were performed with the reactor at power.

3s Operating experience has shown these components usually pass A the Surveillance when performed at the 18 month Frequency.  !

' LwN

B 3.3.i t9A sR 3.3.6. s7 This SR ensures that the individual channel response times 4 -

ke 9tcAk are 1 ss than or equa_1 to the maximum values assumed in the pl M prw M uf85-

?~x-b

- D ra -

W b_ h 3PN

,a 7:MC ,a' ISOLATION SYS"EM RESPONSE TIME

[i D'

l i

eri t.rin .i ncl uded i n LF --- ~ Q-

[_a.num,. m r.w m .v s 7 3L,,2 C='*

A Note to the Surveillance states that the radiation detectors may be excluded from ISOLATION SYSTEM RESPONSE TIME testing. This Note is necessary because of the difficulty of generating an appropriate detector input signal and because the principles of detector operation virtually ensure an instantaneous response time. Response time for radiation detector channels shall be measured from (continued)

BWR/6 STS B 3.3-189 Rev. O, 09/28/92

GNRO 95/00014  !

  • l

. Enclosure 2 Page 25 INSEPT B 3.3-189A Testing is performed only on channels where.the assumed 33GO response time does not correspond to the diesel generator C"# (DG) start time. For channels assumed to respond within the 35 i DG start time, sufficient margin exists in the 10 second

- start time when compared to the typical channel response time (milliseconds) so as to assure adequate response Aw'out a specific measurement test. (Testing of the closure rtimes of cae isolation dampers is not included in this Surveillance since the clo.aure time of the isolation dampers is tested by SR 3.6.4.2.2.

g f3.3. G I

G%ns l I

INSERT B 3.3-189 e

.g GNRO 95/00014 Enclosure 2 Page 26 LOP Instrumentation B 3.3.8.1 BASES --

Sec4ase of A redw*dcac3 of sensers avaM\e, 4, previde ACTIONS M M tk h 5lp W s , M keurs (continued) -

J ith one more c nels of unctiojVinoperapre,3hle y

- fFune n may no e capabl f perfpraina the rintances.)

1 V ction. T refore. on 1 hourAsfallowed to restore the .

nnoperable channel to OPERABLE status. If the inoperab e is l channel cannot be restored to OPERABLE status within the - i allowable out of service time, the channel must be placed i eS m'.. l the tripped condition per Required Action A.1. Placing the inoperable channel in trip would conservatively compensate  %) '

for the inoperability, restore capability to accoseedste a i single failure, and allow operation to continue. ,

Alternately, if it is not desired to place the channel in I trip (e.g., as in the case where placing the channel in trip would result in a DG initiation), Condition 8 must be entered and its Required Action taken.

l

, The Completion Time is intended to allow the operator time n The h)o evaluate and repair hour Completion Time is any discovered acceptable because inoperabilities.

it minimizes risk while allowing time for restoration or tripping of j q channels. ,

FLself T 6 3.S~DS

, , If any Required Action and associated Completion Time is not 3 ' 3,g , l met, the associated Function may not be capable of

""q performing the intended function. Therefore, the associated c DG(s) are declared inoperable iimmediately. This requires 5 entry into applicable Conditions and Required Actions of LC0 3.8.1 and LC0 3.8.2, which provide appropriate actions for the inoperable DG(s).

SURVEILLANCE As noted at the beginning of '.ne SRs, the SRs for each LOP REQUIREMENTS Instrumentation Function .re located in the SRs column of Table 3.3.8.1-1.

The Surveillances are modified by a Note to indicate that whan a channel is placed in an inoperable status solely for perfonsance of requirec' Surveillances, entry into associated ,

onditions and Required Actions may be delayed for up to l g hours provided the associated Function maintains DG initiation capability. Upon completion of the Surveillance, (continued) l BWR/6 STS B 3.3-237 Rev. O, 09/28/92 1

GNRO 95/00014 Enclosure 2 Pags 27 INSERT B 3.3-237A L.1 Required Action B.1 is intended to ensure that appropriate actions are taken if inoperable untripped channels result in the Function not maintaining LOP actuation capability for the associated Deisel Generator (DG). A Function is considered to not be maintaining actuation capability when sufficient channels are not OPERABLE or in trip (or the associated trip system is in trip), such that the given Function will not actuate the associated DG on a valid '

signal. For Functions 1.a, 1.c, 2.a, 2.c, 2d, and 2.e with one-out-of-two taken twice logic, this would require one of the trip systems to have at least two channels inoperable and not in trip. For Functions 1.b, 1.d, and 2.b this would require one trip system to have tbe required channel inoperable and not in trip.

The Completion Time is intended to allow the operator time to evaluate and repair any discovered inoperabilities. The 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Completion Time is acceptable because it minimizes risk while allowing time for restoration or tripping of channel (s).

(3.

3. T. I ce d l

l l

l l

INSERT B 3.3-237

~

GNRO 95/00014 Enclosure 2 Page 28 c, - a a',4 Recirculation Loops Operating 1 ~~ J ; I ~ , j Q\ eau % 341 (g.awtM kWt in 4 :.n 3 D of 4 3.4 REACTOR COOLANT SYSTEM (RCS) g pet 4 3,4.1.

F: ace 3.4.1 - I j / ,,dez, un%o\9e^ ) CJ) 3.4.1 Recirculation Loops Operating , gg p, ,

LCO 3.4.1 Two recirculation loops with matched flows shall be in "S M g

'CM c. - operatio,h gg G^k; 16:b One recirculation loo be in operationJ rovided the 09 M*J gsg followin limits are appn ea when the associated LCO is W applicab e:

q . , s ', gh l *' P o p.cd a "e ," a. LC0 3.2.1, ' AVERAGE PLANAR LINEAR HEAT GENERATION RATE #

spe.c:4:sA (APLHGR) ' single loop operation limits [specified in w Cp LR - theCOLR};

b. LC0 3.2.2, ' MINIMUM CRITICAL POWER RATIO (MCPR)," singig g loop operation limits [specified in the COLR];/m
c. 4C0 3.3 AI, "Reacto Protect 1 I ruments n," Fun n 2.b ystem (Rrs) le Powe M e

-h Moni Flow Sisu The r-H< ,

Value of e 3.3. . 1 is re for si le (Allowab loop operat -- ~ -

[Tnstek 14 h-h APPLICA8ILITY: MODES 1 and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A ". Requirements of the A.1 Satisfy the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCD not met, requirements of the LCO.

i A

P ntinuedf Nenaingresolutionofstaa111tyissue.

/ t * *

.-q kns.c4 1 O J BWR/6 STS 3.4-1 Rev. O, 09/28/92

GNRO 95/00014 i

Enclosure 2 Page 29 l

INSERT 1B (continued) l l

l C.1 @estorjtotalcore C. Total core flow as- )

j a function of / flow as a function ,

THERMAL POWER g of THERMAL POWER to '

within Region C within Region D. I

\

~

1 when not ,

withdrawing control g -

rods for startu .

e s 3,4 M e, e~< h 3

APRM neutron flux noise level s 10% /

peak-to-peak of p RTP. '

' I C

J ,

D. Total core flow as I D.1 Place the reactor Immediately a function of ) mode switch in the THERMAL POWER g shutdown position.

wi_ thin _ Regio _n_ B or egion C when not withdrawing control rods for startup.

M APRM neutron flux noise level > 10%

peak-to-peak of RTP. f E. Total core flow as E.1 Place the reactor Immediately a function of mode switch in the THERMAL POWER shutdown position.

within Region A.

DE No recirculation loops in operation in MODE 1.

i INSERT 3.4-1

GNRO 95/00014 Enclosure 2 Page 30 RCS P/T Limits 3.4.11 SURVEILUU$CE REQUIRDIENTS (continued)

SURVEILLANCE FREQUENCY 7 4' cj# SR 3.4.11.3

. . - - . - ~ ~ - - - - . . - N0 T E - . . . . . - ~ . - - . . . - - - . l M -

Only

  • required to be met in N00ES 1, 2, 3, I

, Av;g and([wigtreactor steam done pressure cse;ec.mie'on a.........

25 psig4. ................................

p 5**" Verify the difference between the botton Once within head coolant temperature and the reactor 15 minutes l pressurevessel(RPV)coolanttemperaturey prior to each l PCol 1s C- - "et ": ::::ffi:: in L " ~

startup of a l recirculation 93/11 '

. . ( jo3op pump R1 SR 3.4.11.4 ..-.~.-....... ~ .N0TE--- -. - -== --- -

only required to be met in NODES 1, 2, 3, l,'S e s.,

\.A: e and (.

....__..................................... l Y9 4 n h , Verify the difference between the reactor Once within 24 s , coolant temperature in the recirculation 15 minutes i

e#- prior to each 15 loop to be temperatu 3 instarted

v. tit;and ^.' the RPV
=n ::::Mi: coolant _ Pstartup of a b pm

~

  1. 0: M: .-4 93// t - recirculatio , 6 =M N

__ _ _ 4.So F' co (R1 ---

SR 3.4.11.5 ------ --- - . .- - . -NO T E. - - - - - . . . -- . . . - . . . .

Only required to be performed when tensioning the reactor vessel head boltinc studs.

Verify reactor vessel flance and honel 30 minutes flange temperatures are @': th; '

=i t." *-

A C ::Pt_ i: .. m e. 4 _ -- -_

D (continued)

C O L.

R3}ll' swA/6 STS 3.4-27 Rev. O, 09/28/92

GNRO 95/00014 Enclosura 2 Page 31 INSERT B5B ]h 4 co +

SR 3.4.1.2 t ..A ll r ThisSRensuresthereactorTHERMALPOWERandkcoreflowsare within appropriate parameter _ limits to orevent. uncontrolled _

power oscillations.;(The limits are Region D of Figure 3.4.1-1 or if withdrawing control rods for startuo, either Regio D (or, Region C 3 / At Fow recirculation flows and high reactor power, the reactor exhibits increased susceptibility to thermal hydraulic instability. Interim actions have been developed based on the guidance provided in References 4 and 5 to respond to operation in these conditions. This SR identifies when the conditions requiring these interim actions are necessary. The Frequency is based on operating experience i and the operators' inherent knowledge of reactor status, including significant changes in THERMAL POWER and core flow.

INSERT B5C G_2.1

- If the required limit modifications for single recirculation ,

loop operation are not performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after transition from two recirculation loop operation to single  ;

recirculation loop operation, the required limits which have

  1. not been modified must be immediately declared not met. The t , Required Actions for the associated limits must then be taken.

s 3.4 cond 4

i r

r i

INSERT B 3. 4 - 5 (i)

GNRO 95/00014 Enclosure 2 Page 32 i

RCS P/T Limits '

B 3.4.11 ,

BASES APPLICABLE are acceptance limits themselves since they preclude SAFETY ANALYSES operation in an unanalyzed condition.

(continued)

RCS P/T limits satisfy Criterion 2 of the NRC Policy Statement.

4 LCO The elements of this LCO are:

6fnnp't a.

RCS pressure empera DtureC o- 'vvC---.. M

[he limits specTfied 6 3N-53 A,l are within t ng: "2

b. The temperature difference between the reactor vessel h ,- bottom head coolant and the reactor pressure ressel (RPV) coolant is di 6 .. O.e M 2 cf tM "L"#iluring_ )

3 l_ 7 g , recirculation pump startug i (6 39-5.38 1. The temperature difference between the reactor coolant 2 in the respective _recircu'ation loop and in the reactor vessel q = x.e r t =_ ~ = during pump startug 5 5@A F d. RCS pressure and temperature are within the 7^ criticality limits specified in-m 7. 07. - -

6 3 N - 5 3 C. j l3 s '7o T

' e. The reactor vessel h

flance and" the head flanne 7** '

temperatures t v- tt: rr : "- "" 5when

-+w sisn%,eactor tS ) vessel head >olting studs _.. . 2 1 d.%.

These limits define allowable operating regions and permit a large number of operating cycles while also providing a wide margin to nonductile failure.

The rate of change of temperature limits control the thermal gradient through the vessel wall and are used as inputs for calculating the heatup, cooldown, and inservice leak and hydrostatic testing P/T limit curves. Thus, the LCO for the rate of change of temperature restricts stresses caused by thermal grad'ents and also ensures the validity of the P/T limit curves.

Violation of the limits places the reactor vessel outside of the bounds of the stress analyses and can increase stresses in other RCS components. The consequences depend on several factors, as follows:

(continued)

BWR/6 STS B 3.4-53 Rev. O, 09/28/92

GNRO 95/00014 Enclosure 2 Page 33 INSERT B 3.4-53A Figure 3.4.11-1 and heatup or cooldown rate is s 100 oF in any one hour period during RCS heatup, cooldown, and inservice leak and hydrostatic testing.

INSERT B 3.4-53B and during increases in THERMAL POWER or loop flow while operating at low THERMAL POWER or loop flow INSERT B 3.4-53C )

Figure 3.4.11-1 prior to achieving criticality 3,9

@me 7 ;t I

i 1

j l

l 1

1 INSERT B 3.4-53

GNRO 95/00014

. Enclosure 2 Page 34 ECCS-Operating I 3.5.1 l SURVEILUUICE REQUIREMENTS (continued)  !

SURVEILUW6CE FREQUENCY SR 3.5.1.7 -----.-.--------.--NOTE.--------------.----  !

Not required to3e performed until_12_ hours gy after reactor.4 teas @ pressure @ o vd %u G :_ -- ;- = _are adegm+e 4 perform Ae +est.

Verify each ADS valve opens when manually 18 sonths on actuated.

a STAGGERED )

TEST BASIS for each valve solenoid 9

In54t.ek 3,5 - (o A

\

(

\

c 3.a5 l

I BWR/6 STS 3.5-6 Rev. O, 09/28/92

GNRO 95/00014

Enclosure 2 Page 35 i

INSERT 3.5-6A f

SR 3.5.1.8 Verify the ECCS RESPONSE TIME for 18 months the HPCS System is within limits. l t

r 3,5 C-m%smh l

l l

l INSERT 3.5-6

, , . . +-

GNRO 95/00014

, Enclosure 2 Page 36 ECCS-Shutdown 3.5.2 SURVEILUUICE REQUIREMENTS (continued)

SURVEILUUICE FREQUENCY.

wak _ __.

SR 3.5.2.5 Verify each required ECCS

..-pump develops the In accordance

'* with the s -

: : 2-- tr c:pecified _ _-: flow rath !---specified 6 h
sthe Inserviceg g u---- r- -

- - - = Testing 3g  : _qde nI,p4 hQ(r3 -rat hErELOPEb Program ee C* }"

- - - ~

hh - _ - = - ._ _ _

b 23I3 FLOW RATE

\f LPCs %a '.7115, k  %

a.'

y j gym ps

, , I LPCI k' t' ps ,

i HPCS Pl7450l 7115 mM laps l

SR 3.5.2.6 -.--.....----.--...N0TE-....-..-----.....;.

Vessel injection / spray may be excluded.

h Verify each required ECC$ injection / spray subsystem actuates on an actual or k18[ months simulated automatic initiation signal.

P bst e- 3.5 g 3.5- JD 6 6

BWR/6 STS 3.5-10 Rev. 0, 09/28/92

GNRO 95/00014 Enclosure 2 Page 37 i

INSERT 3.5-10A SR 3.5.2.7 Verify the ECCS RESPONSE TIME'for 18 months the required HPCS System is within limits.

3.5 Cewnt

-I l

i l

INSERT 3.5-10

~

i GNRO 95/00014 Enclosure 2 Page 38 ECCS-Operating B 3.5.1 BASES SURVEILLANCE SR 3.5.1.7 (continued) de'3 shr+mp fed)

REQUIREMENTS d - ~- -- ^

Surveillance under the conditions that apply (spuca plar.t

,5 C1) outage and the potential

re =forr wit:

Runplanned transienPts.,e]e s.

twM (L e et:::::: e re tr: r:::ter  :: ::;;r. ,-

Operating experience has shown that these components usually

- pass the SR when performed at the 18 month Frequency, which LM) is based on the refueling cycle. Therefore, the Frequency was concluded to be acceptable from a reliability L6 3 5'83A  % standpoint.

n REFERENCES 'i 1.

WRFSAR,SectioD6.3.2.2.37

2. UFSAR,Sectioh6.3.2.2.4[
3. 11FSAR,Section)6.3.2.2.lf
4. tAFSAR,SectioD6.3.2.2.2f'
5. IlFSAR, Section 11";.

Qg 6. UFSAR,SectioD15.6.4f

7. gFSAR, SectioY{15.6.5k l
8. 10 CFR 50, Appendix K.
9. QFSAR, Sectio {6.3.3[
10. 10 CFR 50.46.

11.QFSAR,Sectioh6.3.3.3[

~

12. Memorandum from R.L. Baer (NRC) to V. Stello, Jr.

(NRC), ' Recommended Interim Revisions to LCO's for ECCS Components," December 1,1975.

13. UFSAR, Section 6.3.3.7.8k 114. QFSAR, Sectioh7.3.1.1.1.4.2k l

l BWR/6 STS B 3.5-13 Rev. O, 09/28/92

o l '

GNRO 95/00014

- Enclosure 2 Pags 39 s

INSERT B 3.5-13A SR 3.5.1.8 This SR ensures that the HPCS System response time is less than .

or equal to the maximum value assumed in the accident analysis.  ;

HPCS System ECCS SYSTEM RESPONSE TIME acceptance criteria are included in the applicable plant procedures. Although the ,

associated actuation instrumentation is tested to met this  ;

Surveillance, the Surveillance and ACTION requirements for the associated instrumentation is controlled by LCO 3.3.5.1. l HPCS System ECCS SYSTEM RESPONSE TIME tests are conducted every l' 18 months with the response time testing of the associated HPCS actuation instrumentation performed on a 18 month STAGGERED TEST '

BASIS. This Frequency is consistent with the typical industry refueling cycle and is based on industry operating experience.

i l'

2f . 5 l l

comm=M I

I 1

INSERT l B 3.5-13 J

/

GNRO 95/00014

,' Enclosure 2 Page 40 ECCS-Shutdown B 3.5.2 BASES SURVEILLANCE SR 3.5.2.4 _

REQUIREMENTS (continued) Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides  :

assurance that the proper flow paths will exist for ECCS operation. This SR does not apply to valves that are locked, sealed, or othemise secured in position since these valves were verified to be in the correct position prior to locking, sealing, or securing. A valve that receives an initiation signal is allowed to be in a nonaccident position previded the valve will automatically reposition in the proper stroke time. This SR does not require any testing or valve manipulation; rather, it involves verification that those valves capable of potentially being mispositioned are in the correct position. This SR does not apply to valves that cannot be inadvertently misaligned, such as check valves. The 31 day Frequency is appropriate because the valves are operated under procedural control and the probability of their being mispositioned during this time

period is low.

In MODES 4 and 5, the RHR System may operate in the shutdown -

i i # Y cooling modeMo remove decay heat and sensible heat from the L to allou> reactor. Therefore, RHR valves that are required for LPCI grek means subsystem opfration may be aligned for decay heat removal.

-_- GiEEEfiiiSR Jhis SR is modified by a Note that allows one

' LPCI subsystem of the RHR System to be considered OPERABLE for the ECCS function if all the required valves in the LPCI flow path can be manually realigned (remote or local) to U"k allow injection into the RPV and the system is not othemise inoperable. This will ensure adequate core cooling if an

[ 3#~ N b inadvertent vessel draindown should occur.

c REFERENCES 1. MFSAR, Secti A

6.3.3.'4h BWR/6 STS B 3.5-18 Rev. O, 09/28/92

< GNRO 95/00014 Enclosure 2 Pags 41 INSERT B 3.5-18A SR 3.5.2.7 This SR ensures that the HPCS System response time is less than or equal to the maximum value assumed in the accident analysis. -

HPCS System ECCS SYSTEM RESPONSE TIME acceptance criteria are included in the applicable plant procedures. Although the associated actuation instrumentation is tested to met this surveillance, the Surveillance and ACTION requirements for the associated instrumentation is controlled by LCO 3.3.5.1.

HPCS System ECCS SYSTEM RESPONSE TIME tests are conducted every 18 months with the response time testing of the associated HPCS actuation instrumentation performed on a 18 month STAGGERED TEST BASIS. This Frequency is consistent with the typical industry refueling cycle and is based on industry operating experience. -

7. 5 i

\ cmb l l

1 l

- I l

INSERT B 3.5-13

i e

GNRO 95/00014 Enclosure 2 Page 42 Orywell 3.6.5.1 3.6 CONTAIM ENT SYSTEMS 3.6.5.1 Drywell LCO 3.6.5.1 The drywell shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTIONS CONDITION REQUIRED AC710N COMPLETION TIME l

A. Drywell inoperable. A.1 Restore drywell to 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> OPERABLE status.

. B. Required Action and 8.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met. E B.2 Be in WJOE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> l

o ,

Q wo$$

'n~')~i w m.os f-+~.a.- . k ~- $ E 5 ' ,

SURVEILLANCE REQUIREMENTS 4:ch*)r ja & Ji[; L 7 t

~ ~

[SURVEILLdt FREQUENCY 4 Q83 N merMust h) i 3.6.5.1.11 Verify bypass leakage ishI'0Sthe' 918fmonths- Olt I 6(.Ji_R

..s.I bypass leakage limit y  %

(93/f sj l d

  • T;, "
  • i W nse.e4 sq B '

.Q c--a

, SR 3.6.5.1.2 Visually inspect the exposed accessible nter r and exterior surfaces of the Q@rM- _ 9 g g

, r._.sAh6

' < . ek 'T 9 h,g,g ,g "N#'N h N c, s - L.1 l.l 9

BWR/6 STS 3.6-54 Rev. O, 09/28/92

~

GNRO 95/00014

/.

Enclosura 2 Page 43 6 SecondaryContainmentf B 3.6.4.1 BASES SURVEILLANCE JSR 3.6.4.1. andbR 3.6.4.1,f' (continued) c.

l REQUIREMENTS F 4 i SR 3.6.4.1 erifies that the SGT System will rapidly -- \

establish maintainapressureinthejsecondary pcgA&]ct l

containmentPthat is less than the lowest postulated -

pressureexternaltothe4fsecondarycontainmentFboundary. '

This is confirmed by demonstrating that ong 53iD subsys will draw down the4 secondary containment}4o ej0.25}Hnches of vacuum water gauqe in sJ120}4econds. /

Og } This cannot be accomplished if the* ondary containment}' /

boundary is not intact. SR 3.6.4.1 emonstrates that each I' SGTsubsystemcanmaintaineJ0.266 nches of vacuum water gauge for I hour at a flow fate sj4000Pcfm. The I hour test period allowsjsecondary containmentPto be in thermal equilibrium at steady state conditions. Therefore, these two tests are used to ensurpe{ secondary containment}>-

boundary integrity. Since these SRs arQecondary containmentPtests, they need not be performed with each SGT subsystesL The SGT subsystems are tested on a STAGGERED TEST BASIS, however, to ensure that in addition to the requirements of LCO 3 E A 1- either SGT subsvstem will wrform this test.]The 1Nonth Frequency i li d to per ru this Survei%nce under the cobasedonthe] itions that

- app during plant outage anE the potential fo an unpla ed tran nt if the Surveillance were performed with thereactoratp r./Uperating experience has shown t e 's cm .....ts usually PTss the Surveillance when performed at l the

@ conc /18]8 month Frequency. Therefore, the Frequency was uded to be acceptable from a reliability standpoint.

REFERENCES 1.h t/FSAR, Section h 5.6.5 h  ;

N 2.kFSAR,Sectionk5.7.6h

3. kFSAR, Section 5.7.4 BWR/6 STS B 3.6-91 Rev. O, 09/28/92

' GNRO 95/00014 ,

Enclosure 2 Paga 44 ,

Drywell B 3.6.5.1  ;

BASES l

ACTIONS M (continued) conwn3 urate with the importance of maintaining the drywell OPERABLE during MODES 1, 2, and 3. This time period also  :

ensures that the probability of an accident (requiring drywell OPERABILITV) occurring during periods when the  !

drywell is inoperable is minimal. Also, the Completion Time is the same as that applied to inoperability of the primary containment in LCO 3.6.1.1, " Primary Containment."

i B.1 and 8.2 If the drywell cannot be restored to OPERA 8LE status within ,

the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within i 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and to MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant condition: frca full power conditions in an orderly manner and without challenging plant systems.

s 3.6 .6.1 SR Q.

3.6.5.1.1 o,9 ks % [c y.JD -

SURVEILLANCE REQUIREMENTS The analyses in Reference 2 arelbased on a maximum drywell 4

'g bypass leakage. ThisSurveillanYcensures that the actqalf <

drywell bypas design value o eip u.' "the acceptable ANc M ft assun NethLsafety analysis./L6m-4 :

The'eskagetestisperformed'every714fmonths,' consistent with the difficulty of performing the test, risk of high PCoC radiation exposure, and the remote possibility that a q3/f3 component failure that is not identified h some other drywell or primary containment SR might occur. Operating 2.c .s .

experience has shown that these e dents usually pass the aga Surveillance when performed at the ,18f oonth Frequency.

Therefore, the Frequency was concluded to be acceptable from a reliability standpoint.

l SR 3.6.5.1.2 l The exposed accessible drywell interior and exterior  ;

surfaces are inspected to ensure there are no apparent (continued)

BWR/6 STS 8 3.6-110 Rev. O, 09/28/92 l

l

,' GNRO 95/00014

,' Enclosure 2 Page 45 h SW Systemand[UNS[

S 3.7.1 BASES i wro APPLICABLE is the failure of one of the two standb DGs, which_would in SAFETY ANALYSES turn affect one/SSWf subsystem. Thed low assumed in the analyses is P^6 gpa per pump to t heat exchen er (continued)@ WFSAR,TableJ6.MtRef.7). Reference 2 discusses $$W}*

System performance during these conditions. ,

ThehSW[ System,t therwiththe[UNS[ satisfy Criterion 3 of the Policy Statement.

I LC0 The OPERASILITY of subsystem A (Division 1) and subsystem 8 h (Division 2) of the4SSW}8 System is required to ensure the effective operation of the RHR System in removing heat from the reactor, and the effective operation of other safety related equipment during a DBA or transient. Requiring both subsystems to be OPERABLE ensures that either subsystem A or 8 will be available to provide adequate capability ta meet cooling requirements.of the equipment required for safa

,d shutdown in the event of a single failure.

A subsystem is considered OPERABLE when:

a. The associated pep is OPERABLE; b., L esedeWMfi:: Ofi=d 4,%4 'The associated piping, valves, instrumentation, and controls required to perform the safety related function are OPERABLE.

I 1 -

^OPIERASILITY = r =of..- the h[is r v based ofc- ' on ar "-

e k=

cr e. A *E h -

W;:- t m -" ~

. min' mum assin water leve' at or above e ovation r'-- -

  • ]o js pe#A8L p330 ft 3 inWeean sea level (equivalent to'an indicated [$)

.four WRMER* cooling tower v.

LO d g/ Lg .evel of a 7 ft 3 i fante a* oPse4aw cip6 he bebeenl

. e..tN twee k_cias-w /

h s -

\;c,oMgC The isolation of the Sy su w c - m..; . s or syst may render those components or systems inoperable, but does % ,

g not affect the OPERASILITY of the JS g System.

APPLICA81LITYhInHDDES1,2,and3,the System and are required to be OPERABLE to support 0PERASILITY of the OPERABILsTV o[h Hip Pressure Cote Sptq(BPCO SerAce d[cc Gefs.4 6u5h 's]

dArenad bg Lto 1.17., " HPCS 5 0M." r (continuec)

BWR/6 STS 8 3.7 3 Rev. 0, 09/28/92

. ,- GNRO 95/00014 Enclosure 2 Page 46 Main Condenser Offgas 8 3.7.5 BASES ACT!0 pts 3.1. B.2. B.3.1. and B.3.2 (continued) -

allowed Completion Times are reasonable, based on operating experience, to reach the mquired unit conditions from full 1 power conditions in an orderly manner and without '

challenging unit systems. I I

1 SURVEILLAleCE REQUI SR 3.7.5. b b 3.~l l

% hELh -

' Qs, 3, .]. 5. , on a 31 day Frequency, requires an isotopic ,

analysis of an offgas sample to ensure that the required )

/ ",3 limits am satisfied. The noble gases to be sampled  !

m Cem,

/i Xe-133. Xe-135, Xe-138, Kr-45 Kr-47, and Kr-SS. If the '

freleAjs asesuredtate of radioactivity increases significantly (by

( l(o,/: c.

, a 504 after correcting for espected increases due to changes in THDpt4L POWER), an 1se1asic analysis is aise perfenued  !

r within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after the ' acrease is noted! te sasure that i

' = -

"bqYee) -

5 A 33.5. I the increase is not indicative of a sustained increase la the radioactivity rate. The 31 day Frequency is adequate in view of other instrumentation that continuously menitor the l

\

, effgas, and is acceptable based on operating esperience. I

~

" 9Sfis modified by a liste indicating that the SR is not F.7 O, ired te he rfereed until 31 days after any N g mg - -I 5JAE is in operation. Only in a3l,3 this c on can we fission gases be in the plain do* Condenser Offges System at significant rates.

REFERDICES 1.

A FSAR,Sectionh5 1h

2. IRNtEE-0000.

. 3. 10 CFR 100.

i IWR/6 STS 8 3.7-26 Itev. O, 09/28/92

)

GNRO 95/00014

. Enclosure 2 Page 47 AC Sources-Operating 8 3.8.1

\ & wottrMM BASES SURVEILLANCE

{ &

Where the SRs discussed herein specify voltage an frequency 3-W

~_

A REQUIREMENTS (continued)

(tolerances, the - '2--""-

minimum 7 steady statt output volt' age of' a;;.;M The-(.h the nominal 4160 V .nnut voltage. Tht: & :, d ich i:

04 6 V .;;,u . ii e ~ in am < Wh ("ef. Ib , allo for voltage dro to the reinals , t0D V tors whos minimum oper ting tasp d % A is spe fled as W , or 3600 It also a ows for Mb$ lo#o/ of 0

rolta .

rol ge drops o motors d other e ipment down rough th l2 V level ere mini operatin voltage is so usuall s cified s 90% of me plate r ing. The sp ified

/ ximum eady stat output vol ge of {9756' V is equ to the max a operat g voltage ecified for LOOO V no rs.

It ens res that r a lightly oaded distr' ution' sy tem cy7 the ltage at the. t % e 4 - e terminals

-etM ^="r_Ha" ofval4000 haa . V moyThe specified g uencies of the DG a W 58.8 Hz and minimum and maximum 61.2 Hz, respective 16) freq% are equal to t 2% of the 60 Hz nominal frMuenc0.and are derived from the

) recommendations given in Regulato y ide 1.9 (Ref. 3).

Th Re&eadySykhva/Q

( SR 3.8.1.1 Nf This SR ensures proper circuit continuity for the offsite AC electrical power supply to the onsite distribution network and availability of offsite AC electrical power. The breaker alignment verifies that each breaker is in its correct position to ensure that distribution buses and loads are connected to their preferred power source and that a>propriate independence of offsite circuits is maintained.

T1e 7 day Frequency is adequate since breaker position is not likely to change without the operator being aware of it,

and because its status is displayed in the control room.

,i _ _

S'R 3.8.1.2 fnd ?" 2.". @ ' -

M4hese-Str helho ensure the availability of the standby electrical power supply to mitigate DBAs and transients and maintain the unit in a safe shutdown cordition.

OP33 To minimize the @ wear on moving parts that do not ge lubricated when th ibis SR M: modified by\Noter e engine (Met? is 1 not farurunning, amLv u th;a f ; .";

hn
; ; m is 5" 3.". .2) to indicate that all DG starts for 1 os (continued)

BWR/6 STS B 3.8-16 Rev. O,09/28/92

~

s GNRO 95/00014 Enclosure 2 Paga 48 INSERT 26A ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required -------NOTE---------- ,

battery charger Entry into MODE 1, 2 or 3 30 is not allowed, except Co" inoperable. I

~~ ^- M during power reductions.

................__.......g A.1 Verify battery cell parameters meet Table 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 3.8.6-1 Category A limits. M Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter B. Required Action B.1 Declare associated Immediately and associated battery inoperable.

Completion Time of Condition A not met.

l INSERT 3.8-26

NRO 95/00014

  • Enclosure 2 Page 49 INSERT 30A ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One required -----------NOTE--- --

r battery charger i Entry into MODE 4 or 5, orf g l inoperable, commencing movement of 3,g \

! irradiated fuel is not - -

j l '

allowed, except entry into MODE 4 or 5 can be made as 29 part of a unit shutdown.

A.1 Verify battery cell 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> parameters meet Table 3.8.6-1 AHQ Category A limits.

Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter .

B. Required Action B.1 Declare associated Immediately and associated battery inoperable. i Completion Time of Condition A not

    • U*

3,3 I y dp) 9T INSERT 30B e 1

',fThefollowingshallbeOPERABLE:

a. One Class 1E: DC electrical power subsystem capable of supplying one division of the Division 1 or 2 onsite Class 1E DC electrical power distribution subsystem (s) required by LCO 3.8.8, " Distribution Systems - Shutdown";
b. One Class 1E battery or battery charger, other than the DC electrical power subsystem in LCO 3.8.5.a, capable of supplying the remaining Division 1 or 2 onsite Class 1E DC  !

electrical power distribution subsystem (s) when required by LCO 3.8.8; and

c. The Division 3 DC electrical power subsystem capable of supplying the Division 3 onsite Class 1E DC electrical power distribution subsystem, when the Division 3 onsite Class 1E DC electrical power distribution subsystem is required by LCO 3.8.8.

INSERT 3.8-30 j

' GNRO 95/00014

,. Enclosure 2 Page 50 T3 L.5m :m.e

'caN N _

Ecocp m% J [ p jA 5.0 ADMINISTRATIVE CONTROLS _

' 5. 5 M hnlcal Specifications (TS) Bases _C Tnd b.v. o l'oA 6 @ Changes to the Bases of the TS shall be made under appropriate administrative controls and y::' n :: :: -di ; %

^-' m cMi:n 0 9 /

y 5'

  • @b Licensees may make changes to Bases without prior NRC app o al provided the changes do not involve either of the following:

l i

1. h. A change in the TS in orated in the license; or )
9. I h. A change to the gSAR or Bases that involves an 1

+ unreviewed safety question as defined in 10 CFR 50.59.

l Cp

- Q C.

The Bases Control Program shall contain provisions A ensure th t Bases are maintained consistent with theuFSAR.t9 g,o W 4 e:.'N, 2 7 o g s . g i,1 f 5gnOOc.hn S f. )).b3) - Egyh J C h Proposed changes that'm Mehe criteria of 6? ^- fNbove shall be reviewed and approved by the NRC prior to ' aplementation. )

j Changes to the Bases implemented without prior NRC approval shall '

be provided to the NRC on a frequency consistent with 10 CFR 50.71.

a (Q

i 1

BWR/6 STS 5.0-16 Rev. O, 09/28/92

~

~

GNRO 95/00014

Enclosure 3 Page 1 1

Enclosure 3 TS Tables

I

RCi P T LIMIT!

A - INSERv!CE LEAK AND HYDROTEST 3,4,y y 8 - NON-NUCLEAR HEAT UP & COOLDOWN LIMIT C - NUCLEAR (CORE CRITICAL) HEAT UP & COOLDOWN LIMIT GNRO 95/00014 Enclosure 3 Page 2 A B C 1400 1 i , , ,

!  ! , I J i i i n BOTTOM HEAD ' ' '

PENETRATION CONTROLLED -' i f l r J-f i l~ ~ i 1200 / f N

, - BELTLINE

/ j f CONTROLLED r

i l

i l

/ i r

._ 1 F [

[ [ [ CURVES B & C ARE O 1000 i e J BASED ON AN ART 4 ' I I 0F 25.76 oF p [ [ [ OF BELTL]NE. f a J i 1 CURVE 'A' ]$ NOT o r rh f BELTLINE CONTROLLED.

,~

i i

i.

N 17m s 3

a. 800 l l l ' ~

[ [

Z

/ r i

" FEEDWATER NOZZLE

[ I i CONTROLLED o 2 2

% Y  ?  ?

b 600 / / CURVES A.B & C ARE uJ f f PREDICTED TO BE CC APPLICABLE FOR SERV!CE D PERIODS UP TO AND

$ INCLUDING 10 EFPY.

1 L ----a w 400  % -~~ L L E :Z:0 t

BOLT UP LIMIT / 312 psig --

_. 70o F a , ,

i s

' ' r ACCEPTABLE REGION OF 200 / s r OPERATION 15 TO THE RIGHT OF THE

/ bFEEDWATER APPLICABLE CURVE.

c N0ZZLE

/ CONTROLLED-0 0 100 200 300 RPV METAL TEMPERATURE (oF)

MINIMUM REACTOR VESSEL METAL TEMPERATURE VS. REACTOR VESSEL PRESSURE FIGURE 3.4.11-1 GRAND GULF 3.4-32 AMENDMENT No.

fr _ - - _ . _ _ _ - _ _ _ _ - _ _ _ _ _ - - _

e C

CORE FLOW (MLB/HR) 0 10 20 30 40 50 60 70 80 90 100 11 0 y 11 0 i i i i i i i i i i i

,z o

100 O REGION C F x -

$ 90 kx O f 3 40% FLOW- - * * --- 45% FLOW a 80 r g m <

o I t

m x 70 -

W

" I REGION A gm 60 -

ma mc o

w w 94

  • mA H 50 -

V -

5 o u $

  • y#L/ k, u_ 40 -- \* eD O -

3 O S 9 "l I eS REGION O

$r w

30 -

a< u '

9

$ 20 REGION B r A u- 8 9

o 10 -

T@ J

> 2x I M EO c

O m i i i i i e i i i i

]

z O .em g 0 10 20 30 40 50 60 70 80 90 100 110 wg

, c, .

s'

-4 z PERCENT OF RATED CORE FLOW 5IiE a -

-o z

9

o,. ,

8

?

SI 1

EA o z O

'i o

pyff 130 "

c 8 EO STANDBY LIQUID CONTROL

'/

d - 120 b ) 5 y

SYSTEM SOLUTION MINIMUM TEMPERATURE LIMIT

@ m m 11 0 j -

y LIMITED OPERATION .

's t' A m y '

a 80 w ,0 &

/ f,/

- - - - ~ {nl g

40 ig ~/'~~~'a.e i

/

15 15.2 20 25 28 5 3b p

o hy CONCENTRATION (% BY WEIGHT)

W 2s F$

9A

~I CT

Y'a=

o e 5 e;z o

m 3

E $ >

  • 15.5 LIMITED OPERATION f Q @

o 15.2 .

' W x 2

% y 15  : fp X

c w  :;'s d Z _

E d j'!

g , 5 14.5  ; NORMAL OPERATION f

~

d E- o 14 . ~ UNACCEPTABLE OPERATION / ',4 m 4,2 81 ' l l I 4,808 I 5,088 3 [ 4,600 4,800 5,000 p 4,200 4,400 4 3 w Z

n z

m S A d NET TANK VOLUME (GALLONS)

E E E es A 1 tg l

M 2;

w

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

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