Text

Forwards Review of Selected Tech Specs.Future FSAR Amends Should Identify Nature of Changes & Assessment of Effect on NRC Prior Findings.Recommended Changes Dependent on Acceptability of FSAR Changes
	ML20132C991
Person / Time
Site:	River Bend
Issue date:	04/22/1985
From:	Houston R; Office of Nuclear Reactor Regulation
To:	Crutchfield D; Office of Nuclear Reactor Regulation
Shared Package
ML20132C450	List: IR 05000458/1985035; ML20132C446; ML20132C788; ML20132C814; ML20132C933; ML20132C945; ML20132C982; ML20132C991; ML20132D021; ML20134P251; ML20134P294; ML20134P304; ML20134P354; ML20134P367; ML20134P386;
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_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 f

A UNITED STATES y

g NUCLEAR REGULATORY COMMISSION

-l w AsHincTON, D. C. 20555

\\ *"** /

l April 22,1985 MEMORANDUM FOR: Dennis Crutchfield, Assistant Director for Safety Assessment Division of Licensing FROM:

R. Wayne Houston, Assistant Director for Reactor Safety Division of Systems Integration

SUBJECT:

REVIEW 0F THE TECHNICAL SPECIFICATIONS FOR THE RIVER BEND STATION (RBS)

We have reviewed selected parts of the RBS Technical Specifications as furnished to us by Dean Houston. A marked up copy of the technical specifica-tions, a copy of which was given to R. Benedict on 4/19/85, is enclosed.

We have completed a generally satisfactory set of Technical Specifications for the CSB areas of responsibility. However, since the applicant has been con-tinuously updating the FSAR to rzflect what is in the Technical Speelfications (T.S.), our recommended changes to the T.S. are contingent upon our finding that the recent FSAR changes are acceptable. We are planning to review these recent FSAR changes during the next two weeks.

We recomend that DL require the applicant in its future amendments to the FSAR (i.e.,beyond Amendment 18), to identify in its cover letter submitting the FSAR amendment: 1) the nature of the changes being proposed; and 2) an assess-ment of the effect these changes could have on the staff's prior findings made in the SER.

The sections of the T.S. that we find acceptable, contingent on our evaluation of the recent amendments to the FSAk are: 3.6.1.3, 3.6.1.9, 3.6.2.7, 3.6.4, Table 3.6.4-1, 3.6.5.1 and 3.6.5.6.

-Q

k. ayne Houston, Assistant Director for Reactor Safety l

Divisiqn of Systems Integration cc: See attached list

Contact:

F. Eltawila, CSB X29488 m+ ' !

l gc4gq3%u a er99 L

i I

D. Crutchfield cc w/o enclosure:

H. Thompson R. Bernero T. Novak A. Schwencer E. Butcher S. Stern R. Benedict (w/ enclosure)

G

i 1

DEFINITIONS PRESSURE BOUNDARY LEAKAGE 1.30 PRESSURE BOUNDARY LEAKAGE shall be leakage through a non-isolable fault _

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

PRIMARY CONTAINMENT INTEGRITY - OPERATING ( MOD 6 S Ip 2OMd3) 1.31 PRIMARY CONTAINMENT INTEGRITY - OPERATING shall exist when:

a.

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

1.

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

'?

2.

Closed by at least one vated' automatic valve, manual valve, blind flange, or deacti-secured in its closed position, except as provided in Specification 3.6.4.

b.

All containment equipment hatches are closed and sealed.-

c.

Each containment air lock is in compliance with the requirements of Specification 3.6.1.1{.

d.

The containment leakage rates are within the limits of Specification 3.6.1.2.

e.

The suppression pool is in compliance with the requirements of Speci-fication 3.6.3.1.

f.

The sealing mechanism associated with each primary containment penetra-tion; e.g., welds, bellows or 0-rings, is OPERABLE.

PRIMARY CONTAIN*ENT INTEGRITY - SMU300WT4d#W 1.32 G=1 Sr.JL I w ssut.T' 4

PROCESS CONTROL PROGRAM (PCP) 1.33 The PROCESS CONTROL PROGRAM shall contain the current formula, sampling, analyses, tests, and determinations to be made to ensure that the processing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be accomplished in such a way as to assure compliance with 10 CFR Part 20, 10 CFR Part 61, 10 CFR Part 71 and Federal and State regulations and other requirements governing the disposal of the radioactive waste.

RATED THERMAL POWER 1.34 RATED THERMAL POWER shall be a total reactor core heat transfer rate to the reactor coolant of 42894# MWT.

RIVER BEND - UNIT 1 1-6

1 INSERT AdK95 *D PRIMARY CONTAINMENT INTEGRITY-L"L. u n 5,-/M d

1.32 PRIMARY CONTAINMENT INTEGRITY-N shall exist when:

a)

All containment penetrations required to be closed during accident conditions are closed by at least one manual valve, blind

flange, or deactivated automatic valve secured in its closed position.:::::;; __ _ ;:.ided by Specific: tion 0.0.4.

b)

All containment hatches are closed.

c)

At 1;eei vue d::: in :: h ear 1cck

2. ciced.

Oh SO W

b $

&,;,^r^(^:!*_ ta$ $

L ap q sycL,ws s 3.c,. t.. sj R

i DEFINITIONS REACTOR PROTECTION SYSTEM RESPONSE TIME i

1.35 REACTOR PROTECTION SYSTEM RESPONSE TIME shall be the time interval from when the monitored parameter exceeds its trip setpoint at the channel sensor l

until de-energization of the scram pilot valve solenoids. The response time may be measured by any series of sequential, overlapping or total steps such that the entire response time is measured.

REPORTABLE EVENT 1.36 A REPORTABLE EVENT shall be any of those conditions specified in 10 CFR 50.73.

R00 DENSITY 1.37 ROD DENSITY shall be the number of control rod notches inserted as a fraction of the total number of control rod notches. All rods fully inserted is equivalent to 100% ROD DENSITY.

SECONDARY CONTAINMENT INTEGRITY - FUEL BUILDING 1.38 O:'M Str. Tuscar M o D EE s C. I 2. W 3)

SECONDARY CONTAINMENT INTEGRITY - creeATsw6 f

1.39 SECONDARY CONTAINMENT INTEGRITY - OPERATING shall exist when:

a.

All Auxiliary Building penetrations, Fuel Building penetrations and Shield Building annulus penetrations required to be closed during accident conditions are either:

1.

Capable of being closed by an CPERABLE secondary containment l

automatic isolation signal, or

/

2.

Closed by at least one,eanual valve, blind flange, or deactivated automatic valve or damper, as applicable secured in its closed position, except as provided in Specification 3.6.5.2.

i b.

AllAuxiliaryBuilding,FuelBuildingandShieldBuildingannulus equipment hatches are closed and sealed.

c.

The Standby Gas Treatment System is in compliance with the requirements of Specification 3.6.5.3.

d.

The Fuel Building Charcoal Flitration System is in compliance with 4

the requirements of Specification 3.6.5.6.

e.

At least one door in each access to the Auxiliary Building, Fuel Building and Shield Building annulus is closed, except for routine entry and exit of personnel and equipment.

Q ar. h.

OA, Q z 2 1' _ h s e. k k. k T I " "

c Ap;W3 %-g

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1-/

</

ik RIVER SEND - UNIT 1 g g %.,g e n g y "--

e udv. b e+ m:nGCf

t INSERT SECONDARY CONTAlhHENT INTEGRITY - FUEL BUILDING 1.39 SECONDARY CONTAlhMENT IhTEGRITY - FUEL BUILDING shall exist when:

a) All Fuel Building penetrations required to be closed during accident conditions are closed by valves, blind flanges, or dampers secured in position.

b) All Fuel Building equipment hatch covers are installed.

c) 1he Fuel Building Charco Filtration System is in compliance with the requirements of Specification 5/4.6.5.b.

e) At least one door in each access to the Fuel Building is closed, except for routine entry and exit of personnel and equipment, f) The pressure within the Fuel Building is maintained in compliance with the requirements of Specification 4.6.5.1.2.a.

4 l

l i

i 1

)

r 3/4.6 CCNTAINMENT SYSTEMS 3/4.6.1 PRIMARY CONTAINMENT PRIMARY CONTAINMENT INTEGRITY - OPERATING LIMITING CONDITION FOR OPERATION 3.6.1.1 PRIMARY CONTAINMENT INTEGRITY - OPERATING shall be maintained.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

Without PRIMARY CONTAINMENT INTEGRITY - OPERATING, restore PRIMARY CONTAINMENT INTEGRITY - OPERATING within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

1 SURVEILLANCE REQUIREMENTS 4.6.1.1 PRIMARY CONTAINMENT INTEGRITY - OPERATING shall be demonstrated:

a.

After each closing of each penetration subject to Type B testing, except the primary containment air locks, if opened follo ting Type A D

or B test, by leak rate testing the seals with gas at Pa, +-H /psig, and verifying that when the measured leakage rate for these seals is addedtotheleakaggratesdeterminedpursuanttoSurveillance Requirement 4.6.1./.dforallotherTypeBandCpenetrations,the combined leakage rate is less than 0.60 La.

pmuy b.

At least once per 31 days by verifying that allAcontlinme3 L _ p n e g e

penetrations ** not capable of being closed by OPERABLEacontainment automatic isolation valves and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated auto-matic valves secured in position, except as provided in -M'; :. :.; ;

Specification 3.6.4.

c.

By verifying each primary containment air lock is in compliance with therequirementsofSpecification3.6.1./.

Y d.

By verifying the suppression pool is in compliance with the requirements of Specification 3.6.3.1.

"See Special Test Exception 3.10.1

- Except valves, blind flanges, and deactivated automatic valves which are located inside the primary containment steam tunnel or drywell' and are locked, ~

3 sealed or otherwise secured in the closed position. These penetrations shall l

be verified closed during each COLD SHUTDOWN except such verification need not be performed more often than once per 92 days.

l I

RIVER BEND - UNIT 1 3/4 6-1

+

CONTAINMENT SYSTEMS f/M4 #4fD4 /#C.

PRIMARY CONTAINMENT INTEGRITY - 6 LIMITING CONDITION FOR OPERATION parz. /Ms01/NG 3.6.1.2 PRIMARY CONTAINMENT INTEGRITY - Di'?M shall be maintained.

offM77C#64 cmosr/cy

,y.

f APPLICABILITY.)W When handling irradiated fuel in the primary containment and uring Luru: ALTERATIONS and operations with a potential for draining the reactor vessel.

ACTION:

Without PRIMARY C0NTAINMENT INTEGRITY - 4 G Mt3N, suspend handling of irradiated fuel in the primary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

SURVEILLANCE REQUIREMENTS pygz //AfDL/A/GV)

4. 6.1. 2 PRIMARY CONTAINMENT INTEGRITY - 6tfitTJA shall be demonstrated:

~:

.y sWfk

'y a.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prio to and at least once per m during by verifying that all/ containment penetrations " ~ -

~

:..."Sid I

..., re6uired to be closed during h r'

'2-f ' g

.i :. - -

accident conditions are closed by hatches, valves, blind flanges, or deactivated automatic valves secured in position, 2.;t es.

. J..

", ^ b.. ; ^ d.. l., 2, ^. A.

b

" '3 ' ; : :: $-

n - t '- :-t :' '::'

-- ; ' i ;.;;

i t ' -'e

,re '"'i re me n t e ef he-4f4en* inn *

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d 6

W l

RIVER BEND - UNIT 1 3/4 6-2 l

l 1

D.

e s

I*

CONTAINMENT SYSTEMS Xw CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 1 4 E.

N T H f&

4 3.6.1.3~ Containment leakage rates shall be limited to:

a-I d (1'.

a.

An overall integrated leakage rate of less than or equal to La, j ej d 0.26 percent by weight of the containment air per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months at Pa, fd-ag T

a psi -

G b-b.

A combined leakage rate of less than 0.60 La for all penetrations "5

and all valves subject to Type 8 and C tests when pressurized in t=

accordance with Table 3.6.4-1 of Specification 3.6.4.

c.

A leakage rate of less than 340 SCFH for each of the valve groups identified below when t ted in accordance with the surveillance requirements of 4.6.1.

f.

3 H$.9L.C,1hsiecA 1.

Division I N!"": and Division I PVLCS Valves i m Hs -PLcs VM g

o 2.

Division II #G4We and Division II PVLCS Valves g

v15 'VLLS Vsiev

,l j p.

3.

Division I.M&4W4 and all first outboard PVLCS Valves 53, Coo w

d) 4 d.

A combined leakage rate of less than or equal to 3G.rGee cc/hr for qd.D )

all penetrations shown in Table O.C[. " 1.i b :'-:ad. - 2.;.4 as s e r W -,, - ~ r'- :.t bypass leakag paths when pressurized to Pa, W psis.

's.4,. l.3 - 1 7-C.

.g A combined leakage rate of less than or equal to I gpm tim the total number of ECCE n IC containment isolation valves in hy ostatically A*T M 3.6 81-l tested linesawhich penetrate the primary containment, when tested at h

1.10Pafr:44)psig.

0/MMM

1. G" APPLICASILITY: When PRIMARY CONTAINMENT INTEGRITY,is required per Specifica-tion 3.6.1.1.

ACTION:

With:

~

/""*">

a.

The measured overall integrateM containment leakage rate equaling or exceeding 0.75 La or, b.

The measured combined leakage rate for all penetrations and all valves subject to Type B and C tests exceeding 0.60 La, or c.

The measured leakage rate greater than or equal to 340 SCFH for each valvegroupingidentifiedin3.6.1.f.c.1,3.6.1..c.2gr3.6.1.f.c.3, or 3

J 1

_ v.____..

e

-,..m.,-.

.m.

RIVER BEND - UNIT 1 3/4 6-3 W

e es.4mm

CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued) is" l

iA ACTION (Continued) s f 3. 6.l.3 - 1 k,)T d.

The combined leakage rate 1or all penetrations shown in Table 3,4 4-I A

as m :-f: j ::- M ----t bypass leakage paths exceeding 34ih490 cc/hr

(

or Advvvudau) 83,500 t*1

-4 g

b7 The measured combined leakage rate for all F r :-f ^::C containment

'N isolation valves in hydrostatically tested lines which penetrate the o

primary containment exceeding I gpm times the to 'a1 number of such d

valves *

%}ThMa 3.4.Y

I 4

restore:

I

}

>g a.

The overall integrated leakage rate (s) to less than 0.75 La as

't applicable, and

. 9 E i d t

yM b.

The combined leakage rate for all penetrations and all valves subject to Type B and C tests to less than or equal to 0.60 La,'and s

t'

'bI c.

The measured leakage rate to 1 ss than 340 SCFH for each of the valve g

oupings identified in 3.6.1

.c.1, 3.6.1.

.c.2, and 3.6.1

.c.3 3.t.

3-i d.

The combined leakage rate for all penetrations shown in Table 3,4-4-1 g

as n: -f:,, ;;.^..:... c ^. bypass leakage paths to less than or equal t

to 34h400 cc/hr and * %

D) 83,rao v

g.

The combined leakage rate for all " " :-f E !C containment isolation dN T

valves in hydrostatically tested linespwhich penetrate the primary A

J containment to less than or equal to I gpm times the total number of such valves, p

7g,g

}3 prior to increasing reactor coolant system temperature above 200*F.

u

.g SURVEILLANCE REQUIREMENTS t

o'

'P The,; %

4D 4.6.1.3

entainment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria specified d}

in Appendix J of 10 CFR 50 using the methods and provisions of ANSI N45.4 - (1972):

Ih Three Type A Overall Integrated Containment Leakage Rate tests shall a.

]l MT(

be conducted at 40 + 10 month intervals during shutdown at Pa, +917.0 psig, during each 10 year service period. The third test of each

, %p i

D set shall be conducted during the shutdown for the 10 year plant inserviceinspect{on, y,

4 E__;

G. rr A m =< Y A C IN AW

l RIVER BEND - UNIT 1 3/4 6-4 g

fayp, i.,n... u f-g.m m a y g r

p A u data 4. aam. o. z s L. [L.t ( L..,,+

e c

L e ) 4 0. Zs la.~. M bc

^ j$-S14 tsar

...sA.

CONTAINMENT SYSTEM Lc l.a g 3* 8. A k r F =f y.44 SURVEILLANCE REQUIREM n.5 L...ouca; b.

If any periodic Type A test fails to meet 0.75 La, the test schedule for subsequent Type A tests shall be reviewed and approved by the Commission.

If two consecutive Type A tests fail to meet 0.75 La, a, Type A test shall be perforned at least every 18 months until two consecutive Type A tests meet 0.75 La, at which time the above test schedule may be resumed.

c.

The accuracy of each Type A test shall be verified by a supplemental test which:

1.

Confires the accuracy of the test by verifying that the _ '..

e w. 7, 3....., y -

,. m.

v -- - *. -

..:.g3

_a

-- a s.

u.

' m 7,,9

<&y,e r',,a Ac-l.<lA, 4.,. -

f

T ;;,

Has duration sufficient to establish accu}rately the change in "" g r

7 2.

leakage rate between the Type A test and the supplemental test.

Requirestheqant[t[0cf gas injected into the c nt or 3.

bled from th containment during the supplemental. test to be between 0.75 La and 1.25 La.

4ser-7.6 d.

Type B and C tests shall be conducted with gas at Pa. 454T psig*, at K

intervals no greater than 24 months except for tests involving:

A r locks, p g g,p g&J

.(gs,pg,ggyp h w PV l C5 V"I4dL*s 2.

Main steam : ': '

4-a 3.

Penetrations using continuous leakage monitoring systems, I

:' "! : ;-::: r'::: _i".'. .!! '........;., m,

4 g.

ECC: :t "CIC containment isolation valves in hydrostatically tested linesg% Ta1.44 3.6 4-3which penetrate the primary containment, and g/

Purge supply and exhaust isolation valves with resilient material

seals, Air locks shall be tested and demonstrated OPERABLE per Surveillance e.

Requirement 4.6.1./.

Y f.

Total sealing air leakage into the primary containment at a test pressure of /11.5/ psid for main steam isolation valves and /f3 / psid for penetration leakage control system sealed valves shall be tested at least once per 18 months.

"Unless a hydrostatic test is required per Table 3.6.4-1.

RIVER BEND - UNIT 1 3/4 6-5

CONTAINMENT SYSTEMS SURVE1LLAN E REQUIREMENTS (Continued) li i

Type B periodic tests are not required for penetrations continuously j

g.

monitored by the Primary Containment Penetration Pressurization Systeri, provided the system is OPERABLE per Specification 3.6.1.9.

j gls % C*0 Type B tests for, penetrations employing a continuous leakage monitoring h.

system shall be conducted at Pa, +;;41 psig, at intervals no greater K

V than once per 3 years.

tian 74 A 1'w L c 5

,eal Leakage from isolation valves that are sealed with _id ' n o

7L s p &eg ray be excluded e"k,4=-t to the nenvitinae af * - - " - 1, g

"Cli2^ III.t ?, when determining the combined leakage rate provided d

the seal system and valves are pressurized to at least 1.10 Pa,

/

f 56 fcoe psig, and the seal system capacity is adequate to maintain f

8 system pressure for at least 30 days.

j.

$856%bsk4E444 : -t:" :-t ':r' t':

-; 9:::

id e-t:t t: ;

+-^d F

e6211 8.

1 26

+.e.ed c rim 2 ry r an+ 2 4 ~ +

lin.u sf-*

non.+r2*.

the q, _ t}

r. : : n t - - p * * ' a - + + h s.

/

Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE per Surveillance Requirerne nts 4. 6.1./. 3.

9 The provisions of Specification 4.0.2 are not applicable to

y Specifications 4.6.1.3.a. 4.6.1.3.b, 4.6.1.3.d, 4.6.1.3.e and 4.6.1.3./.

cf RIVER BEND - UNIT 1 3/4 6-6 O

O

c

_ TABL E

3. c. t.1 - I AAINLL L u. s BYPA ss L E'A kA C E PATHT t

1.

L e s k sys f* +dr k 4 F.a s t f t.o.,

Pe.a s 4.

+.. -

A II. w a W L e s les s a. ( A. )

C. 4...

. t..

/k L'IR C s OR 4 *L iR 2.

La ka,. f. 4,

+e ds A -sala. y 8..t.t.

g Wies Me Vo te s ave,

k rie ws i fs.l-( o., :). '

- /e- * +- = 4.. -

(p,, s)

_t4.es g (/c %.)

W~

t K'36013 I LMVA A Aavlif LMeg 9 Acvt1.3 o

Lk.T64&os~E LCMSesov2 A s cm s e s ov2rc.

W LkTCet40s~F Leu r s sov2tc.

A m t g sovsrA I

O

\\

t K78 + 1018 LS$$ t 30VI3 8 155R M So VI s e 4

C oa+.. e + s.:. lesA L TRt r otA1 b

Cte rea.e vs f Ls+ 4 140 I

G)

L s n '. :.5 2.

L ll :;;-. ?, "

!= t. --

?!Y !. !. y-

_(-) L *.

- + y,=

~ ;. _,

lgLp.. f,,L

='

A=1

-?; l. e-

/4; w. v.,

3/4 g.-tA Nn51E5"

_,. ~....

~. -,...

l CONTAINMENT SYSTEMS k

l

/

& h akf I

PA:M3aY CONTAINMENT AIR LOCKS /

['m >, los es if

./

LIMITING CONDITION FOR OPERATION 4

/

p,d..

.,y

.6.1.4 Each containment air lock shall be OPERABLE with:

a.

80th doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and

,,, cco,.pt a.u ~WA 1,k:ss d 34 i 5 d b.

An overall air lock leakage rate # ?;;; Wa 0 e^":1 to 0.05 L; ;t

^

, e, 0. n ;; 4. 'e

" c 4 _* '"! ' 0", u = a 5 r e * %. 4-

-Lice : oxM

, i. e.. ;,. - w W p x ss a. k cd h Pc, '7. ca ps'.g.

o APPLICABI ITY: OPERATIONAL CONDITIONS 1, 2* and 3.

ACTION:

p,,

.,y With one^ containment air lock door inoperable:

a.

1.

Maintain at least the OPERABLE air lock door closed and either resdo're the inoperable air lock door to OPERA 8LE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months er lock the OPERABLE air lock door closed.

2.

Operation may then continue until performance of the next required overall air lock leakage test provided that the OPERA 8LE air lock door is verified to be locked closed at least once per 31 days.

3.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

The provisions of Specification 3.0.4 are not applicable.

Wit $ @coltainment air lock inoperable, except as a result of an b.

incperable air lock door, maintain at least one sir lock door closed; restore the inoperable air lock to OPERA 8LE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

p..m With one4 containment air lock door inflatable seal systes air flask c.

pressure instrumentation channel inoperable, restore the inoperable channel to OPERA 8LE status within 7 days or verify air flask pressures to be > Mfpsig at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

loo 5:: O:;f:1 7 :^ L;;et5 ?. '.".1, 0

o t

RIVER SEND - UNIT 1 3/4 6-7 y g_

I CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS B

l g ran.< y 4.6.1.4 Eachacontainment air lock shall be demonstrated OPERABLE:

Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following each closing, except when the air lock is a.

being used for multiple entries, then at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by verifying seal leakage rate h:: th:n Or W >^ ^ --' ;:- ':;r I,, c.mpa.aa-dd.

when the gap between the door seals is pressurized 6to Pa,-frit,psig.

& h.,;m o f 34.o3 s

i---

9 7"4 " "" " F* T-N W ^ F41N74 Mb.

By conducting an overall air lock leakage test at Pa.gG-M-psig, and verifying that the overall air lock leakage rate is within its limit:

1.

At least once per 6 months #

/ 7 I" F enaaTM 2.

Prior to establishing PRIMARY CONTAINMENT INTEGRITY'when maintenance has been performed on the air lock that could affect the air lock sealing capability."

At least once per 6 months by verifying that only one door in eack' c.

air lock can be opened at a time.

By verifying the door inflatable seal systee OPERABLE by:

d.

1.

L ::n:tr:t h; (tue) :::1 cir f h:k ;r:::gr: S:tr=:nt:t hn h;nn:i(:) OPE"." ELE tj p rf:=:n : Of ::

-:)

C"^?HEL FL'MCT!0M^.L TEST :t h::t :n:: ;;r 31 ::j:, :::

t)

C"*?HEL C*LI""^.TI^" :t h::t en:: p:- 1" rentt,

-zith : ? u pr:::er: ::tpetet of 120 p:fg.

2' At least once per 7 days, verifying seal air flask pressure to t

be greater than or equal to 80 psig.

s X.

At least once per 18 months,, conducting a seal pneumatic system leak test and verifying that system pressure does not decay more than 4-G psig from MG psig within 46 hours5.324074e-4 days 0.0128 hours 7.60582e-5 weeks 1.7503e-5 months .

Or*t~

,W W

f.C C, 100

z. y

The provisions of Specification 4.0.2 are not applicable.

Exemption to Appendix J of 10 CFR 50.

./

M 01 E RIVER BEND - UNIT 1 3/4 6-8

l CONTAINMENT SYSTEMS MSIV LEAKAGE CONTROL SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.5 Two independent main steam positive leakage control system (MS-PLCS) divisions shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.

ACTION:

With one MS-PLCS division inoperable, restore the inoperable division to OPERABLE status within 30 days or be in at least NOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS EachMhlCSdivisionshallbedemonstratedOPERABLE:

4.6.1.5 At least once per 31 days by verifying ( Q

[

a.

RABILITY by en-systeme f[om-tie conteel-coom end ep n t hs th: Systee for at least 25 minutes I

u r= ;h tr.e e m ur.

WibH4 LCS byK n W Dr verle m *-a S.,me;tla n a Resuonmens 4, t,. t. g o. s During each COLD SHUTDOWN, if not performed within the previous b.

92 days, by cycling each remote, manual and automatic motor operated valve through at least one complete cycle of full travel. 7 At least once per 18 months by performance of a functional test which c.

includes simulated actuation of'the division throughout its operating I

sequence, and verifying that each automatic valve actuates to its correct position and that ;r::t:r th:2 Or :; :! t- '

) ; W sealing pressure is established in each steam line.

Eg.y!3p.;4 d.

By verifying the 4 flow.ad

f. pressure, t:g :r:tur: :rd !: :1) Joperatingt instrumentation to be OPERA 8LE by performance of a:

1.

CHANNEL FUNCTIONAL TEST at least once per 31 days, and l

2.

CHANNEL CALIBRATION at least once per 18 months.

g RIVER BEND - UNIT 1 3/4 6-9 l

l

-. ~ - - - - -

=

CONTAINMENT SYSTEMS PA/MMf. AINMENT STRU'TURAL INTEGRITY

_A CON LIMITING CONDITION FOR OPERATION

,0++4 ssp.

3.6.1.6 The structural integrity of theAcontainment shall be maintained ta levelconsistentwiththeacceptancecriteriainSpecification4.6.1.dI

) ~~ion APPLICABILIT'Y: OP ACTION:~~

~

~~With one drywell air lock door inoperable:~~

a.

1.

Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2.

~~Operation may then continue provided that the OPERABLE air lock door is verified to be locked closed at least once per 31 days.~~

3.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

4.

~~The provisions of Specification 3.0.4 are not applicable.~~

b.

With the drywell air lock inoperable, except as a result of en inoperable air lock door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least NOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN with following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

~~With one drywell air lock door infl,atable seal system air flask pressure c.~~

instrumentation channel inoperable, restore the inoperable channel t CPERABLE status within 7 days or verify air flask pressure to be 1 (c%o psig' at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

~~go "See Special Test Exception 3.10.1.~~

~~RIVER BEND - UNIT 1 3/4 6-19 M~~

~~a CONTAINMENT SYSTEMS SURVE!LLANCE REQUIREMENTS 4.6.2.3 The drywell air lock shall be demonstrated OPERABLE:~~

a.

~~Within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months following each closing, except when the air lock is I~~

~~being used for multiple entries, then at least on er 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , by l~~

~~verifying seal leakage rate less than or equal t cf per hour when I~~

~~the gap bete.een the door seals is pressurized to Pa, IVD psig.d I~~

~~f' wigs 4 0A CatL. re-te~~

~~.t. rs ig a ))~~

~~2.o i~~

~~s j~~

~~b, conducting an overall air lock' leakage test at J%,, M psig and verifying that the overall air lock leakage rate is wit,hin its limit:~~

1.

~~At least once per 6 months #.~~

2.

~~Prior to establishing DRYWELL INTEGRITY " : = 't: = :: Na8 Y been performed on the air lock that could affect the air lock sealing capability s _' ! = ""~~

m_

~~4 5~~

~~8 At 'eri : ;: ;:- E i:-it Sy verifying that onl air lock can be opened at a timep_~~

~~s.1,- h'-y one door in the_~~
c.
//
8*'
/J
-4
~~Pad 4 A A^g~~
__f-
/
a g_g _. _ y
[
M By verifying the door inflatable seal system W ERABLE by:
~ 4{,
n.
.... g -,.,,,,,
.s p w r c ut,6 t
.u. a..,._
r..g g4
,.....e.
o.
M
^...,....a runwituhnt a r.a 4.... -....
~~e. o a%.,~~
_J s
e,
. r. n ;... a w,.. c r n...,..
a.
..~..;.s r.
4c..... m.
/.[.
At least once per 7 days verifying seul air flask pressure to be greater than or equal to $ psig.
ID J.f.
At least once per 18 months conducting a seal pneumatic system leak test and verifying that system pressure does not decay more j
thangpsig from Jaf'psig within Whours.
L
~~7f 8~~
O
\\e\\b l*0 M
( el. k JnA*
M9 0) d g,g), Sy M M ?, D.0 444 e an a dk er db
\\
I p ig v
/
f S C.F W
e mm w or s.
,The provisions of Specificatio
.0.2 are not applicable.
RIVER BEND - UNIT 1 3/4 6-20
a CONTAINMENT SYSTEMS DRYWELL STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.6.2.4 The structural integrity of the drywell shall be maintained at a level consistent with the acceptance criteria in Specification 4.6.2.4.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
With the structural integrity of the drywell not conforming to the above requirements, restore the structural integrity to within the limits within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00VN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLAN:E REQUIREMENTS 4.6.2.4.1 The structural integrity of the exposed accessible interior and I
exterior surfaces of the drywell shall be determined during the shutdown for each Type A containment leakage rate test by a visual inspection of those surfaces. This inspection shall be performed prior to the Type A containment leakage rate test to verify no apparent changes in appearance or other abnormal degradation.
1 e (r a
.6,,
-,3 a,..,s..r--
s it; g,,_
,,,,,3 de "; t' ; ;;.... y. i co inspe.cion,an.. u e i c g.... 6v ene w..
Q"**"
1; [s.;$'l.u.$.
$.0 7 Thit reDert chall 47 _;,
9 gg3g;3p,3yg y3 tt;
-d'.... w

...
~~..,;tr, +ha insnect4r- --~~
~~d..~~
,,,,, tv... m,.,;
. -'4'*:,
~~..,os uv4. s. 6 a c...;.;~~
^..,sa.
a l
RIVER BEND - UNIT 1 3/4 6-21
CONTAINMENT SYSTEMS ORYWELL INTERNAL PRESSURE LIMITING CONDITION FOR OPERATION I
3.6.2.5 Drpell to containment diff erential pressure shall be maintained between - gert/ and + Q/. / psid.
03 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
With the drywell to containment differential pressure outside of the specified limits, restore the differential pressure to within the limits within I hour or be in at least H01 SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREMENTS 4.6.2.5 The drywell to containment differential pressure shall be determined to be within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
D e
RIVER BEND - UNIT 1 3/4 6-22
CONTAINMENT SYSTEMS DRYWELL AVERAGE AIR TEMPERATURE LIMITING CONDITION FOR OPERATION WO 3.6.2.6 Orywell average air temperature shall not exceed M S*F.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
/i'd With the drpell average air temperature greater than 435*F, reddce the average air temperature to within the limit within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREMENTS 4.6.2.6 The drywell average air temperature shall be the arithmetical /
average of the temperatures at the following locations an shall be determined
[
to be within the limit at least once per 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months s:
Elevation Azimuth a.
s145' 20 < A < 60 b.
s145' 200* < A < 150*
c.
145' 190* 1 A 5 265*
~~i,i1 d.~~
145' 290* 5 A 5 330*
i RIVER BEND - UNIT 1 3/4 6-23 i
9 CONTAINMENT SYSTFMS
/
DRYWELL VENT AND PURGE LIMITING CONDITION FOR OPERATION 3.6.2.7 Tpedrywellventandpur0esystemsupplyandexhaustvalvesshallbe pr g,,an up;'y c-
--k="
m'ves closed w e r m i me ;;
'--h
" a* " *--a+
h
=" ~J except,while in OPERATIONAL CONDITION 3, the drywell vent and purge
[
system 24 inch valves may be open during operation of the drywell vent and purge mode of the containment cooling system for up to 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months per 365 days for the purpose of reducing drywell airborne radioactivity levels prior to and during personnel entries or for controlling drywell pressure. The drywell may be vented for up to 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months per 365 days in OPERATIONAL CONDITIONS I and 2, for controlling drywell pressure by opening the 24 inch drywell purge supply or exhaust valves; however, only one line may e open at a time.
[
h A
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
With the drywell vent and purg*e system supply or exhaust valves open a.
in OPERATIONAL CONDITIONS 1 M 2 and the 36 inch containment purge h
system supply or exha d valves open, immediately close the drywell K-vent and purge system 4alves or be in at least HOT SHUTDOWN within the next 12 hotTs.
F A
b.
With the drywell vent and purge sy em supply or exhaust valves open during OPERATIONAL CONDITIONS 1 2 for more than 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months per X
365 days, immediately close the drywell vent valves or be in at least HDT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
c.
With both the drywell purge supply and exhaust valves open at the same time in OPERATIONAL CONDITIONS I a48 2, immediately isolate X
either the supply or exhaust line; otherwise, be in at least HDT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
d.
With the drywell vent or purge mode of the containment cooling system per 365 days), immediately close the drywell vent and purge 24 inch
[
in operation during OPERATIONAL CONDITION 3 for more than 90 hours0.00104 days 0.025 hours 1.488095e-4 weeks 3.4245e-5 months f
valves or be in at least COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
D RIVER BEND - UNIT 1 3/4 6-24
i 1
\\
1 CONTAINMENT SYSTEMS BASES ATM35PHERE CONTROL (Continued)
The operability of the containment and drywell hydrogen igniters ensures that hydrogen combustiog can e accomplished in a controlled manner following a degraded core event pYoduc hydrogen concentrations in excess of LOCA j>(
conditions.
4 s
d e
I O
6 1
e e
RIVER BEND - UNIT 1 8 3/4 6-8
=
=
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.2.7 At least once per 7 days, determine the cumul ive time that:
/(
1.
The drywell vent and purge system supply r exhaust valves have been open during OPERATIONAL CONDITIONS 1, 2 during the past 365 days, pc and 2.
The drywell vent and purge mode of the containment cooling system has been in operation during OPERATIONAL CONDIT10N 3 within the past 365 days.
e e
0 e
e 9
e e
4
=
RIVER BEND - UNIT 1 3/4 6-25
CONTAINMENT SYSTEMS 3/4.6.3 DEPRESSURIZATON SYSTEMS 1
SUPPRESSION POOL LIMITING CONDITION FOR OPERATION 3.6.3.1 The suppression pool shall be OPERABLE with the pool water:
a.
Volume between 137,571 ft3 3
and 141,036 ft, equivalent to a level between 19'6" and 20'0" and a b.
Maximum average temperature of 95'F during OPERATIONAL CONDITION 1 or 2, except that the maximum average temperature may be permitted to increase to:
1.
105*Fduringtestingwhichaddsheattothesuppressionpool;
)(
2.
110 F with THERMAL POWER less than er equal to 1% of RATED THERMAL POWER; awd 3.
120*F with the main steam line isolation valves clos'ed following a scram.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With the suppression pool water level outside the above limits, restore the water level to within the limits within I hour or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
b.
In OPERATIONAL CONDITION 1 or 2 with the suppression pool average water temperature greater than 95'F, restore the average temperature to less than or equal to 95*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , except, as permitted above:
1.
With the suppression pool avera yater temperature greater than 105'F during testing Bdsheattothesuppression
/4 pool, stop all testing wAssd s heat to the suppression pool X,
and restore the average temperature to less than 95*F within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
l RIVER BEND - UNIT 1 3/4 6-26 l
l
' CONTAINMENT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)
ACTION:
(Continued) 2.
With the suppression pool average water temperature greater than:
a) 95'F for more than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and THERHAL POWER greater than 1% of RATED THERMAL POWER, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
b) 110*F, place the reactor mode switch in the Shutdown position and operate at least one residual heat removal loop in the suppression pool cooling mode.
3.
With the suppression pool average water temperature greater than 120*F, depressurize the reactor pressure vessel to less than 200 psig within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
n I.
c.
With only one suppression chamber water level indicator OPERABLE and/or with less than eight suppression pool water temperature indicators, one in each of the eight locations OPERABLE, restore the inoperable indicator (s) to OPERABLE status within 7 days or verify sup)ression chamber water level and/or temperature to be within the limits at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
d.
With no suppression chamber water level indicators OPERABLE and/or with less than seven suppression pool water temperature indicators covering at least seven locations OPERABLE, restore at least one water level indicator and at least six water temperature indicators to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REOUIREMENTS 4.6.3.1 The suppression pool shall be demonstrated OPERABLE:
a.
By verifying the suppression pool water volume to be within the limits at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
b.
At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,in OPERATIONAL CONDITION 1 or 2 by y
verifying the suppression hool average water temperature to be less than or equal to 95*F, except:
At least once per 5 minutes,during testing whis fa ds heat to
)(
1.
the suppression pool, by verifying the suppression pool average water temperature less than or equal to 105*F.
RIVER BEND - UNIT 1 3/4 6-27
CONTAINMENT SYSTEMS N
SURVEILLANCE REQUIREMENTS (Continued) 2.
At least once per hour when suppression pool average water Y
g temperature is greater than or equal to 95'F, by verifying suppression pool average water temperature to be less than or equal to 110*F and THERMAL POWER to be less than or equal to 1%
of RATED THERMAL POWER.
3.
At least once per 30 minutes following a scramywith suppression
);
pool average water temperature greater than or equal to 95'F, by verifying. mpression pool average water temperature less than or equal to 120*F.
6 9
8 4
RIVER BEND - UNIT 1 3/4 6-28
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT UNIT COOLERS LIMITING CONDITION FOR OPERATION 3.6.3.2 Both primary containment unit coolers shall be OPERABLE and capable of rejecting heat to the Standby Service Water System.
APPLICABILITY: OPERATIONAL CONDITIOh5 1, 2 and 3.
ACTION:
~
a.
With one of the primary containment unit coolers inoperable, restore the inoperable unit cooler to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HDT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
b.
With both primary containment unit coolers inoperable, restore at least one unit cooler to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREMENTS
/
4.6.3.2 Both primary containment unit coolers shall be demonstrated OPERABLE:
a.
At least once per 31 days by verifying that each pressure relief and
,~
~
uackdraf t damper in the flow path that is not locked, sealed or other-K y
wha :::gr in position, is in its correct position.
b.
Byverifyingthateachoftherequiredunitcoolerjdevelopsaflov X
of at least fe on recirculation flow through the unit cooler, Y
at least o per JC 3
c.
At least once per 18 months by performance of a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence and verifying that each pressure relief and backdraft damper in the flow path actuates to 1
its correct position.
9 RIVER BEND - UNIT 1 3/4 6-29
CONTAINMENT SYSTEMS
[
SUPPRESSION POOL COOLING LIMITING CONDITION FOR OPERATION 3.6.3.3 The suppression pool cooling mode of the residual heat removal (RHR) system shall be OPERABLE with two independent loops, each loop consisting of:
a.
One OPERABLE RHR pump; and b.
An OPERABLE flow path capable of retirculating water from the suppression pool through an RHRSW heat exchanger.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3.
ACTION:
a.
With one suppression pool cooling loop inoperable, restore the inoperable locp to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
b.
With both suppression pool cooling loops inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN" within the next 24 nours.
SURVEILLANCE REQUIREMENTS 4.6.3.3 The suppression pool cooling mode of the RHR system shall be demon-strated OPERABLE:
)
At least once per 31 days b verifying that each valve [ manual,
}
a.
power operated or automati in the flow path that is nTt locked, l
sealed or otherwise secure in position, is in its correct position.
b.
By verifying that each of the required RHR pumps develops a flow of at least 5050 gpm on recirculation flow through the RHR heat exchangers to the suppression pool when tested pursuant to Specifi-cation 4.0.5.
"Whenever both RHR loops are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature'as low as practical by use of alternate heat removal methods.
RIVER BEND - UNIT 1 3/4 6-30 L
.~,
'\\
CONTAINMENT SYSTEMS r-3 /4. 6. 4 CONTAINMENT AND ORYWELL ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.4 The primary contairveent and dryweli isolation valves in Table 3.6.4-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.4-1.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3 ACTION:
a.
With one or more of the containment or drywell isolation valves shown in Table 3.6.4-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:
1.
Restore the inoperable valve (s) to OPERABLE status, or 2.
Isolate each affected penetration by use of at least one deactivated automatic valve secured in the isolated position,* or 3.
Isolate each affected penetration by use of at least one closed manual valve or blind flange
9pp44c.mL43.a.d/he.sywJ: MM M TL p n i m Otherwise, in be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00VN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
.r a
{9 %
dag( e L 4
~~5 t e ^ ?^ W~~
' A m A s M A.
cu:L k a.z &d A 3 h, a p dut+Aat A v =_ M +,:4 y _ A,a o
a dalmad a.pabb. s J n
=
M f tLal: q % Av. & 4-u
" Isolation valves closed to satisfy these requirements may be re, opened on an intermittent basis under administrative controls.
l M
JtIVER BEND - UNIT 1..
3/4 6-31
\\
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS 4.6.4.1 Each isolation valve shown in Table 3.6.4-1 shall be demonstrated OPERABLE prior to returning the valve to service after maintenance, repair or replacement work is performed on the valve or its associated actuator, control t,gp or power circuit by cycling the valve through at least one complett cycle of full travel and verifying the specified isolation time.
{
4.6.4.2 Each automatic isolation valve shown in Table 3.6.4-1 shall be demon-i'*,
strated OPERABLE during COLD SHUTDOWN or REFUELING at least once per 18 months
,} t by verifying that on an isolation test signal each automatic isolation valve actuates to its isolation position.
, t..sl c/
4.6.4.3 The isolation time of each power operated or automatic valve shown in f( f Table 3.6.4-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.
9, jfo
~~]Y 4~~
RIVER BEND - UNIT 1 3/4 6-32
.w
-o+--
~
~
y p f,fg Nb TABLE 3.6.4-1
////ew' n t' **
j y
- he x'
CONTAINMENT AND DRYWELL ISOLATION VALVES g fes.r m
l
?
04 5
MAXIMUM SECONDARY Its o VALVE PENETRATION ISOLATION TIME CONTAINMENT P
URE e
NUMBER NUMBER VALVE GROUP (Seconds)
BYPASS PATH (f)
(
,y g
(Yes/No) 7 fg a.
Automatic Isolation Valves 1.
Primary Containment 1821*A0V)022A IKJB*ZIA 6
5 No f
1821*A0V F02?B 1KJB*Z10 6
5 No 1
II9)
IKJB*Z1C 6
5 No IB21*A0V F022C(b)(g) 1821*A0V F022D IKJB*Z10 6
5 No 31 w
IU) 1 1821*A0V F028A 1KJB*ZIA 6
5 No 6.
I9) 1KJB*Z1B 6
5 No 1821*A0V F028B m
I9)
IKJB*Z1C 6
5 No 31 J.
1821*A0V F028CI9) 1B2)*A0%J028p9) 1KJB*Z10 6
5 No 6.
1821*MOVF067A 1KJB*ZIA 6
/7,F-717.IP No 1821*MOVF067B(UI IKJB*ZlB 6
die /4./
No 31 I9) 1KJB*Z1C 6
A3 /S 7 No
~~6. L 1821*MOVF067C r~~
I9) 1KJB*Z10 6
M /98 No 1821*MOVF067 1821*MOVF016{I9)
DII9) 1KJB*Z2 6
16.5 No
.31 1821*MOVF019 1KJB*Z2 6
17.6 No 6.
1E12*MOVF053A 1KJB*Z3A 5
10.7 No 6.3 IE12*MOVF053{U)
IKJB*Z38 Bf 5
10.7 No 4
5 36.3 No
.31 1E12*MOVF023 3
1E12*MOVF0 IKJB*Z20 5
29.7 No 6.
)
IE12*MOVF009 IKJB*Z20 5
25.3 No IE12*MOVF037A IKJB*Z21A
~~f/I 73.7 No 31 1E12*MOVF0379 )~~
IKJB*Z218 Jf//
74.8 No 6.
td 1E33*MOVF008 1KJB*ZIA,B,C,0 4
288r /#4~
No 1
.~
.-~
TABLE 3.6.4-1 (continued)
B CONTAINMENT AND ORYWELL ISOLATION VALVES y
5 MAXIMUM SECONDARY T
5 VALVE PENETRATION ISOLATION TIME CONTAINMENT P
NUMBER NUMBER VALVE GROUP (Seconds)
BYPASS PATH (f)
~)_
e (Yes/No) c 36#
w a.
Automatic Isolation Valves
[
1.
PrimaryContainment(Continued) 1G33*H0VF028 1KJB*Z4 7
20.9 Yes 1
1G33*MOVF040 IKJB*Z6 7
24.2 No I IU) 1KJB*Z7 7
'19.8 No 6.
1G33*H0VF001 IKJB*Z129 7
5.5 No 0.
1G33*MOVF053(h) 1KJB'Z4 7
-44W9.20 7 Yes
.31 1G33*MOVF034(h) w 1KJB*Z6 7
24.2 No D
1G33*MOVF039(h)U) 1KJB*Z7 7
6.6 No 1G33*MOVF004(h) e.
de 1G33*MOVF054 1KJB*Z129 7
5.5 No 31 1WCS*MOV17d 1KJB*Z5 1
12.1 Yes 6.
1WCS*MOV172 IKJB"Z5 1
12.6 Yes o.ai 1E22*MOVF023 IKJB*Z11 1
50 No 1
1E12*MOVF024A IKJB*Z24A 10 63.8 No 6.
IE12*MOVF011A IKJB*Z24A 10 34.1 No 1E21*M0VF012 IKJB*Z24A 10 57.2 No 1
1E12*MOVF024B IKJB*Z24B 10 63.8 No 6.3 1E12*M0VF0118 IKJB*Z24B 10 30.8 No 5.31 1E12*M0VF021 1KJBT24 C - E 10 97.9 No 31 ISFC*MOV119 IKJill26 1
6B No
~~6. M SFC*MOV120 IKJr Z27 1~~
62.7 No 6.31
~1SFC*MOV139 1KJi l28 1
39.6 No No e
ISFC*MOV121 1KJtil28 1
39.6 l
=
k 1 sfcryota.y
~~tWJ8 MEA 7 1~~
W W"
)
i
-~
TABLE 3.6.4-1 (continued) 5 CONTAINMENT AND DRYWELL ISOLATION VALVES g
R MAXIMUM SECONDARY I
VALVE PENETRATION ISOLATION TIME CONTAINMENT PRt NUMBER NUMBER VALVE GROUP (Seconds)
BYPASS PATH (f) _ sie L (Yes/No) c.
z P
i U
MN Automatic Isolation Valves a.
l /bf7><d PrimaryContainment(Continued (g) l 4f 1.
F-10FR*A0V102(b) 1KJB*Z35 1
N/A No IDRF*A0V101((b) 1KJB*Z35 1
N/A No
.31 10ER*A0V127(b) 1KJB*Z38 1
N/A No 6.
b) 10ER*A0V126 1KJB*Z38 1
N/A No
.a-IFPW*MOV121 IKJB*241 1
34.1 Yes w1 15AS*MOV102 IKJB*Z44 1
22.0 Yes IIAS*MOV106 1KJB*Z46 1
18.7 Yes
.31 J,
ICCP*MOV138 IKJB*Z48 1
22.0 No 6.
v' ICCB*MOV158 IKJB*Z49 1
23.1 No 6.31 1CCP*MOV159 1KJB*Z49 1
24.2 No 15WP*MOVSA IKJB"Z53A 1
50.6 No 15WP*H0V5B 1KJB"Z53B 1
53.9 No 31 1HVN*MOV102 1KJB*Z131 1
31.9 Yes 6.
IllVN*MOV128 IKJB*Z131 1
28.6 Yes 1HVN*MOV127 IKJB*Z132 1
27.5 Yes ICN5*MOV125 IKJB*Z134 1
22.0 Yes e
I
TARLE 3.6.4-1 (continued) 5
{g CONTAINMENT AND DRYWELL ISOLATION VALVES MAXIMUM SECONDARY it3 -
is VALVE PENETRATION ISOLATION TIME CONTAINMENT SURE NUMBER NUMBER VALVE GROUP (Seconds)
BYPASS PATH (f)
(Yes/No) ez E(A,se a.
Automatic Isolation Valves f<M74
, --gr 1.
Primary Containment (Continued) 1E51*MOVF063(b) 1KJB*Z15 2
9.9 No IE51*MOVF076(b) 1KJB*Z15 2
13.4 No 1E51*MOVF064 1KJB*Z15 2
9.9 No 6.3 IE51*MOVF031 IKJB*Z16 2
M Jd.S No w
3:
1E51*MOVF077 IKJB*Z17 3
14.2 No 1
IE51*MOVF078 IKJB*Z1BB C 3
16.5 No 6.3 J,
1HVR*A0V165 1KJB*231 8
3 No c'
1HVB*A0V123 IKJB*Z31 8
3 No 1
1HVR*A0V128 IKJB*Z33 8
3 No 6
1HVR*A0V166 IKJB*233 8
3 No
.31 155R*SOV130 1KJB* 01B 10 3
No 6.
ISSR*SOV131 IKJB 6018 10 3
No i?
l
t TABLE 3.6.4-1 (continued)
CONTAINMENT AND DRYWELL ISOLATION VALVES j$
R' MAXIMUM SECONDARY jj VALVE PENETRATION ISOLATION TIME CONTAINMENT P
HUMBER NUMBER VALVE GROUP (Seconds)
BYPASS PATH (f)
(Yes/No) c:
~~'P a.~~
Automatic Isolation Valves s,.A0f Drywe116)
A in I
2.
1HVR*A0V147 10RB*Z32 1
3 No ICCP*MOV142 1DRB*Z50 1
30 No ICCP*MOV144 1DRB*Z51 1
30 No
/A d
ICCP*MOV143 IDRB*Z51 1
30 No N
ISWP*MOV4A IDRO*Z54 1
52.8 No ISWP*MOV4B IDRD*Z54 1
51.7 No A
15WP"MOVSA IDRB"Z55 1
50.6 No N
a ISWP*MOV5B 10RB*Z55 1
53.9 No
-d IRCS*MOV58A IDRB*Z152 1
11.0 No
/A 1RCS*MOV59A IDRB*Z153 1
10.6 No 1RCS*MOV60A 10RB*Z154 1
6.3 No N/
1RCS*MOV61A 3DRB*Z155 1
8.6 No 1RCS*MOV58B IDR3*Z156 1
10.6 No 1RCS*MOV598 1DRB*Z157 1
10.8 No
/A 1RCS*H0V60B IDRB*Z158 1
6.38 No N
t IRCS*MOV61B IDRBaZ159 1
8.9 No
/
1HVR*A0V125 1DRB*Z32 1
3 No l
1HVR*A0V126 10RB'Z34 1
3 No 1HVR*A0V148 IDRB*Z34 1
3 No l
.~
TABLE 3.6.4-1 (continued) y CONTAINMENT AND ORYWELL ISOLATION VALVES E
MAXIMUM SECONDARY ST 5
VALVE PENETRATION ISOLATION TIME CONTAINMENT PR e
NUMBER NUMBER VALVE GROUP (Seconds)
BYPAS$ PATH (f)
'L e
(Yes/No)
's-4 a.
Automatic Isolation Valves s
p 4
2.
Drywell (Continued)h p
i 1 CPM *MOV2A 1DRBZ57A 10 33 No iICPM*MOV4A 1DRBZ57A 10 3/3 No ICPM*MOV2B IDRBZ578 10 3#3 No ICPM*MOV4B 10RB257B 10 313 No w
ICPM*MOV3A 10RBZ58A 10 3FJ No D
ICPM*MOVIA 10RBZ58A 10 3#3 No N
m ICPM*MOV3B 10RBZ588 10 313 No 0
1 CPM *MOV1B 10RBZ58B 10 36 7 No IB33*A0VF019 10RBZ449 9
.(QS" No IB33*A0VF020 10RBZ449 9
(6W No
TABLE 3.6.4-1 (Continued) jj CONTAINMENT AND ORYWELL ISOLATION VALVES 5
SECOP'OARY
( IL5l
VALVE PENETRATION CONTAINMENT P M IRE NUttBER NUMBER BYPASS PATH (f)
([ps i g)--
c:
(Yes/No)
(
[cgo j),)p I b.
Manual Isolation Valves 1.
Primary Containment 1E12*F099A 1KJB*Z21A No 0.";
1E12*F0998 IKJB*Z210 No i 1HVR*VB 1KJB*2602A No 1HVR*V10 1KJB*Z602B No
.31 u,
3:
ILSV*V64 1KJB*Z6020 No 6.
1HVR*V12 IKJB*Z602F No
~~u. 31 m~~
J, ILMS*V14 1KJB*Z603A No
.31
~~ILMS*V12 1KJB*Z603A No ILMS*V7 IKJB*Z603C No~~
' 3; ILMS*V16 IKJB*Z603C No
.31 1 CMS *V2 1KJB"Z605A No 6.
ICMS*V3 IKJB*Z605B No 6.31 1HVR*V14 IKJB'Z606A No 6.31 1HVR*V16 1KJB*2606B No ICMS*V16 IKJB*Z606C No ICMS*V15 IKJB*Z6060 No 31 ILSV*V65 IKJB"Z606E No 1HVR*V18 IKJB*2606F No 6.3 1E12*VF044A 1KJB*Z21A No 1E12*Vr044B IKJB*Z218
No
~
TABLE 3.6.4-1 (Continued) 5 g
CONTAINMENT AND DRYWELL ISOLATION VALVES
~~5 SECONDARY ESI '~~
VALVE PENETRATION CONTAINMENT E55URE c.
t NUMBER NUMBER BYPASS PATH (f) 5 ygge (Yes/No)
IM[
b.
Manual Isolation valves 1.
Primary Containment jIFWS*MOV7A*))
I IKJB*Z3A Yes
~~6. n --~~
I 1KJB*Z3B Yes 1
IFWS*MOV7B '(')
1E22*MOVF015(b)(e)
IKJB*Z8 No i
IE22*MOVF004 1KJB*Z9, Bf210 No 1
1 IE22*MOVF012('I IKJB*Z11 No c '
w 1E21*MOVF001 1KJB*Z12 No 31 g,)
1 1E21*MOVF005 IKJB*Z13 14 No 6.
,1E51*MOVF068,))
g IKJB*Z17 No b.31 o
I 1E51*MOVF019 '
1KJB*Z1BA No 1
I
')
1E51*MOVF013 1KJB*Z119, ORB *Z130 No 1E12*MOVF027A('I I
1KJB"Z21A No
.31 1E12*MOVF042A '))
1KJB*Z2]A No 6
I 1E12*MOVF027B '
IKJB*Z21B No
.31 1E12*MOVF042B ')
1KJB*Z21B No C
IE12*MOVF042C '))
I 1KJB*Z2]C No 6.31 I
1E12*MOVF073A '
IKJB*Z23A No
.31 1E12*H0VF073B ')
1KJB*Z23B No 6.
I 1E12*MOVF064p')
I 1KJB*Z24A No IKJB*Z24A No l _ y E21*MOVF011
)
1KJB'Z24B No IE12*MOVF0648 IE12*MOVF064C(')
I 1KJB*Z24C
'No 1
E12*MOVF004p))
1KJB*Z25JfA No E12*MOVF105 1KJB'Z25C No 1
-. tE/2M-AMVF00'/8 1Ir38 K E t4~8 JYo A
j $387Y-30V/39
.~
TABLE 3.6.4-1 (Continued)
CONTAINMENT AND DRYWELL ISOLATION VALVES E5 SECONDARY TESI '
VALVE PENETRATION CONTAINMENT ESSURE I
NUMBER NUMBER BYPASS PATN(f)
(
e
[(d'O#
(Yes/No)
_3 b.
Manual Isolation Valves 1.
Primary Containment (Continued)
IC11*MOVFOBg*I')
1KJB*Z29 No i
)
ICPP'MOV104 1KJB*Z33 No
~~6. 3T ICPP*MOV105 ')~~
1KJB*Z3'3 No I
ISWP*MOV507A 1KJB*Z52A No
~~b..ir w~~
IKJB*Z52B No 1
ISWP*MOV507p
}
ISWP*MOV81A(,)
1KJB*Z53A No 6.3
)
ISWP*MOVBIB,I IKJB*Z53B No
. 31 --
4 ISWP'MOV503A '))
1KJB*Z53A No ISWP*MOV50gg*
1KJB'Z538 No c1 ISVV*MOVIB 1KJB*Z102 No
.31 I)
ISVV*MOVIA 'I')
1KJB*Z103 No 6.
ICPP*SOV140 1KJB*Z31 No 1 CMS *SOV350 ')
1KJB*Z601E No 31 I
1 CMS *SOV31B ')I I
1KJB*Z601E No 6.
I ICMS*SOV35B '
1KJB*2601F No
~~6. 3I-ICMS*SOV310 '))~~
I 1KJB*Z601F No I
1KJB*Z605E No ICMS*SOV35C ')
I ICMS*SOV31A '
1KJB*2605E No 31 1 CMS *SOV35A 'I 1KJB*Z605F No I
ICMS*SOV31C 'I IKJD*Z605F I
No e
t
l TABLE 3.6.4-1 (Continued)
CONTAINMENT AND ORYWELL ISOLATION VALVES 5
SECONDARY vi VALVE PENETRATION CONTAINMENT SSURE NUMBER NUMBER BYPASS PATH (f)
(ns e
Z (Yes/No)
M fengs
~~fppy /(~~
b.
Manual Isolation Valves 2.
Drywell ISAS*V489 IDRB*Z45 No I
l 11A5*V79 1DRB"Z47 No n, m 1HVN*V542 1DRB*Z54' No ISWP*V205 IDRB*Z54 No
^/.-_
w2 ISWP*V206 1DRB*Z55 No
/A ISVV*V50 1DRB*Z107 No i
1SVV*V53 1DRB*2112 No n, n ino-*-.--
fg u
,m
!?." ' * "J T ^ ^. -
2"""*'
A N
1RCS*V132 1DRB*Z152 No IRCS*V131 1DRB'Z153 No 1RCS*V162 IDRB*Z154 No
' ^
1RCS*V156 IDRB*Z155 No IRCS*V187 3DRO*Z156 No IRCS*V186 IDRB*Z157 No A
1RCS*V217 IDRB"Z158 No N
1RCS*V211 IDRB*Z159 No m
$C2$^i^rO~vsuukg'
$CCC 2$0i M
ILna aV V J'II f,('
E""
~~7 $ ', U M~~
$C I[3uvJ1L -
-r M
e
.1 CMS 430V3YA
.$-M8% 2 600 Mo 1cnjSNJ0VJY8
.1NBf E VJo go
.1 CMS #30VJ V' 2 D/8f 2-f99 No
_t cntyg.Sov3VD
_g pppyygay
,y, d CMSEJ0VJEA
.2 D48f2333 We 1 cms # Jov3DG-
_.z pgyz y
/Vo
s 9
TABLE 3.6.4-1 (Continued)
B CONTAINMENT AND ORYWELL ISOLATION VALVES g
SECONDARY ST VALVE PENETRATION CONTAINMENT SSURE NUMBER HUMBER BYPASS PATH (f)
_(ps e
3 5
(Yes/No)
C
? c.)f.
Isolation Valves EfA
/.
/1 a%.rr a, Cos / 52s,rs / N f.
seyw.w; r - - t i.ran)
IC) 1KJB'Z3A Yes 94 1921*A0VF032A 1B21*A0VVF010p )
ID IKJB*l3A Yes 6.
IB21*A0VF0328 IKJB*Z38 Yes
. f.
g 1821*A0VVF01{g)(c))
1KJB*Z3B Yes
.94 1
1E22*A0VF005 IKJB*Z9, RBkl0 No 6.
w
)
IE22*RVF014 IKJB'Z11 No 6.31(a))
58 i
1E22*RVF035 1KJB*Z11 No
~~IE22*RVF039 (b)(c)~~
IKJB*Z11 [
No 1E21*A0VF006(b)(c) 1KJB*Z13,iDRB*Z14 No 6.31-IE51*A0VF065 1KJB"Z19.. ' ORB *Z130 No
.31
..E51*A0VF066(b)(c) 1KJB*Z19,jpRB*Z130 No EE12*A0VF041C(b)(c)
IKJB*Z21C.70RBp22C No
~~6. 3 L C~~
1KJB*Z23A No 6.
1RHS*RV3A 1E12*RVF055A IKJB*Z23A No 1E12*RVF025A IKJB*Z23A No 6.
1E12*RVF017A IKJB*Z23A No
(*
1E12*RVF005 1KJB*Z23A No IE21*RVF018 IKJB*Z23A No
'?
E21*RVF031 1KJB*Z23A No
.3b ".
'IRHS*RV3#6 IKJB*Z238 No 6.
e 1E12*RVF055B IKJB*Z23B No G. M 1E12*RVF025C IKJB*Z238 No 1
,-3 eng.gyppg, Jys8+2.43A Me

~~.1 R//s.+ V Wo~~

.2 h78y22 Wo w
,3 TABLE 3.6.4-1 (Continued)
M CONTAINMENT AND ORYWELL ISOLATION VALVES E
SECONDARY LST 5
VALVE PENETRATION CONTAINMENT P
URE NUMBER NUMBER BYPASS PATH (f)
Js n _
e E
c=.p.g w n e. A c)l.
Isolation Valves i.
c-s-~ m
~~f.,/)f-;,_ :: (Continued) 67) 1E12*RVF025B 1KJB*Z23B No 1E12*RVF030 IKJB*Z238 No il IE12*RVF101 1KJB*Z230 No 6.3 IE12*RVF0178 1KJB*Z23B No~~
.31 w1 JSFC*V101 1KJB*Z26 No 1
~~C11*VF122 1KJB*Z29 No 6.3 m
4 10FR*V180 IKJB'Z35 No
~~1FPW*V263 IKJB*Z41 Yes 6.31 15AS*V486 1KJB'Z44 Yes v.~~
11AS*V80 IKJB*246 Yes
{
CP*V118 IKJB*248 No
.31 15WP*V174 1KJB*Z52A No 6.
ISWP*V175 1KJB*Z52B No ISVV*V9 1KJB*Z102 No 6.31 Q SVV*V31 IKJB*Z103 No
..HVN*V541 1KJB*Z132 Yes 6.31 1CNS*V86 1KJB*2134 Yes
' f gygy V/3)[
jgygg y,
.1W8#2 +'7
. No L-- AccP,+ V/4 o
~Z M81238 He
.1 Of4W-VY
[ 1 sfcf V3SO
.1.kT8 FED 7 A4 1 krs+zas-so 1
y.sece vas/
~
s TABLE 3.6.4-1 (Continued) 5 CONTAINMENT AND DRYWELL ISOLATION VALVES g
SECONDARY Si g
VALVE PENETRATION CONTAINMENT ESSURE NUMBER NUMBER BYPASS PATH (f)
(p, (Yes/No) c3 I
T]ces.73n 2
C.
0//e f
M b.
-Mammt Isolation Valves w
Q) ^
)
I 3
2.
Drywell,"
1821*RVF047A IDRB*Z136 No I 1821*RVF041A IDRB*Z137 No N/A 1821*RVF051G IDRO*Z138 No 1821*RVF041L IDRO*Z139 No N/A w) 1821*RVF047C IDRB*Z140 No 1821*RVF041G IDRB*Z141 No 1
IB21*RVF051C 1DRB*Z142 No N/A
~~IB21*RVF041C 1DRB*Z143 No 1821*RVF0478 1DRB*Z144 No 1821*RVF041B IDRB*Z145 No A~~
1821*RVF051B 1DRB*Z146 No N
1821*RVF041F IDRB*Z147 No 1821*RVF047F IDRB*Z148 No A
1821*RVF0410 1DRB*Z149 No IB21*RVF047D IDRB*Z150 No
/A 1021*RVF051D IDRB*Z151 No IC)
IE17'A0VF041A 1DRB*Z22A No IE12*A0VF041B(c) 1DRB*Z22B No i
q
TABLE 3.6.4-1 (Continued)
{
CONTAINMENT AND DRYWELL ISOLATION VALVES E
SECONDARY VALVE PENETRATION CONTAINMENT SURE e
NUMBER HUMBER BYPASS PATH (f) e (Yes/No) 5 #l hchv*75".
~p c.
0/6r g[se 4.
themm1 Isolation Valves Drywell_@(Continued) 2.
1DFR*V4 1DRB*Z37A No 10FR*V3 IDRB*Z37A, No A
1DFR*V1 1DRB*Z37B bo N
w IDFR*V2 IDRH*237B No N/A IDER*V14 IDRB*240A No 10ER*V15 IDRB*Z40A No e
I IDER*V16 IDRB*Z40B No N/A
. 1 DER *V17 IDRR*Z40B No 15AS*V487 IDRB*Z45 No IIAS*V78 1DRB*Z47 No
/A ICCP*V119 1DRB*250 No N
q ISWP*RV119 IDRB*Z54 No Ogyg ICM*VEXF004A IDRB*ZS6 No
/A ICA f*VEXF0048 1DRB*Z56 No N
10 t"VF006 1DRB*Z56 No N
2 10 4'VF007 1DRD*Z56 No ICCP*V133 1DRB*Z51 No n
.~
~
s TABLE 3.6.4-1 (Continued)
B CONTAINMENT AND DRYWELL ISOLATION VALVES g
5 SECONDARY
'Zs.
5 VALVE PENETRATION CONTAINMENT E55URE NUMDER NUMBER BYPASS PATH (f)
~
(Yes/No) e r
$5/C& '
y
/2
'[
Other Isolation Valves w
c.
o I
2.
Drywell (Continued)
'1821*VF036A 1DRB*Z107 No A
1921*VF036F IDRB*Z1Q7 No 1821*VF036G 1DRB*Z107 No 1821*VF036P IDRB*Z107 No N/A w}
1821*VF039C IDRB*Z107 No
/A 1921*VF039H IDRB*Z107 No A
L 1821*VF039K IDRB*Z107 No N
1821*VF0395 1DRB*Z107 No n/a 1821*VF036J 1DRB*Z112 No 1821*VF036L IDRB*Z112 No N/
1821*VF036M 3DRB*Z112 N3 N/A 1821*VF036N IDRB*Z112 No IB21*VF036R IDRB*Z112 No 1821*VF039B IDRB*Z112 No
/A 1821*VF039D IDRB'Z112 No l
IB21*VF039E IDRB*Z112 No 1833*VF013A 1DRB*Z133 No 1933*VF017A IDRB*Z133 Pa N/
1833*VF0138 1DRB*Z135 No N/A IB33*VF0178 IDRB*Z135 No
~~f CMS 4-VYl~~
.t57A'8Wff$37
/Vo 1 cir c f V t'0
-.LDfaf 2" '
l l
e, l
{
4
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=
1 k3 E
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' q g a%
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g C
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C 4
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2
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8 8
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=
=
s W
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RIVER BEND - UNIT 1 3/4 6-48 0Q4
. t i.
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J
CONTAINMENT SYSTEMS 3/4.6.5 SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY - OPERATING LIMITING CONDITION FOR OPERATION 3.6.5.1 SECONDARY CONTAINMENT INTEGRITY - OPERATING shall be maintained.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.
ACTION:
Without SECONDARY CONTAINMENT INTEGRITY - OPERAThG restore SECONDAR CONTAINMENT INTEGRITY - OPERATING within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
SURVEILLANCE REQUIREMENTS 4.6.5.1 SECONDARY CONTAINMENT INTEGRITY - OPERATING shall be demonstrated by:
/.
Verifying at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the pressure within the a.
Annulus Building, the Auxiliary Building and the Fuel Building are less than or equal to 3.0,445 and 4,46 inches of vacuum water gauge, respectively.
00 o.o b.
Verifying at least once per 31 days that:
1.
r.ll secondary containment equipment hatch covers are installed.
2.
The door in each access to the secondary containment is closed, except fe==owstone eritry and exit.
c/urog ec M 3.
All secondary containment penetrations not capable of being closed by OPERABLE secondary containment automatic isolation dampers and required to be closed during accident conditions are closed by valves, blind flanges, or deactivated automatic dampers / valves secured i,n position.
%.:n ir.edieted f=1-is-being -handled-in-the secondary-containment-end during C0ri.^/.T:P.".T:0^:: n.d ;;;;; tin.; cith :. ;;tn.ti;'
7.,
...L..uw 6u.
...uv.
4*e.+e4 W
RIVER BEND - UNIT 1 3/4 6-49
~
e+
e
. me e
v*f
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) c.
At least once per 18 months:
1.
Verifying that one standby gas treatment subsystem will draw down the Shield Building Annulus and the Auxiliary Building to greater than or equal to 0.5 and 0.25 inches of vacuum water gauge in less than or equal to b6976 and 45 seconds respec-tively, and, 19 3 g ol 2.
Operating one standby gas treatment subsystem for. one hour and maintaining the Shield Building and the Auxiliary Building less than or equal to and 0.25 inches of vacuum water gauge at a' flow rate not exc eding 2000 and 5000 CFM, respectively.
O5 3.
Verifying that one fuel building ventilation subsystem will draw down the fuel building to less than -0.25 inches of vacuum water in less than -pr equal to 44 5 seconds, and EG 4.
Operating one fuel building ventilation subsystem for one hour and maintaining less than or equal tc -0.25 inches of vacuum water gauge in the fuel building at a flow rate not exceeding 5000 CFM.
(
9 4
RIVER BEND - UNIT 1 3/4 6-50
~
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w'***
r
CONTAINMENT SYSTEMS 3/4.6.5 SECONDARY CONTAINMENT SECONDARY CONTAINMENT INTEGRITY - FUEL BUILDING LIMITING CONDITION FOR OPERATION 3.6.5.2 SECONDARY CONTAINMENT INTEGRITY - FUEL BUILDING shall be maintained.
APPLICABILITY: OPERATIONAL CONDITIONS
~~ACTION:~~
Without SECONDARY CONTAINMENT INTEGRITY - FUEL BUILDING suspend handling of irradiated fuel in the Fuel Building. The provisions of Specification 3.0.3 are not applicable.
A Eyre Eo s/S _
g.-
U SURVEILLANCE REQUIREMENTS
_t R ft.:. A R M D M 'G 4.6.5.2 SECONDARY CONTAINMENT INTEGRITY - SPEM4.4 shall be demonstrated within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to and at least once per 7 days during handling of h'
irradiated fuel in the Fuel Building by varifying that:
The pressure within the Fuel Building is less than or equal to a.
0.25 inches of vacuum water gauge.
b.
All Fuel Building equipment hatch covers are installed, al. Lo't m 3
-T+re door in each access to the Fuel Building is closed except for c.
routine entry and exit.
d.
All Fuel Building penatrations except the Fuel Building Ventilation System charcoal filtration Msystem Ammunsre penetrations required to be closed during Fuel Handling accident conditions are closed by valves, blind flanges, or dampers secured in position.
l l
~~Wnen irradiated fuel is being handled in the Fuel Building-~~
~~'3 A ' t r o m, r.ul M0 in onTu t~~
~~0 L 2e r. '~~
re
- - r L-
^~
RIVER BEND - UNIT 1 3/4 6-51
CONTAINMENT SYSTEMS SECONDARY CONTAINMENT AUTOMATIC ISOLATION DAMPERS LIMITING CONDITION FOR OPERATION 3.6.5.3 The secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.3-1 shall be OPERABLE with isolation times less than or equal to the times shown in Table 3.6.5.3-1.
APPLICABILITY: 4PGAAT'^L 00 C!'!O"; 1, 0, 0 e..
^.
As s itc w n u, Td k 3.G.S.3 -1 With one or more of the secondary containment ventilation system automatic isolation dampers shown in Table 3.6.5.3-1 inoperable, maintain at least one isolation damper OPERABLE in each affected penetration that is open, and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months either:
a.
Restore the inoperable _ damper (s) to OPERABLE status, or b.
Isolate each affected penetration by use of at least 6ne deactivated automatic damper secured in the isolation position, or c.
Isolate each affected penetration by use of at least one closed manual valve or blind flange.
< g# ({
A-4The.
s neovisiewa
.a S pa r e mvs on 3.0. 4 a r c. nd-appuc4hle -
Otherwise, '- 0"E""!CML 0^T!TMN 0, 0.. h be in at least HOT SHUTDOWN within the next 32 hours3.703704e-4 days 0.00889 hours 5.291005e-5 weeks 1.2176e-5 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
t': 1!:+, '- 0;;r:t': :1 0:nd't':n
, :.;;;nd h;-di'n; :f 2 r:d':';d -
5:' '- th: ;;::nd:q ::nt:i ::nt, 00"E ^.LTE""!ONE :-d :;:r:ti:m; u'tr ;
p tenti:' fr-d :t # ;; t' reitter ;::: 1
'h: pr:;':!: z e' Epe:4":2-J n;t ;;;15 ;5 @1;. io ts*$cdLA ". at S **" N g tien 0.0.0 :r:
fw M +k AC770M lo ed/t4 above.
M&
SURVEILLANCE REQUIREMENTS 4 M, W f 4 declaud AcM h4 44,_ QA W
Ac,TJ04 h gtk.x @ an.q w.
4.6.5.3 Each secondary containment ventilation system automatic isolation damper shown in Table 3.6.5.3-1 shall be demonstrated OPERABLE:
Prior to returning the damper to service after maintenance, repair or a.
replacemer.t work is perfort,ed on the damper or its associated actuator, control or power circuit by cycling the damper through at least one complete cycle of full travel and verifying the specified isolation time.
"r.; r
.. i;t;; f.;l i; 0,;in; t;.ndi:: i-th: ;;;;.dery :.nt:'-.;nt :nd d.ri;g 00" "LTC^J.T!ONS.. J ep;ietie ; ith e pet;i.tiei fer diai ' ; th: 7:::i:7 x;;;I.
RIVER BEND - UNIT 1 3/4 6-52 e.
i CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) v b.
During COLD SHUTDOWN or REFUELING at least once per 18 months by verifying that on a containment isolation test signal each isolation damper actuates to its isolation position.
c.
By verifying the isolation time to be within its limit when tested pursuant to Specification 4.0.5.
M 5
k mel RIVER BEND - UNIT 1 3/4 6-53
s TABLE 3.6.5.3-1 SECONDARY CONTAINMENT VENTILATION SYSTEM AUTOMATIC ISOLATION DAMPERS
[E'AAmPLE i l H VR,at A C D l(e l MAXIMUM L__-
csddk'((dnm ISOLAT10N TIME DAMPER DAMPER FUNCTION (Seconds)
GROUP" ShieldBuildingApnulujfeA00jltion4 48
,,2, 3 15 12 Venti 1.
V Exhaust Damper (I HVR o Ventilation Shield Building AnnulujL'iOD Z3 A) l,1,3 15 12 2.
F Exhaust Damper (1 HVR a 3.
Shield Building Annulu Ve tilation F
Il5 15 12 Exhaust Damper (I HVR efd f
OD 238) a Auxiliary Building Ventilation / 4) 1.1.3 15 4.
Exhaust Damper (1ffiVRVah40D 21 11 5.
Auxiliary Building Ventilajion#
Exhaust Damper (IMiVR4*FAOD 262) i, L,3 15 11 6.
Auxiliary Building Vent lation
' A0D 249)
I.1, 5 15 11
/
Exhaust Damper (ITHVRf 7.
Auxiliary BuildingVenjilation f
F Exhaust Damper (]THVR7afd AOD 10A)
/,2. 3 15 11 8.
Auxiliary Building,Ventila, tion g Exhaust Damper (17HVR7aWAODJiGF)
J, z,3 15 11 9.
Auxiliary Buildin Ventilation Supply Damper (1 VRVa%FAOD#i43)
/, 2, 3 1>
11
~~10. Auxiliary BuildinJ ' Ventilation g Supply Damper (17HVR/aR&%0Df161) l,1. '$~~
15 11 Fuel Building Vintila@ tion Supply, 11.
Damper (IMiVRfahdOD 121 i, s, 3,p 15 13 F
~~12. Fuel Builqing V ntilation Supply Damper (IrHVR/~~
ADDF101)
I,2,3,#
15 13 F
A00@pp4y E'srha6ust.
fg ()-
~~13. Fuel Building V lation 6.~~
15 13 Mp6 Damper (IfHVRd gg
, g, 3, p 14.
Fuel Building Ventilation Supp4y Esc havs4
/
15 13 Damper (17HVRFEd AOD@g37 g,3,3,g F
e tet cn twwd% lrradikd (vd 'in +tu Nel 6didi,13 RIVER BEND - WIT 1 3/4 6-54 re
i TABLE 3.6.5.3-1 (Continued)
MAXIMUM A pA. c w.g cienn,% % mg..s.:3 ISOLATION TIME DAMPER (Seconds)
GROUP" DAMPER FUNCTION Fuel BuilpHVFfekplation Exhaust ng Ven I'l' 5 #
15.
Damper (1 AOC502) 15 33 16.
Fuel Building Vgntilat 'on Exhaust Damper (1 HVFVand %0 12) i,1. 5.5 15 13 F
4 "See Table 3.3.2-1.
~~Wku Laul\\ leg dradikd $r( in $ FVt I but l00 I~~
RIVER BEND - UNIT 1 3/4 6-55
CONTAINMENT SYSTEMS STANDBY GAS TREATMENT SYSTEM
{
LIMITING CONDITION FOR OPERATION 3.6.5.4 Two independent standby gas treatment subsystems shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 aasr*.
ACTION:
With one standby gas treatment subsystem inoperable, restore the a.
inoperable subsystem to OPERABLE status within 7 days, or4-)
1.
I.m 0"EP_^?!O'*L 00'DITIOM 1. ? et ? The in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months w
~
!- 0;;r_ti; nil 0;;.d-:::.i.
Jel
...r.ow...mw,,ow w,
nn.u..
e secondary containment, CORE ALTERATIONS an ations with a ial for draining the reactor v The provi-sions of Speci n 3.0.3 are not icable.
b.
With both standby gas trea ubs inoperable in Operational Condition 8, suspend ing of irradiated the secondary
~'
containment, TERATIONS or operations with a p.
I for drainin reactor vessel. The provisions of Specificatio 3.
---34,76, 7 SURVEILLANCE REQUIREMENTS 4.6.5.4 Each standby gas treatment subsystem shall be demonstrated OPERABLE:
a.
At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters OPERABLE.
t.;.. irradi ;;d ' ;1 i; i;in; i;ndl.J...
.o.
....d_,
ng
.. wow.,y 6.o....s,..
!O".C.^.' TE""?!OME :nd :;;r:ti:n; vith : ; ; t ;., t.. ',.".. u.. n..,,......t..
....:1.
RIVER BEND - UNIT 2 3/4 6-56 v-..
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following q
painting, fire or chemical release in any ventilation Zone communi-cating with the subsystem by:
i 1.
Verifying that the subsystem satisfies the in-place penetration and bypass leakage testing acceptance criterit, of less than 0.05%
and uses the test procedure guidance in Regulatory Positions C.S.a. C.S.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 12,500 cfm'1 10%.
2.
Verifying, within 31 days after removal, that a laboratory analysis of a representative carbon sample obtained in accor-dance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, Yor a methyl iodide penetration of less than 0.175%; and 3.
Verifying a subsystem flow rate of 12,500 cfm i 10% during system operation when tested in accordance with ANSI N510-1975.
i i
c.
After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation, by verifying within 31 days after removal, that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 0.175%.
d.
At least once per 18 months by:
1.
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence for the:
a)
LOCA, and AMA*6 d t...C kg n.e,a./, f n b' Ass.rgf*f)-
b) 2.
Verifying that the pressur*e drop across the combined HEPA l
filters and charcoal adsorber banks is less than 8 inches Water
~
Gauge while operating the filter train at a flow rate of 12,500 cfm i 10%.
3.
Verifying that the filter train starts and isolation dampers open on each of the following test signals:
I l
l RIVER BEND - UNIT 1 3/4 6-57 y,.
O CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a.
Manual initiation from the control room, and b.
Simulated automatic initiation signal.
4.
Verifying that the filter cooling bypass dampers can be manually l
opened and the fan can be manually started.
5.
Verifying that the heaters dissipate > 61 kw when tested in accordance with ANSI N510-1975.
e.
Af ter each complete or partial replacement of a HEPA filter bank by verifying that the HEPA filter bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1975 while operating the sys'.em at a flow rate of 12,500 cfm 2 10%.
f.
Af ter each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and bypass leakage testing acceptar.ce criteria
~
of less than 0.05% in accordance with ANSI N510-1975 for'a halo-genated hydrocarbon refrigerant test gas while operating the system at a flow rate of 12,500 cfm 210%.
e O
e RIVER BEND - UNIT 3 3/4 6-58
+.
CONTAINMENT SYSTEMS SHIELD BUILDING ANNULUS MIXING SYSTEM LIMITING CONDITION FOR OPERATION
~
3.6.5.5 Two independent Shield Building Annulus Mixing subsystems shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3 an5:*7 ACTION:
With one Shield Building Annulus Mixing subsystem inoperable, restore a.
the inoperable subsystem to OPERABLE status within 7 days, or4) 1.
.. ^N ZT

^:m ^^Z:T:Z !, O ;-___2,fbe in at least HOT SHUTDOWN ithin the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SH' TDOWN within the J
~~following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .~~
~~- ^;; ;;i;ca' 0.......m.~~
^
...r nw nonweing vi n1.u.
in the secondary containment, CORE ALTERATI nd opera-tions otential for draining the r r vessel. The provisions of ication 3.0.3 ot applicable.
b.
With both Shield Buildi.
us
~
ubsystems inoperable in
[
Operational Conditi suspend handling o diated fuel in the secondary co ent, CORE ALTERATIONS or operatic a potential for de g the reactor vessel. The provisions of Specifi
~
3 aa+
--a'i--e SURVEILLANCE REQUIREMENTS 4.6.5.5 Each Shield Building Annulus Mixing subsystem shall be demonstrated OPERABLE:
At least once per 31 days by initiating, from the control room, a.
verifying that the subsystem operates for at least il"
...,,;-and
/f MWe r a
~~- - 2 _ _ g e.. g a.. 1 a, q t.. L -_ y s g 2.~~
$t_ ___;
7aa{ atTreattnot and an...+(m.,
mt.6
.....r.1 s__
g__z_2
_. _3
,,,,,j, RIVER BEND - UNIT 1 3/4 6-59
-.w
CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.
At least once per 18 months by:
1.
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence for the:
a)
LOCA, and b) f :1 52-d!'n; :::'i ^ deds rW M et n.a,c.;
.rpuA Verifyingthateachsubsystemwasaflowrateof[52,500/cfm 2.
+ 10%.
3.
Verifying that the subsystem starts and isolation dampers open on each of the,following test signals:
a.
Manual initiation from the control room, and b.
Simulated automatic imitation signal.
e t
RIVER BEND - UNIT 1 3/4 6-60
CONTAINMENT SYSTEMS FUEL BUILDING VENTILATION LIMITING CONDITION FOR OPERATION 3.6.5.6 Two independent Fuel Building Ventilation Charcoal Filtration subsystems shall be OPERABLE 64 A OPERATro#AL Co#DITToN e eu apMy 4 Wu.
7 A
PERATIONAL CONDITIONS 1, 2, 3 and *.
ACTION:
With ohe Fuel Butiding Ventilation Charcoal Filtration subsystem a.
inoperable, restore the inoperable subsystem to OPERABLE status within 7 days, or:
1.
In OPERATIONAL CONDITION 1, 2 or 3, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SNUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .
2.
In Operational Condition
, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS and operations with a potential for draining the reactor vessel. The provi-sions of Specification 3.0.3 are not applicable.
ot.dnLL. m met apeuhd A Atu.e e p c rMv4 o
With both' Fuel Building Ventilation Charcoal Filtration su;bsystems
[
b.
inoperableNin Operational Condition *, suspend handling of irradiated fuel in the secondary containment, CORE ALTERATIONS or operations with a potential for draining the reactor vessel. The provisions of Specification 3.0.3. are not applicable.
SURVEILLANCE REQUIREMENTS 4.6.5.6 Each Fuel Building ventilation Charcoal Filtration subsystem shall be demonstrated OPERABLE:
1.
At least once per 31 days by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the subsystem operates for at least 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months with the heaters OPERABLE.
")
L
, % %V y On'-
CPE2A *TIONA L.
COND17EoM
~~Cua L.>oL.) u j M charstr h % gei3 N M he.4. f2u. 12 b.~~
~~When irradiated fuel is being handled in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.~~
RIVER BEND - UNIT 1 3/4 6-61
-l l
l I
CONTA!NMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) l h [.
At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire or chemical release in any ventilation zone communi-cating with the subsystem by:
1.
Verifying that the subsystem satisfies the in place penetration and bypass leakage testing acceptance criteria of less than 0.05%
and uses the test procedure guidance in Regulatory Positions C.5.a. C.5.c and C.S.d of Regulatory Guide 1.52, Revision 2, March 1978, and the system flow rate is 10,000 cfm 2 10%.
2.
Verifying within 31 days after removal that a laboratory analysis of a representative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52. Revision 2 March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 0.175%; and 3.
Verifying a subsystem flow rate of 10,000 cfm 2 10% during system operation when tested in accordance with ANSI N510-1975.
1 p'.
After every 720 hours0.00833 days 0.2 hours 0.00119 weeks 2.7396e-4 months of charcoal adsorber operation by verifying F1 /
within 31 days af ter removal that a laboratory analysis of a repre-sentative carbon sample obtained in accordance with Regulatory Position C.6.b of Regulatory Guide 1.52, Revision 2, March 1978, meets the laboratory testing criteria of Regulatory Position C.6.a of Regulatory Guide 1.52, Revision 2, March 1978, for a methyl iodide penetration of less than 0.175%.
f At least once per 18 months by:
1.
Performing a system functional test which includes simulated automatic actuation of the system throughout its emergency operating sequence for the:
a)
LOCA,'and E
b)
FH "dHnc ecident.
MM 4N J
~
n*W LA. ef-#
l 2.
Verifying that the pressure drop across the combined HEPA filters and charcoal adsorber banks is less than 8 inches Water Gauge while operating the filter train at a flow rate of 10,000 cfm 1 10%.
3.
Verifying that the subsystem starts and isolation dampers actuate to isolate the normal flow path and to divert flow through the charcoal filters on each of the following test signals:
RIVER BEND - UNIT 1 3/4 6-62
' CONTAINMENT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) a.
Manual initiation from the control room, and b.
Simulated automatic imitation signal.
4.
Verifying that the filter cooling bypass dampers can be manually opened and the fan can be manually started.
1 99 5.
Verifying that the heaters dissipate 32 =?tF9 kw when tested in 3
accordance with ANSI N510-1975.
r, ei After each complete or partial replacement of a HEPA filter bank by 5
verifying that the HEPA filter bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1975 while operating the system at a flow rate of 10,000 cfm i 10%.
e f.
After each complete or partial replacement of a charcoal adsorber bank by verifying that the charcoal adsorber bank satisfies the inplace penetration and bypass leakage testing acceptance criteria of less than 0.05% in accordance with ANSI N510-1975 for'a halo-genated hydrocarbon refrigerant test gas while operating the system at a flow rate of 10,000 cfm i 10%.
RIVER BEND - UNIT 1 3/4 6-63 1
CONTAINMENT SYSTEMS 3 /4. 6. 6 ATMOSPHERE CONTROL PRIMARY CONTAINMENT HYDROGEN RECOMBINER SYSTEMS LIMITING CONDITION FOR OPERATION 3.6.6.1 Two independent primary containment hydrogen recombiner systems shall be OPERABLE.
APPLICABILITY: OPERATIONAL CONDITIONS I and 2.
ACTION:
With one primary containment hydrogen recombiner system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HDT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
SURVEILLANCE REQUIREMENTS 4.6.6.1 Each primary containment hydrogen recombiner system shall be demon-strated OPERABLE:
At least once per 6 months by verifying during g recombiner system a.
functionaltestthattheminimum/heatersheath/ temp /90/ minutes.
erature increasestogreaterthanorequalto[700/*Fwithin b.
At least once per 18 months by.
1.
Performing a CHANNEL CALIBRATION of all control room recombiner indication instrumentation and control circuits.
s_
CF ).
Verifying the integrity of all heater electrical circuits by performing a resistance to ground test within 30 minutes follow-ing the above required functional test. The resistance to ground for any heater phase shall be greater than or equal to [10,000/
chms.
i[)l.
Verifying durin
/heatersheath/garecombinersystemfunctionaltestthatthe to 1215'F within /5/perature increases to greater than or equal tem hours.
L4 W'
Verifying through a visual examination that there is no evidence of abnormal conditions within the recombiner enclosure; i.e, materials,etc.lstructuralconnections,depositsofforeign loose wiring or RIVER BEND - UNIT 1 3/4 6-64
CONTAINMENT SYSTEMS PRIMARY CONTAINMENT /ORYWELL HYDROGEN MIXING SYSTEM LIMITING CONDITION FOR OPERATION
~
3.6.6.2 Two independent primary containment /drywell hydrogen mixing systems
~~shall be OPERABLE.~~
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.
ACTION:
With one primary containment /drywell hydrogen mixing system inoperable, restore the inoperable system to OPERABLE status within 30 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
SURVEILLANCE REQUIREMENTS 4.6.6.2 Each primary containment /drywell hydrogen mixing syst'em tha11 be demonstrated OPERABLE:
1%eena Let k (No SHrorwu il nei 9efsemed sa %L brnLtb&st,
a.
': ::::: : :: ;;=v52 oays cy:
1.
Starting the system from the control room, and 2.
Verifying that the system operates for at least 15 minutes.
b.
At least once per 18 months by verifying a system flow rate of at least StT'cfm.
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i 4
e RIVER BEND - UNIT 1 3/4 6-65
CONTAINMENT SYSTEMS CONTAINMENT AND DRYVELL HYDROGEN IGNITION SYSTEM LIMITIN3 CONDTION FOR OPERATION
~~3. 6.7. 2 The containment and drywell hydrogen ignition system consisting of the following:~~
At least two igniter assemblies in each enclosed area specified in a.
Table 3.6.7.2-2, eL_ EP J3 b.
. All igniter assemblias-adjacent to any inoperable igniter assembly in eachapen-arenspecified-11n9able--3.-4.-7.2-2. and..,
~
Cs PETAYY" c.
Two independent con neent and drywell hydrogen. ignition
~~subsystems; ?~~
(as listad in Table 3.6.7.2-with_nc mora -na' gni msembMe7seopera.b_ Fj g.
fgg J
' hall %eyPERABLE'.euqr h'/
APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2 c
ACTION:
With less than two igniter assemblies OPERABLE in any enclosed area a.
specified in Table 3.6.7.2-2, restore at least two igniter assemblies to OPERABLE status within 7. days or be in at least HOT SHUTDOWN within -
the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
2.
With any adjacent igniter assemblies within an open area as specified in Table 3.6.7.2-2 inoperable, restore the igniter assemblies in that open area so that all igniter assemblies adjacent to an inoperable igniter assembly are OPERABLE within 7 days or be in at least NOT SHLTTDOWN within the next 22 hours2.546296e-4 days 0.00611 hours 3.637566e-5 weeks 8.371e-6 months .
With one containment and drywell hydrogen ignition subsystem inoperable, c.
restore the inoperable subsystem to OPERABLE status within 7 days or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .
SURVEILLANCE REQUIREMENTS 4.6.7.2 The containment and drywell hdrogen ignition system shall be demonstrated OPERABLE:
At least once per 92 days by energizing the supply breakers and:
.a.
l'.
Verifying a visible glow from the glow plug tip of each normally accessible igniter assembly specified in Table 3.6.7.2-2, 1
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,COhiAINMENT SYSTEM _5 CONTAINMEhT AND DRYVELL HYDROGEN IGNITION SYSTEM
~
i SURVEILLANCE REOUIREMENTS (Continued).
2.
Verifying that each circuit of each containment and drywell hydrogen ignition subsystem is conducting sufficient current to energize the minimum ' required number of igniter assemblies specified in Table 4.6.7.2-1.
b.
At every COLD SHUTDOWN, but no more frequently than once per 92 days, by energizing the supply breakers and verifying a visible glow from the glow plug tip of each normally inaccessible igniter assembly specified in Table 3.6.7.2-2.
c.
At least once per 18 months by:
ihgthe.$an nTe s11-each.q] W Q Q g.n}lslia N n.
M 2.
Energizing each glow plug and ifying a surface temperature of at least 1700*F.
h
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4,
Q TABLE 3.6.6.3-1 HYOROGEN IGNITERS AND LOCATIONS DIST. FROM CENTERLINE IGNITER DIV./ CIRCUIT ELEVATION A2IMUTH OF REACTOR NORMALLY ACCESSIBLE Open Areas Containment NORMALLY INACCESSIBLE Open Areas Drywell Enclosed Areas
/'
MJIL Steam Tunnel RWCU Backward Room RW V Heat Exchanger Room Filter /Demineralizer Room i
RWOU Pur.p Area RWOU Sar.ple Area (Listing of Igniters to be provided by GSU) 4 e
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RIVER BEND - UNIT 1 3/4 6-68 p.
I 3.4.6 CONTAINMENT SYSTEMS BASES 3/4.6.1 CONTAINMENT
.rd -W. 4. /. A.
3/4.6.1.1 A PRIMARY CONTAINMENT INTEGRITY
,m o,so rse a n a " "'gg)
PRIMAR [ QCONTAINMEhT INTEGRITYAensures that the release of radioact materials from theAcontainment atmosphere will be restricted to those leakage paths and associated leak rates assumed in the accident analyses. This restric-tion, in conjunction with the leakage rate limitation, will limit the site boundary radiation doses to within the limits of 10 CFR Part 100 during accident conditions.
3 3/4.6.1.f PRIMARY CONTAINMENT LEAKAGE 7 f*
pm.by.
pr %
The limitations onocontainment leakage rates ensure that the totalacontain-ment leakage volume will not exceed he value assumed in the accident analyses at the peak accident pressure of psig, Pa.
As an added conser,vatism, the measured overall integrated leakage rate is further limited to less than or equal to 0.75 La during performance of the periodic tests to account for possible degradation of thep/^'Q ontainment leakage barriers between leakage tests.
Operating experience with the main steam line isolation valvas has indicated that degradation has occasionally occurred in the leak tightness of the valves; therefore the special requirement for testing these valves.
The surveillance testing for measuring leakage rates is consistent with the requirements of Appendix J to 10 CFR 50 with the exception of exemption (s) granted for main steam isolation valve leak testing.
3/4.6.1.
PRIMARY CONTAINMENT AIR LOCKS The limitations on closure and leak rate for the primary containment air lect s are required to meet the restrictions on PRIMARY CONTAINMENT INTEGRITY-MMN and the primary containment leakage rate given in Specifications 3.6.1.1 and 3.6.1.A 3,The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation. Only one closed door in each air lock is required tomaintaintheintegrityofthepontainment.
g RIVER BEND - UNIT I B 3/4 6-1
i
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CONTAINMENT SYSTEMS BASES S
3/4.6.1 / MSIV POSITIVE LEAKAGE CONTROL SYSTEM Calculated doses resulting from the maximum leakage allowance for the isolation valves in the postulated LOCA situations would be a small fraction of the 10 CFR 100 guidelines. Operating experience has indicated that degra-dation has occasionally occurred in the leak tightness of the MSIV's such that the specified leakage control system will prevent untreated leak, age from the MSIV's when isolation of the primary system and containment is required.
3/5.6.1.
PRIMARY CONTAINMENT STRUCTURAL INTEGRITY This limitation eraures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the unit. Structural integrity is required to ensure that the containment will withstand the maximum pressu're of psig in the event of a LOCA. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
p,4;;
3/4.6.1.7PRIMARYCONTAINMENTINTERNALPRESSURE u
f The limitations on primary containment to secondary c tainment differential pressure ensure that the containment peak pressure of psig does not exceed
[
the design pressure of 15.0 psig during LOCA conditions or that the external pressure differential does not exceed the design maximum external pressure differen'.ial of + 0.6 psid or the differential at which water would overflow the # e _.all into the drywell of 0.58 psid. The limit of - 0.1 to + 1.5 psid K
/*) Nr initiale containment to secondary containment pressure will limit the containmant pressure tog-$t pJs / which is less than the dasign pressure and is consist 6
~~with the Aafetyfanalysis, 7~~
~~7'S 8~~
~~N p' 3/4.6.1./ PRIMARY CONTAINMENT AVERAGE AIR TEMPERATURE~~
['
The limitation on primary containment average air temperature ensures that the containment peak air temperature does not exceed the design temperature of 185*F during LOCA conditions and is consistent with the safety analysis.
i JtIVER BEND - UNIT 1,.
8 3/4 6-2
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CONTAINMENT SYSTEMS BASES 3/4.6.1.
DRfWELL AND PRIHARY CONTAINHENT PURGE SYSTEM M
Fw, s
The.trwr inchf f :".J)4 containment purge supply and exhaust isolation valves are required to be sealed closed during plant operation since these valves have not been demonstrated capabla of closing during a (LOCA or
?
steam line break accident). Maintaining these valves sealed closed during plant operatinns ensures that excessive quantities of radioactive materials will not be released via the containment purge system. To provide assurance s
that the (20) inch valves cannot be inadvertently opentd. they are sealed we MM5 a
closed in accordance with Standard Review Plan 6.2.4,twhich includear mechanical j
f devices to seal or lock the valve closed or prevent power from being supplied to the valve operator.
~~reg, The use of the 'f. :!'..~}jcontainment purgg lines is restricted to the (6) inch purge supply and exhaust isolation valves llS51,'/unlike the 42-inch x~~
valves, the (6) inch valves will close during a LOCA or steam line break f
accident and therefore the site boundary dose guidelines of 10 CFR Part 100 2C f
j would not be exceeded in the event of an accident during purging operations.
The design of the (6) inch purge supply and exhaust isolation valves meets the requirements of Branch Technical Position CSB 6-4, " Containment Purging During Normal Plant Operations."
Leakage integrity tests supply and exhaust isolation,with a maximum allowable leakage rate for purge
[s valvesjwill provide early indication of resilient
>C material seal degradation and will allow the opportunity for repair before gross leakage failure develops. The 0.60 La leakage limit shall not be exceeded when the leakage ratesfdetermined by the leakage integrity tests of these valves
/C are added to the previously determined total for all valves and penetrations y
subject to Type B and C tests.
/0 3/4.6.1.g PENETRATION VALVE LEAKAGE CONTROL SYSTEM The OPERABILITY of the penetration valve leakage control system is required to meet the restrictions on overall containment leak rate assumed in the accident analyses.
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..wn 3/4.6.2 ORYWELL 3/4.6.2.1 DRYWELL INTEGRITY Drywell integrity ensures that the steam released for the full spectrum of drywell pioe breaks is condensed inside the primary containment either by the suppression pool or by the primary containment ventilation system unit coolers. By utilizing the suppression pool as a heat sink, energy released to the containment is minimized and the severity of the transient is reduced.
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RIVER BEND - UNIT 1,,
8 3/4 6-3 y.e
+
i CONTAINMENT SYSTEMS BASES i
3/4.6.2.2 DRWELL BYPASS LEAKAGE The limitation on drywell bypass leakage rate is based on having at least j
one containment ventilation system unit cooler OPERABLE.
It ensures that the l
maximum leakage which could bypass the suppression pool during an accident would not result in the ontainment exceeding its design pressure of 15.0 psig.
The integrated drywell leakage value is limited to 10% of the design drywell leakage rate.
ANp The limiting case accident is a very small reactor coolant system break which will not automatically result in a reactor depressurization.
The long term differential pressure created between the drywell and tontainment will result in a significant pressure buildup in the containment due to this bypass leakage.
j,.4 3/4.6.2.3 DRWELL AIR LOCKS The limitations on closure for the drywell air locks are required to meet the restrictions on DRWELL INTEGRITY and the drywell leakage rate given in Specifications 3.6.2.1 and 3.6.2.2.
The specification makes allowances for the fact that there may be long periods of time when the air locks will be in a closed and secured position during reactor operation. Only one closed door
\\
in the air lock is required to maintain the integrity of the drywell.
3/4.6.2.4 DRWELL STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the drywell will be maintained comparable to the original design specification for the life of the unit. A visual inspection in conjunction with Type A leakage tests is sufficient to demonstrate this capability.
3/4.6.2.5 DRWELL INTERNAL PRESSURE
/%R fM The limitations on drywell-to[ontainment dif ferential that the drywell peak pressure ofA&e-4 psid does not exceed (pressure ensure the design pressure of 25.0 psid and that the containment peak pressure of 4s46psig does not exceed 1
thedesignpressureof1E.0psigduringLO[ conditions. The maximum external drywell pressure differential is limited t a
psid, well b low the 0.58 psid at which suppression p o water will*be forced over the wall and into f
the drywell. The limit of.
psid for initial positive drywell to containment pressure will limit the drywell pressure to psid which is less than the design pressure and is consistent with the safety analysis.
/ 7, A 3/4.6.2.6 DRWELL AVERAGE AIR TEMPERATURE The limitation on drywell average air temperature ensures that peak drywell temperature does not exceed the design temperature of 330 'F during LOCA condi-tions and is consistent with the safety analysis.
i
[ se d Co. Q RIVER BEND - UNIT 1 8 3/4 6-4
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INSERT A 3 /4. 6.2.7 DRYhTN VEh"r AND PURGE The 24 inch drywell purge supply and exhaust isolation valves are required to be closed during plant operationf M these valves have f not been demonstrated capable of closing during a LOCA or steam line break accident.
The use of the dry g l,1,,p,uy,ge line is restricted to 90 t-T hours per 365 days and, while'A'open dug brief periods for 6 pressure control, e
~~.rze a licensed operator t the valve controls. 3~~
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river BEND-//#/77
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CONTAINMENT SYSTEMS BASES 3/4.6.3 DEPRESSURI2ATION SYSTEMS yn 9 The specifications of this section ensure that the drywell andhcontainment pressure {will not exceed the design pressurejof 25 psig and 15 psig, respectively, K during primary system blowdown from full operating pressure.
7""*c'>
The suppression pool water volume must abscrb the associate decay and structural sensible heat released during a reactor blowdown f rom 10erpsWg Using conservative parameter inputs, the maximum calculated containment jn pressure during and following a design basis accident is below the g 5ntainment design pressure of 15 psig. Similarly the drywell pressure remains below the design pressure of 25 psia. The maximum and minimum water volumes for the J'll,030 ~ suppression pool aretTM;s@ cubic feet and @~ cubic feet,4e:.n.-tr.
f.[
These values include the water volumesof the ontainment pool, horizontal vents, and weir annulus. Testing in 'the Mark III Pressure Suppression Test Facility and analysis hue aso.tced that the suppression pool temperature will notriseabove185'FfortheUfullrangeof reak, sizes.
[
/~~y Should it be necessary to make the suppression pool inoperable, this shall only be done as specified in Specification 3.5.3.
f-*9 Experimental data indicates that effective steam condensation without excessive load on th containment pool walls will occur with a quencher device and pool temperature below 200'F during relief valve operation. Specifications have been placed on the envelope of reactor operating conditions to assure the bulk pool temperature does not rise above 185'F in compliance with~ the contain-ment structural design criteria.
In addition to the limits on temperature of the suppression pool water, operating procedures define the action to be taken in the event a safety-relief valve inadvertently opens or sticks open. As a minimum this action shall include:
(1) use of all available means to close the valve, (2) initiate suppression pool water cooling, (3) initiate reactor shutdownpand (4)y if other
[
p safety-relief valves are used to depressurize the reactor, their discharge shall be separated from that of the stuck-open safety relief valve to assure mixing and uniformity of energy insertion to the pool.
pnmp TheAcontainment ventilation system consists of three 100% capacity unit coolers, two of which are safety related. Each of these two unit coolers provides independent 100% heat removal cahacity in case of steam bypass of the sukessionpool. The turbulence caused by the* 4 st= aids in mixing the K
conlainmentairvolumetomaintainahomogeneoukxtureforH control.
2 mW a,s._,
duppression pool cooling funcWa is a mode of the RHR system and
/
functions as part of the containment heat removal system. The purpose of the system is to ensure containment integrity following a LOCA by preventing exces-sive containment pressures and temperatures. The suppression pool cooling mode is designed to limit the long term bulk temperature of the pool to 185'F RIVER BEND - UNIT 1 B 3/4 6-5
e CONTAINMENT SYSTEMS
/
t BASES DEPRESSURIZATION SYSTEMS (Continued) considering all of the post-LOCA energy additions. The suppression pool cooling trains, being an integral part of the RHR system, are redundant, safety-related cc,---, systems that are initiated following the recovery of the reactor vessel
/(
water level by ECCS flows from the RHR system. Heat rejection to the standby service water is accomplished in the RHR heat exchangers.
3/4.6.4 PRIMARY CONTAINMENT AND DRYWELL ISOLATION VALVES pna.ryo-The OPERABILITY of theAcontFinment isolation valves ensures that the
,, containment atmosphere will be isolated from the outside environnent in the
/C y
g y j,, _ event of a release of radioactive material to thefcontainment atmospnere or r
F v
pressurization of theAcontainmentjand is consistent with the requirements of s_
2C GDC 54 through 57 of Appendix A to 10 CFR 50. Afontainment and drywell
/ *7 5 isolation within the time limits specified for those isolation valves designed X
y to close automatically', ensures that the release of radioactive material to the X
environment will be consistent with the assumptions used in the analyses for a LOCA.
The operability of the drywell isolation valves ensures that the drywell l
atmosphere will be directed to the suppression pool for the full spectrum of pipe breaks inside the drywell and is consistent with the requirements of GDC 54 through 57 of Appendix A to 10 CFR 50. Since the allowable value of drywell leakage is so large, individual drywell penetration leakag[e js not l
l seasured. By checking valve operability on any penetration wh4sA, ould
/(
contribute a large fraction of the design leakage, the total leakage is maintained at less than the design value.
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RIVER BEND - UNIT I B 3/4 6-6 e*
a F9e CONTAINMENT SYSTEMS i
BASES ATMDSPHERE CONTROL (Continued)
The operability of the containment and drywell hydrogen igniters ensures that hydrogen combustiog can be accomplished in a controlled manner following a degraded core event pYoduc k hydrogen concentrations in excess of LOCA
/
^
conditions.
e 9
I.
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RIVER BEND - UNIT 1 8 3/4 6-8
-

ML20132C991

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