ML20202H261

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Revised TS Pages Re Change 190,w/typos Corrected
ML20202H261
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 02/06/1998
From:
VERMONT YANKEE NUCLEAR POWER CORP.
To:
Shared Package
ML20202H239 List:
References
NUDOCS 9802200339
Download: ML20202H261 (17)
v • d • e


Text

_ _ _ _ _ _ _ - _ _ _ - _ - - - _ _ _ _ _ _ -

VYllPS 3.7 LIMITIlh CollDITIOt1S FOR 4.7 SURVEILLA!JCE REQUIRD4E!1TS OPERATIOff

e. Minimum Water Volume -

68,000 cubic feet de, hary C wlau.wed l

( 2.

y,*W."*'**

90,000 cubic teet Primary containment integrity chall be 2.

t 4a4 Rda Tosdia4 Pr w

(,PCL R7Y),

The primary containment integrity shall be maintained at all times demonstrated as required l when the reactor is p di J t 10 FR

! critical or when the t . he ri ry reactor water n i nt tal me temperature is above t c tai en 212*F and fuel is in the cc tan r ir men reactor vessel except while performing low a

pe fo h ix.

t t /

power physics tests at atmospheric pressure at nepatjens n power levels not to - setra list exceed 5 Hw(t). Able .7 s 1 e ak est d

3. Wh ever rima 4 psi (P .

ntal ent re red the tal ima b. Ty C es al 11 co ai t- 1 age . ate - ppf o ed e iali te eed -

is lati v ve 0.8 igh ere t pe 1 to in d .( L at a ress e t ab 4. .2 .

. 44 sig ' ) .). / 3.

Vior o v ol in th

4. Whenever primary / int it o a p ma ste e

_ containment is required, ou id t

,.e tt eaka fro any 9(e nt nm t, hi is co oc d a va e bg N

lati ot e eed val pere sha Y of

[ st i Tab 4 .2b g,

th imt all able i h s ati va es ak ra (L ) at p nd g. eo ni o accid t pre ure ,) / I"h ha for h e d.

e e

es he leakage from any f

%g one main steam line en gc no be m isolation valve shall is ate fr th o

not exceed 15.5 scf/hr nta en by 4 '

at 44 psig (P ) . . sol io vai es ic me t ac pt ce

~

ite a Ap nd J

$$ (10 RP t ), bl k F a.Q.

fa nge ha be led n e p f , v- ( s' . w. e [s., syi # w ika,6 at ope ing it cess /00td fe 64 a.% S dsssies 4. e ak e f om yo of f(4, powary t* %Ialw Wa h b la f e be e s Mok s*s e $s it. bhot a ((< c k-tk o

rat exceed /5t at LtJ6. /

The leakage from any one faW4 f' g 8 e W [le av jS t= g b 'y M IT # g . main steam line A h l < A K {. 0 % <. C bost.e( c, s,k de ellivdtd  ; y g , 7 as,-ah va ,a.,,.e ~ a-  ::d ;e :i" Hih P

conducted to insure E4 h< pr $ [tN ka n )(, .

compliance.

Amendment tio. -%- 147 o o

_ _ _ _ _ _ _ _ _ _ _ _ _ .._ _ _ _ ._ . _ _ . . _ __m..m_.__ . _ _ _ _ _ _ . . _ _ . _ _ _ . . _ _ _

4 WNPS 3.7 LfwtTING CONDITIONS FOR 4.7 SURVEIL?ANCE REQUIREMENTS l-Op?y.ATION

) 5. Core 6 pray and LPCI pump 5. The es .<e spray and LPCI lower compartment door lower compartment l openings shall be closed openings shall be at all times except checked closed daily.

during passage or when

reactor eaolant

, temperature is less than

! 212*F.

D. Primary containment D. Primary containment Isolation Valves Isolation Valves

1. During reactor power 1. surveillance of the co wia6*mts(operating conditions alt primary centainment j isolation valvesIFLiett, unrT4bL6 /4 M 41 and all isolation velves should be performed as follows:

! instrument ~ line flow check valves shall be a. The operable

! operable except as isolation valves specified in that are power Specification 3.7.D.2. operated and automatically initiated shall be tested for automatic initiation and the closure times specified in Table 4.7.2 at least once per operating cycle.

  • b. Operability testing of the primary containment isolation valves shall be performed in accordance with Specification 4.6 E.
c. At least once per quarter, with the reactor power less than 75 percent of rated, trip all main steam isolation valves (one at a time) and verify closure time.
d. At least twice per week, the main

. steam line isolation valves shall be exercised by partial closure and subsequent reopening.

Amendment No. H. M. H4. H4N 156

VY!JPS -

3.7 LIMITING CO!JDITIO!JS FOR 4.7 SURVEILLANCE REQUIREME!JTS OPEPATIOt1 d .( w SMles e m e w !

p. . 2. In the event any unk,n ad 2. Whenev a la.,lation__

-9 ' isolation valve --

valve r W/nA A M i s iswevi tief i / % hfe/d MM inoperable, the position becomes inoperable, of at least one other reactor power cperation valve in each line may continue provided at having an inoperable least one valve in each valve shell be logged li.ne havin an daily.

inoperable valve is in the mode co responding to the isola ed condition.

  • " M '
3. If Specifications 3.7.D.1 and 3.7.D 2 Mc cannot be mot, an orderly shutdown shall .. ( /4 h w a be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

157

i .

VYNPS TA 4.7.1 [

/, /[

NETRAT S AND S S SUBJ TO TY PE IVh i c'! ItJG P etrat n

/ N er of N I ntificati Pe tratione X-7A, D in Ste Line A, 4, X- , B Feetw er Line A B 2

-11 HPC Steam Li 1 X-12 e utdown Co ing Sur y 1 X-1 , B RHR Retu- to Rea or 2 14 Suppl to Reac r Water leanup X-16A, Cor Spray Reactor 2

X-1 ipment ccess H ch 1 X- Drywel Head F1 ge 1

-4 D 11 Head ccess Hat X-6 Remova Hatch 1 SLH ,- H - Shear L Access C etu 8

- 2 0 7.\ . H J, K Vacu Relief A ess Cov s T Drains 2

& M 3 2. /

X- g>[, - B rus Manw s l

sz, ,,y e coto6.s u 3 nu m e.

158

VYllPS TABLE 4_7.2h PRIMARY COf1 TAIT.HEffT ISOLATIOf2 VALVES MMdES/IUdCTM TM

- 1 1 1 s

[LEMdCEJrkST[

s / 1 -

13 umber of Power ,

Operated Valves Maximum Action on

. Operating flormal Initiating I8 **" Inboard Outboard Time (sec) Position Sional Group (1) valve Identification 1 Main Steam Line Isolation (2-80A, D& 4 4 5 (13ote 2) Open GC 2-86A, D)

Main Steam Line Drain (2-74, 2-77) 1 1 35 Closed SC l 1 1 Recirculation Loop Sample Line (2-39, 2-40) 1 1 5 Closed SC 2 RHR Discharge to Radwaste (10-57, 10-66) 2 25 Closed hC Drywell Floor Drain (20-82, 20-83) 2 20 Open GC 2

Drywell Equipment Drain (20-94, 20-95) 2 20 Open GC 2

Drywell Air Purge Inlet (16-19-9) 1 10 Closed S,'

3 1 10 Chul gc, 3 Drywell Air Purge Inlet (16-19-8) j Drywell Purge & Vent' Outlet (16-19-7A) 1 10 Closed

  • SC 3

1 10 Closed SC 3 Drywell Purge & Vent Outlet Bypass (16-19-6A)

Drywell & Suppression Chamber Main Exhaust 1 10 Closed

  • SC 3

(16-19-7)

Suppression Chamber Purge Supply (16-19-10) 1 10 closed SC 3

1 10 Closed SC 3 Suppression Chamber Purge & Vent Outlet (16-19-7B) i 10 'Open GC 3 Suppression Chamber Purge & Vent Outlet Bypass (16-19-6B)

  • Valves 16-19-7 and 16-19-7A shall have stops installed to limit valve opening to 50' or less.

159 Amendment flo . %, 91, M

--my

A-,

l VYNPS i l l

TABLE 4.7.

(Cont'd) '

PRIMARY CONTAfffMEth iSOLATIOff VALVES ]

VfLVJdi/ SUdECTMo s <

TVICs LEMAG/TESd / <

/ /

12 umber of Power operated Valves Maximum Action on Operating Normal Initiating r Valve Identification Inboard outboard Time (sec) Position Sional 3 Exhaust to Standby Gas Treatment System 1 10 Open GC-(16-19-6) 3 containment Purge Supply (16-19-23) 1 10 @ ele / S C.

3 cntainm nt 16-20-22 Makeup 'if-20-2S, 2

hI NA Closed SC

@ 5"P f f.$ -

5 Reactor Cleanup System (12-15, 12-18) 1 1 25 open GC 6 HPCI (23-15, 23-16) 1 1 55 Open GC 6 RCIC (13-15, 13-16) 1 1 20 Open GC Primary / Secondary Vacuum Relief (16-19-11A, . NA Closed SC 16-19-11B)

Primary / Secondary Vacuum Relief (16-19-12A, 2 NA Closed Process

)

i 16-19-12B)

J, s

l : 3 containment Air Sampling (VG 23, VG 26, 4 5 Open CC 109-76ALB)

J e - s-C.k d Akuq LP t W 'A ~

3 16- 20-DM Amendment No. Se, frh M , 9+, M 160

- ~ '- ' ' -" ' " ' I

' ' ' " ' ' ' - - ' ' ' ' ' " - ' ' ' ' ' ' ' " ' ' ' ' ' ' ' ' - - ~ ' - " ' " ' ' ' ' - - - ' " ' " ' ' ' ' ' ' ' ' ' ' ' ' ' ' " ~ '

-=-,%'- ' - ~ ' - ' ~'-

1-

- ' - - - ' ~ ' -

VYNPS- -

&ABLE4.7.2h

.,o y PRIMARY CONTAINMErrr ISOLATION VALVES

~

[AdESJIOT f I /

SJdkTEdTO

/ / /

MPE /

[LEMbGEMSd

/ / /

Number of Power Operated Valves Maximum Action on Operating Normal Initiating ro Valve Identification Inboard Outboard Time (sec) Position Sicnal 2 RHR Return to Suppression Pool (10-39A, B) 2 70 - Closed SC 2 RHR Return to Suppression Pool (10-34A, B) 2 120 Closed SC 2 RHR Drywell spray (10-26A, B& 10-31A, B) 4 70 Closed SC 2 RHR Suppression Chamber Spray (10-38A, B) 2 45 Closed SC 3 Containment Air Compressor Suction (72-38A, 2 20 Open GC B) 4 RHR Shutdown C wling Supply (10-18, 10-17) 1 1 28 Closed SC c\ and Liquid Control Check Valves (11-16, 1 1 NA Closed Proc.

  • Hydrogen Monitoring (109-75 A, 1-4; 10 NA NA rIA 109-75 B-D, 1-2)

Sampling. Valves - Inlet

  • Hydrogen Monitoring (VG-24, 25, 33, 34) 4 fM NA NA
  • These valves are remote manual sampling valves which do not receive an isolation signal. Only one valve in each line is required to be operable.

Amendment !!o . 58, GF, MG, -itt- 161

VYNPS BASES: 4.7 (Cont'd)

The maximum allowable test leak rate at the peak accident pressure of 44 psig (ba) is 0.80 weight % per day. The maximum allowable test leak rate at the retest pressure of 24 psig (Lt) has been conservatively determired to be 0.59 weight percent per day. This value will be verified to be conservative by actual primary containment leak rate measurements at both 44 psig and'24 psig upon completion of the containment structure.

T al w as[ar n f r po sib 1 le age ete lor ion 'etw nt t nt al th ma mum 11ow le per ion 1 1 kr e ( m), h h wi be et or in nt no al est che le, a0 5L.

As most loakage and deterioration of integrity is expected to occur through penetrations, especially those with resilient seals, a periodic leak rate test program of such penetration is conducted at the peak ac ident pressure of 44 psig to insure not only that the leakage remaint acceptably low but also that the sealir.g materials can withstand the accident pressure. .

g The eak ate esting rogram is based onlA96 ad de[in /a for 4 b*9"9bu"*md development of leak rate testing and surveillance schedules fo APPax/DSX$

reactor containment vessels.

Surveillance of the suppression Chamber-Reactor Building vacuum breakers consists of operability checks and leakage tests (conducted as part of the containment leak-tightness tests). These vacuum breakers are normally in the closed position and open only during tests or an accident condition. Operability testing is performed in conjunction with Specification 4.6.E. Inspections and calibrations are performed during the refueling outages; this f requency being based on equipment quality, experience, and engineering judgment.

The ten (10) drywell-suppression vacuum relief valves are designed to open to the full open position (the position that curtain area is equivalent to valve bore) with a force equivalent to a 0.5 psi differential acting on the suppression chamber face of the valve disk. This opening specification assures that the design limit of 2.0 paid between the drywell and external environment is not exceeded. Once each refueling outage each valve is tested to assure that it will open fully in response to a force less than that specified. Also it is inspected to assure that it closes freely and operates properly.

The containment design has been examined to establish the allowab1q bypass area between the drywell and suppression chamber as 0.12 ft'.

This is equivalent to one vacuum breaker open by three-eighths of an inch (3/8') as measured at all points around the circumference of the disk or three-fourths of an inch (3/4') as measured at the bottom of the disk when the top of the disk is on the seat. Since these valves open in a manner that is purely neither mode, a conservative allowance of one-half inch (1/2*) has been selected as the maximum permissible valve opening. Assuming that permissible valve opening could be evenly divided among all ten vacuum breakers at once, valve open position assumed to indication for an individual valve must be activated less than fifty-thousandths of an inch (0.050') at all points along the seal surface of the disk. Valve closure within this limit may be determined by light indication from two independent position detection and indication systems. Either system provides a control room alarm for a nonseated valve.

Amendment No. 60,-Fe&~ 168

4 VYNPS

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents and/or quantity of solid waste that differ from those previously predicted in the license application and amendments thereto;
5. An evaluation of the change, which shows the expected maximum exposures to member (s) of the public at the site boundary and to the general population that differ'from those previously estimated in the license application and amendments thereto;
6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous offluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;
7. An estimate of the exposure to plant operating personnel as a result of the changer and
8. Documentation of the fact that the change was reviewed and found acceptable by PORC, B. Shall become effective upon review and acceptance by PORC and approval by the Plant Manager.

>=

^

^%~ ,

Q \

6.15 Primary Containment Leak Pate Testina Prortram A program shall be established to ireplement the leak rate testing of the primary containment as required.by 10CFR50.54(o) and 10CFR50, Appendix J. option B as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, entitled

  • Performance Based Containment Leak-Test Program
  • dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 44 psig.

The rnaximum allowable primary containment leak rate, La, at Pa, shall be 0.8% of primary containment air weight per day.

Leak rate acceptance criteria are

1. Primary containment leak rate acceptance criterion i 1.0 La.
2. The as-left primary containment integrated leak rate test (Type A test) acceptance criterion is 1 0. 7 5 La .
3. The combined local leak rate test (Type B and C tests) acceptance criterion-is 1 0.60 La, calculated on a maximum pathway basis, prior to entering a mode of operation where containment integrity is required,
4. The combined local leak rate test (Type B and C tests) acceptance criterion is 1 0.60 La. calculated on a minimum pathway basis, at all times when primary containment integrity la required.
5. Airlock overall leak rate acceptance criterion is 1 0.10 La when tested at 3,Pa.

The provision of the Definition (1.0.Y) for Surveillance Frequency does not apply to the test frequencies specified in the Primary Containment Leak Rate Testing Program.

Amendment No. 64, HP 29'

. - . _ . . . . . - . - . . . _~ . - _ _ _ _ _ . . . . - . _ _ - . . _ . ~ . . . . - ~ . . . . . . ~ . . - . . . . . . . . . - . .

1 i .

VYNPS 3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS 3 .. OPERATION

e. Minimum Water Volume -

68,000 cubic feet

f. Maximum Water 4

Volume -

70,000 cubic feet

2. Primary containment 2. The primary containment
integrity shall be integrity shall be i

maintained at all times demonstrated as required when the reactor is by the Primary

, critical or when the Containment Leak Rate 3

reactor water Testing Program temperature is above (PCLRTP).

2120F and fuel is in the reactor vessel except while performing low power physics tests at atmospheric pressure at power levels not to exceed 5 Mw(t).

3. If a portion of a system 3, (Blank) l that.is considered to be an extension of primary i

containment is to be

opened, isolate the affected penetration 1

flow path by use of at i least one closed and j deactivated automatic valve, closed manual valve or blind flange.

-4. Whenever primary containment is required, 4. The leakage from any one l l l the leakage from any one main steam line main steam line isolation valve shall isolation valve shall not exceed 11.5 scf/hr not exceed 15.5 sef/hr at 24 psig (Pt). Repair at 44 psig (P,). and retest shall be conducted to insure compliance, j

)

i i

Amendment No. 50, 147 4

p

VYNPS d

3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION

5. Core spray and LPCI pump 5. The core spray and LPCI lower compartment door lower compartment openings shall be closed openings shall be at all times except checked closed daily.

during passage or when reactor coolant temperature is less than 2120F, D. primary Containment D. Primary Containment Isolation valves Isolation valves

1. During reactor power 1. Surveillance of the operating conditions all primary containment

] containment isolation isolation valves should valves and all be performed as follows:

instrument line flow check valves shall be a. The operable

, operable except as isolation valves i

specified in that are power Specification 3.7.D.2. operated and automatically initiated shall be tested for automatic initiation and the closure times specified in Table 4.7.2 at

least once per t operating cycle,
b. Operability testing of the primary containment isolation valves shall be performed in accordance with Specification 4.6.E.
c. At least once per quarter, with the reactor power less than 75 percent of rated, trip all main steam isolation valves (one at a time) and verify closure time.
d. At least twice per week, the main steam line

, isolation valves shall be exercised by partial closure and subsequent reopening.

Amendment No. %, M, 4M, H4, 144, 156

.__ ~ _ . __ _ . _ _ . _ .. . . . . _ _ _ _ . , _ _ _ _ . . - _ . . _ _ _ _ _ _ . _ . _ . . ._. _ ~..____ _ . _

4 WNPS 3.7 LIMITING CONDITIONS FOR 4.7 SURVEILLANCE REQUIREMENTS OPERATION __

, 2. In the event any 2. Whenever a containment l containment isolation isolation valve is I valve becomes inoperable, the position inoperable, reactor of at least one other power operation may valve in each line continue provided at having an inoperable least one containment valve shall be logged 1 solation valve in each daily.

line having an 4

inoperable valve is in the mode corresponding j to the isolated condition.

3. If Specifications 3.7.D.1 and 3.7.D.2
  • cannot be met, an orderly shutdown shall be initiated and the reactor shall be in the cold shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

Amendment No. 157  ;

.. _ _ , - _ _ _ . . . . _ _ . . ~ . _ . . _ . - _ _ _ _ _ _ _ . . . _ _ . _ _ _ _ - _ . - _ . _ _ . . _ _ _ _ -

1 i.

VYNPS 4

.a 1

e I This page intentionally left blank.

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1 1.

1 4

a Y

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.i Amendment No. 158

_ . . - . _ . . _- .._ . . . _ . . - . . _ . _ . .. . . . _ ~. - _ _ _ . . . - . .. ._ . ~ -, . . _ . . . _ _ _ . .

i i

r

~.

VYNPS l TABLE 4.7.2 PRIMARY CONTAINMENT ISOLATION VALVES I

Number of Power Operated valvn Maximum Action on Isolation Operating Normal InitIcting Group (1) Valve Identification Inboard Outboard Time (sec) Position Signal 1 Main Steam Line Isolation (2-80A, D &. 4 4 5 (Note 2) Open GC l 2-86A, D)'  !

,1 t 1 Main Steam Line Drain (2-74, 2-77) 1 1 35 Closed SC I i

1 Recirculation Loop Sample Line (2-39, 2-40) 1 1 5 Closed SC l l 2 RHR Discharge to Radwaste (10-57, 10-66) 2 25 Closed SC  :

2 Drywell rioor Drain (20-82, 20-83) 2 20 Open GC 2 Drywell Equioment Drain (20-94, 20-95) 2 20 Open GC i 3 Drywell Air Purge Inlet (16-19-9) 1 10 Closed SC t l 3 Drywell Air Purge Inlet (16-19-8) 1 10 Closed SC  !

3 Drywell Purge & Vent Outlet (16-19-7A) 1 10 Closed

  • SC 3 Drywell Purge & Vent Outlet Bypass 1 10 Closed SC (16-19-6A).  ;

3 Drywell & Suppression Chamber Main Exhaust 1 10 Closed

  • SC (16-19-7) . j 3 Suppression Chamber Purge Supply (16-19-10) 1 10 Closed SC i

, 3 Suppression Chamber Purge & Vent Outlet 1 10 Closed SC (16-19-7B) ,

3 Suppression Chamber Purge & Vent Outlet 1 10 Open GC Bypass (16-19-6B) l

[

Valves 16-19-7 and 16-19-7A shall have stops installed to limit valve opening to 500 or less.

e b

f Amendment No. 50, 91, 431, 159

-d , _ _ ___ _ _ __ _ _ _

VYNPS j' TABLE 4.7.2 (Cont'd)

PRIMARY CONTAINMENT ISOLATION VALVES I

Number of Power Operated valves Maximula Action on Isolation Operating Normal Initiating Group (1) Valve Identification Inboard Outboard Time (sec) Position Signal 3 Exhaust to Standby Gas Treatment System 1 '10 Open GC (16-19-6) l 3 . Containment Purge Supply (16-19-23) 1 10 Closed SC 3 Containment Makeup Supply (16-20-22A) 1 NA Closed SC l

3 Containment Makeup Supply (16-20-20, 2 5 Open GC 16-20-22B) 5 Reactor Cleanup System (12-15, 12-18) 1 1 25 Open GC 6 HPCI (23-15, 23-16) 1 1 55 Open GC 6 RCIC (13-15, 13-16) 1 1 20 Open GC Prirnary/ Secondary Vacuum Relief (16-19-11A, '

2 NA Closed SC 16-19-11B)

Primary /Secondt w Vacuum Relief (16-19-12A, 2 NA Closed Process 16-19-12B) 3 Containment Air Sampling (VG 23, VG 26, 4 5 Open GC 109-76A&B)

Feedwater Check Valves (V2-27A, ~96A, -28A, NA Open Process

-28B) i 1

Amendment No. 58, 61, -74, M, 4-22, 16C

__m ... . . . , . ___ _ m _ _ . . _ _ . - . -. _. . . _ _ _ , , _ - . , _ . . - _ . _ _ m .- . _ -

_m. . - - . . _ _ . . _ - - _ . . . - . . _ - . . - ..

I I .

VYNPS-l TABLE 4.7.2 (Cont'd) .

PRIMARY CONTAINMENT ISOLATION VALVES I

Number of Power Operated Valves Maximum Action on Isolation Operating Normal Initiating Group M Valve Identification Inboard Outboard Time (sec) Position Signal 2 RHR Return to Suppression Pool...(10-39A, B) 2 70 Closed SC 2 RHR Return to Suppression Pool (10-34A, B) 2 120 Closed SC ,

I 2 RHR Drywell Spray (10-26A, B & 10-31A, B) 4 70 Closed SC 2 RHR Suppression Chamber Spray (10-38A, B) 2 45 Closed SC  ;

i .

3 containment Air Compressor Suction (72-39A, 2 20 Open GC l B) 4 RHR Shutdown Cooling Supply (10-18, 10-17) 1 1 28 Closed SC

, Standby Liquid Control Check Valves (11-16, 1 1 NA Closed Proc.  !

i 11-17) -

Hydrogen Monitoring (109-75 A, 1-4; 10 NA NA NA  ;

4 109-75 B-D, 1-2)

Sampling Valves - Inlet j i

  • Hydrogen Monitoring (VG-24, 25, 33, 34) 4 NA NA NA [

e

! i

. t

! I These valves are remote manual sampling valves which do not receive an isolation signal. Only one valve in

[

each line is required to be operable. j

, i

! i Amendment No. 66, M, M6, +2-2, 161

VYNPS

BASES
4.7 (Cont'd) l The maximum allowable test leak rate at the peak accident pressure of 44 psig (La) is 0.80 weight % per day. The maximum allowable test lean rate at the retest pressure of 24 psig (Lt) has been conservatively determined to be 0.59 weight percent per day. This value will be verified to be conservative'by actual primary
containment leak rate measurements at both 44 psig and 24 psig upon >

completion of the containment structure.

4 I

l As most leakage and deterioration of integrity is expected to occur through penetrations, especially those with resilient seals, a periodic leak rate test program of Eucn penetration is conducted at the peak accident pressure of 44 psig to insure not only that the I leakage remains acceptably low but also that the sealing materials '

i can withstand the accident pressure.

The primary Containment Leak Rate Testing Program is based on Option B to 10CFR50, Appendix J, for development of leak rate testing and surveillance schedules for reactor containment vessels, a

Surveillance of the suppression Chamber-Reactor Building vacuum breakers consists of operability checks and leakage tests (conducted as part of the containment leak-tightness tests). These vacuum i

breakers are normally in the closed position and open only durino I

tests or an accident condition. Operability testing is performed in conjunction with Specification 4.6.E. Inspections and calibrations

, are performed during the refueling outages; this frequency being j based on equipment quality, experience, and engineering. judgment.

f The ten (10) drywell-suppression vacuum relief valves are designed to open to the tull open position (the position that curtain area is

, equivalent to valve bore) with a force equivalent to a 0.5 psi i differential acting on the suppression chamber face of the valve.

disk. This opening specification assures that the design limit of

+

2.0 psid between the drywell and external environmert is not 1

exceeded. Once each refueling outage each valve is tested to assure that it will open fully in response to a force less than that specified. Also it is inspected.to assure that it closes freely and operates properly,

The containment design has been examined to establish the ellowable

. . bypass area between the drywell and suppressien chamber as 0.12 ft 2, l This is equivalent to one vacuum breaker open by three-eighths of an j inch-(3/8") as measured at all points around the circumference of the

! disk or three-fourths-of an inch (3/4") as measured at the bottom of the disk when the top of the disk is on the seat. Since these valves

, open in a manner that is purely neither mode, a conservative allowance of one-half inch (1/2") has been selected as the maximum-permissible valve opening. Asnuming that permissible valve opening could be evenly divided among all ten vacuum breakers at once,-valve 4

open position assumed to indication for an indivicual valve must be

i. activated less than fifty-thousandths of an inch (0.050") at all points along the seal surface of the disk. Valve closure within this limit may be determined by light indication from two independent 4 position detection and indication systems. Either system provides a control room alarm for a nonseated valve.

l l

i Amendment No. 50, lee, 168 l

r 3. , , _ . . ..r

m ps

4. An evaluation of the change, which shows the predicted releases of radioactive materials in liquid and gaseous effluents andior quantity of solid waste that differ from those previously predicted in the license application and amendments thereto; 1
5. An evaluation of the change, which shows the expected maximum exposures to member (s) of the public at the site boundary and to the general population that differ from those previously estimated in the license application and amendments thereto;
6. A comparison of the predicted releases of radioactive materials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made;
7. An estimate of the exposure to plant operating personnel as a result of the. change; and B. Documentation of the fact that the change was reviewed and found acceptable by PORC.

B. Shall become effective upon review and acceptance by PORC and approval by the Plant Manager.

6.15 Primary Containment Leak Rate Testing Procram A program shall be established to implement the leak rate testing of the primary containment as required by 10CFR50.54(o) and 10CFR50, Appendix J, Option B as modified by approved exemptions.

This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, entitled " Performance Based Containment Leak-Test Program," dated September 1995.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is-44 psig.

The maximum allowable primary containment leak rate, La, at Pa, shall be 0.8% of primary containment air weight per day.

Leak rate acceptance criteria are:

1. Primary containment leak rate acceptance criterion i 1.0 La.
2. The as-left primary containment integrated leak rate test (Type A test) acceptt.nce criterion is 1 0.75 La.
3. The combined local leak rate test (Type B and C tests) acceptance criterion is 1 0.60 La, calculated on a maximum pathway basis, prior to entering a mode of operation where containment integrity is required.
4. The combined local leak rate test (Type B and C tests) acceptance criterion is 1 0.60 La, calculated on a minimum pathway basis, at all times when primary containment integrity is required.
5. Airlock overall leak rate-acceptance criterion is 1 0.10 La when tested at > Pa.

The provision of the Definition (1.0.Y) for Surveillance Frequency does not apply to the test frequencica specified in the Primary Containment Leak Rate Testing Program.

Amendment No. B4, 95, 279

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