ML20236D390

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Summary Rept:Reactor Containment Bldg Integrated Leak Rate Test,Point Beach Nuclear Plant Unit 1,1987
ML20236D390
Person / Time
Site: Point Beach NextEra Energy icon.png
Issue date: 07/22/1987
From:
WISCONSIN ELECTRIC POWER CO.
To:
Shared Package
ML20236D380 List:
References
NUDOCS 8707300432
Download: ML20236D390 (13)
v • d • e


Text

_ _ _ _ _ _ _ _ _ _ _ _

l

SUMMARY

REPORT REACTOR CONTAINMENT-BUILDING INTEGRATED LEAK RATE TEST POINT BEACH NUCLEAR PLANT UNIT 1, 1987 TABLE OF CONTENTS 1.0 General Data 2.0 Technical Data ,

1 3.0 Test Data i 4.0 Analysis ar.d Interpretation I 5.0 Type C Leakage Corrections 6.0 Type B Tests Performed Between Refuelings  ;

7.0 Type C Tests Performed Between Refuelings L 8.0 Type B and C Test Summary 9.0 Comments on Valves With ' Excessive Leakage i

B707300432 870722 PDR ADOCK 05000266 G PDR

l REACTOR CONTAINMENT BUILDING INTEGRATED LEAK RATE TEST POINT BEACH NUCLEAR PLANT UNIT 1, 1987 1

1.0 GENERAL DATA 1.1 Owner - Wisconsin Electric Power Company 1.2 Docket Number 266 l

1.3 Location - Two Rivers, Wisconsin 1.4 Containment Description - 3 foot thick pre-stressed post-tensioned concrete cylinder with % inch welded ASTM A-442 steel liner 1

1.5 Date Test was Completed - April 9, 1987 1 2.0 TECHNICAL DATA 2.1 Containment Net Free Volurae - 1,000,000 cubic feet 2.2 Design Pressure - 60 psig ,

l 2.3 Design Temperature - 286 F 1

2.4 Calculated Accident Peak Pressure (Pac) - 53 psig 2.5 Calculated Accident Peak Temperature (Tac) - 286 F l

3.0 TEST DATA 3.1 Test Method - Absolute l

3. 2 Data Analysis Technique - Total Time 3.3 Test Pressure 30.4 psig 3.4 Maximum Allowable Leak' Rate, L - 0.400%/ day a
3. 5 Reduced Pressure Allowable Leak Rate, Lt- 0.283%/ day 3.6 Allowable Operational Leak Rate, 75% L t- 0.212%/ day 3.7 Integrated Leakage Rate Test Results Total Time Leak Rate, L 0.083%/ day 95%UpperConfidenceLeN1(95%UCL) 0.132%/ day 3.8 Verification Test Results 3.8.1 Imposed Verification Leak Rate 0.283%/ day (6.02 scfm) 3.8.2 Total Time Analysis 0.325%/ day 3.8.3 Verification Test Limits Lower Limit 0.295%/ day Upper Limit 0.437%/ day

4 1987 Unit 1 ILRT

+ Page 2

3.9 Corrections

Containment Volume Changes 0.004%/ day Penetrations Not in Post-LOCA Alignment 0.0001%/ day Gas Additions 0.006%/ day Total 0.010%/ day .i 3.10 As-found Penalties:

Steam Generator Val've Packing Leakage' O.155%/ day 3.11 Corrected Leakage Rates (95% UCL):

As-found 0.297%/ day As-left 0.142%/ day 4.0 ANALYSIS AND INTERPRETATION The fifth periodic Type A integrated leakage rate test of the Point l Beach Nuclear Plant (PBNP) Unit 1 containment was performed April 7-9, 1987. The testing program was conducted in accordance with the PBNP FSAR and Section 15.4.4 of'the PBNP Technical Specifications.

Twelve penetrations were not in a post loss-of-coolant accident (LOCA) alignment. Their combined Type C leakage was 11017 sccm. This requires a correction to the ILRT results of 0.0001%/ day. Containment water  ;

volume changes were 2122.2 cubic feet. This requires a correction to d the ILRT results of 0.004%/ day. Nitrogen additions to containment from '

the SI accumulators and the power-operated relief valves nitrogen bottles were 0.14310.404 lbm/ hour. Air leakage into the containment from'the inflatable seal on the outer purge exhaust valve (CV-3212) was 512 sccm.

The correction to the ILRT results for these gas additions is 0.006%/ day.

Four steam generator level transmitter isolation valves had developed ,

excessive packing leakage and were replaced prior to the ILRT. These are I not containment isolation. valves but are part of the containment ~ boundary. ,

The four valves that had been removed were tested for packing leakage and  !

a total of 88,00014,000 sccm was measured. This as-found penalty to the ILRT results is 0.155%/ day.

The calculated leakage. rate during the ILRT was 0.083%/ day by the total time method with a 95% UCL of 0.132%/ day. Adding the corrections to the calculated leakage rate yields the following corrected values:

TOTAL TIME LEAKAGE RATES (%/ day)

Leakage Rate 95% UCL Calculated 0.083 0.132 Corrections 0.010 0.010 ,

! As-Left 0.093 0.142 l l As-Found Penalty 0.155 0.155 l As-Found 0.248 0.297 The as-left 95% UCL is less than 0.75L (0.212%/ day), the allowable l operational leakage rate. This demonstrates that the as-left leakage through the primary containment and the systems and components pene-

, trating primary containment are less than the allowable leakage rate i

specified in the PBNP FSAR and Technical Specifications.

l

, 1987. Unit 1 ILRT

o. A '

Page 3 The-as-found 95% UCL' exceeded 0.75L (0.212%/ day) and was reported in Licensee;EventReport-(LER)87-002-bOdatedMay6,1987.

5.0 TYPE C LEAKAGE CORRECTIONS' Due to;the test configuration of.the containment,. twelve penetrations'-

,. were not' subjected to the 30 psig. Type A test pressure.- These penetra-tions, justification, and Type C test' results are identified below:

Type C Results Penetration- . Justification -(Minimum Pathway)

.CVCS Supply Line In use to control primary 13.9:sccm:

(#26) system pressure CVCS Letdown Linea In use to control primary. 31.0 sccm

(#10)' system pressure RCP "A" Seal Injection Maintain flow of clean- 9.3 sccm Line (#29A) water through-RCP seals

. RCP "B'! Seal Injection Maintain flow.of clean 2.3 sccm

'Line~(#298) water through RCP seals Service Air Line Modified to allow for 13.0 secm .!

(#33C) containment depressurization 'l Containment Pressure Modified to provide a 3.0 sccm Sensing Line-(#31A) pressure sensing point for .

Type A test purposes l Auxiliary Charging- Proper. venting of line is 28.0 sccm Line.(#32C) .not possible when seal

injection lines are in use PACVS Supply Line Modified to provide'a flow 0.5 sccm  ;

(#31C) verification path Sump A Drain Line was not vented in order- 2.0 sccm

(#71) to maintain the ability to pump Sump A during the ILRT

-RCOT Pump Suction- Line was not vented in order to 6.0 sccm

-(#9) maintain the ability to pump the RCDT Instrument Air Line was not vented in order to 0.0 sccm i Supply 3047 (#33A)- maintain the ability to operate instrument air in an emergency ,

l' Instrument Air Line was not vented in order to 1.0 sccm Supply 3048 (#33B) maintain the ability to operate  !

instrument air in an emergency j i

1987 Unit?l'ILRT-p39,'4

< 4 NOTES: 1. Type C; tests,were performed prior to the valvezline-up for:

the: Type A test to . ensure an as-found condition. All test-u results are 12 sccm.

. 6.01L TYPE B TESTS PERFORMED'BETWEEN REFUELINGS.

' Procedure Component Date- Leak' Rate' TS-30. Lower Personnel Hatch 8/30/84 '1086 sccm TS-10. Upper Personnel Hatch 8/30/84 3000 sccm  ;

TS ~ Lower Personnel Hatch 9/04/85 546 cccm d

-TS-10' Upper Personne1' Hatch .9/04/85- 1708 sccm 1 '

TS . Lower Personnel Hatch '3/04/86 2000 sccm TS-10' Upper Personnel Hatch 3/04/86 1622 sccm-

  • TS-35 Purge Exhaust.(V1). 11/08/86 99.sccm

~

  • TS-35 < Purge. Supply (V2) .

11/08/86 68 sccm 4

'TS-10 Upper Personne1' Hatch '11/04/86 39 sccm TS-10 Lower Personnel' Hatch 11/06/86- 87 sccm TS-10 Upper Personnel Hatch 11/07/86~ 384 scem

  • Amendment to Operating License No. 104-reclassified the-leakage testing of.

the purge supply and exhaust valves as Type B tests on 9/26/86.

7.0' TYPE C~ TESTS PERFORMED BETWEEN REFUELINGS Procedure Penetration Date Valve (s) Tested. Leak Rate.

E TS-35 -V2 9/21/84, Purge Supply >112,000 sccm TS-35 'V2
  • 9/21/84.~ . Purge Supply 410.sccm TS-35 V1 9/21/84 ' Purge Exhaust- 190 sccm TS-35 V2 9/27/84 Purge Supply 0 secm TS-35 V1 12/22/85 ' Purge. Exhaust 5 secm TS-35 V2- 12/22/85 Purge Supply 4000'sccm ORT-50 34A. 8/07/86' Sample Line PRT 93 sccm

.to Gas Analyzer 8.0 TYPE B AND C TEST

SUMMARY

The'following tables are the as-found and as-left leakage rates for the a Type B and.C tests conducted between the 1984 and 1987 ILRT's.

I q

1 k

l l:

o ,

L._ -__: . . _ _

E T G R -

R ARI A A A A A A A A A A A A A L KEAm/ / / / / / / / / / / / /

I 3 ATP c N N N N N N N N N N N N N 1 EFE c 1 R6 LAR s 8

t 19 i U1 n' D U5 gy NE na UG 6 6 0 1 3 8 6 8 0 0 4 5 6 7 e i M OA 3 2 2 .

8 8 g l - FK m 4 4 9a el - Ac 1P ui SE c f r AL s ep RA-E G R -

2 ARI A A A A A A A A A A A A 15 KEAm 2 / / / / / / / / / / / /

R8 ATP c 1 N N N N N N N N N N N N 9 EFE c 11 LAR s 0.e gn nu D i J NE l - UG .

el OA 8 9 2 2 0 4 0 6 0 6 0 8 9 ui FK m 2 1 4 2 7 f r - Ac ep SE c RA AL s -

)

n N o O i I ) t T s a A e r R n t T i e E t t t L n t t t N s s s e s s s E e e e e n P e e e PD g T T T i T T T

.R n a e n

TO S a e n n n n n n r b n n NC T l g o o o o o o D u o o o EE S E F n i i i i i i T i i i MR E L a t t t t t t t t t N - T T e l a a a a a a "8 r a a a r

IE I b F r r r r r r " e r r AG B T u t t t t t t f t t t TA T h e e e e e e & s e e e NK E c n n n n n n n n n n OA P r t e e e e e e a e e e CE Y e a P P P P P P "A r P P P L T f H -

" T G s l l l l l l l l l a a a p a a a N n t a a a l I a n c c c c c c m e c c c L r e i i i i i i u u i i i E T m r r r n n n S F n n n U p t t t a a a ( ( a a a F l i c c c h h h h h h c

E e u e e e c c c T T c c R u q l l l e e e P P e e e F E E E E M M M M M M M M 1

6 7 9 8 N 2 ,

9 O & 48 57 1 I r r 3 r ,

44 34

- T e e 2 15 0 e 7 7 15 A b b 2 5 7 b 2 3 , , , ,

8 R m m ,& m ,06 635 9 T u u , ,

u ,

44 ,45

  1. 1 E N N 8 1 8 02 8 7 9 N 3 6 N 5 2 2 55 5 5 6 1 3 , ,

5 ,

t e E o lo - - - - - - - - o - 85 - 94 i t P N i E E E PP P P P N P P34 P35 na UD T .

RO 2 3 1 2 3 5 6 7 8 9 0 1 2 ON 1 1 7 7 7 7 7 7 7 7 8 8 8

E _

T G .R R ARI - A A A A L KEAm/ / / /

I 3 ATP c N N N N 1 EFE c 1 R6 LAR s 8

t 19 i U1 n D U6 gy NE 0 8

na UG 7 9 0 3 7 e iM OA 1 4 0 4 8g l - FK m 5 1 9 a el - Ac 1P ui SE c f r AL s ep RA E

G R ~

2 ARI A A A A 15 KEAm / / / /

R8 ATP c N N N N 9 EFE c -

11 LAR s U '

e gn nu D iJ NE 3 9 l - UG 1 7 el OA 0 7 5 1 ui FK m 1 1 1 f r - Ac ep SE c RA AL s N

O I

T A

R T

E t t N s s E e e PD T T

- R TO S n n NC T o o h h EE S E i i c c MR E L t t t t S N T T a a a a T IE I r r H H S AG B T t t E TA e e l l f NK E n n e e OA P e e n n B CE Y P P n n L T o o E G l l s s P N a a r r Y I c c e e T L i i P P E n n F U a a r r O F h h e e E c c p w D R e e p o N M M U L E 6

8 N ,

9 O ,7 1 I 1 9

- T 1 15 A 1 , ,

8 R ,6 8 9 T 1

  1. 1 E 0 ,2 N 1 ,

72 t e E 58 -

it P P11 P&

na UD 0 9 1 1 T . - -

RO 3 4 S S ON 8 8 T T

[

y J1

,J l]llljil

!Ii>

~

m ' -

m '

E' T G R u 'R '

~

ARI A A~ A. A A 5 5 A A 'A A 9. A A.

- L -

KEAm / / / / / 8 9 / / / / 5 / /

I~ 3 ATPc N N N N N 3 N N N N 1 N N 1 EF 1 R6 8

L A (I cs t 19

. i U1 .

n .D' U7 gy NE~

-- na UG  :  :

7e i M OA 7 0 1 0 A' 2 2 8 1 2 3 0 5 1 u 8g l - FK m 2 1 9 ~1 / 4~ . 1 9 3 4 1 5 1 9a1

'1 P el ui SEc Ac 2 ~~ 2 N 1 2, f r ALs 1 ep 1 RA E

G . R~

A A A A 2 ARI A A A A A A 8 A. 8 15 KEAm / / / 0 / /~ ./ 3 / / 1 / / /

R8 ATP c N N N N N~ N N N N N N 9 EFEc 11 LAR s Ugn

'e nu D~

iJ NE 2.

l - UG 7 8 0 '5 2 2 0 0 0 7 0 8 8 el OA 1 2 1 1 1 0 0 6 1 ui FK m 4 9 0 f r Ac 1 3 ep SEc RA ALs s

N r O o I 't .

T a e A ) l l p

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E

(~ -

m u

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R h V p a y EE S E i) .) r )' 7) P t S p l MR E L Lt t ut ) ( r k S p N .T T .s s t s 6 e o o -

c. d p u

IE I ne e ee ( th t t. e e i m u a AG C T ot )t Rt nt n h S TA i 4 .

n ee y y i C q e n

NK E tt (t. rt o Vg l p

l p

L e

e i t S o OA P cs s es e i o l p

L CE Y ue ee t e n t Tt p p n n -

i L T Sh nh ah i c R u u r i m r r t -

G -

g ig Wg L e Ps S S u L a e e c N pi L. hi i n t t S z z e I mh lh 'r n ds n n e g i i j L u n . a e o ne e e R n g r r n E P r wr er t C at g g e u u I i

U e oe e a o o S g L s s F

E Tt Dn dt tn S.

P n t W t s

Td Dd t r

t r V C

r a t s

e s

e l

a R CE eE CE I e CA i i A h o P

r P

r e R( L( R( D T R( N N P C H S 6

8 N 9 O 1 I

- T C 1 5 A A 8 C A C C A 8 A. -

8 R 9 0 1 2 2 2 4 4 5 6 8 8 8 9 9 T 1 1 1 1 1 1 1 2 2 2 2 2 2

  1. 1 E N

te E it P l

na UD .

T . _

RO 5 6 7 8 9 0 1 2 3 4 5 6 7 9 ON 2 2 2 2 2 3 3 -

3 3 3 3 3 3 3

E T G R -

R ARI A A A A A A A A 2 A A A L -

KEAm / / / / / / / / 6 / / /

I 3 ATP c N N N N N N N N N N N 1 - EFE c 1 R6 LAR s 8

t 19 i U1 n _

D U8 gy NE na UG 7 e i M OA 2 A 2 2 1 3 5 6 0 8 3 8 8 g l - FK m 2 / 1 -

4 3 1 8 0 1 2 2 9 a el - Ac N '

0 5 1P ui SE c 1 2 f r AL s ~

ep RA E  ;

G R -

2 ARI A A A A A A A A A A A A 15 KEAm/ / / / / / / / / / / /

R8 ATP c N N N N N N N N N N N N 9 EFE c 11 LAR s U

gn e

nu D iJ NE .

l - UG 0 2 6 O 4 4 0 8 0 2 A A el OA 4 9 1 7 3 / /

ui FK m 7 0 3 1 N N f r - Ac -

1 1 ep SE c RA AL s -

N O

I T r A -

e R z T "B -

y E " y l N l 7 8 a E P p 4 4 n PD C p -

0 0 A R R u e e 3 3 _

TO S S n n s ) )

NC T y i i y y . a 2 2 EE S E l r) L) ) L l) l) G) ( (

MR E L p ) et t t -

pt pt t N T T p 6 t s es s g ps ps y os e e I E I u ( ae l e e n ue ue l t e n n AG C T S Wt pt t i St St p t i i TA n m e g p T L L NK E n o pt at nt r rt rt u Rt OA P o i us S s is a i s is S P s e e CE Y i t ee e Le h Ae Ae e l l L T t c kh th h C h h r eh p p G c e ag ng t g t g tg i ng m m N e n Mi ei ni y ni ni A ii a a I j n h mh eh r eh eh Lh S S L n o r n V a m m e .

E I C or ir r i ur ur c er G G U t e ae S e l re re i l e S S F l t ct tt Vt i tt tt v pt E a s an nn C n x sn sn r mn R e e eE oE AE u nE nE e aE "A "B S T R( C( P( A I( I( S S( " "

6 8 N 9 O 1 I

- T 15 A 8 A C B C C A B C A C B 8 R 9 0 0 1 1 2 3 3 3 4 4 4 9 T 2 3 3 3 3 3 3 3 3 3 3 3

  1. 1 E N

te E it P na UD '

T< .

iO 0 1 2 3 4 6 7 8 9 0 1 2 ON 4 4 4 4 4 4 4 4 4 5 5 5

-- T R

L E

G ARI KEAm/

R A A

/

A

/

A

/

A

/

0 1

A

/

N A

/

N 8

3 7

3 A

/

N A

/

N A

/

N A

/

N A

/

N I 3 ATP c N N N N N 1 EFE c 1 R6 LAR s 8

t 19 i U1 n D U9 gy NE na UG 9 0 3 9 9 -

7 e i M OA 2 9 3 3 0 6 4 2 -

8 g l - FK m 3 8 9 1 6 2 1 9 a el - Ac 8 2 8 1P ui SEc 1 f r AL s ep RA E

G R 2 ARI A A A A A 0 4 A 6 0 1 A A A A 15 KEAm / / / / / 2 2 / 0 4 1 / / / /

R8 ATP c N N N N N 5 1 N 1 N N N N 9 EFE c 11 LAR s U

- gn nu e

D iJ NE l - UG 8 9 9 4 0 5 0 0 5 3 6 2 3 6 0 el OA 1 0 2 3 1 6 9 5 ui FK m 6 4 3 2 1 1 9 2 f r - Ac 1 1 ep SE c RA AL s ) )

8 8

( (

e e g v v 8 9 l l n 6 ) 6 N t a a i 9 8

(

9 O n V V d I e l d d T m k k i n 8 n A n c c u a 4 a R i e e B 9 T a h h 6 0 E t n C C y 4 d 5 N n o r 9 n 9 E ) ) o i e e a a PD 9 9 C t g g i n , ,

R c r r l r 5 7 9 TO S , ,

m e a a i y u 4 4 4 NC T 2 2 o n h h x l t 9 9 9 EE S E y r n c c u p) e) - - -

MR E L , , l f o s s A pt Rt T T T N T T 1 1 p C i i us s P P P IE I ( ( p n D D o S e ee AG C T u r t t t gt f f f TA n n S u s p p n r o o o NK E w w t e m m n ot at OA P o o m e T u u i t i s h s t t t CE Y d d a R P P a s y t e ce s s s L T w w e t r u l ch sh e e e G o o t e n y y D a p ug i g T T T N l l S t e a a h p Si Di I B B a m r r x u h h e e e L g s n p p A" E S 2 2 r r r E G G n n i S S " 1 r 1 r u u u U S S i e a e e R e R e s s s F t d t A B p g g /t /t s s s E a n n 4 4 m r r 1 n 1 n e e e R "B "A e o o 1 1 u u u 1E 1E r r r

" " H C C P P S P P R( R( P P P 6

8 N 9 O 1 I

- T 15 A A 8 A 8 R 0 1 2 3 6 4 5 1 1 2 1 2 1 4 2 9 T 5 5 5 5 5 5 5 7 V V X X 3 1 3

  1. 1 E N

t e E it P na UD T . A 8 C RO 4 5 6 7 8 9 0 1 2 3 4 5 6 6 6 ON 5 5 5 5 5 5 6 6 6 6 6 6 6 6 6

E -

T G R R ARI A 4 A KEAm/

L -

0 /

I 3 ATP c N 2 N 1: -

EFE c -

1 R6 LAR s 8

t 19 i U1 n0 D - 0 U1 gy NE 0 na UG 0, 5) 7 e iM OA 9 0 8g l - FK m 7( 2 9 a el - Ac 3 8 1P ui SE c 1 f r ep AL s >

RA E

G R -

2 - ARI - A A 9

~

15 KEAm / / 9 R8 ATP c N N 7 9 EFE c 1 11 LAR s U -

gn e

nu D iJ NE l - UG 2 2 5 el OA 3 1 2 ui FK m 0 f r - Ac 1 ep SE c 1 RA AL s N X O E I H T

A n R w T o E d N t E e PD L R P P TO S s C C NC T s R R EE S E e) ) )

MR E L cr r r S N T T xe "A e "B e T S

IE I Eh " h " h AG C T t t t E TA me og me og me og T

NK E OA P ro ro ro C CE Y ft ft ft L T E G d s d s d s P N nt nt nt Y I as as as T L re e e E ot ot ot F U t t t O F d d d E Wd Wd Wd D R C6 CA CA N C( C( C( E 6

8 N 0 7 8 9 O 2 1 1 1 I

- T & & &

15 A 8 R 9 5 6 9 T 1 1 1

  1. 1 E N

t e E it P na UD T

RO . 7 8 6

9 6

ON 6

1987 Unit 1 ILRT

. Page 11 1

Notes for Type B & C Test Summary Tables

1. Modification M-730, completed December 1981 installed an additional automatic containment isolation valve in each blowdown line. These new valves are located inside containment in series with the existing valves. Periodic leak testing of the new isolation valves as well as the original isolation valves commenced following installation during the 1981 refueling outage.
2. The pump and valve test program submitted to the NRC on March 28, 1985 committed to leak testing of the steam generator blowdown and sample valves and continuation of leak testing of the new blowdown valves inside containment. Although the blowdown line isolation valves outside containment receive a containment isolation signal, they cannot be relied upon for isolation purposes since they are not seismic-ally installed. These valves were not included in the test program although they will continue to be leak tested until the containment isolation signal is removed.
3. Modification M-681, completed March 1984, installed an additional auto-matic containment isolation valve in the reactor coolant pump seal return line. The new valve is located inside containment and in series with the existing isolation vi. m Periodic leak testing of the new isolation valve commenced fo110wi.,9 installation during the 1984 refueling outage.
4. Modification M-683, completed February 1984, installed an additional automatic containment isolation valve in the letdown line. The new valve is located inside containment and in series with the existing isolation valve. Periodic leak testing of the new valve commenced following instal-lation during the 1984 refueling outage.
5. The valve leak rate could not be determined. The test volume could not be pressurized to full test pressure due to e> essive leakage.

It measured 137,000 sccm at 42 psig.

6. -Based on a review of containment penetrations documented in the M. F.

Moylan to J. J. Zach memo dated February 2, 1984, it was determined that these penetrations were not required to be Type C tested. Testing was discontinued after 1985.

7. Modification 86-002, completed in May 1986, installed a test connection '

between the isolation valves in the nitrogen supply line to penetration 12C.

This allows individual testing of the isolation valves and ORT 30 was revised.

8. ORTS 66A, 66B, and 66C were performed as one combined test in 1986.
9. The automatic trip signal to the steam generator blowdown line isolation valves outside containment was removed during the 1987 refueling outage.

Testing is no longer required.

1987 Unit 1 ILRT

. Page 12 l 1

9. 0 COMMENTS ON VALVES WITH EXC' SSIVE LEAKAGE TS-35 (9/21/84)

The containment purge supply penetration was tested and found to leak in excess of 112,000 secm. The required test pressure could not be achieved and, therefore, the leakage at rated pressure could not be quantified.

An inspection revealed that the inner purge supply valve, 1-CV-3245, was

{ unseated. The operating mechanism for valve 1-CV-3245 was tapped in the closed direction to seat the valve and a leakage rate of 410 sccm was measured. Follow-up investigation concluded that applying pressure for a leakage test could unseat the valve. A new setpoint for the mechanical stop in the valve operator was developed and set in 1-CV-3245 to prevent this from reoccurring. (Licensee Event Report No. 84-006-00 is currently being prepared and will be transmitted shortly.)

l ORT 68 (1986) )

1 Check valve 1-755A, "A" reactor coolant pump component cooling water supply, appeared to stick partially open during the initial Type C test.

The required test pressure could not be achieved and, therefore, the leakage at rated pressure could not be quantified. Maintenance exam-ination and repair revealed that a disc hinge pin bushing had migrated toward the disc swing arm and resulted in the valve disc sticking. The l valve was repaired and retested. The leakage after repair was 204 sccm. l (Licensee Event Report No. 86-002-00, 5/16/86.) l

..

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