ML20037C845

From kanterella
Jump to navigation Jump to search
RO 81-014/01P:on 810221,during Startup Preparations,Weld Where RC-11 Nipple Penetrated RCS Boundary Found Leaking. Action Plan Being Determined.Plant Is in Mode 5 & Is Being Drained to Midspan in RCS Loops to Allow for Repair
ML20037C845
Person / Time
Site: Beaver Valley
Issue date: 02/23/1981
From: Werling J
DUQUESNE LIGHT CO.
To: Grier B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
BVPS:JAW:1111, RO-81-014-01P-0, RO-81-14-1P, NUDOCS 8103020385
Download: ML20037C845 (3)


Text

y

\\

k f.y.:. %

k QM tota 4tadoes

~

an===4 w*

DUQUESNE LIGRT COMPANT

[- Q.

,'T; in Beaver Valley Power Station Post Office Box 4 I

~. s.h Thippingpert, PA 15077 i

~' -

~

Februa ry 23, 1981 BvFS JAWc1111 i

.s N

...e

.E Beaver Valley Power Station, Unit No.1

?

Ikicket No. 50-334, Licence No. DPR-66 LER 81-014/017

'" ~=:m T '...-~~1~.1

~

e 3m I

Mr. 3.' E.~ Crier,- Director of-Regulation..

I United' States Nuclear Regulatory Commission

- Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 '

Dear Mr. Criers In accordance with Appendix A, Beaver Valley Technical Specifications -'"

=-Licensee : Event Report LER' 81-014/01F,' Technical-Specification"6.9 4148.c.

Pressure Boundry.Wald Crack,. is submitted., This occurrence was reported tom l

the Beaver Valley JULC Resident inspector Hr..J. D. Hegner at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> andi on-the Motirne phone at -1206 hours on February 22, 19810-

, M- ~ At 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> on Saturday, February 21, 1981, while taaking preparations w far plant startup, instrument technicians reported - a leak at a reactor coolant,

cystem (RCS) valve.

The reactor coolant system pressure was 2235 psig and -

tcaperature viss 547* F.

'Ihe leak was' traced to the v.icinity of RC-11, which -

10 the root stop for PT-RC-403 (RCS wide range pressure transmitter] and MrW-RH-700 (Resf dual Heat Removal System inlet.) ' At this point it was felt that. it was a body to bonnet leak on one of:these two valves, but couldn't~.

bi confirmed due to the altror insulation surrounding the piping and valves. -

Plans were started tu provide a method of sealing the valve. On the cfternoon shif t the RCS leakage inventory was calculated to be less than 0.5 spm.

RC5 laskage was calculated on the midnight shift on February 22,1981 to be 2,7 gpa. At 0100 huura on February 22, 1981, a cooldown to mode S was commenced due to the increased leakage. While the cooldown.was in progress the mirror W

/ /

=.@

=..

f,r-T

~

...;y.

M-

'7.

8103020385 S

T v

a Febr.ary 15. HR, BVFS:JAU1111 Page 2 i

taeulation was being removed for a complete view of the leak.

At 0700 hours0.0081 days <br />0.194 hours <br />0.00116 weeks <br />2.6635e-4 months <br /> the leak rate *was up to ICgps. At 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br /> on February 22, 1981 workmen entered the containment building and were able to identify positively a weld i

leek, there the AC-11 mipple penetrates the RCs boundry.

(

37.2,

..*~ ~ 1?i'Vi?ikT'???"ay??5225 '2.WQEti,'.Miy.* :At the present tiene discuss 10es are 2.*

. :2.*2 stin~shouse'and"~~ y

77 ~72,

w Doguesne Light Company Engineering Department to determine an action plan to l

be followe(. The plant. is in moJe 5 and.is being drained to mid span in the

)

RCS logps to allow the cracked weld.to be repaired.

A complete fo11ovup report'will be submitted'and the resident inspector will be kept up to date -

on the progress of the job,'

l l

Very truly yours,

(:K'*-%Q.

.5E-i-n= =5-L-

.,: 3+ = -- :-- ~ ~ ~ ~

/

HM 3 i.;.di_- r.

T

_Ti_

-ha J. A. lierling.m.

cm _ n

.__2 2 _.

Superintendent-c

~

=h

===~

- - - IT[Troctor-Of Management & Prograin Analy,is

United States Muelear Regulatory Constission Washington, D, C.

20555 D, A.' Chaney, BVPS Licensing Project Hansge'r United States Muclear Regulatory Commission,_.

Washington,,D.,Cw_2_0555 J Zn,,._,,, _ s

,. x. J.D "

Z 1 ~~

c

. =.. :.

g_xx,.,

._&_ n

.a D.7 A. Seeksenf. Nuclear Regulatory Cossaission,. BVPS Sita. Inspector :=.

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

. ~.... -

Nuclear Safety' Analysis Center, Palo Alto.- Californiar

'~~

M.v.- John Alford,- FA Public Utilities Cossaission, NscrisburgIPA-

= - -- --

m-9 em e

9 g

.m

. e.

O m

G L

U. S. NUCLEA7 C EEULATORY COMMISSION NRC FORM 366 LICENSEE EVENT REPORT CONTROL 8 LOCK: l l

l l

l l]

ape EASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6

ITITl I I

I I

I I

l@l i

I I

I I

I I

I I

I l@l l

I I

I l@l l

I@

7 8 9 UCENSEE CODE 14 15 LICENSE NUVSER 25 26 LICENSE TYPE J0

$7 CAT 68 CONT GIDITIOloirsl3131YGlo I41 'N W 81/ Gloill>lllT I / l@

IOli!

lli"C; i 7

8 60 61 DOCKET NUM8ER 68 69 EVENT DATE 14 75 REPORT OATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h l

10121l 10131 1 h

b5 62 l

l 10141 l l

10151l i

10161l l

10171 l l

101811 80 DE CODE S SC E COMPONENT CODE SL8 CODE SU E

LOLJ I

I l@ l l@ l l@ l I

I I

I

.I l@ U@ L_J@

7 8

9 10 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE REPORT REV;SION LER EVENfYEAR REPOR T NO CODE TYPE N O.

O sug/RO 1% Il I l-l 101/l%.

Ld I

I I

I I

L-J l

I at 21 22 23 24 26 27 N

29 30 31 32 KN 4 ON O

T MET HOURS S8 I E POR1 8.

SUPPLI MANUF C RER I

l@l l@

I l@

l l@

l i

I I

I U@

l l@

l l@

l l

l l

l@

34 35 36 37 40 41 42 43 44 47 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l

11101l I

li til i l

I1 171 l l

11 131 l l

l i 141 l 80 7

8 9 STA

% POWER OTHER STATUS dis RY DISCOVERY DESCRIPTION Ii Ie I I l@ l l

I l@l l

I l@l I

ACTIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l1 l6l hl l

l l

l l

7 8 9 to 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE DESCRIPTION l1l7ll l

l l

l l

l l

PERSONNE L INJURIES NUV8ER DESCRIPTION l1 l8 l l l

l l

l l

80 7

8 9 11 12 TY E @l I

DESCR PT ON ITTil I l

80 7

'8 9

13 I I I I I I I I I I I I I [I ISSUED DE CRIPTION Lu 2J l 181 I

68 69 80 5 7

8 9 70 NAME OF PREFARER PHONE:

k