ML17252B511

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LER 77-045/01T-0 for Dresden, Unit 2 Re While Preforming Leak Rate Testing Procedure Dts 1600-1, Measured Leakage for Reactor Feed Check Valves 2-220-58B&62B Were 1149 and 195 Scfh
ML17252B511
Person / Time
Site: Dresden Constellation icon.png
Issue date: 10/18/1977
From: Stephenson B
Commonwealth Edison Co
To: James Keppler
NRC/RGN-III
References
BBS LTR 966-77 LER 77-045/01T-0
Download: ML17252B511 (5)
v • d • e


Text

_,, .

,. Coinm~nwea9Edison

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liiiii ~orris, Nuclear Power Station Illinois 60450

. Telephone 815/942-2920

--- ~---------

October. 18, 1977 BBS LTR /1966.;.77 James G. Keppler, Regional .Director Directorate of Regulatory Operations - Region III U.S. Nuclear Reg,ulatory Commission 799 Roosevelt Road*

Gleri Ellyn, IL 60137 I

Reportable Occurrence,;'-1Interim Report'.' 77-045/0lT--'0 is hereby submitted to your office -in accotdancewith Dresden Nuclear Power Station Techni-cal Specification 6~6 B.l.c., abnormal degradation discovered in primary containment.

Dresden BBS*';dlz

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Enclosure cc r Director of Inspection & Enforcement Director of Management Information & Program Control File/NRC

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OCT 2 O 1977

ti.'!.. ~'tJtlt 'At:trotJt'f"OR\' 'CC1l'VllQI ISSI ON' e LICENSEE EVENT REPORT e

  • , co~.,"TROL BLOCK: I I If,\.

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!PLEASE PRINT oR TYPE ALL REau1RED INFORMATION!

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  • I LI n I RI s I 2101 o I o I - I o I o I o I o I o I ,. I o I olI 4 I i I i I i I i I©I I I0 7 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25. 26 LICENSE TYPE JO 57 CAT 58 CON'T

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  • 8 60 61 DOCKET NUMBER 68 69 .EVENT DATE 74 75 REPORTDATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

((DJ I While performing local leak rate testing procedure DTS 1600..-1, measured leakages for reactor feed check valves 2-220 .. 58B&62B were 1149 and. 195 SCFH respectively, exceeding limits for single valve leakage, (29.3) and total allowable primary containment thru

~

@:ill leakage (176), T.S.4.7.A.2.f.(2). (a)&(b), Public safety is not affected, other valves are available for isolation. Similar events: 50-237/76..,-18, 74-60,61; 50 ...249/76-18,25; I

@ID 50-249/75-20,21,29; 50-249/74-5,9.

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[QI[J 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE e

CODE CODE SUBCODE COMPONENT CODE SUBCODE *SUBCODE

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7 8. 9 10 11 12 13 ~8 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION

~ LER/RO CVENT Y.EAR REPORT NO.

  • CODE TYPE NO.

\.!...!./ REPORT NUMBER I 7j 71 I I I 0 1 41 51 1,...-1 I o 11 I L!J l.:=l LQJ 21 22 23 24 26 . 27 28 29 30 31 32 ACTION FUTURE EFFECT SHUTDOWN ~ ATTACHMENT NPRD-4 PRIME COMP. .COMPONENT TAKEN ACTION ON PLANT METHOD HOURS ~ SUBMITTED FORM SUB. SUPPLIER MANUFACTURER W@~@

33 34 LI@

35 LU 36 I 01 37 01 01 01 40 Lx.J@

41 W

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47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

  • v--.. r I(__* ~~~es 2.,.220. . . 58B&62B are being\;\disassembled to determine cause and steps needed to re-I duce leakages below T. S. limits prior to startup. When complete information is avail-I able, an updated}i.'-E'!l will be submitted, The valves are 18 inch tilting disc c4eck DJ)) I valves, Crane Company Model 973, carbon steel, 1250 PSIG, 5750F.

rr:m 7 8 9 80 FACILITY METHOD OF STATUS  % POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION @

ETIJ ~@ I 01 01 01@1.__ _ _N_A_ __ L!J@I Local Leak Rate Testing

7. 8 9 10 12 11 44 45 46 BO ACTIVITY CONTENT t::;;,.

RELEASED OF RELEASE AMOUNT OF ACTIVITY~ LOCATION OF RELEASE @

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. NA 44 45 NA 80 PERSONNEL EXPOSURES

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NUMBER (,;:;\TYPE DESCRIPTION

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7 8 9 I 0I 0 I OJ0~@~-------------=-N=A-------------'

11 12 . 13 80 PERSONNEL INJURIES Q DESCRIPTION~

~ Oj NUMBER 01 OJ@)._________________NA ___________ ~

7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY 143' TYPE . DESCRIPTION ~

ETTI 7 8 L.:J@)~------------------N_A_ _ _ _ _ _ _ _ _ _ _ __,

9 10 BO PUBLICITY {.;;\ NRC USE ONLY ISSUEDQ DESCRIPTION~ .,

~~~---*------~~-------~NA~--~

7 8 9 10 68 1111111111111~

69 80 ;;

0 NAMEOFPREPARER--~~~P-.a~r_c_e_l_l~~~~~~~~~~- PHONE:-----.:2.;:;6.:.5_ _ _ __ ~

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

ATTACHMENT TO LICENSEE EVENT REPORT 77-045/0lT..:.O COMMONWEALTH EDISON COMPANY (CWE)

DRESDEN UNIT 2 (ILDRS-2)

DOCKET II 50-237 While performing local leak rate testing of primary system isolation valves using.procedure DTS 1600.:.1, the measured ieakages.for reactor feed water check valves 2--:220--58B&62B were 1149 SCFii.and_l95 SCFH respectively. As a result the technical specification (LS.4.7.A.2.f.

(2). (b); limits for single valve leakage 5Q(J*~L-tE -= 29 .3 SCFH)and total allowable primary containment through leakag*~ _,(T.. S. 4, 7-.A. 2 .. f. (2). (a); .

30%1,..w~= 176 SCFH) were.exceeded;

  • The reactor feedwater check valves were tested by pressurizing the test Volume with water to about 50 PSIG. To seat -the valves the ~ater is
  • drained while maintaining the test volume at ~bout ,50 PSIG with air to maintain valve seating* .The pressure decay method.is then used to deter-mine th~ leakage.

This event. has little safety significance* since there are motor* operated *

'@.l~es available. for isol.ation.

  • I t has occurred frequently in the past,* * *

~~S.:..e;v'~~J,loccurrences were the result of dirt between the* d:j_sc and seat. and were corrected by clep.ning, Other occurrences w:ere caused by da11,1p.ge to the valve seat-to-body .~0,~Ring *.

  • Check val:ves
  • 2-221§-SBB & 62B ~re being*

disassembled .:i.nd inspecteg.

1 \> :*-

) When. completed, an updated @;,~B' will be* submitted describing the cause of the excessive leakage and steps taken to reduce the'leakqge below tech-nical specification iimits.

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TO: tl!'rE':

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  • .. c; .. ~
  • Regional Director *
- . * "
-, Directorate of Regulat9- Qperations -Telecop_i_ Date

... . . ~- Region III . . or .

_. _............ \.__ '."U.S. Nuclear Regulatory Commission . -* .:Telegrannned

  • GE //; 1-foS'

, .79:9 Roosevelt Road

  • Glen Ellyn, IL .60137 DC

-**-----** --ci~-:-------------------*:**--~--------'--------*--*-*-- ...:_*-----*By_: _________ *---------------*-

Director Office of Management*Inform~tion*and Program Control V-S~ N~clear Regulatory .Connnission Washington, be 20555 SUBJECT~

I bPR- /Z

, . * ---=====::.:__

!~

Dresden Nuclear Power Station, Unit

__::~--======-

'l This will confirm l'Ynversation with ~ ~ of Q /tJ/6/77 ~

your off ice at CJ/ '3eJ hrs this date concerning ~.J

.oa'. A. /Zee.ou;,,..ve..d- e,/,.,e- ~~c,,,c L~,,L

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.To Call:

GE 858-2660xl6 f .

  • B. B. Stephenson, Superintendent Dresden Nuclear Power Static~

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DC 1-301-492-7617 (auto) Commonwealth Edison Company N I

WU. - 815-942-4.44.9/4321 R.R. #1 . . "Vt'

  • i Morris, IL 60450 Station Dist: Originator*\~*( copy)

~ncid:ent File (copy) *

'a Telephone: 815-942~2920/2QZl~Z12

~ftlAA~;tm. fjl~ !A~i~) ~ ~teleco.P~ x262)

  • RECEIVED DOCUM[tlT P~DCESStNG U~iT 19} f NOV AM 7 39 1"'*.

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