ML18139B213

Updated LER 80-010/01X-1:on 800131,overstress on 18-inch Line CC-9-121,unit 2 Supply to RHR Exchanger,Found During Pipe Stress Reanalysis on Show Cause Lines.Caused by Supports Installed to Prevent Overstress During DBE

ML18139B213
Person / Time
Site:	Surry
Issue date:	03/27/1981
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139B212	List: ML18139B211 ML18139B213 ML18139B214 ML18139B215 ML18139B216
References
LER-80-010-01X-01, LER-80-10-1X-1, NUDOCS 8104020621
Download: ML18139B213 (2)

Text

{{#Wiki_filter:NAC ~ORM 365 ' t;~n, . UPDATE REPORT

• U.S. NUCLEAR REGULATORY COMMISSION e LICENSEE EVENT REPORT PREVIceREPORT DATE 02-14-80 CONTROL BLOCK: I l Ii' (PL.EASE PRiNT OF! TYPE AL.L REOUIREO INFORMATION!

!o-1 _...__.._.._ ...... _..._-:.6 \.!./ [IE] I V l A I S I P I S I 1 IQ)l O I O l -I 7 S 9 ~ICENSES COOE 14 is 0 l 01 01 01 01 -I Ol O l(Dl 4 11 11 1111101 ' I© LICENSE NUMBER . 2S . 2S LICENSE TYPE JO 57 CAT 58 CON~ 1 o i 1 : ; 6 !!!.J© I o I s l o I o I o I 21 s I o 101 o I 1 I 3 11 I s l o I© I O 13 1 2 l 7 J s f 1 I© 60 61 OOCKET NUMBER 66 69 EVENi OAT! .74 7S REPORT CA, E 80 EVENT OESCi:IIPTlON ANO PROBABLE CONSEQUENCES@ l Pipe stress reanalysis on show cause liries outside cont*ainment has **t-eV'ealed an over-[[ID I stress on line 18"-CC-9-121, Unit No~ 2 supply to the "A" Residual Heat Removal .[[E) J Exchanger. This event is reportable in accordance with. the NRC-order lifting []J]J lsion of facility operation dated August 22,1979 and Technical Specification 6.6.2.a.9.J ]The health and safety of the public were not affected since the redundant train was .[]JI] ! operable and isolation capability of the affected line was available. [ill] 7 8 9 r:rril 7 8 *SYSTEM cooE 1w IB I@ 9 10 CAUSE CAUSE COMP. CODE SUBCODE COMPONENT CCDE SU8COOE Ll.J@ L!..J@ , p , r , p , E , x , x ,e 1..~..1 11 12 1:J 18 19 SEQUENTIAL OCCURRENCE REPORT VAL.VE SUBCODE w@ 20 t:::... LERIRO LVENT YE.11,.R REPORT NO. CODE TYPE v.:.; Re"oRT I a I o I I I lo *1 1 I o I I /I I o I 1 I .LLJ 1-1 NUMBER 21 22 2:J 24 26 27 2S 29 :JO :n ACTION FUTURE EFF!:CT

• SHUTDOWN ATTACHMENT NPFID-4 PRIME COMP. REVISION NO. w __ 3' COMPONENT MANUFACTURER I so 'TAKEN ACTION ON PLANT METHOO HOUR$ SUBMITTED . FORM tiUB. SUl"PUER LI@W@ W W !,o lo! *o Io I L.!J@). L!J* W@ :J:l :JS :J6 :17 40 41 42 '3 '-Jz I 2 I 2 I 2 I CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @ 47 . . [II§] JStress calculations revealed that the installed supports would riot prevent an oyer-o::::o:::J 1stressed condition on the affected line during a Design Basis Earthguake.

Modifics1,tjorl o:II] !was initiated in accordance with preliminary design drawings and completed priori~ to [il]J !the final stress calculation. {IE] .-.L.....---------~--------------------------~ , a 9 *so FACIL.ITY . '3o' METHOD OF t,;:;\ STATUS . POWER . OTHER STATUS \:::;:/ DISCOVERY DISCOVERY DESCRIPTION tIELLl.J 11 I O I O '*' _ __;.;N~/ A;;,;,_ ___ *__. W@I Architect Engineer Analysis I : -a....,=~.:..:--:;.;....:;:.:;,:.c.i.;;=--:--:==.~=------8""'-0 8 9 10 12 13 44 45 '6 ACTIVITY CONTENT /.:'\ . . . . REL.EASED OF RELEASE AMOUNT OF ACTIVITY . . _I.DCA'!ION OF RELEASE _ITJI] UJ@ WI . . N/A I I N/A . , a e 10 11 " 7 80 PERSONNEL EXPOSURES IC\ NUMBER ~TYPE~ DESCRll'TION [TITI jO j O I O ,~Ll.J~l,,_..----.;;;.N:..:/ A,;,__ ___ ~--------------~ , a e 11 ,2 13

• so PERSONNEL INJURIES t::':'\ NUMBER OESCRll"TION\!,;., EE] Jo I o I o l@i...* ------~N1..:./A;!,.._

____ ....;... ___________ 7 8 9 11 12 80 I.OSS OF OR OAMAGE TO FA(;II.ITY '43' TYPE DESCRIPTION [TJil -~{s)'---*-**--*------~N~/A~----------------------~ 7 a SI 10 80 PUBLICITY . NRC USE ONLY "' ISSUED~ OESCR.IPTION \e!,I [fIT] l!Ll~-------------N_/ A _____________ _ I I I 1 l I I I I l I I J_! 7 8 9 10 68 69 80 ;; l>Y0N::.....;;(_B0_4..;.)_*_35_7_-_3_l_B4__, __ _ SURRY POWER DOCKET NO: REPORT NO: EVENT DATE: STATION, UNIT 1 50-280 80-010/0lX-l 01-31-80 e TITLE OF REPORT: EXCESSIVE STRESS ON PIPE 18"-CC-9-121

1. DESCRIPTION OF EVENT: During progress of the pipe stress reanalysis effort, it was determined that line 18"-CC-9-121 would have been overstressed (exceeding 50 percent ultimate capacity) in the event of a Design Basis Earthquake.

The affected line feeds the Unit No.2 "A" RHR. Heat Exchanger. This event is reportable in accordance:JWith the NRC order lifting suspension of unit operation dated August 22,1979 and Tech. Spec. 6.6.2.a.9.

2. PROBABLE CONSEQUENCES AND STATUS OF REDUNDANT SYSTEMS: Since the redundant train was operable and isolation capability, for the affected line was available, the health and safety of the public were not affected.

3. CAUSE: The problem was disclosed when the architect engineer, who is conducting the pipe stress reanalysis required by the NRC Show Cause Order, discovered the overstress condition.

4. IMMEDIATE CORRECTIVE ACTION: The overstressed condition was relieved by installing a constraint in accordance with preliminary design drawings.

5. SUBSEQUENT CORRECTIVE ACTION: No subsequent action is required since the overstressed

condition has been rectified.

6. FUTURE CORRECTIVE ACTION: None required.

7. GENERIC IMPLICATIONS:

The reanalysis has been directed towards all Show Cause Lines. As overstressed conditions arise*, the appropriate corrective actions are implemented.}}