05000366/LER-1980-156-03, /03L-0:on 801113,determined RHR Return Inboard & Outboard Thermal Expansion Bellows Leaking in Excess of Spec.Caused by Cracks in Test Connection Tubing.Retest to Be Performed
| ML19345E283 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 12/11/1980 |
| From: | Coggin C GEORGIA POWER CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19345E278 | List: |
| References | |
| LER-80-156-03L, LER-80-156-3L, NUDOCS 8012230549 | |
| Download: ML19345E283 (3) | |
| Event date: | |
|---|---|
| Report date: | |
| 3661980156R03 - NRC Website | |
text
{{#Wiki_filter:NHC FOnM 366 M.MVioMQaAnMmLMevMgnismouf (7 77) LICENSEE EVENT REPORT O,ONTROL DLOCK: C l l l l l l@ (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) b l0 lil lG l A lE II lH l2 l@l Ol Ol -l O f 0101 O l O l - 101 O l@l 4 l 11 I l ll ll@l l l@ 7 8 9 LICENSEE CODE 14 15 LICENSC NUMBEH 2h 26 LICENbE TYPE JO $1 CAI $8 CON'T 10111 E7n$ [L _j@l0 l Sl 010101316161@l 11 Il 1131'810 l@l 112111 118l Ol@ ? 8 60 61 DOCKET NUYB E R 68
- t,3 EVENT DATE 74 75 REPORT O ATE 80 EVENT oESCRIPTION AND PROBABLE CONSEQUENCES h 10121 i On 11-12-80. with Unit 2 in refuelina an LLRT by orocedure HNP-2-3952 l
lO la i I was performed on the RHR return inboard and outboa'rd thermal expansion-l 10 64 l I bellows of drywell penetration X13A. On 11-13-80, when the LLRT coor-1 10151 1 dinator reviewed the data sheet it was determined that the bellows were l IO !c i i leaki ng in excess of specified acceptance criteria. This is a repet-l 10171 l itive occurrence - see LER 50-366/1980-155. There were no effects on l l O ta l L public health or safety due to this event. I 80 7 8 9 So'sSEOE SEEe '^TE S0s*C$5e COMPONENT COOE C CO 10191 l Sl DI@ Lr_J@ L2J @ I P l i l P l E l X l X 18 LA_j@ LZ.j @ 7 8 9 10 11 12 13 18 19 20 SE QUENTi a l OCCURRENCE REPORT REVISION ,._ EVENT YE AR REPORT NO. CODE TYPE N O, @ y"LE R/ROl810l [--j l115l6l l/l 1013 l lL I l-1 Loj uQat ,,_21 22 23 24 26 21 28 29 30 31 32 T KE A I ON LANT 1 T HOURS 22 SB I F 1 UB. SUPPL 4 MAN FACTURER W@l F l@ [ Z l@ [Z_J@ l010101 l l Y l@ l Yl@ lAl@ lX191919l@ 33 34 35 36 3/ 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li 1011 The leakaae of the bellows was due to cracks in the test connection tub-1 li 11 I I ing which were anoarently caused by the weiaht of a test connection I 1 2 1 valve 2T23-IF25. The tubina of the test connection is betwhen the inneri I land outer ply of the bellows such that the inner ply could maintain I i a ( li ta l l orimary containment oer Tech Specs 3.6.1.1. An update report will be submitted 80 ' 7 8 9 STA 5 % POWER OTHER ST ATUS ISC RY DISCOVERY DESCRIPTION li Is l Lfj@ l 0101 Ol@l NA l lBl@l Performed LLRT l 1 M M 4 4 80 CO' TENT AC VITY etLE AsEo OF RELE ASE AMOUNT OF ACTIVITY LOCATION Or HEEEASE lli16i L.21@ LZJ@l NA I l NA l 7 15 9 10 11 44 45 80 Pt nSONNEL EXPOSURES NUMBE R TYPE
DESCRIPTION
li l ? l 1010101@l 2 l@l NA l PtnSONNd'm;u'n%S otSCniPriON@ NuMatn li la I l o l o l o l@l NA l 80 I 8 9 11 12 EOss Or OH D AMAGE TO F ACitITY TYPE DESCHtPTION W @l NA l i 9 80 r n v ,o a g leu ["bl""StSCniPuON @ 2380 3Gp unC USE ONLY' f I llll111111Il15 llL NA 2 " 68 69 80 5 7 8 9 10 - ~.. -.-,-.-..-{.- NAME Or PnEPAllEH P.l rnggin. Sunt. Plt. Fna. Serv. PHONE:_ 912-367-7781
LER #: 50-366/1980-156 Licensee: Georgia Power Company Facility Name: Edwin I. Ila t c h Docket #: 50-366
Narrative
Report for LER 50-366/1980-156 On 11-12-80, with Unit 2 in the refueling mode, a local leak rate test was performed per procedure HNP-2-3952, " Primary Containment Periodic Type B and Type C Leakage Tests", on the RIIR ret urn "A" lins inboard and outboard thermal expansion bellows of drywell penetration X13A. On 11-13-80, the LLRT coordinator reviewed the data in which the outboard bellows were found to be Icaking at 400 accm, and the inboard bellows' icakage was such that the test volume could not be pressur-ized. Since the test volume on the inboard bellows could not be pressurized it must be assumed that the .60 La overall allowable leakage limit of Tech Specs 3.6.1.2.B.1 would have been exceeded. In addition good engineering practices dictate that the 400 acem Icakage of the outboard bellows be repaired to prevent the Icakage from exceeding specified criteria. Since the leakages were due to cracks in the test line which communicates to the area between the inner and outer ply of the bellows, primary containment was maintained as required by Tech Specs 3.6.1.1 by the inner ply of the bellows. The bellows will be retested by LLRT procedure 11N P 3 9 5 2 when the test connections are repaired prior to startup to verify that primary containment integrity had been ' maint ained (also to verify successfulltess of modification). This is a repetitive occurrence - see LER 50-366/1980-155. There were no effects public healt.h or safety due to this event. on The Icakage of both expansion bellows was due to cracks in the 1/4" nominal sch 80 carbon steel pipe of the test connection which were probably caused by stresses resulting from the pipe supporting the weight of gate valves which were installed on the test connection piping. The valves on t.he test connection piping are neither required by any acceptance criteria nor do they serve any purpose; therefore, the valves should be rem-oved from all drywell penetrations where this condition may exist. Drywell penetrations which have a potential for devel-oping cracks due to this arrangement of the test connection are as follow: the main steam line drywell penctrations (X7A, B, C, D), the condensate drain penetration (X8), the 2 feed-water inlet penetrations (X9A, B), the RCIC stcam penetration (X10), the IIPCI steam penetration.(X11), the RilR suction penetration (X12), the 2 Rl!R return penetrations (13A, B), the RWCU supply penetration X14), the 2 core spray penetrations W
s (X16, A, B), and the RPV heid spray penetration (X17). Test connections on all of the above thermal expansion bellows will be repaired and retested by LLRT procedure llNP-2-3952 prior to Unit 2 startup. An update report will be submitted after the retests are performed. It is believed that this test line configuration does not exist on Unit 1. An inspection will be performed during the upcoming Unit I refueling outage to verify that this configuration is not present. t I i e n t l 9 i r I W }}