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{{Adams
#REDIRECT [[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]]
| number = ML19345E283
| issue date = 12/11/1980
| title = LER 80-156/03L-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
| author name = Coggin C
| author affiliation = GEORGIA POWER CO.
| addressee name =
| addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| docket = 05000366
| license number =
| contact person =
| document report number = LER-80-156-03L, LER-80-156-3L, NUDOCS 8012230549
| package number = ML19345E278
| document type = LICENSEE EVENT REPORT (SEE ALSO AO,RO), TEXT-SAFETY REPORT
| page count = 3
}}
 
=Text=
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  ?          8                      60          61                  DOCKET NUYB E R                                      EVENT DATE 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
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                                      ,._ EVENT YE AR                                  REPORT NO.                                  CODE                TYPE                          N O,
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( li ta l l orimary containment oer Tech Specs 3.6.1.1. An update report will be submitted80
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                                - -                        - ~ . .        .        .-        . - - - - - - . - . -                                - - -
 
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 on public healt.h or safety due to this event.
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 Unit          and retested by LLRT procedure llNP-2-3952 prior to 2 startup.
retests            An update are performed. It report will be submitted after the 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 verify that this configuration is not present.                    to t
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