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| {{Adams
| | #REDIRECT [[05000346/LER-1980-048-01, /01T-1:on 800627,during IE Bulletin 79-14 Insp, Pipe Support HCV-40-B1 Found Not Installed & CCA-8-H15 Mislocated.Caused by Const/Installation Error.Pipe Support HCB-40-B1 to Be added.CCA-8-H15 to Be Designed & Relocated]] |
| | number = ML19347F640
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| | issue date = 05/15/1981
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| | title = /01X-2:on 800627,per IE Bulletin 79-14,pipe Support HCB-40-B1 Was Found Not installed,CCA-8-H15 Was Found Mislocated & Supports SR-11,EBB-1-H3 & EBB-1-H4 Exceeded Design Loads.Caused by Const/Installation Error
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| | author name = Mekbel C
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| | author affiliation = TOLEDO EDISON CO.
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
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| | docket = 05000346
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| | license number =
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| | contact person =
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| | document report number = IEB-79-14, LER-80-048-01X, LER-80-48-1X, NUDOCS 8105220290
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| | package number = ML19347F638
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| | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
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| | page count = 3
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| }}
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| {{LER
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| | Title = /01X-2:on 800627,per IE Bulletin 79-14,pipe Support HCB-40-B1 Was Found Not installed,CCA-8-H15 Was Found Mislocated & Supports SR-11,EBB-1-H3 & EBB-1-H4 Exceeded Design Loads.Caused by Const/Installation Error
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| | Plant =
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| | Reporting criterion =
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| | Power level =
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| | Mode =
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| | Docket = 05000346
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| | LER year = 1980
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| | LER number = 48
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| | LER revision = 1
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| | Event date =
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| | Report date =
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| | ENS =
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| | abstract =
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| }}
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| =text=
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| {{#Wiki_filter:?.SC F ORM 36G 17 77)
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| LICENSEE EVENT REPORT
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| /
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| CoNTRot eLoCK: l l
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| l l* l l
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| (PLEASE PRINT C*) TYPE ALL REIUIRE3 INFCRMATl*N) l 0 l H l D l B l S l 1 l@l 9 l $ l _ l 6 l 9 l 9 l @ l @ l _ l 0 l 6 ]@l 4 l1 l1 l1 l 1 l@l l
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| ]g o i i
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| 8 9 LICENSEE CODE 14 15 LICENSE NUMUER 25 26 LICENSE TYPE JO 57 CAT 66 CCTT Lo L5_]
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| Z,"CE I L l@l 0 l 5 l 9 l 0 l 0.l 3 l 4 l 6 l@l 0 l 6 l 2 l7 l 8 l g l@l0 l5 l1 l5 l8 l1l@
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| 7 8
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| 60 61 DOCK ET NUUSER 68 69 EVENT DATE 74 75 REPOR7 DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h ITTTl ](NP-32-80-09) While evaluating the inaccessible piping systems as reauired by IE Bulle-l l
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| g l tin 79-14 pipe support HCB-40-B1 was found not installed and CCA-8-H15 was found mis-E g [ocated. Also stress calculation 10A found that loads for supports SR-11. EBB-1-H3. and g g KBB-1-H4 exceeded their design load.
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| It was determined that the found condition was leds ponservative than assumed in the accident analysis of the safety analysis report and isi ae ITTT1 being reported under Technical Specification 6.9.1.8.1.
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| There was no danger "to the health l
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| g pnd safety of the public or station personnel.
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| DE CODE SUBC E COMPONENT CODE SU8C DE SU E
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| h W h lS lU lP l0 lR h' jh W h W h O 9 7
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| 8 9
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| to II 12 13 18 13 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER EVENT YEAR R EPORT NO.
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| CODE TYPE N O.
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| @,ag/Ro 18lel L.]
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| 1814181 12.1 18111 LX_J L]
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| L2_j
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| _ 23 22 23 24 26*
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| 27 28 29 30 31 32 AK N AC 0 ON PL NT ET HOURS SB 1 FOR B.
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| SUPPLIE MAN F CTURER lF lg y @
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| 33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRCCTIVE ACTIONS h
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| @] The cause of the 'not installed' and the 'mislocated' nine sunporem t.rn s nn infein1 1
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| E] l construction / installation error.
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| Under FCR 80-091 Sunninmone 6-ncn An n1 u411 %
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| I nnafrfnn undar l
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| g ] ladded and CCA-8-H15 will be designed and relocated to its cricinn1 wa.s_.co_rrscted by 1.he.]
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| 3 ] lFCR 80-131, Supplement 3. The problem with the remainine sunnnven g gaddition of support SR-47 under FCR 80-079 Supplement 10.
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| J 7
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| 8 '
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| OTHER STATUS D bEbME
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| /ERY DESCRIPTION S" TANS'
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| % POWE R NA l
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| [D,,jhlIEBulletin79-14
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| .}
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| li l l (H_j@ l 6 l 6 l 0 l@l f.CTIVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATION OF RELEASE l
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| NA l
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| l NA [1_j.6] d @ [z_j@l 80 8 9 10 11 44 45 PERSONNEL EXPOSURES NUV8ER TYPE
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| ==DESCRIPTION==
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| l FT7] 10 l0 l0 l@lz l@l NA
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| ,ERSoNNE'L%unS DESCRiPT:ON@
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| __ }
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| Nuves R FT1 le lo la l@l 80 NA 7
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| 8 3 11 12 LOSS OF OR DAYACE TO FACILITY l
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| T4PE OESCRIPiloN L'.l.2J Iz l@l NA 0
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| 8 9 10 NRC USE ONLY Pust tCs TY iiiil}
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| 8105220804 i
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| i i i i i i i i
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| , O 68 69 63 &
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| 7 8 9 to 419-259-5608 2
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| ChafleS Mehhel PHONE:
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| NAME OC PHEPARER
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| ~
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| .]
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| .i' TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-32-80 t DATE OF EVENT _: June 27, 1980 FACILITY: Davis-Besse Unit 1
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| ~ IDENTIFICATION OF OCCURRENCE: Pipe supports HCB-40-B1 and CCA-8-H15 not installed as designed.
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| Conditiot.3' Prior to Occurrence:.The unit was in Mode 6, with Power (MWT) = 0 and Load (Gross MWE) = 0.
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| Description of Occurrence: While performing the walkdown and engineering evaluation i
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| i for inaccessible piping systems. required by IE Bulletin 79-14, the following was found:
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| j l
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| Pipe support HCB-40-B1 on the component cooling water (CCW) supply to the control rod drive ~(CRD) mechanism coolers was not installed. This would have left approxi-i mately 21 feet of 3 inch pipe between the containment penetration and the isolation valve laterally unrestrained during an earthquake..
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| Lateral: restraint CCA-B-HIS on the pressurizer relief inlet was located about 9 inches from its analyzed location. This discrepancy would have caused an overstressed con.
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| dition in a welded attachment to this line during an earthquake.
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| j On August 1, 1980, while reviewing stress calculation 10A for the main steam line 1
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| outside of containment, it was found that the support loads for supports SR-11, EBB-1-H3, and EBB-1-H4 exceeded their design load.
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| During the detailed engineering evaluation of these discrepancies, it was determined that the'found condition was less conservative than assumed in the accident analysis of the safety anaylsis report and is being reported under Technical Specification 6.9.1.8.i.
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| Designation of Apparent Cause of Occurrence: The cause of the occurrence was an ini-
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| :- tial construction / installation error.
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| HGB-40-B1 was never installed and CCA-8-H15 was mislocated.
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| The cause of the August 1, 1980, finding was a design error by the architect engineer 1
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| Bechtel Power Corporation.
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| j Analysis of Occurrence: There was no danger to the health and safety of the public j
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| or to station personnel. These restraints do not affect normal unit operation. Pipe support HCB-40-H1 is only required to resist loads resulting from a design basis i
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| I earthquake.
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| Latgral restraint CCA-8-H15, in its as-found condition, would not have been overstressed except during a design basis earthquake, since 98% of the restraints design load is seismic.
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| LER #80-048 I
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| l q.,
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| TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE PACE 2 SUPPLEMENTAL INFORMATION FOR LER NP-32-80-09 a problem that was a result of the support loads The August 1, 1980, finding was not being printed out when stress calculation 10A was run for the as-built conditions.
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| This is not a generic problem but unique to stress calculation 10A. Pechtel has re-viewed all other stress calculations performed for IE Bulletin 79-14 and found no other calculations where the as-built support loads were not calculated.
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| ==Corrective Action==
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| Pipe support HCB-40-B1 will be added under FCR 80-091 Supplement 6.
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| Lateral restraint CCA-8-H15 will be redesigned and relocated to its original position under FCR 80-131 Supplement 3.
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| These discrepancies will be corrected prior to startup from the current refueling outage.
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| A modification was designed and issued as Supplement 10 to FCR 80-079 that added 2
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| support SR-47 to the main steam line outside of containment. This new support reduces the loads on supports SR-ll, EBB-1-H3, an4 EBB-1-H4 to within acceptable limits.
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| Failure Data: There have been no previous reported findings where the installation was not per design.
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| Previous reported findings of pipe support design errors were reported in NP-32-79-08 (79-064), NP-32-79-13 (79-106), and NP-33-79-154 (79-133).
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| LER #80-048 i
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