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| {{Adams
| | #REDIRECT [[05000259/LER-1980-049-03, Increase in Pressure Detected on Shell Side of RHR 1-C Hx.Caused by Loose Locking & Full Nuts on Floating Head Due to Thermal Cycling & Vibration.Locking Tabs Installed on Nuts]] |
| | number = ML19326D864
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| | issue date = 07/15/1980
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| | title = /03L-0:on 800620,during Surveillance Check,Ti 36A, Pressure Increase Detected on Shell Side of 1-C RHR Heat Exchanger.Caused by Loosened Nuts Due to Thermal Cycling & Vibration.Heat Exchanger Reassembled & Tested
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| | author name =
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| | author affiliation = TENNESSEE VALLEY AUTHORITY
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
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| | docket = 05000259
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| | license number =
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| | contact person =
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| | document report number = LER-80-049-03L, LER-80-49-3L, NUDOCS 8007230474
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| | package number = ML19326D863
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| | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
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| | page count = 2
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| }}
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| {{LER
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| | Title = /03L-0:on 800620,during Surveillance Check,Ti 36A, Pressure Increase Detected on Shell Side of 1-C RHR Heat Exchanger.Caused by Loosened Nuts Due to Thermal Cycling & Vibration.Heat Exchanger Reassembled & Tested
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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 = 05000259
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| | LER year = 1980
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| | LER number = 49
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| | LER revision = 3
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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:N RW F C'HnI Jim U. S "4 n. e_ A te
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| .sL A l t,o 0 77),
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| t.ICENSEE EVENT REPORT
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| /
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| Q CONTROt.8 LOCK: l l
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| l 'l Ih (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
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| 7 8 9 LICENSEE CODE
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| ;4 LICENSE NUM8ER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T 53 5o$"CE I L hl 0 l 5 l 0 l 0 l 0 l 2 l 5 l 9 @l 0 l 6 l 2 l 0 l 8 l 0 l@l nl 71 i l s; l al nl@
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| 7 8
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| 60 61 DOCKET NUMBER 68 69 EVENT OATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l 0 J 2 l l With Unit 1 at 92 percent steady state power TI 36A was beine run when an increase l
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| lTj q l in pressure was detected on the shell side of 1-C RHR heat exchanger.
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| There was no l
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| l0 i A i l danger to the health or safety of the public, and no resulting significant chain of I
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| l0IslIevents. B and D RHR loops were operable.
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| See tech. spec.3.5.B.S.
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| Previous l
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| IC l6 l l occurrence BFRO-50-259-80043.
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| 7 8
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| 9 10 11 12 13 18 19 20 SEOUENTIAL OCCURRENCE REPORT REVISION LER EVENTYEAR REPORT NO.
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| COOE TYPE NO.
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| _ 21 22 23 24 26 27 28 29 30 31 32 K N AC O ON PL NT AE HOURS SB IT FOR 8.
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| 33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Disassembly and inspection of the eat exchanger revealed that about 30 percent of
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| , g y the locking and full nuts on the floating head had loosened due to thermal cycling and vibration.
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| There were no tube leaks. The exchanger was reassembled and tested per 21-49.
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| A determination of recurrence control measures to be taken is being g
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| made.
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| 7 8 9 80
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| $A S TPUWER OTHER STATUS IS O RY OlSCOVERY DESCRIPTION li l s l l E l@ l0 l 9 l 2 l@l NA l
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| lB l@lFounc'_duringroutinetest l
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| A fiv1TY CO TENT AMOUNT OP ACTIVITY @ l LOCATION OF RELEASE @
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| l i I e l I Z l @D OF RELEASE 1.Z_J@l RELEASE l
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| NA l
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| NA 7
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| 8 9 to 11 44 45 80 PERSONNEL FxPOSURES NUMBER TYPE
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| | |
| ==DESCRIPTION==
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| l i I 7 l l 0 l 0 l 0 l@l Z l@l NA l
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| PERSONNEt N;u'4ES oESCniPriON@
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| NuveER li l a l l 0 l 0 l 0 l@l NA l
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| 7 8 9 11 12 80 LOSS OF OR DAVAGE TO FACILITY TYPE
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| | |
| ==DESCRIPTION==
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| l Z l@l NA l
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| i 9 P.
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| 8 9 to 80 PV8LICITY NRC USE ONLY tSSUED
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| ==DESCRIPTION==
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| :- Tdnn::ss;o Vall:;y Authority ~ _
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| Form BF.17 Browns Ferry Nuclear Plant BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION BFRO 259 / 8049 Technical Specification Involved 3.5.B.5 Reported Under Technical Specification
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| : 6. 7. 2.b (2)
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| Date of Occurrence 6/20/80 Time of Occurrence _1230p.m. Unit _1 Identification and Description of Occurrence:
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| RHR heat exchanger 1-C was discovered to have loosened lock nuts -during routine
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| ~
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| test TI-36A.
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| Conditions" Prior to Occurrence:
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| Unit 10 92% steady state power Unit 2 in routine shut-down condition Unit' 3 0100% steady state power 9
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| Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.
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| B & D RHR loops were operable Apparent Cauce of Occurrence:
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| Nuts had loosened d~ue to thermal cycling and vibration.
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| Analysis of Occurrence:
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| No danger to health or safety of.the public, no significant resulting chain of events, no damage to plant or equipment,'and no release of activity.
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| ==Corrective Action==
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| Heat exchanger was reassembled and tested per MMI-49.
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| Recurrence control is being determined by Engineering Design and Outage Management Group.
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| Fai. lure Data:
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| 'LER BFRO-50-259-80043, LER BFRO-50-259-78023, LER BFRO-50-259-77003.
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| * Retention:
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| criod - Lifetime; Responsibility - Administrative Supervisor
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| * Revision:
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| Go a
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| }}
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| {{LER-Nav}}
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