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| {{Adams
| | #REDIRECT [[05000289/LER-1978-008-01, /01T-0:on 780202,once-through Steam Generator Feedwater Nozzles Flooded During Operation Below 5% Full Power.Caused by Incorrect Procedure Due to Operating Inexperience.Shutdown & Cooldown Procedures Revised]] |
| | number = ML19261F260
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| | issue date = 02/16/1978
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| | title = /01T-0:on 780202,facility Flooded once-through Steam Generator Feedwater Nozzles During Operation Below 5% Full Power Per B&W Recommended Procedure
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| | author name =
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| | author affiliation = METROPOLITAN EDISON CO.
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| | addressee name =
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| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
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| | docket = 05000289
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| | license number =
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| | contact person =
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| | document report number = LER-78-008-01T, LER-78-8-1T, NUDOCS 7910250698
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| | package number = ML19261F259
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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 = /01T-0:on 780202,facility Flooded once-through Steam Generator Feedwater Nozzles During Operation Below 5% Full Power Per B&W Recommended Procedure
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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 = 05000289
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| | LER year = 1978
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| | LER number = 8
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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:February 16,1978 GQL c'%
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| =NARRATIVE=
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| OF LICENSEE EVENT REPORT 78-08/1T
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| 'n' hen the Main Steam Line Break Analysis was originally performed, the B&W recc== ended operating procedure required a 30" vater levs1 in the CTSG's at low power levels. As B&W gained operating experience, flood-ing of the feedvater nozzles at low power levels was recce= ended to prevent thermal shocking of the nozzles.
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| 'IMI-1 has been following the latter B&W recoc= ended operating procedure and operates with the second-ary side feedvater nozzles submerged when belov 5% full power in order to avoid kng-term feedvater nozzle ther=al degradation.
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| Operation vith feedvater nozzles submerged, when below 5% full power was apparent,
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| ly not considered for the Steam Line Break Analysis and is therefore reportable per section 6.9.2.A(9).
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| Since these conditions occur during startup and shutdown, which constitutes a small percentage of total operating time, the probability of a steam line. break occurring during startup or shutdown is significantly less than the probebility of a steam line break occurring as analyzed.
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| Preliminary Met-Ed analysis indicates that should a main steam line break occur during operation belev 5", full power with OTSG nozzles flooded, no return to criticality vill occur following reactor trip. However, the TMI-1 shutdown and cooldovn procedures have been changed to prevent opera-tion below 5". full power vitb the OTSG nozzles flooded. Met-Ed is atte=pting to verify the above preli=inary evaluation, and to obtain B&W's concurrence with Met-Ed's analysis.
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| 4 1481 27I 791gggy
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| (URM 366 v. S UL. 6An hvULAl OrtY COMMlZION
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| )
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| LINNSEE EVENT REPORT CONTROL BLUCK: l l
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| l l
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| l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6
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| ] lol3lmlvltl,l@l 01 0l -l Ol0 l0 l0 0 l-l0 l0 l@lL l1 lil1l@l l
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| l@
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| 8 9 LICENSEE CODE 14 15 LICENSE N6M8ER 25 26 LICENSE TY PE J0 57 CAT 58 (T
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| 3
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| "'3"C l L l@ 0 l 5101010121819 l@l 01210121718 l@l012 li 16 I? lA l@
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| O 8
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| 60 61 DOCK ET NUMB ER 68 69 EVENT DATE 74 75 REPCRT DATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h 1 lIn accordance with a B&W reccenended overating trecedure. mvI-1 kog wa - c1 mm.
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| I e
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| y 10TSG feedvater nozzles during operatien belev 5% full power.
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| This cenditien was not I
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| g analyzed in the FSAR and is therefore reportable ter 6.9.2. A(9).
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| Because this utm-1 y
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| tien occ;rs only during startup ar.1 shutdown, the erobability of a steam line break at1 4
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| 9 l such times u significantly less than the probability of a steem line break cecurrinc !
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| ] | |
| as analyzed.
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| I 1.l I
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| 80 8 9 SYSTEM
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| ==CAUSE==
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| CAUSE COMP.
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| VALVE CCDE CODE SUSCODE COMPONENT CODE SUSCODE SUSCODE I
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| I z 12 l@ l_qj@ l Zl@ l Z I Z I z l Z I Z I z l@ LZ_J@ LZ_j @
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| 8 9
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| 10 11 12 13 18 19 20 SEQUENTIAL OCCURRENCE REPORT REVISION LER RO EVENT YEAR REPORT NO.
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| CODE TYPE N O.
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| @, reg U l8 l l-l l0 0l 8l [d
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| l0 1l Tl
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| [-j l0l u
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| 21 22 23 24 26 27 28 29 30 31 32
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| ( KEN AC ON ON PL NT ME HOURS S8 I FOR B.
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| SLPPLIE MANUFACTURER IC l@lz l@
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| lz l@
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| l Zl@
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| l 0] 0l 0l 0l l Ylg Nl@
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| l Zl@
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| l Z l 9 l9 9 l@
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| 33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRITTION AND CORRECTIVE ACTIONS lWhen the Main Steam Line Break Analysis was originally performed, the B&W recc= mended l o
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| (cperating procedure required a 30" vater level in the OTSG's at lov tower levels.
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| As I i
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| lB&W gained operating experience, flooding of the feedvater nozzles at low power levels 7
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| lvas reccc= ended to prevent ther=al shocking of the nozzles. The shutdown and cooldevnl 3
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| l procedures were changed to prevent floeding the nozzles when <:5% full power.
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| [
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| 4 8 9 80 ST
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| % POWER OTHER STATUS Dis O RY DISCOVERY DESCRIPTION B LF,_J@ l,Inlnl@l u I
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| Iz l@l NA I
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| '5
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| '8
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| 'o A!TiviTY CATE~T aELEASED OF REL E ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE B la_] @ Lz_i @
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| NA l
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| l
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| 'M l
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| 8 9 iO 11 44 46 80 PERSONNEL EXPOSURES NUM8ER TYPE
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| ==DESCRIPTION==
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| B 101010 l@lz l@l NA PERSO~~Er.Na s I=481 272 8 -
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| oESCRiPTiO~@
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| NUMBE.
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| B 10 10 10l@l NA l
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| 9 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE D ESCHiP TION NA l
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| h 8 9 10 80 PU B LICITY NRC USE ONLY 2 [J_j@ DESCRIPTION ISSUED l
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| weakiv news release IIIIIIIIIIIIl!
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| }}
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| {{LER-Nav}}
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