View source for 05000266/LER-1985-002, Forwards LER 85-002-01 Re Details of Fuel Damage Found on Fuel Assembly H14,which Spent Last Cycle in Core Position D12.Rept Suppls Original Rept

{{Adams
| number = ML20198E637
| issue date = 05/19/1986
| title = Forwards LER 85-002-01 Re Details of Fuel Damage Found on Fuel Assembly H14,which Spent Last Cycle in Core Position D12.Rept Suppls Original Rept
| author name = Fay C
| author affiliation = WISCONSIN ELECTRIC POWER CO.
| addressee name = Keppler J
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION III)
| docket = 05000266
| license number = 
| contact person = 
| case reference number = CON-NRC-86-45
| document report number = LER-85-402, VPNPD-86-223, NUDOCS 8605280129
| title reference date = 06-11-1985
| package number = ML20198D711
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE, LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT, UTILITY TO NRC
| page count = 1
}}
{{LER
| Title = Forwards LER 85-002-01 Re Details of Fuel Damage Found on Fuel Assembly H14,which Spent Last Cycle in Core Position D12.Rept Suppls Original Rept 
| Plant = 
| Reporting criterion = 
| Power level = 
| Mode = 
| Docket = 05000266
| LER year = 2085
| LER number = 2
| LER revision = 
| Event date = 
| Report date = 
| ENS = 
| abstract = 
}}

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0771 h WISCONSIN Electnc row cwwr 231 W. MICHIGAN, P.O. BOX 2046 MILWAUME, Wi M?M VPNPD-86-223 NRC-86-45 May 19, 1986 1
Mr. J. G. Keppier, Regional Administrator i
Of fice of In.3pection and Enforcentent Reglon III U. L. NUCLEM REG *JLATORY COMMISSION 799 Roosevelt Road Glen Ellyn, IllinolB 60137

==Dear Mr. Keppler:==

DOCKf.T 50-266:
LICENSEE EVENT _NEPORT 85-_002--01 FAILCD FUEL ROD IN ASSEMBLY E14 POINT' BEACH NUCLEAR PLANT,[ UNIT._1 Enclosed is Licensee Event Report 85-002-01 for Point Beach Nuclear Plant, Unit 1. This report             is a supplement to LER 85-002-00 dated June 11, 1985.
This report details the fuel damage found on Fuel Assembly H14, which spent the last cycle in Core Position D12. This is the same core position occupied by damaged Assembly H09 during the last cycle. Both assemblies exhibited the same type of damagc.
LER 85-002-00 was filed under the reporting requirement of 10 CFR 50.73(a)(2)tii), "Any event or condition that resulted in the condition of the nuclear power plant, including its principal safety barriers, being seriously degraded."
Very truly yours,
               *        ~
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C. W. Fay                '
Vice Preside Nuclear Power 2nclosure Copies to NRC Document Control. Desk Washington, DC (with original)
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On April 27, 1986, during the inspection of discharged fuel which had been located in core position next to core baffle joints at Unit 1 of Point Beach Nuclear Plant, have failed cladding in one fuel rod. fuel assembly H14 was found to The fuel rod cladding appears to     have failed due to vibration of the rod against the grid and grid springs.
water impingement through a slightly widened core baffle plate bu joint next to core locaticn D12. The fuel cladding was failed to the extent that fuel pellets could be seen through the hole in the clad.           However, no pellets escaped from the rod.
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     'hnc Form assa y a muctgam pioutaTOmv Comesissiom LICENSEE EVENT REPORT (LER) TEXT CONTINUATIONamovio ous ~o vio-oio.
4CILaf y manet Us                                                                                E mpenE5 8'3195 DOCat? muedeta (2' LER huusta ter                    PAGE 13)
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Point Seach Nuclear Plant                                               i      u o .
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q1 g2 or                 6 0l Operating Conditions Before the Event:
Point Beach Nuclear Plant, Unit 1, operated from June, 1985, until April, 1986, power level decreases for various tests.with few interruptions other than minor lo Status of Structures, Components, or Systems That Were Inoperable at the Start of the Event and That Contributed to the Event:
At Cycle the13,  end of Cycle 12 in 1985 and prior to the beginning of the core baffle plate at core location D12 was inspected.
The baffle joint was found to have a possible 4 to 7 mil gap between the rows of cap screws (see LER 85-002-00). This gap is in a location H14.
assembly           which is opposite the location of the fuel damage on fuel Dates and Approximate Times of Occurrences:
The level of dose equivalent I-131 had shown no evidence of fuel failure above that expected normally until the second week of March, 1986.
At that point, levels did increase slightly until a level shut down 0.1 just     above        for micro-curies  /cc was measured just before the annual refueling. (See    the attached chart of dose equivalent I-131 versus time.)
PBNP Technical Specifications.This level is 10 percent of that allowed by An inspection was made of fuel assembly H14 on April 27, 1986.
NOTE:
ALL INDICATIONS WERE ON THE WEST FACE OF THETHE                                            ASSEMBLY.
SEVEN GRIDS ARE NUMBERED FROM TOP TO BOTTOM.
Grid 1:
Shiny marks visible on rod Nos.
against the grid.                             13 and 14 due to vibration of rod Grid 2:
Rod No. 14 was completely severed at Grid 2.
dence of fuel pellet fragments behind Grid 2. There was some evi-
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION                         anaovio ovs =o vio+o.
E xPimEs af3,35 PactLITV NAME 111                              DOCsiti Wueset h (2'           LER huMSER166                   P AGE (3+
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                                                                                  " 2 % '.''   - I'#,?:
Point Beach Nuclear Plant                    o l5 jo jo lo l2 l6 l6 8l5   -
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Ol 1 0l 3      0F 0 l6 rut <,     .s   . . , - _ ve ,   ., n 7, Grid 3:
Rod No. 14 (the rod immediately adjacent to the baffle joint) was severed immediately behind the third grid from the top of the fuel assembly. The fuel inside the rod was visible. No pellets appeared to have escaped from the fuel rod. Some small fragments were visible and lodged behind Grid 3 preventing the rod from wiggling.
Rod No. 13 shows a grid-shaped gouge apparently due to rod vibration against Grid 3.
Grids 4 and 5:
Gouges appear on Rod No. 14 below the grid.                        Rod No. 13 shows gouges behind the grids.
Grids 6 and 7:
There is a shiny appearance behind the grids on Rod No. 13.
Bottom Nozzle:
Rod Nos. 13 and 14 are on the bottom. All other rods are 1/2 inch off the bottom. Rod No. 13, not held by grids, wiggles at the bottom.
General:
Rod No. 12 wiggles near the center due to apparent lack of grid support.
This assembly had no other indications.
Other Assemblies:
Assembly Q17 was inspected on April 24, 1986. This assembly was in                                                                 :
core location number E2 during Cycle 13. A dark blotch was found on the east face of Grids 3 and 4. The mark had a sharp edge to the                                                                   l north. No other indications were found.                                                                                            '
Fuel Assembly M17 was also inspected on April 27, 1986, because of its location next to the baffle and, therefore, its potential for baf fle jetting damage.              Small gray marks were found on Grids 2, 3, 4, and                                           5 opposite Rod No. 12 on the east face of the assembly. This assembly had no other indications. The assembly was in core location B4 during Cycle 13.
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LICENSEE EVENT REPORT (LERI TEXT CONTINUATION                               Areaovao ous ~o vio-cioa sac LITY haast 116                                                                                     taPamis gr3195 DOCatiapuessem c' LER huuGIR (6J PAGE(31
                                                                                    "=a  i    !"Ot*;i.''  l      7J.?,7 Point Beach Nuclear Plant rm a-                                               os o oo 2l6l6 8l5._
                        . _2       ,wc w m m,7,                                                0l0)2            0 l1 0 [4 or O6       f The        following fuel assemblies were inspected in detail for similar indications.
Cycle 13.         No indications were found.These assemblies had been next to baffle Fuel Assembly No.
Core Location for Cycle 13 H05 LOS                                              J2 Kll                                                I L15                                                                                                  '
L19                                              C11 L22                                              C3 M12                                               K3 M13                                              H1 M14                                               F1 M15                                               F13 M20                                                B10 M25                                                L4 M27                                                A6 M28                                                M8 M29                                                M6 M31                                                 A8 N01                                                H13 NO3                                                D2 N04                                                L10 QO3                                                J12 Q04                                                B5 Q07                                                L9 Q13                                                I2 Q15                                                E12 Q22                                                L5 Q25                                                B9 112 Summary of Fuel Assembly H14 Operating History:
Fuel assembly identification:                H14 nozzle (standard fuel assem!;1y).Prepressurized low parasitic                                                 om            desig FabricatedbyWestinghouse1{uclearFuelsDivision, Columbia Carolina.                                                                                           ,    Sguth Date received on site:                  September 30, 1976.
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PaCILITT NAME 118                                                                                         E tremf 5 8'3115 DOCK E T NUMSi m Llt ggg gygggg gg,                  i pggg gg, ve*=    " t *,;;'."  (    ? :,1:
Point Beach           Nuclear Plant rurre-          . 2.,  = we,      w,,nn                o ls [o lo [o l2 [6 l6 8j 5         0j 0l 2            0; 1 0l 5 or 0l 6 Initial inspection revealed no abnormalities.
Loaded thimble plug  into Unit device.1 Cycle 5 at core position M7.                        Insert was a Burnup during Cycle 5 was 7,768 MWD /MTU.
Loaded into Unit 1 C thimble plug device.ycle 6 at core position D7.                                  Insert was a Burnup during Cycle 6 was 10,907 MWD /MTU.
Loaded plug thimble       into Unit   1 Cycle 7 at core position F11.
device.                                                       Insert was a Burnup during Cycle 7 was 10,562 MWD /MTU.
Loaded plug thimble       into Unit    1 Cycle 13 at core position D12.
device.                                                        Insert was a Burnup during Cycle 13 was 4,219 MWD /MTU.
Total burnup:            33,465 MWD /MTU.
There was October        25, no   evidence 1979,   and May  of 2, abnormalities during inspections of 1985.
Fuel cladding damage was found as noted above on April 27                                         ,    1986.
Corrective Action:
No tionchangeswill be madein configuration during Cycleof14.         the vessel internals or flow direc-in the attached chart show the level of coolant activi~ty duriThe                                           ng chemistry re i type of activity trend are expected.
activity will be trended to monitor it and Technical Specifications allow M                       fuel failure shown during Cycle 13.
equipment to modify the flow direction i has been issued. The Public Service
                                                    .so being consulted for fiscal author-
                                                   ; ion.
i               The modification will modify the 1
flow     outside        the core baffle as the flow through the core. plate e the cross baffle plate pressure This
                                                  >w in the flow through the core baffle the control rod to vibrate.
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      '=ac *w* sesa ua muctsan nacutaTonV con esissi on LICENSEE EVENT REPORT (LER) TEXT CONTINUATION                                   ** aovEm ows =o use-w PACILITV haast 813                                                                                           EltPIRES 8'3115 DOCE ET NueeBER 120 Lgm Nuneet A let                    '
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Point Beach             Nuclear Plant             opjojojol2l6l6 8l5 rirr a i .       . ,_ u   -we ,       .,,m 0l 0l 2         ._
                                                                                                                        '0l 10 l6 or 0l                              6 Previous Similar Events:
There in the has    past. been similar damage found at the Point Beach Nuclear Plant LERs 50-266/75-18 and 85-002-00,The details of such damage can be found in U and Unit 2 LER 85-004-00. The damage           found LER supplemental report. during   these    events       was similar to that found in this similar.                                 The mechanism for the damage was also Safety Evaluation:
The following safety concerns have been evaluated: (1) tial for locations other        further fuel failure by the same mechanism in the same orThe poten-activit                     and (2) the effect of increased primary system public.y on the health and safety of plant personnel and the general There is a potential for failure of fuel rods in the same location.
However, this failure does not appear to happen quickly.
Monitoring of primary coolant activity during startup and subsequent operation any     other core   willposition.
provide indication of any failure of fuel at this or supply system vendor, Westinghouse,After consultation with the nuclear steam to modify any fuel assemblies to mitigate baffle jetting effectsthe decision ha                                       .
Unit 1 Cycle 14 core is not considered to pose a hazard to health and safety of the plant personnel or the public. The fuel assemblies in those areas which have been identified as potential locations after the completionfor this type      of situation of Cycle     14. will be thoroughly inspected h3 DOEen 364a
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