|
|
| Line 1: |
Line 1: |
| {{Adams
| | #REDIRECT [[05000280/LER-1981-033-03, /03L-0:on 810518,amp Reading for Heat Tracing Panel 8,circuit 6A,found Below Acceptance Criteria.Caused by Excessive Heat.Tracing Replaced & Tested.Design Change Initiated]] |
| | number = ML20010H238
| |
| | issue date = 09/15/1981
| |
| | title = /03L-0:on 810822 & 23,post-reactor Trip Specific Activity Samples of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit.Caused by Fuel Element Defect in Reactor Core Resulting in Iodine Spike
| |
| | author name = Wilson J
| |
| | author affiliation = VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
| |
| | addressee name =
| |
| | addressee affiliation = NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
| |
| | docket = 05000280
| |
| | license number =
| |
| | contact person =
| |
| | document report number = LER-81-033-03L-04, LER-81-33-3L-4, NUDOCS 8109240254
| |
| | package number = ML20010H231
| |
| | document type = LICENSEE EVENT REPORT (SEE ALSO AO RO), TEXT-SAFETY REPORT
| |
| | page count = 3
| |
| }}
| |
| {{LER
| |
| | Title = /03L-0:on 810822 & 23,post-reactor Trip Specific Activity Samples of RCS Indicated Dose Equivalent I-131 Level Greater than Tech Spec Limit.Caused by Fuel Element Defect in Reactor Core Resulting in Iodine Spike
| |
| | Plant =
| |
| | Reporting criterion =
| |
| | Power level =
| |
| | Mode =
| |
| | Docket = 05000280
| |
| | LER year = 1981
| |
| | LER number = 33
| |
| | LER revision = 3
| |
| | Event date =
| |
| | Report date =
| |
| | ENS =
| |
| | abstract =
| |
| }}
| |
| | |
| =text=
| |
| {{#Wiki_filter:,
| |
| . 4 *,* t M.' :oi U.S NUCLE AR A! OUL AT OR
| |
| * ODMM!U.:O%
| |
| ~
| |
| LICENSEE EVENT REPORT l@
| |
| 3 1
| |
| i 1
| |
| I
| |
| :osTRO.E.:tx PLEASE PRINT OR TYPE ALL REOUIREO INFORMATION E
| |
| .-l 1 Y ! A l S I'P ! Sl 1l@l0101-1010101 01 01 -l 010 l@a4 l 1 l'1 l 1 l 1 l@l l
| |
| l(B v-a >
| |
| ..CEssEE :::t ia
| |
| :s uCeNsE Nn es=
| |
| a uCENst Tv.
| |
| a e a: $1
| |
| ::N-
| |
| ,C IL @lOi5lDIO!01218!Ol@0 18 1212l811l@l0 1911 151 6l1 l@
| |
| 4 60 61 DOCKET NunagER H
| |
| En EVENT CATg 34 76 P,PORTGATg 3;
| |
| ON ANO *ROBABLE CONSIOUENCES h Iv;NTDEs:A ss v:
| |
| On August 22 and 23, post reactor trip specific a.:tivity samples of the reactor i
| |
| ;,;;, coolant system iidicated a dose equivalent I-131 level greater than the T.S.3.1.D.2 l
| |
| ,2 i ;
| |
| limit. Since the integrity of the steam generator tubes was maintained and the J
| |
| :,3i ;
| |
| activity remained below the TS-3.1.D.3 limit, the health and safety of the public 1
| |
| is ; ;
| |
| were not affected. This event is reNetable per T.S. 6.6.2.b. (2)and the specia'.
| |
| I oI7II reporting requirements of T.S.3.1.D.4.
| |
| I o se 11 I
| |
| so
| |
| $YSTEM
| |
| | |
| ==CAUSE==
| |
| CAUSE COM*.
| |
| VAtvE CCDE CCOE SusCODE COMPONE NT CODE
| |
| $UgCODE gggggDg oisi l a I c l@ W@ l c l@ I F IU l E l L lX I X lh lZ }@ l Zl h 8
| |
| 6 10 11 10 12 it 15 20 SE cuf NTI AL OCCURRENC!
| |
| REeoRT REVI510N
| |
| _EVENTvEAR REPORT NO.
| |
| CODE TY'E No.
| |
| @ **.,g a,qot'"'" "
| |
| ._ ln E* ORT 8 l 11 l-l l0l3I3l l/l 1013 l lL l l-l i l0 l | |
| =
| |
| a a
| |
| a a
| |
| a x
| |
| n
| |
| =
| |
| ACTION FUTUmg EssgC-Sa L~DC'WN AMACHMENT NP R D-'
| |
| 84 MECDM8 COMPONfNT
| |
| *aKEN ACT 8 cN CN PLANT METH00 HOURS SueulTTE:
| |
| FORM nUE.
| |
| SUPPLIER M ANU8 Act uR E R I x l@ul Z l@ I c l@
| |
| l Z I@
| |
| ,l_ 01 O ! O f I
| |
| lYl@
| |
| l Nl@
| |
| lNl@
| |
| lU l1 l2 l0 lg u
| |
| n u
| |
| aC e
| |
| n n
| |
| as a
| |
| cAusE DESCRIPTION AND CORRECTIVE ACTIONS
| |
| )o i l This event was caused by a fuel element defect in the reactor core. Post arip i
| |
| i iiJl conditions in the core enhanced the release of fission products to the reactor coolatt i,-!!
| |
| system resulting in an iodine spike. An accelerated sampling frequency and maximum l i 31 l primary purification was implemented until the RCS specific activity returned to less]
| |
| 2
| |
| .i.il than the limit of T.S.3.1.D.2.
| |
| 1 aC A
| |
| % POWE R OTH ER STATUS Ot CV Rv DISCOVERY DESCRarTION l
| |
| l 5 l lG l@ l 0 l 010 l@l N/A l
| |
| lC l@l Post Trip Chemistry Sample.
| |
| ] | |
| l ACTsvtTv CO TENT EE LEASED 08 RELE ASE AuovNT 05 ACT8vtTV LOCATION OF RELEASE i s l lZ l @ l Z l@l U/A l
| |
| l U/A l
| |
| i 4 7 BC 11 44 di aC l
| |
| *ER5oNNEL ED PCSURE1 DE 50RtPTION (c) 9 NuuBEP "vP!
| |
| i:1101010 l@l Z i@l N/A i
| |
| a s u
| |
| u u.
| |
| 50 PE R50NN E. ;NJuniE5 vuMEER
| |
| :E5:ai Ti N Ivi 10. O! Ol@l N/A i
| |
| e s n
| |
| u Ec
| |
| * 055 C8 cm O AMAGE TC rAcuTY TvF[
| |
| ?[$[ RAFT lQN 19I IZJ @ l N/A l
| |
| E a i:
| |
| sc 7'"'' ESC =i,TioNO NRC USE OW I o l l N Jh: 8109240254 8109IS 132 l
| |
| Ul*
| |
| l II IIIII'''!'I5 PDR ADOCK 05000280 5 *. "
| |
| 5: i s
| |
| EPDR a t enn (80 0 357-3184
| |
| | |
| v ATTACHMEhT 1 SURRY POWER STATION, UNIT 1 DOCKET NO:
| |
| 50-280 REPORT NO:
| |
| 81-033/03L-0 EVENT DATE:
| |
| 3-22-81 TITLE OF EVZhT:
| |
| JJQGH I-131 IN RCS 1.
| |
| | |
| ==DESCRIPTION OF EVENT==
| |
| At 0410, on August 22,1981, following a reactor trip from 100% power, the specific activity sample of the reactor coolant showed a peak dose equiva-lent I-131 level of 2.73 microcuries/ce, exceeding the T.S.3.1.D.2 limit of < l.0 microcuries/ce, The dose equivalent I-131 returned to within the T.S. limit at 2115 and remained within the limit until 0303 on August 23.
| |
| The second peak measured 1.01 nicrocuries/cc. This event is reportable per T. S. -6. 6.2. b (2) and TS-3.1.D.4.
| |
| 2.
| |
| PROBABLE CONSEQUENCES:
| |
| The limitations on the specific activity of the primary coolant ensure that the ecsulting 2 hour doses at the site boundary will not exceed an appro-priately small fraction of 10CFR 100 limits following a postulated steam generator tube rupture. Since the dose equivalent 1-131 peak was below the technical specification upper limit of 10 microcaries/ce, the reactor coolant gross activity was below the value analyzed in t he FSAR for a tube rupture and 1% failed fuel. Therefore, the health and safety of the public were not af f ect ed.
| |
| 3.
| |
| | |
| ==CAUSE OF EVENT==
| |
| The iodine spike was caused by known, yet not specifically located, fuel element defects in the reactor core. Post trip conditions enhanced the release of fission products, specifically I-131, to the reactor coolant system, causing an increase in the coolant specific activity level.
| |
| 4.
| |
| I!BIEDIATE CORRECTIVE ACTION:
| |
| The immediate corrective action was to implement the actions requirs by T.S.
| |
| table 4.1-2B.
| |
| Specifically, the level of dose equivalent 1-131 was mao! yred every 4 hours until the level returned to less than 1.0 microcurie /ce, at which time the reactor was restarted and returned to power.
| |
| 5.
| |
| SCHEDULED CORRECTIVE ACTION:
| |
| No further corrective actions will be taken at this time.
| |
| 6.
| |
| ACTIONS TAKEN TO PREVENT RECURRENCE:
| |
| The specific activity of the reactor toolant system will continue to be monitored ae required by T.S. table 4.1-2B.
| |
| 7.
| |
| GENERIC IMPLICATIONS:
| |
| There nie no generic implications associated with this event.
| |
| | |
| .y
| |
| .,. v ATTAC101ENT:
| |
| PAGE 2 of 2 REPORT NO. 81-033/03L-0 l
| |
| SUPPLEMENTAL INFORMATION:
| |
| The supplemental information required by T.S.3.1.D.4 "Special Report" is included as follows:
| |
| 1.
| |
| Resctor power history 48 hours prior to these events August 20,1981 - 24 hours at 100%
| |
| August 21,1981 - 24 hours at 100%
| |
| August 22,1981 - 0258 Reactor Trip August 22,1981 - 2248 Reactor Startup 2.
| |
| Fuel Burnup by core region - as of 2400, August 22,1981; Fuel Batch 4A: 12548 MND/MTU 6B: 12447 MWD /MTU 4C:
| |
| 25800 MUD /MTU 6C:
| |
| 22386 MWD /MTU 7A: 17848 MWD /MTU 7B:
| |
| 16943 MWD /MTU 8A: 1586 MWD /MTU 8B: 1378 MWD /MTU Cycle 6 Burnup - 1364.77 MWD /MTU 3.
| |
| Normal letdown prior to trip and dilution to criticality.
| |
| Average flow rate of letdown 116 gpm.
| |
| 4.
| |
| No De-gassing operations were performed.
| |
| 5.
| |
| Duration of I-131 spike August 22,1981 - Post Trip sample (0410) 2.73 microcuries/cc 2001 - 1.02 microcuries/cc 2115
| |
| .927 microcuries/cc August 23,1981 0303 - 1.01 microcuries/cc 0539
| |
| .769 microcuries/cc Duration approximately 18.5 hours.
| |
| }}
| |
| | |
| {{LER-Nav}}
| |