ML20041F579

From kanterella
Revision as of 09:34, 13 March 2020 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
LER 82-007/01T-0:on 820222,control Rod Pairs for Regions 7 & 28 Did Not Insert Automatically Following Manual Scram. Possibly Caused by Binding or Sticking of Control Rod Drive Mechanism.Control Rods Exercised to Eliminate Sticking
ML20041F579
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 03/08/1982
From: Fuller C
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20041F576 List:
References
LER-82-007-01T, LER-82-7-1T, TAC-55294, NUDOCS 8203170185
Download: ML20041F579 (2)


Text

NnC FORM 366 U. S. NUCLEAR REGULATMY COMMISSION 87 77)

LICENSEE EVENT REPORT CONTROL BLOCK: l 1

l l l l l _6 lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI foTT1 I cI Ol FI S I Vi 114 l@l15 0 l 0 l -l 0 lLICENSE 0 l 0NUMBERl 0 l 0 i - l 0 l 025 l@l28 4 l LICENSE 1 l 1 TYPEl 2 lJO0 l@l l ST CAT $8 l@

7 8 9 LICENSEE CODE CON'T ITIIl 7 8 3u,$lLl@l015l01010l2l6l7l@l012l2l2I812l@l0l310l8l8l2l@

60 61 DOCKET NUMBER 68 69 EVENT OATE 74 75 REPORT OATE 80 ,

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h I o i 21 I On February 22, 1982, while the reactor was subcritical with some rod arouos with- I

[TITl I drawn, it was observed that the control rod pairs for regions 7 and 28 did not insert l ITTTI I automatically following a manual scram. The rods wem subsequently inserted using l 10 i s i i normal control rod drive power. There wem no accompanying occurrences and no vio- l 101s i i lations of Technical Specifications. There was no affect on public health or safety. l 10 l 71 1 This is being reported per Fort St. Vrain Technical Specification AC 7.5.2(a)9. No I i O ia i i similar reports. 80 I

7 8 9 E CODE SUSC E COMPONENT CODE SUBCOD'E SU E ITITl IR lB l@ [XJ@ l Z l@ l C l R l D l R I V l E l@ lZ_j@ [Z,_j 20 7 8 9 10 11 12 13 18 19 SEQUENTIAL OCCURRENCE REPORT REVISION EVENT YEAR R EPORT NO. CODE TYPE N O.

LER RO O aE, yu l8l2l l-l l010l7l 1011 l lT l [---J l0 l

,,,,, 21 22 23 24 26 27 28 29 30 31 32 AK N AC N ON PL NT ME HOURS SB 1 FOR B. SUPPLIE MANUFAC RER LxJ@L.7J@

33 34 LZ.J@

35 LI_l@

36 l0101010I40 3/

LY_j@

41 W@

42

[N_J@

43 lGl0l6I3l@

44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h li 101 l Bindina or stickina of the control rod drive mechanism is the most orobable cause for l l i l i 1 I this occurmnce. Exercisino the control rods has eliminated the stickina tendencies . I m l While shutdown, the. control rods will be exercised daily. When plant operation is I lii3l l resumed, the monthly rod drop surveillance will be comoleted weekly. Unless further l 1114 I I problems develop, no further action is anticipated. I ST S  % POWER OTHER STATUS ISCO RY OISCOVERY DESCRIPTION

[.1 [5_,,j [fj @ l0l 0l 0l @ l N/A l [Aj@l Ooerator Observation l A TlVITY CO TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATIC4 OF RELEASE l5l6I [.,Zj @ LZj @ l N/A l l N/A l PERSONNEL EXPOS ES NUueeR TYPE DESCRIPTION @

l117 I l 0] Ol Ol@[Z_,j@l N/A l PERSONNE't iN;uWiES NuMsER DESCRipriON@ ',

N/A I li la l8 l9 01 01 Ol@l12 7 11 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION 11191[,,Zj@l N/A l

'o 80 7 8 S 8203170185 820308 NRC USE ONLY DESCRIPTION @ PDR ADOCK 05000267 ,

S PDR  ; ; ;;;;;;;;;;ly

[,2_[ 0,,) ISSUE @lN/A [

NAME OF PREPARER .s/M PHONE:

(303) 785-2224 5

FACSIMILE FEBRUARY 23, 1982 i

MR. JOHN T. COLLINS, REGIONAL ADMINISTRATOR REGION IV NUCLEAR REGULATORY COMMISSION 611 RYAN PLAZA DRIVE SUITE 1000 ARLINGTON, TX 76011 ON HONDAY, FEBRUARY 22, 1982, AT ABOUT 2145 HOURS, WHILE THE PLANT WAS SUBCRITICAL WITH SOME ROD GROUPS WITHDRAWN, THE REACTOR WAS MANUALLY SCRAMMED TO COMPLY WITH LCO 4.2.11. IT WAS DETERMINED THAT THE CONTROL ROD PAIRS IN REGIONS 7 AND 28 DID NOT INSERT AUTOMATICALLY DURING THE SCRAM. THESE RODS WERE SUBSEQUENTLY INSERTED WITH NORMAL CONTROL ROD DRIVE POWER.

AN INVESTIGATION IS IN PROGRESS TO IDENTIFY THE CAUSE.

THIS EVENT IS REPORTABLE PER FORT ST. VRAIN TECHNICAL SPECIFICATION AC 7.5.2(a)9 AS REPORTABLE OCCURRENCE No. 50-267/82-007/01-T-0.

PLEASE CONFIRM RECEIPT OF THIS TRANSMITTAL BY CALL BACK TO CHUCK FULLER AT (303) 785-2224, EXTENSION 270.

CHARLES H. FULLER FORT ST. VRAIN NUCLEAR GENERATING STATION PUBLIC SERVICE COMPANY OF COLORADO 16805 WELD COUNTY ROAD 19 1/2 PLATTEVILLE, COLORADO 80651-9298

.*