ML17192A533: Difference between revisions

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ffi] lJLl~"-----_.w.---~-~--------~~~-~--..J                                                                                                                              I  I  I I I I I I I I        I I  I~
8 .9                  10                                                                                                                                    68    69                                80*c;;
8 .9                  10                                                                                                                                    68    69                                80*c;;
                                                                                                                                                  ;..
                                                                                                                                                                   . X-529.                                      0}}
                                                                                                                                                                   . X-529.                                      0}}

Latest revision as of 11:12, 24 February 2020

Forwards LER 80-005/01T-0
ML17192A533
Person / Time
Site: Dresden Constellation icon.png
Issue date: 02/25/1980
From: Stephenson B
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML17192A534 List:
References
80-148, NUDOCS 8003040531
Download: ML17192A533 (3)


Text

'*"~;.~* ~

Com~o~wea1t19tison

., ~

-~ *. }.-.*~*-.:~"h-~

Dresden Nuclear Power Station R.R. #1 Morris, lllfnois 60450 Telephone 815/942-2920 February 25, 1980 BBS LTR //80~148 James G. K?ppler, Regional Director Directorate of Regulatory Operations - Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 Reportable Occurrence Report #80-5/0lT-0, Docket #050-249, is hereby submitted to your office in accordance with D~esden Nuclear Power Station Technical Specification 6.6.B.l.(a), failure* of the reactor*

protection system or other systems subject to limiting safety sys-tem settings to initiate the required protective function by the time a monitored parameter reached the setpoint specified as the limiting safety system setting in the technical specifications or failure to complete the required protective function.

B. B. Stephenson Station Superintendent Dresden Nuclear Power Station BBS:lcg Enclos*ure cc: Director of Inspection & Enforcement

,,; Director of Management Information & Program Control File/NRC

~*o 0 3ot/.-OS 3/

c:

ATTACHMENT TO LICENSEE EVENT REPORT 80-5/0lT-Q COMMONWEALTH EDISON COHPANY (CWE)

DRESDEN UNIT ILDRS 3 DOCKET fl 050-249 Quad Cities Station was requested by the NRC to check the MSIV scram limit switch s~tpoints. Several setpoints were not < 10% as required by Tech Spec. Table 3.1.1. During the current Unit 3 refuel outage, the MSIV scram limit switches were checked*. Of the sixteen

  • (16) limit switches, two (2) were found to have setpoints greater than*

10%. _J1SIV.:._3-:-2G3-::1B:.had __ one (1) limit switch with a setpoint of 12%,

1 while MSIV 3-203-2D had one (1) limit switch with a setpoint of 13.4%.

These two (2) MSIV's had a ~edundant MSIV in the line with setpoints

< 10%, and therefore this event is of minimal sa~ety significance.

This type of event has occurred before at Dresden. (See RO 1179-57/

OlT-0, Docket /1050-237).

The Namco Controls Snap-Lock Limit Switch setpoints were set by the manufacturer. The need for field calibration of the exact limit switch trip point did not seem-necessary at the time of installation.

The limit switches were readjusted and demonstrated operable. No further action is necessary;

EID

  • ~'Jc6N~OL

. "' ~ -; ;:' BLOCK: j '(i\

LICENSEE EVENT REPORT

~........_......____,...__.__...__---'16 I rl 1.1DIRIsI3.IQ)lo lo I- lo lo lo

\.Y

.1.0 (PLEASE PRINT OR TYPE ALL.QUIRED INFORMATION}

ro I- lo lo 1014 11 Ii Ii 11 101 I 10 8 9 LICENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO 57 CAT 58 lON'T OD 8

~;~~~~ ~©I 60 61 o I s- I o I o I o DOCKErNUMBER 12 I 4 I9 68 101 oI 69 2f ii

!'VENT DATE 31 sl ol@lo 74 75-12 12 Is Is REPORT.DATE lo 80I@

EVENT' DESCRIPTION AND PROBABLE CONSEQUENCES@

I While in the.S/D mode of operation the MSIV scram limit switches were checked. Of E:J:I1Ithe16 limit switches 2 were found to have setpoints> 10%. This event was of minimal jiJTI I safety significance since the MSIV' s with limit switch setpoints :::> 10% also had a re-f[IIJ I dunda~~ MSIV:'in the same line with limit switch setpoints of( 10% as. required by Tech.I

~ I Spec. Tabl.e 3.1.1. This type of event has occurred before at Dresden. (See R0/179-57/

[DJ I OlT-0, Docket 11050~237)*.

!§JI]

8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SUBCODE, COMPONENTCOOE SUB CODE SUBCODE

[ill I I IAI@ ~@ ~@ IIINIS!TfRIUI@ ~@ ~@

8 : 9 . 10 11 12 13 18 19 20.

SEQUENTIAL OCCURRENCE REPORT REVISION

(.:;\ LEA/RO CVENT YEAR REPORT NO. CODE TYPE NO.

v.:.; REPORT NUMBER I 8I 0I I23 I I o I oI s I I/! *1o ! i I LLl L=J LQJ 21 22 24 26 27 28 29 JO 31 32 ACTION FUTURE EFFECT SHUTDOWN . ~ ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT . METHOD . HOURS ~ .. SUBMITTED* FORM :;us. SUPPLIER MANUFACTURER LU@l.U@ l.Ll@ ~ I 01 ol 01 01

  • lLl@ WU L!!J@ IN I 0 11 IS I@

33 34 JS JO. . 37. 40 41. 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

jThe Namco Snap Lock limit switch setpoints were set bv the manufacturer. *The need for

IIIJ I field calibration of the *exa-Ct limit switch trfp p~fnt did not seem- necessary at the _ I*

I time of installation. The limit swftches were readjusted* and dem6ns~ratea operable.*

I No further action is necessary.

rm 8 9 80 F*ACILITY STATUS  % POWER OTHER STATUS f:iO\

\::::;:J METHOD OF DISCOVERY DISCOVERY DESCRIPTION r:;::;...

'23; till W@ 10 10 10 I@!.....__N_A_ _ __ ~@!.._E_x_t_e_r_n_a_l_S_o_u_r_c_e_-_Q.;..u_a_d_C_i_*t....i_*e_s_ _ _ _ _ ___,

8 9 10 12 11 44 45 46 80 ACTIVITY CONTENT Q\

CT";;jRELEASED OF RELEASE AMOUN~ OF ACTIVITY .. LOCATION OF RELEASE@

~ W @) ~@.._I____N_A.....___ _ _ ____, NA 8 9 10 11 44 45 80 PERSONNEL EXPOSURES Q.

m *' o, o 1 o 0 a 9 NUMBER 11 1

A TYPE 12 DESCRIPTION~

~@..___N_A__._____________________--'

13 80 PERSONNEL INJURIES r,;";\

tfil. Io I o I o l@'---__N_11_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~

NUMBER DESCRIPTION6 8 9 11 12 ' BO LOSS OF OR DAMAGE TO FACILITY 0

~ TYPE DESCRIPTION \::.;:J

~ L:J@ NA a 9 10 so

. PUBLICITY G\ NRC USE rNLY ISSUEDt,;:;'\OESCRIPTION ~ *. J "'

ffi] lJLl~"-----_.w.---~-~--------~~~-~--..J I I I I I I I I I I I I I~

8 .9 10 68 69 80*c;;

. X-529. 0