ML17352B250

LER 93-014-00:on 930902,discovered That IRM 11 & APRM Both in Bypassed Condition W/O Half Scram Being Inserted Due to Work Practices.Irm 11 Taken Out of Bypassed Condition & Individual Involved counselled.W/931001 Ltr

ML17352B250
Person / Time
Site:	Quad Cities
Issue date:	10/01/1993
From:	Bax R, Thayer D COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-93-014-04, LER-93-14-4, RLB-93-143, NUDOCS 9310120313
Download: ML17352B250 (12)

Text

ACCELERATED DOCUMENT DISTRIBUTION SYSTEM REGULBTOZ INFORMATION DISTRIBUTZOIYSTEM (RIDE)

ACCESSION NBR:9310120313 DOC.DATE: 93/10/01 NOTARIZED: NO DOCKET

~r'ACIL".50-254 Quad-Cities Station, Unit 1, Commonwealth Edison Co. 05000254 AUTH. NAME AUTHOR AFFILIATION R THAYER,D. Commonwealth Edison Co.

BAX,R.L. Commonwealth Edison Co.

RECIP.NAME RECIPIENT AFFILIATION D

SUBJECT:

LER 93-014-00:on 930902,discovered that IRM 11 a APRM both in bypassed condition w/o half scram being inserted due to work practices.IRM individual involved ll taken out of bypassed condition a counselled.W/931001 ltr.

DISTRIBUTION.'ODE: ZE22T COPIES RECEIVED:LTR i ENCL / SIZE: A TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.

NOTES: D RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-2 LA 1 1 PD3-2 PD 1 1 PATEL,C 1 1 INTERNAL: ACRS 2 2 AEOD/DOA ,1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DE/EELB 1 1 NRR/DE/EMEB 1 1 NRR/DORS/OEAB 1 1 NRR/DRCH/HHFB 1 1 NRR/DRCH/HICB 1 1 NRR/DRCH/HOLB 1 1 1 NRR/DRSS/PRPB 2 2' NRR/DRIL/RPEB 1 NRR/DSSA/SPLB 1 1 NRR/DSSA/SRXB 1 EG F L 02 1 1 RES/DSIR/EIB 1 1 RGN3 FILE 01 1 1 EXTERNAL'G&G BRYCEF J ~ H 2 2 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY F G. A 1 1 NSIC POOREFW '1 1 NUDOCS FULL TXT 1 1 D

A NOTE TO ALL"RIDS" RECIPIENTS: D PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT COYTROL DESK, ROOhI I'!-37 (EXT. 504-2065) TO ELIMINATE YOUR NAhlE Fl<Ohh DIS'I'Rll)UTION D LISTS FOR DOCUMENTS YOU DON'T NEED!

'S FULL 'TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30

0 0 I

I

t Commonwealth Edison Quad Cities Nuclear Power Station 22710 206 Avenue North Cordova, illinois 61242 Telephone 309/654-2241 RLB-93-143 October 1, 1993 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555

Reference:

Quad Cities Nuclear Power Station Docket Number 50-254, DPR-29, Unit One Enclosed is Licensee Event Report (LER)93-014, Revision 00, for Quad Cities Nuclear Power Station.

This report is submitted in accordance with the requirements of the Code of Federal Regulations, Title 10, Part 50.73(a)(2)'(i)(B). The licensee shall report any operation or condition prohibited by the plant's Technical Specification.

Respectfully, COMMONWEALTH EDISON COMPANY

'QUAD CITIES NUCLEAR POWER STATION Station Manager RLB/TB/plm Enclosure cc: J. Schrage T. Taylor INPO Records Center NRC Region III HfjP I i STMGRt1 4393.RLB 9310120313 931001 PDR.,ADOCK 05000254 S PDR

4!

LICENSEE EVENT REPORT (LER) Form Rcv. 2.0 acday Name (I) Docket Number ) Page )

Cities Unit One 0 5, 0 0 0 2 5 4 I of 0 4 t c()

f11 and APRM ff3 Were Both Bypassed Without A 1/2 Scram Being Inserted vent ale u r ) eport ate ) cr ac mcs vov ( )

Month Day Year Sequential Revision Month Day Year Facility Docket Number(s)

Number Number Names 0 5 0

0. 9 0 2 .9 3 9 3 0 1 4 0 0 1 0 0 I 9 3 0 5 0 0.0 MODE (9) Check one or more of the fonowing) (I I)

~ (b) (c) (a)(2)ov) . 1(b)

.405(a)(1)(i) 036(c)(1) O 73(a)(2)(v) .71(c) 0.405(a)(1)(ii) 036(c)(2) 0 73(a)(2)(vII) cr (Specify (10) 0 0 0.405(a)(1)(iii) 0.73(a)(2) Q 0.73(a)(2)(viii)(A) ut Abstract 1

t).4O5( )(1)(i ) 0.73(a)(2)(ii) 0.73(a)(2)(viig(B) below and in 0.405(a)(I)(v) 0.73(a)(2)(ill 0.73(a)(2)(x) Text)

LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUMBER AREA CODE ale Thayer, Ext. 3109 3 0 9 6 5 4 '- 2 2 4 1 COMPLEIE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (I ),

M A POR TO NPRDS TO NPRDS SUPPLEMENTAL REPORT EXPECIED (14) Expected Month, Day Year Submission YES (lfycs, compictc EXPECIKD SUBMISSION DATE) X 0 Date (15)

Cr,(Ltnut to I spaces, t.e., approxtmstcly t n stnglc-space typcwnucn hncs) (16)

A. ~BS TRACT:

Unit 1 was in the RUN mode at lOOX power on 09/Ol/93 at 1714 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.52177e-4 months <br /> when Average Power Range Honitor (APRH) [IG, HON] ¹3 was placed. in the bypassed condition. On 09/02/93 at approximately 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, Intermediate Range Honitor (IRH) [IG, HON] ¹ll was placed in the bypassed condition due to being subject to spiking problems, and no half scram was inserted as a result of IRH ¹ll and APRH ¹3 both being in the bypassed condition.

At 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br /> on 09/02/93, the Unit 1 Nuclear Station Operator (NSO) discovered that IRH ¹ll and APRH ¹3 were both in the bypassed condition without a half'cram being inserted.

The immediate corrective action performed by the Unit 1 NSO was taking IRH ¹ll out of the bypassed condition at 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br /> on 09/02/93.

The primary causal factor of this event is MORK PRACTICES.

LER254I93I014.WPF

0 ~k LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 ACILITYNAME (I) . DOCKER NUMBER ) LER NUMBER (6) PAGE )

Year Scrtuenttal .,;; Rcvtsron Number Number Cities Unit One 0 5 0 0 0 2 5 4 9 3 0 I, 4 0 0 2 OF 0 4 Energy Industry Idcntr canon System (EIIS) codes are rdcntr red tn the text as pO(I PLANT AND SYSTEH IDENTIFICATION:

General Electric - Boiling Water Reactor 2511 HWt rated core thermal power.

V NT IDENTIFICATION: IRH ¹ 11 and APRH ¹. 3 were both bypassed without a 1/2 scram being inserted.

A. COND ONS RIOR TO EVENT:

Unit: One Event Date:September 2, 1993 Event Time: 0825 Reactor Node: 4 Node Name: RUN Power Level.: 100X This report was initiated by Licensee Report 254'/93-014.

RUN (4) In this position the reactor system pressure is at or above 825 psig, and the reactor protection system is energized, with APRN protection and -RBN interlocks in service (excluding the 15X high flux scram).

B. DESCRIPTION OF EVENT:

On 09/01/93 (shift ¹3 on duty), Unit 1 was operating in the RUN .mode at 100X power when Average Power Range Honitor (APRN) [IG, HON] ¹3 was placed in bypass at 1714 hours0.0198 days <br />0.476 hours <br />0.00283 weeks <br />6.52177e-4 months <br /> for Instrument Haintenance personnel to perform Local Power Range Honitor (LPRH) [IG, NON] calibration.

On 09/02/93 at approximately 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> (shift ¹1 on duty), the Unit 1 Nuclear Station Operator (NSO) was taking log readings and the Shift Control Room Engineer (SCRE) was walking down the Unit 1 control. boards [CBD]. The SCRE noticed the Nuclear Work Request (NWR) tag on the Intermediate Range Honitor (IRH) [IG, HON]

bypass which is used to bypass IRN. ¹11 and several other IRH channels. From experience and the presence of the NWR tag, the SCRE was aware that IRH ¹ll was subject to spiking. The SCRE believed that IRN ¹ll should be placed in bypass, and NSO that IRN reported this situation to the Unit 1 NSO. The SCRE recommended to the

, ¹ll be placed in bypass.

¹ll The Unit 1 NSO agreed with the in bypass. The SCRE and the Unit SCRE's NSO recommendation, failed to and self-check the SCRE placed IRH 1 and notice that APRH ¹3 was already bypassed, thereby requiring a half scram to be inserted in accordance with Technical Specification Section 3. 1.

On 09/02/93 at 0825 hours0.00955 days <br />0.229 hours <br />0.00136 weeks <br />3.139125e-4 months <br /> (shift ¹2 on duty), the Unit 1 NSO discovered that IRH ¹ll and APRN ¹3 were both in the bypassed condition, without a half scram being inserted, and immediately took IRN ¹ll out of bypass. The duration of this event was approximately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />, 25 minutes.

LER254t93t014.WPF

0 LlCENSEE EVENT REPORT (LER) TEXT CONTINUATION Form Rev. 2.0 AGILITY AME (I) DOCKEP NUMBER ) I.ER NUMBER ( ) PAGE )

Year Setlucntial Rcvtston Number Number Cities Unit One 0 5 0 0 0 2 5 4 9 3 0 1 4 0 0 3 OF 0 4 EXT Energy Industry Idcnu tcatton System (EIIS) codes are tdenu ted m the text as [XX)

C. PPAREN CAUS OF EVENT:

The primary Casual Factor related to this event is WORK PRACTICES. This Casual Factor contributed to this event due to the shift ¹I NSO and SCRE failing to perform '"Self Check" before bypassing IRH ¹ll in that they did not recognize the need for inserting a half scram due to APRH ¹3 already being in the bypassed condition.

D. SAFETY NALYSIS OF EVENT:

The safety impact of this event is minimal due to:

1. the IRH/APRH .scram protection feature is provided to afford protection at low reactor power levels to assure adequate reactor power monitoring capability. The plant was not operating in a condition that this feature is designed to protect against.

2. the IRH/APRH scram protection feature has been evaluated and has been proposed to be removed from the Technical Specifications in the Technical Specification Upgrade Program. This trip feature has already been removed from the Dresden Units 2 and 3 Technical Specifications.

E. CORRECTIVE ACTIONS:

1. CORRECTIVE ACTIONS COMPLETED:

a. IRH ¹ll was taken out. of the bypassed condition.

b. The individuals involved were counselled, and the self-check program has been re-emphasized with the entire Operating department.

2. CORRECTIVE ACTIONS TO BE COMPLETED:

a. Regulatory Assurance will ensure prompt completion of the station's actions in response to SOER 92-1, Reducing the Occurrence of Plant Events Through Improved Human Performance, with respect to re-evaluating and upgrading the self-check program. (This corrective action was previously identified in Investigation Report ¹254-180-93-01700, dated 09/17/93, and is being tracked as NTS ¹254-180 01711.)

b. Regulatory Assurance will perform a follow-up review within 3-6 months of the Integrated Reporting Process human performance cause code data and, if warranted, implement a station-wide effective human error reduction program. (This corrective action was previously identified in Investigation Report ¹254-180 01700, dated 09/17/93, and is being tracked as NTS ¹254-180-93-01712.)

LER254t93t014.WPF

0 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Fotnt Rcv. 2.0 ACILKYNAME(I)~. DOCKET NUMBER ) ER NUMBER( ) PAGE )

Year Scitucntial Revision Number Number Cities Unit One ,0 5 0 0 0 '2 5 .4 9 3 0 1 4 0 0 4 OF 0 4 Energy Industry Idenu cauon System (EIIS) codes are idcnu icd in the text as iXXI

.c. Technical Specification changes have been- submitted as part of the Technical Specification Upgrade Program which will eliminate this trip feature. The approval of these changes is not expected until 1995. A separate revision will be prepared and stIbmitted to the NRC to remove the companion trip feature from the guad Cities Technical Specifications. This will provide for 'a pore timely revision. (This, corrective action was previously identified in', LER 1-93-18, and is being tracked as NTS ¹254-180-93-01801.)

F. ~EIIEN The following previous events were identified relating to IRH/APRH companion trip from 1988 to the present:

LER 88-004, Unit 2 APRH ¹4 was bypassed while IRH ¹15 was already bypassed without a half scram being inserted. Duration of the event was 18 minutes.

LER 93-018, Unit 1 APRH ¹4 was bypassed while IRH ¹16 was already bypassed without a half scram being inserted. Duration of the event was 16 minutes.

G. COHPONENT 'FAILURE DATA:

There wer'e no equipment failures directly involved in this event. This report is not NPRDS reportable.

LER254593t014.WPF

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