ML20012B650

LER 90-002-00:on 900209,Operating Surveillance LOS-TG-W1 Determined to Have Exceeded Required Testing Interval,Per Tech Spec 3/4.7.10.Caused by Personnel Error.Personnel Counseled & Ref Procedures Will Be revised.W/900309 Ltr

ML20012B650
Person / Time
Site:	LaSalle
Issue date:	03/09/1990
From:	Crowl D, Diederich G COMMONWEALTH EDISON CO.
To:	Office of Nuclear Reactor Regulation
References
LER-90-002-06, LER-90-2-6, NUDOCS 9003160033
Download: ML20012B650 (7)

Text

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'I LaSalle County Nuct:ar Station

'f RuralRoute #1, Box 220

'l v Marseilles, Illinois 61341

\ Telephone 815/357 6761 March 9, 1990 a

Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Station F1-137 Washington, D.C. 20555

Dear Sir:

Licensee Event Report #90-002-00, Docket #050-374 is being submitted to your office in accordance with 10CFR50.73(a)(2)(i).

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hl.J.Diederich station Manager LaSalle County station GJD/DAC/kg Enclosure xc: Nuclear Licensing Administrator NRC Resident Inspector NRC Region III Administrator IMPO - Records Center l.

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i LICENSEE EVENT RF, PORT (LER)

F P LO Docket thseer (2) Pane (3) ]

F'acility Name (1)

Iatalle County Station Unit 2 015101010131714 1 ofl0l6 Title (4)

Surveillance Not PerfwmJ Within Recuired Time Interval Out to Personnel Error and Procedural Inadecuacles Event Date (5) LER thster (6) Report Date (T) Other Facilities involved (8) l Month Day Year Year fy/ // Sequential //j Revision / Month Day Year Facility Neues Docket thseer(s)  ;

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/ thster 01 51 01 01 01 I I l 01 2 01 9 91 0 91 0 01012

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01 0 013 01 9 91 0 01 51 01 01 01 1 I  ;

THls REPORT IS SUBMITTED PUR$U4NT TO THE REQUIREMENTS OF 10CFR

" (cwt one or more of the followina) (11)

" 1 20.402(b) ,,,,_ 20.405(c) ,,,,,, 50.73(a)(2)(lv) 73.71(b)

POER , 20.405(a)(1)(l) ,,,,,,_ 50.36(c)(1) _ 50.73(a)(2)(v) _ 73.71(c) 20.405(a)(1)(ll) 50.36(c)(2) 50.73(a)(2)(vil) Other (Specify  !

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(10) 01 41 0 _ 20.40$(a)(1)(lli) .x ,, 50.73(a)(2)(l) _ 50.73(a)(2)(vill)(A) in Abstract  !

50.73(a)(2)(ll) 50.73(a)(2)(vill)(B) below and in

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50.73(a)(2)(lli) 50.73(a)(2)(x) Text)

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tlCENSEE CONTACT FOR THis LER (12)

TELEPHONE NUISER Name AREA CODE Don Crevi. Reoulatory Assurance extension 2e60 8 I i 15 315111-l6171611 C0pFLETE ONE LINE FOR EACH (XWFONENT FAILURE DESCRf tED IN THIS REPORT (13)

C0pFONENT MANUFAC. REPORTA8LE CAUSE SYSTEM COMPONENT MANUFAC- REPORTA8LE CAUSE SYSTEM '

TURER 10 IIPRDS TURER TO NPRDS A l l l l l l l N l l l l l l l }

0 I I I I l l l N I I I I I I I .

SUPPLE 8 ENTAL REPORT EXPECTED (14) Expected Month l Day l Year Submission

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lyes (if ves, conDiete EXPECTED SUBMISSION DATE) YlNO l ll !l '

l ABSTRACT (Limit to 1400 spaces, i.e, approximately fifteen single-space typewritten Innes) (16)

On february 9, 1990 with Unit 2 in the Run Mode (Operational Condition 1) the LaSalle Operating Surveillance LOS-TG-W1. " Turbine Weekly Surveillance," was detemined to have exceeded its required testing interval as established in Technical Specification 3/4.7.10.

On february 8,1990 at 2045 hours0.0237 days <br />0.568 hours <br />0.00338 weeks <br />7.781225e-4 months <br /> the 7 day +25% period to perfom LOS-TG-W1 as required by Technical specification 4.7.10 was exceeded. The Operating personnel inadvertently allowed the surveillance frequency '

to be exceeded without declaring the bypass valves inoperable due to inattention to detall.

Neither LaSalle Operating Procedure LOP TG-02, " Turbine Generator Startup," nor LaSalle General Procedure, LGP-1-1, 'Nomal Unit Startup," indicate any specific power level requirement which could not be exceeded prior to perfoming Loi-TG411 during a unit startup. LOP-1-1 did Indicate that the surveillance should be started at 15% power. This contributed to allowing Operating personnel miss the requirement for perfoming this surveillance prior to exceeding 25% power.

LOS-TG-W1 was successfully perfomed on february 9,1990 at 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> without further event.

Personnel involved in this event were counselled on attention to details. Procedures LGP-1-1 and LOP-TG-02 will be revised to aid to prevent recurrence of this type of event in the future.

This event is being submitted pursuant to the requirements of 10CFR50.73(a)(2)(l) due to exceeding the required surveillance test time interval.

1 L W 8 EVENT KpcRT (Lit) TEXT CaffilaaATi m Fom Rev 2.0 l pACILlif NRpE (1) DOCKET NueER (2) LER IM WER (6) Peae (3) l Voor /// Sequentia) /,/,/, Revision  ;

/// thster - T// thader j

• 11e County Statlan unit 2 015Io1010131114 910 - 01012 - 0I 0 01 2 cF 01 6  !

TEXT Energy Industry identification System (Ells) codes are identified in the test as [XX] l

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PLANT AND $YSTEM 10EWilFICA110N t

General Electric - telling teater Reactor Energy Industry identification System (Ells) codes are identified in the test as [XX).

.j A. CONDlil0N PRIOR 10 EVEW1 Unit (s): 2 Event Date: 2/9/90 Event ilme: 0000 Hours Reactor Mode (s): 1 Mode (s) ieme: Run PowerLevel(s): ,_,4,,E ,

f S. OESCRIFil0N OF EVENT $

l On February 9,1990 with Unit 2 in the Run Mode (Operational Condition 1) the LaSalle Operating Surveillance LOS-1G41, "Tuttine Weekly Surveillance,' was detemined to have escoeded its required i testing interval as estabitshed in Technical Specification 3/4.7.10.

Technical Specification 3.7.10 requires the Main Turbine (1G) [1A) bypass valves to be operable when I therms) power is greater than 295 of rated themel power and Technical Specification 4.7.10 requires the l bypass valves to be demonstrated operable at least once per 7 days by cycline each valve through at  !

least one couplete cycle of full travel.

Listed below is a chronological description of events:

I January 31,1990 Lo$-1G41 was successfully completed.

I February 6,1990 Unit 2 scranned during the performance of LaSalle Instroent Surveillance LIS-NR l

403,- ' Wit 2 Average Power Range Monitor, Rod Block Monitor and Scra Functional Test." W 1e testin0AveragePowerRangeMonitor(APRM,NR)[lG)ChannelF.ReactorProtectionSystem(RPS

- Channel B) flow biased thermal trip which Initiates 1/2 scrm, another 1/2 scrm was received from APRM Channel E (RPS Channel A). This completed the logic for a full reactor scrm (LER 374/90-001-00).

't 1 February 7,1990 LOS-1G41 was scheduled to be performed. This surveillance is not required when

! the unit is shutdown and could not be performed until the Main Turbine was operating at rated speed.

February 7,1990 Unit 2 startup was commenced in accordance with LaSalle General Procedure LOP-1-1,

- " Normal Unit Startup."

j February 8,1990 LOS-TG41 was scheduled to be critical (includes 25% grace period; this is the date the surveillance must be perfomed or the system is declared inoperable).

L1csaem EWimi IEp0RT (LER) 1Exf OWillRIAfle Fem hev 2.0 fACIL11Y MlWE (1) 00CEt1 Nupett (2) LER GRpmER (6) Peae (3)

Year // 5eguential // Revision l

// th e er /j/j/

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% 11e county Station unit 2 0 1 5 1 0 1 0 1 0 1 31 71 4 910 - 01012 - 01 0 01 3 0F 01 6 l lItxt Energy Industry identification system (tils) codes are identified in the test as [xx)  !

i S. Ot$CRIPiloll 0F EVtW1 (Continued) i I

Following shift turnover at the beginning of day shift 40700-1500 hours), a review of the l surveillance schedule and a review of LGP-l-1 was perfomed by the Unit 2 Shift Forsman ($F, l Ilcensed Senior Reactor Operator). The Unit 2 SF determined that Lo$-TG41, LOS-AP43, ' Turbine .l 1

Stop Valve Scram functional," and LOS-AP-M4, 'Tuttine Control Valve Monthly Survelliance," would need to be performed once the Main Turbine was on line, f At 1056 hours0.0122 days <br />0.293 hours <br />0.00175 weeks <br />4.01808e-4 months <br /> the reactor mode switch was placed in the Run Mode (Operational Condition 1) in l

accordance with LGP-1-1.

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At.1323 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.034015e-4 months <br /> the Main forbine was placed on line and the Main Generator was loaded to the grid, reactorpowerwassubsequentlyincreasedto235bywithdrawingcontrolrods(RD)(AA).

At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />, shift turnover took place. The same Unit 2 SF renalned on duty. The Unit 2 5F was aware that LOS-TG41, LOS-AP43 and LOS-AP-M4 needed to be performed as required by LGP-1-1, but, was not aware of the requirement to dauenstrate operability of the tuttine bypass valves prior to i reaching 25E thermal power. LOP-1-1 did not Indicate this requirement. ,

j At 1650 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.27825e-4 months <br /> control rod withdrawal was stopped for the performance of control rod scram time l testing; reactor power was 24.55 of rated thermal power at this time.

Getween 1700 and 1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />, the Unit 2 Shift Foreman had issued the surveillances to be peformed [

to the Unit 2 Nuclear Station Operator (WSo, licensed Reactor Operator).  !

-At 2015 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.667075e-4 months <br /> control rod scram time testing was completed.

At 2045 hcurs the critical time to perform LOS-1G41 was exceeded and the Unit 2 Main Turbine '

Bypass Valves became Inoperable due to exceeding their required surveillance testing time interva) per Technical Specification 4.7.10. Control rod withdrawal was reestabilshed for the purpose of ,

raising reactor power per LGP-1-1.

At 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br /> reactor power was increased to greater than 25% of rated thermal power, without performance of LOS-TG41 as required by Technical Specification 3.7.10.

At the end of the afternoon shift (1500-2300 hours) the Unit 2 SF questioned the Unit 2 NSO on whether or not the surveillance was performed. The NSO indicated that the surveillance was not done and would have to be completed on the nemt shift. .

At 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> the afternoon shift turned over to the midnight shift (2300-0700 hours). The written turnover had indicated that LOS-TG41, LOS-RP-M3 and LOS-AP-M4 needed to be performed.

At 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> on February 9, 1990, LOS-1G 41 was satisfactorily coupleted. At this time the Technical Specification timeclock was exceeded by approminately 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> and 5 minutes. (The action ,

statement of specification 3.7.10 allows 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to restore the bypass valves to operable status.)

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I L P2 ant! Evidfi REptuti (LIR) 1EHT Ciuf11NuAT10N Form nov 2.0- i Fame (3) j FACIL11Y INfE (1) 00CKE1 Nu mER (2) LER NWWER (6) __

Year /// Sequential Revision i ff fff

/// thster //)/

// thater l tda11e County statlan unit 2 0 1 5 1 0 1 0 1 0 1 31 71 4 910 - 01012 - 0I o 01 4 0F 01 6 l TEXT Energy Industry identification System (Ells) codes are identified in the text as (KK)

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8. Df.5CRIPiloN OF EVENT (Continued)

During a subsequent review of coupleted surveillances performed on February 14, 1990, it was I determined that the Limiting Condition for Operating per Technical Specification 3.7.10 was enceeded.

This event is being submitted pursuant to the requirements of 10CFR$0.73(a)(2)(l) due to enceeding the required surveillance test time interval.

C. APPARENT CAU$E OF EVENT l

the cause of this event was due to inattention to detall in that a surveillance was allowed to exceed the critical date without declaring the associated equipment inoperable.

l A contributing factor was that the surveillance could not be performed while the unit was shutdown with the Main Steam isolation valves open. $1nce the Main furtine bypass valves are not required to be operable with the reactor less than 25 power, this was not a problem and the 745ay surveillance requirement did not need to be met. However, under these conditions the surveillance must have been i done prior to exceeding 25 power (if the bypass valves wre to remain operable). ,

It is not required to complete one step of the normal unit startup procedure before continuing on with ,

the rest of the procedure. LGP.1-1 currently has a signoff step prior to the step for increasing reactor power to greater than 15 which requires verification that LOS-TG4f1 has been performed. This i

was not done untl) the midnight shift because the Turbine Generator was still being placed on line in accordance with LDP-1G-02. There is no specific guidance in LGP-1-1 that this verification means that the bypass valves must have been tested in the previous 7 days prior to exceeding 2M power.

t Other factors wre identified and listed below:

1. The Unit 2 Shift Forseln and Unit 2 NSO were not aware of the Technical Specification requirement l to perform LOS-TG4dl prior to exceeding 25 of rated thermal power, ,

2. Neither LGP-1-1, "Notaal Unit Startup," or LDP-TG-02, " Turbine GeMrator Startup," Identified the {

requirement.

3. The surveillances wre noted in the last step of LOP-TG-02 after placing the Monsture Separator ,

L Reheater's (MS) [$8), on line.

4. TheUnit2SFandExtraSROwereintheprocessofplacingfeedwaterheaters(HD)($M) inservice i_ during shift turnover from the day shift to the afternoon shift. This prevented them from actually participating in the shift (crew) briefing. ,

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i LF8mL88 EVENT REpeni (LER) TEHT CONilenahT10N Fem her 2.0 DOCKET IRpSER (2) LER 1RWe m (6) Pee Cl) I hlCILITY IllfE (1)  !

fear /jff Sequential / Revision

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Lasalle cannty station unit 2 015101010131il4 910 - 01012 - 01 0 01 5 0F 01 6 TEXT Energy ladustry Identification System (Ell 5) codes are identified in the tent as [KX]

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0. SAFETY AleALY$15 0F EVENT ),

The tJ41ne bypass system is not required to effect or support safe shutdown of the reactor or to  :

perfom in the operation of reactor safety features. The tuelne bypass system is designed to control reactor pressure as follows: .l l

a) during the reactor heatup to rated pressure while the turbine generator is being brought up to  ;

speed and synchrontred,

.b) during power opera *.lon when the reactor steam generation exceeds the transient tustne stean requirements, and

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c) during reactor cooldown.

t the allowable tolerance for perfoming surveillance activities is sufficiently restrictive to ensure  !

that the reliability associated with the surveillance activity is not significantly degraded beyond that ,

obtained from the nominal survelliance interval, too degradation was observed when the surveillance was i perfomed.  :

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l E.- CORRECTIVE ACTIONS l

At 0415 hours0.0048 days <br />0.115 hours <br />6.861772e-4 weeks <br />1.579075e-4 months <br /> on february 9,1990 LOS-TG41 was satisfactorily completed. .

Personnel involved were counselled on this event. ,

LGP-1-1, LGP-1-3, "Startup from Hot Standby to Power Operations," and LOP-TG-42 will be revised to J include the requirement to perfo m LOS-TG 41 prior to exceeding 25% power per Technical Specifications. J Operating procedures such as startup of the Off-Gas system will be reviewed to detemine if there Is any other Technical Specificatien related equipment where a slallar problem could occur. Action item Record ]

(AIR) 374-200-90-00001 will be issueJ to track the completion of this corre:tive action. .j All licensed operators will be tallgated on this event. Emphasis will be placed on the need to perfom  !

all surveillances by the critical date or declare associated equipment inoperable and take the associated actions. AIR 374-200-90-00002 will be Issued to track the completion of this corrective action.

'The LaSalle Aeninistrative Procedure LAP-1600-2, " Conduct of Operations," will be revised to require a discussion of any critical surveillances due in shift briefings. AIR 314-200-90-00003 will be issued to track the completion of this corrective action.

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LVM53 EWEdif REPORT (LER) TERT CiuffitalAf tm Form her 2.0 LER th5GER (6) Paas (3)

'PACillif II W (1) DOCKET tR5GER (2)

Year / Sequential g/// Ilusher g/ hevision

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l Lasalle County station unit 2 015Io1010131714 910 - 01012 - 01 0 01 6 0F 01 6 TEXT Energy industry identification System (Ell 5) codes are identified in the tent as (XX) l l

i F. PREVIOUS EVENTS  !

LER Number Title i

373/M-06140 Failure to Run 1A Olesel Generator Within I Hour Timectock ,

373/95-069 4 0 Missed Fire Protection Surveillance by Mechanical Maintenance Department l 373/M-003 00 Missed Surveillance on heactor Water pil Due to Personnel Error l 373/E 406-00 Unit 1 Reactor Water Conductivity Missed Sample Due to Misunderstanding the j Technical Specification nequirements 373/N-02640 Frequency of Prime y Contalament Air Lock Leakage Rate Test Enceeded 373 4 7-000-00 Missed off Gas Hydrogen Sample Due to Personnel Error 373/87-019 4 0 Failure to Cycle Interundlate Control hads During Surveillance Due to Personnel Error 374/N41040 Failure to Perforn Surveillance on had Worth Minlalzer and mod Serpence control System Durin0 Pouer noduction 374/80 4 04-00 Missed Technical Specification Surveillance Due to Personnel Error 374/08-006-00 Missed Loose Parts Monitor Survelliance Due to Personnel Error G. CopFONENT FAILURE DATA hot appilcable.

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