ML17213B041

Forwards Justification for Not Implementing,Prior to Core Load,Certain Control Panel Mods,Required as Result of Human Factors Engineering Branch Audit Findings

ML17213B041
Person / Time
Site:	Saint Lucie
Issue date:	02/14/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
References
L-83-74, NUDOCS 8302180313
Download: ML17213B041 (85)

Text

REGULATORY l ORMATION DISTRIBUTION 'SYS l (RIDS) y P

'AOCESAION %BR; 8302180313 DOC o DA'TE ~ 83/02/10 NOTARIZED:

NO FACIE'..5'0<<389 St Lucie Plantr Uni~t 2

Florida Power 8 Light 'Co

'AUTHyNAME AUTHOR AFFILIATION UHRIG~R,.E,'1 or ida tPower 8.Light Co, RBCIP ~ NAME

'ECIPIENT AFFILIATION EISENHUTiD ~ G ~

<<Di,vi,sion of Licensing

SUBJECT:

For wards justification for nat implementing prior lto core loadicer tain cantrol panel modsrrequit ed as eesul t of Human 'Factor s Engineer in'g ~Branch audi t findings.

DISTRIBUTION >CODE!

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Licensing 'Submittal:

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FLORIOA POWER & LIGHT COMPANY February 14, 1983 L-83-74 Office of Nuclear Reactor Regulations Attention: 'r. Darrell G. Eisenhut, Director Divison of Licensing U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Mr. Eisenhut:

Re:

St. Lucie Unit 2 Docket No. 50-389 Human Factors Engineering Branch Audit Findin s During a telephone conversation with your Human Factors Engineering Branch (HFEB) Staff on February 4, 1983, Florida Power and Light Company agreed to provide the justification for not implementing, prior to core load, certain control panel modifications, required as a result of the HFEB audit.

The attachment to this letter provides that justification.

Very truly yours, obert E. Uhrig Vice President Advanced Systems.g Technology REU/RJS/PPC/njb Attachment cc:. J.P.

O'Reil ly, Region II Harold F. Reis, Esquire 83021803i3 8302i4 PDR ADOCK 05000389'.

A PDR PEOPLE... SERVING PEOPLE

ATTACHMENT INTRODUCTION As a result of recent discussions between FP&L and the Human Factors Engineering Branch (HFEB) staff several issues of contention have arisen regarding St. Lucie Unit 2 SER Supplement No.

1 Appendix C findings A.8..7 and A.8.9 (Attachment 1).

The areas needing immediate resolution are the amount of work to be performed to satisfy the two findings and the schedule of implemen'takion of'..'theubject~work.

Florida Power

& Light has reviewed the HFEB staff request that the subject controls and displays on Control Board 8206 be rearranged to agree with normal plant convention prior.to core load..

With the current project status, any addition-al. work in the area of safeguards will delay core load and power ascension by an.

estimated 10 days.

The bases for this conclusion is contained below.

BASES Florida Power

& Light Company has completed a work scope evaluation which upon implementation will rearrange the subject displays and controls into the normal plant alphabetical/numeiical convention.

A..sketch depicting Control Board //206 (front view) showing the physical rearrangements required was provided to your Mr. Victor Nerses on January 26, 1982.

Attachment 2 provides a summary of Control Board //206 rework with detailed wire diagrams.

FP&L project personnel have coordinated with Construction, Quality Control, Start-up and Scheduling to review the overall'mpact of performing this work prior to core load.

The present project schedule indicates that if this work is required to be com-pleted prior to fuel load it will have to be scheduled to begin after the integrated safeguards test.

This test is expected to'egin in the later part of February, 1983.

The integrated safeguards test is expected to take seven days to successfully complete.

FP&L's Startup and Construction representatives have estimated that it would take ten days to complete this modification.

The effort would be worked on concurrently by Construction, Quality.Control and Startup personnel.

The work, would be performed with two ten hour shifts per day.

The number of personnel which can be utilized for this task is restricted by the limited access to internals of the subject con-trol panel.

This estimate takes into account that the instruments and controls would be calibrated and retested as soon as the construction effort is complete.

The above estimate also takes into account completion of the engineering by mid-February',

1983.

This includes preparation of drawings and documents ready for issuance with advance. copies sent to Construction and Startup.

This will insure that all work which can be performed prior to system turn-over is in fact complete (i.e. preparation of re-entries, pre-fab wire tags, pre-cut panel wires).

r 2

l l,

.7This effort would divert qualified Startup technician manpower from critical path turn-over items.

This, therefore, directly impacts the scheduled core load date.

The net overall impact on project schedule is an estimated delay of core load by a minimum of 10 work days due to delays in the area of construction, instrumentation, calibration, system turn-over and system functional testing.

This schedule delay will cause financial hardship to FPL customers due to the following:

(1) additional overheads and interest associated with the delay in the commercial operation of the unit; (2) added fuel costs and increased oil consumption resulting from the delay;,and (3) potential adverse effects in our current rate hearings.

In the last item, FPL has filed with the Florida Public Service Commission for inclusion of St. Lucie Unit No.

2 in our rate base.

Since the requested revenues

.are based on certain assumptions concerning commercial operation, any change in that date could affect the-required revenues and ad-versely affect our financial situation.

In addition to the above basis, FP&L and Essex Corporation have prepared a

task analysis and risk assessment review.

As a result of this effort, it has been determined that the possibility of operator error is low and that if the error does occur it will be recognized and corrected in less than sixty seconds.

A copy of this task analysis is attached for your review (see Attachment 3).

CONCLUSION Florida Power

& Light has demonstrated that a requirement to modify Control Panel

//206 display and control instruments per the HFEB findings prior to core load will impose significant financial hardships on this utility.

The additional safety gained by this modification is not commensurate with the financial hardships.

l.l I

ATTACHHENT NO.

1 SER Supplement No.

1 Appendix C Finding A.8.7 and A.8.9 FINDING A.8.7 There is a reversal from normal left-to-right convention of the indicator lights for the LPSI HDR A TO LOOP 2Al VALVE and the LPSI HDR A TO LOOP 2A2 VALVE on Panel 206.

(8.13)

RESPONSE

The arrangement of the'IPSI and LIPSI control displays will be reviewed and rearranged to complement the control/

display demarcation effort.

This item is scheduled for implementation prior to issuance of an operating license.

FINDING A.8.9 There are many locations in the control room where components are not arranged left-to-right and/or top-to-bottom, and are not identified in alphabetical or numerical sequence.

(8.16)

Examples:

a)

The HOLDUP TANK LEVEL INDICATORS on Panel 205 are arranged from right to left.

b)

On Panel 206, the HDR B ISOL VALVE is above the HDR A ISOL VALVE.

RESPONSE

a)

The HOLDUP TANK LEVEL INDICATORS will be rearranged to agree with left to right convention.

b)

The HDR B and HDR A ISOL VALVE key operated switches and indicating lights will be rearranged to agree with top to bottom convention.

These will be implemented prior to issuance of an operating license.

ATTACHMENT NO.

2 CONTROL BOARD 206 EQUIPMENT REWORK

SUMMARY

Total displays to be relocated Total hand controllers to be relocated Total hand switches to be relocated Total indicating lights to be relocated l2 l0 Total number of new wires to be pulled 55 Total number of wires to be reused i.e.

repulled and cut at new location 55 Total number of wires to have wire marker 349 changes

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TASK ANALYSIS PREPARED BY ESSEX CORPORATION ATTACHMENT 3

TASK ANALYSIS SLIDES SLIDE 81 This slide presents the plant. event and assumptions used in performing the task analysis ta: determine the worst case operating errors.

II C ~ g SLIDES //2 6 83 Slides 2 and '3 present a simplified version of the piping drawings depicting the arrangement of the subject flow elements and.isolation valves in question. Piping drawings along with plant'perating procedures were used to develop a description of the task demands. l r P Eg 'I 'I ~ 1 ~ ' k

HS 3615 FROM L.P. HEADERA'O LOOP 2A2 FI QKV ELEMENTS ARE UP STREAIM GF THE ISO'TIGM YVLVES'."-

2. 7REFlE ARE TVifO LPSt PUMPS.'EACH PUMP WtLf PUMP

~ = $000 GPM AT A DISCHARGE PRESSURE OF = 575 PSfG. TRFRE ARE 4 FLGW ELEMENTS, Ok~E GM EACH ~ I GVy'Flt=SSURE INJECTIGM LINE. EACH VrtIf I -IMD[CA.TE =1600 GPfVi WHFN BGTH PUMPS ARE OPERATING. THERE ARE ALARMSASSOCIATED Vi~I I H 7YiE PUMPS, . LPSI FLOM(s, AND St HEADER PRESSURES ON P ENUNCIATOR PANEL "8".

FE 3312 3G15 FROI'tl Sl TANK2A2 V-3444 LPSI PUMP 2A TO CONTAMINANT SPRAY HEADER LOY( PRESSURE HEADER n FE 3322 I.IS 3G25 FROfe'l HPSI TO ." LOOP 2A2 FROM Sl TANK2A1 TO LOOP 2A1, l FE 330G FE 3332 HS 3G35 PROD HPSI FROf>1 Sl TANK 201'.3432 LPSI PUMP 28 TO CONTAMINANT SPRAY HEADER - LOYY PRESSURE-. HEADER.;-- ~ 0 FE 3342 HS 3G45 FROM i HPSI I I l TO LOOP 201 ~ FROM Sl TANK202 i TO ~ LOOP 2 'IOfi5 RYifT >f'I !TAINMENT lp FE 3301 FROM HSPI FROM RYilT FROM CONTAINf1ENT SUMP Si LUCRE 2 li P"II 4

SLIDE //4 Slide 4 presents a tabled format of the observed symptoms detected by the operator along with the expected condition and desired response.

1 6 3 6 SYMPTOMS NORM/Hl LOW NOR Mi/HI LON CONDITIONS FOR BREAK INSIDE CNTMT INITIATINGA LOCA FROM A COLD LFG LEAK IN 2A LOOPS NORM/HI NORM/HI HIGH LON LOW HIGH NO/I OVI tiOILOEV NO/LOVE HIGH NO/LOKV NO/LOht FLOKV FLOW FLOVI FE 3336 ~ FE 33'l2 FE 3322 HOT LEG RUPTURE/LEAK L NORM NORM N RM CON DITION NORM BREAK BETVfEEN 3312 AND 3306 BREAK BETWEEN 3322 AND 3306 BREAK AFTER 3312 AND 3615 BPiEAK AFTER 3322 AND 3625 BREAK BEFORE 3306 . BR EAK BET WEEN 3306 AND COOP-2nd COMMON HDR

RESPONSE

NO RESPONSE REQUIRED ISOLATE LOOP 2A (V 3444) ISOLATE LOOP 2A (V 3444) ISOLATE LOOP 2A2 (V 3615) ISOLATE LOOP 2A1 (V 3625) 'SOLATE LOOP 2A (V.3444) ISOLATE LOOP 2A (V 3444)

I ~ C 1

SLIDE 85 Slide /!5 presents the assessment. of risk due to operator responses and the potential of a substitution error occurring for the tasks identified.

~ 4 g Ff':ILURP.fERROR. SEQVEt'~! CE LEAVINGTQ REFUELING VifATER SPILLAGE TG RB SVMP FAIL U RE/ERRO R

1. *FAILTO IDENTIFY BREAK AT COLD LEG CUES TO CORRECT PROBABILITY RESPONDING LOW LOOP FLOVf'INDICATORS 4 LPSI PUMP AMPS

+ ANNUMCIATORS

2. MISDIAGNOSE LOOP

MED,

~ LOOP FLOVf INDICATORS 2A2/2A1 BREAK-". -' '-,:=' LABELS LOCATION

3. ISOLATE INCORRECT MED LOOP o LABELS 4.

FAlL TO MONITOR LOOP FLOWS

5. FAIL'O DIAGNOSE INCORRECT LOOP ISOLATED LOW LOW"

~ CONTROL RESPONSE + PROCEDURES ~ LOOP FLOW INDICATORS < LPSI PUMP AMPS ANNUNCIATORS

6. DIAGNOSE INCORRECT LOW LOOP, BUT FAIL TO TAKE CORRECTIYE ACTION,

4'

• FAILURE/ERROR INDEPENDENT 0 DESIGN F CORRECT PANEL

I 7 I k

4 ( SLIDE 86 Slide 86 presents an overview of the subject task analysis findings which concludes that although the HPSX/LPSI arrangment for 2A2-2Al is not presented in an ascending left to right and top to bottom configuration, it is grouped symetrically and in a consistent functional arrangement. The task analysis demonstrates that the same operator.traffic pattern for the sequence of, symptoms and,responses in question would occur regardless of the subject loop orientation. Due to the nature of the event and the required operator responses, it was demonstrated I that even if a substitution error did occur it.would be detected and corrected. It is estimated that in the event of an operator making a substitution error of this nature the total response time to the original emergency condition would. be increased by less than sixty seconds.

0 o HPSI/LPSI ARRANGEMENT (2A2.2A i.2B ~.282) MAYBE MCGERATEEV CQf<~FUSfNG- ~ ViODERATE POTENTIAL, I=OR SELECTED SEQUENCES, t=GR CGNTRQL. SUBSTtTUT)GN ERRORS < LQVi~lVERV f GVI PROBABtL)TV't= FA)LURE TO QETECT ERROR OF CQNTRQt SUBSTITUTION CON t RGL. SUBSTITUTION ERROR tS REVELS)BLE ~ OVERAf t PRGBABfLITYQF UNBETECTEO/UNCORRECTEt3 EhRQR fS t GVd o PROBABILITYOF TEMPORAL ERRORS (( 60 SECONDS) [8 MQQERATE

SLIDES 8 7 & 811 Slides seven through eleven are the raw data developed as part of the subject task analysis..

PZSPONSE SEI.ECTION DIA,GRAM RSD DESCRIPTION REMARKS 0 I III41/ - Hi]h cr ~- Psych Or>> iiI .oM A~ -/s.hb 4~> l, - 33I> L~~p >II> rc (>> 5 Ue.fv( CDhki~q p J 2 Z3c Q nz Ag>p l .>>i) P)(%+ T' ~ ~ f ~

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