ML20006E777

Forwards Review of Technical Content of 891218 Senior Reactor Operator Exam

ML20006E777
Person / Time
Site:	Crystal River
Issue date:	12/19/1989
From:	Kelly L FLORIDA POWER CORP.
To:	Casto C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20006E756	List: ML20006E777
References
TRA89-0106, TRA89-106, NUDOCS 9002260341
Download: ML20006E777 (13)

Text

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ENCLOSURE 3 i-i D. - C ORPOR ATIO N !

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• ' December 19, 1989 m- (TRA89 0106

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M - Mr. Chuck Casto-l Operator. Licensing Section, Region-1I:

U. S.: Nuclear Regulatory Commission-

. Suite 2900 l101:.Marietta Street, NW

Atlanta, GA 30323

Subject:

Crystal' River Unit 3 1 December. 18,:1989 - NRC Issued License Exams

Dear Mr. Casto:

'lAs-per the: current practice for. examination reviews after NRC issued-operator-

, examinations,, please- find- enclosed our review of'the : technical content of the-December 18,-1989,- Senior Reactor Operator Examination given at Crystal River

Unit 3.- .We are including our comments and recommended action for each quest. ion under review.1

.If youidesire':any further information, please contact Mr.'Johnie Smith,: Nuclear. ,

OperationsLTraining Supervisor,'at (904) 795-0504,- ext.107. Thank you for your l attention;to.this very important matter. .

3 a

Very _truly yours,

-Lar . Kelleyc . .

, m LDirector, Nuclear Operations Training 1

JGS/LCK/lb

-Attachment.

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.xc: E. M. Good I l

g. ' ~ -NUCLEAR OPERATIONS TRAINING DEPARTMENT: 8200 West Seven Rivers Drive

• Crystal River, Florida 32629 A Florida Progress Company l 29002260341'900202 Db 9 iPDR' ADOCK 05000302 M t L iM . rpret. M i

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EMERGENCY AND ABNORMAL PLANT EVOLUTIONS QUESTION #-17 ,

The referenced procedure and lesson plan require that the RCP's be started in

. region 4 by bypassing start interlocks (except motor electric faults) and permanently damaging the pumps if necessary. The exam question infers that there is guidance for tripping the pump under certain conditions when in this

< region, when in fact our procedures and lessons give no such guidance. From

' the referenced lesson plan there is guidance for considering tripping the pumps.for motor / electrical faults, but this is in reference to region 3. It is understood that for region 4 the pumps will be sacrificed to attempt core-cooling. Therefore the question has no correct response. See reference 1.

-RECOMMENDATION: Delete question from exam.  ;

PLANT SYSTEMS AND PLANT-WIDE GENERIC RESPONSIBILITIES QUESTION # 11 1.- This question appears to reference a Lesson plan that is out of date. Refer to ROT-4-15, Revision 4 or later. There have been hardware changes to the-circuit for bypassing MFW pumps. This modification was made during the refueling outage in 1987. It now requires that the RPS be in shutdown bypass I in order for the loss of run signal for the two pumps to be blocked. This would make response 'A' correct.

There is bistable within the RPS system that allows bypassing the loss of four RCPs EFIC start signal. This bistable-trips at 10% increasing, resetting the circuit and resets at 5% decreasing allowing the operator to bypass the circuit. To make this response incorrect the candidate must assume that a plant startup was in progress and that the 10% setpoint had not been reached.

This would make response 'D' correct.

Based on these facts there appear to be three correct responses to the question. See reference 2.

RECOMMENDATION: From the way the choices are worded 'C' appears to be the most correct response and therefore should have been c l picked by the candidates. But the wording of the question l' is confusing and increases the chances for an incorrect response. Revise exam bank to ensure accuracy with regard to future exams.

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' PLANT SYSTEMS AND PLANT-WIDE GENERIC RESPONSIBILITIES QUESTION # 25

.This question requires that the student memorize information that is readily available to him on the Main Control Board. While we acknowledge that a

-thorough understanding of the operation of the system is necessary, this

.should not include details of specific block loading. In the event that the ,

equipment-in question did not start as required the operator would take remedial action as soon as he observed the abnormal indication to ensure operation of-those components. Therefore, requiring this level of knowledge does not improve the operators ability to operate the plant.

RECOMMENDATION: Delete question from exam.

PLANT SYSTEMS AND PLANT-WIDE GENERIC RESPONSIBILITIES QUESTION # 36 A portion of the reference indicated on the key is incorrect. RSP-101 section 3.2.13 pg 10 does not support the required information, concerning the administrative dose limits- for CR-3. The correct reference is HPP-300, Administrative Dose Limits and Dose Guidelines, section 2.4.3.c pg 5.

Three of the Key responses (c, e, g) are incorrect. The administrative dose limit for Yearly Whole Body without management approval is 4 rem /yr, .not 5 rem /yr. The limit for Quarterly Extremities is 18 rem /qtr, not 18.75 rem /qtr.

The limit for Quarterly Skin of Whole Body is 7 rem /qtr, not 7.5 rem /qtr. See the above mentioned reference for the correct response. See reference 3.

RECOMMENDATION: Revise answer key per above.

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. N EXPLANATION OF STEPS .:

'Q [P-290 .INADE00 ATE CORE C0OLING .]

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.N0TE : Beginning with step 3.15 the procedure enters the section addressing Region 3, clad temperatures greater than 1400'F. It is 3 apparent at this )oint that the ES systems are not cooling the

= core. The steps:wiich follow are trying to establish.the OTSGs as j

an active heat sink with forced RC flow. 1 h .3.15 If the start permissives for the RCPs can be met then start one pump in each loo) to pump any water in the-steam generators into l the core, even tiough adequate NPSH is-not available. This- action {

, will also sweep the steam void mixture-that exists through the q core and steam generators. However, ICC conditions are not so  :

'J severe as to justify. permanently. damaging RCPs. Consequently, 1 normal RCP interlocks on cooling water and seal injection, as well l as overload should not be overridden at this time. However, once I an RCP is started, .it should not be tripped for other than motor j

/ electrical faults unless another RCP is started in the same loop. . 1 If' starting the RCP does not help cool the core, the RC will heat  !

up.into Region 4. Region 4 allows bypassing the RCP start J interlocks (except motor electric faults) and permanently damaging ,

the RCPs if necessary. Therefore, if the RC is heating up into .

l q Region 4, there is no reason to trip the RCP./If the RC remains in g1 Region 3 or returns to Region 2, then running the RCP may be helping cool the core. Therefore, an RCP:should not be tripped. To ensure the OTSGs are capable of removing heat in this situation (i.e., boiler-condenser. cooling), raise their levels to 95% and do this manually to ensure continuous: flow.

3.16 This step-is establishing a 100'F delta T between the RCS and the OTSGs. Maintaining this-differential temperature will periodically

require operator attention to adjust-valve position, as the RCS L cools and depressurizes. The pressure difference between the RCS

and the OTSG will ensure that the OTSG's-are available as heat  !

sinks and will provide sufficient thermal driving head for Natural Circulation if necessary.

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ROT-5-19 22 l

l 7 ,( 3.0 FOLLOW-UP ACY1MS (CONT *D) '

!] DETAILS  !

ACTIONS g l The following steps are for incore TEMPS in region 3.

3,15 IE RCPs are available, o RCPs are available when RCP .

Igli start 1 RCP/ loop start permissives are met,  ;

S Q manually control OTSG 1evels at 95%. o Select all 4 EFIC control '

. valves to manual and control level at 95%.- -

3.16 Maintain OTSG Tsat 100'F Lower OTSG PRESS using TBVs below Tsat for existing or ADVs. 1 RC PRESS until OTSG Heat removal is established. ,

3.17 Open all high point vents. Open:

_ RCV-157 RCV-158 RCV-159 RCV-160 RCV-163 RCV-164.

3.18 _ Notify Chemistry to begin Notify Chemistry to refer to  !

monitoring RB atmosphere EM-308, Post Accident Sampling H2 level. of the RB Atmosphere.

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. ,o 3.0 FOLLOW-UP M ilGIts (ColG'D1 I

ACTIONS DETAILS l

11 subcooled Nat Cire is established, i "E N the PZR vents should be used to depressurize I the RCS to ensure a slow rate of depressurization. -l 4

3.23 IE incore TEMPS enter See Enclosure 1 for ICC regions.

region 2.  :

IEN GO TO Step 3.11  ;

in this procedure.

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The following steps are for incore TEMPS in region 4.

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t 3.24 IE incore TEMPS enter Ensure Open:

\ region 4,  !

18 3 ensure PORV is open, -

RCV-10 RCV-Il  ;

AND all RCS high point vents are open. RCV-157 RCV-158 _

RCV 159 RCV-160 RCV-163 RCV-164.

3.25 IE RCP power is available, Bypass start permissives using IM H bypass RCP start key 36 in the SS00 key locker, permissives,'

AtEl start all RCPs.

3.26 Manually control OTSG Select all 4 EFIC control levels at 95%. valves to manual.

ROT-5-19 27

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L.. . i b EP-1 COOLING NOTE : A slow rate of depressurization will minimize the possibility of steam formation in hot portions of the RCS (Head Region) which could inhibit Natural Circulation by blocking the ' Candy Cane" Region .

Step 3.23 With the Actions taken up to this point, the RCS Temp / Press profile must move in one of two directions. .Either the actions i will prove to be effective and the P/T trace will enter Region 2 t or conditions will continue to degrade and the P/T trace will enter Region 4. If effective core cooling has been established,  ;

this step directs the operator to step 3.11 to ensure that cooling )

is maintained. i i

Step 3.24 This step is the beginning of the second branch point referenced from Step 3.10 earlier in this procedure. The following steps give >

guidance if the P-T point of SPDS has entered Region 4, clad temperatures > 1800'F. Reduced RCS Pressure allows LPI and CF to  !

become available.  :

i Step 3.25 Refer. to earlier discussions about operating philosophy.

Conditions are now severe enough in the core that the possibility of RCP damage is considered secondary to core integrity.

Step 3.26 This step serves the same function as step 3.15, that is, control e the flow of EFW in manual to maintain uninterrupted flow, thereby J maximizing the height of the thermal center.

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i ROT-5 19 28 l

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3.0 FoltoW-up ACTIONS (CONT'D1

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AC.TIONS DETAILS ,

g 11011 E subcooled Nat Circ is established,  !

i ItiD[ the PZR vents should be used to depressurize the RCS to ensure a slow rate of depressurization.

3.23 E incore TEMPS enter See Enclosure 1 for ICC regions. I r ion 2, '

GO TO Step 3.11 in this procedure.

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The following steps are for incore TEMPS in region 4.

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3.24 ' E incore TEMPS enter Ensure Open:

, region 4, Itui ensure PORY is open, RCV-10 _ RCV-Il f

&ND all RCS high point vents are open. RCV 157 RCV-158 RCV-159 RCV-160 1

RCV-163 RCV 164.  ;

J 3.25 E RCP power is available, Bypass start permissives using ,

ItiDi bypass RCP start key 36 in the 5S00 key locker, l l

permissives, AND start all RCPs. l l

3.26 Manually control OTSG Select all 4 EFIC control levels at 95%. valves to manual. i 1 j c.

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EP-290 REV. 8 PAGE 25 of 33 ICC I

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EFIC channels also receive inputs frun NI/RPS ard ES as follows

.l * 'Ihe running status of main feedwater punps. A loss of both  ;

l main feedwater punps will occur when both are tri; ped, reactor l- l l power >20% and RPS is tot in shutdown bypass. ,

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• 'Ibe runnirn status of RC punps frun their power monitors. l l- Reactor power >10% will instate this trip function based on a l loss of all RC punps. Reactor power <5%,is the power level at l which this signal may be bypassed, interrupting EFW initiation l on loss of all RC punps. -

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• RPS channel irVrnt in channel bypass. 'Ihis interlock is  !

l aa$wiated with placirg an EFIC channel in maintenance bypass. f I

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• For channels A ard B of EFIC only; receive input signals frun l the Engineered Safeguards Actuation Systan (ESAS). If both l the A and B ESAS HPI channels are actuated, both trains of EFW

.l will be initiated. ,

t Durirg plant operation, the four EFIC systan monitoring channels j constantly monitor pressure, level, NI/RPS and ES input signals to .

determine if a condition has developed that requires the initiation ,

of EFW.

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'Ibe analog signals are ocmpared to predetermined setpoints in r

bistable relays and an EFW initiate signal will be issued if a l RCTI'-4-15 14 l

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i-f' l 7. With the system in marmal (out-of-limit condition still l present), the operator may m-actuate the autmatic logic by l depressing either initiate push-button for the respective train.

Since all 4 EFIC channels monitor the same parameters, they should all issue initiate commands at the same time ard both DW trains l should be started anytime DM is initiated. It is, however, l conceivable that only two or three of the EFIC channels could sense l a condition that warrants an initiating signal. Under these l conditions only the train where the trip module logics are satisfied, l as shown on Figure 3, will be actuated. 'Iherefore, during plant l evolutions such as surveillance testing or maintenance sme conditions l may srise where only one train of EPIC will be actuated. In addition, l- the design of the Trip Module allcws for a manual trip to be instated l even though a channel may be in maintenarce bypass or shutdown bypass.

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'Ihe EFIC system will auttnatically initiate DW upon detection of {

any of the following corditions: ,

• Loss of both main feedwater punps, ard RPS NOT in Shutdown Bypass,

• Iow level (<6") in either OISG for >2 seconds,

• Loss of all RCP's, ,

• Low pressure (<600 PSIG) in either OrSG,

• HPI actuation on bqth A and B ESAS channels, i

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the " RESET" button (Figure 9) for the respective DW train. 'Ihis action will clear the trip be and reset all control logic.

I After the DM actuation is reset, the DW punps may be stopped and i j

the systan placed back into its standby node of cperation. -i l

Regardless of whether the system has been placed in marmal or reset f the DV f1w control valves will continue to modulate flow in response to level demands until they are' separately reset. In order j i

to place the DM flew control valves back in their stardby mode, L-i the Vector Enable signal to them must be reset. 'Ihis function is '!

performed in the "A" and "B" EPIC cabinets by placing the "l%N" - l l "RESEr" toggle switch on the vector enable trip nodules (EF200ZY(A) j u

l and D'200ZY(B)) to the " RESET" position. 'Ihe switch is spring  ;

returned to the center position. If the module has reset, the two lights on the module will step blinking but remain dimly lit.

Additionally, r=*r that the flow signal must be below 10%; refer g to section 2.2.1 for details. I i

H 'Ihe control valve H/A stations may be placed in " HAND" at any time ard do B2r require that the system be placed in manual or reset.

2.2.3.2 Shutdown Bypassing .

EFIC incorporated several bypass functions into its control logic Y

to allow a normal plant shutdown ard cooldown. During a plant shutdown, the DM initiation based on loss of both main feodwater punps is bypassed when the RPS is placed in Shutdown Bypass. 'Ibe

. logic also requires that reactor power be below 20%. Since the RPS ROT-4-15 29

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L cannot be placed in shutdown bypass with the reactor operating, l

, that part of the logic normally has no effect on the b 3passing of the EFW actuatim.

Se EFW initiation had on low OPSG pressure may be bypassed When ,

main steam pressure in EITHER OPSG dd:reases below 750 PSIG and .

nust be bypassed before pressure goes below 600 PSIG. h is bypass ,

i can be initiated frm the main control board PSA panel by depressing  !

the Channel A, B,' C, and D push buttons (Figure 10) or on the

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" INITIATE"- (Figure 12) modules in each EFIC cabinet by momentarily ,

i placing the SG BYPASS /RESEr toggle cwitch in the BYPASS (up) position.  ;

he bypass will be autmatically removed durinj the s*=agant plant .,

startup when both OTSG's outlet pressure increases above 750 PSIG.

a t B e EFW initiation based on loss of all 4 RCP's may be bypaccai when reactor power is below 5%, and must be bypaccai prior to stopping the last RCP. Bis bypass may be done only at the EFIC cabinets by momentarily placing the "RCP BYPASS /ht:r" toggle switch, -

located in each EPIC cabinet on the " Initiate" module, in the "B) pass" (Up) position, mis bypass will be autenatically removed when reactor power increases above 10%.

2e EFW initiation based on low OISG level cannot be bypassed.

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} ;c ~ -f b) If the dose history is not complete. -i.e.,

NRC Fora 4 l incomplete or uonexistent, and the inception quarter dose has been estimated by the individual, then the administrative limits are: {

L, 0.900 roms per quarter whole body '

7.000 reas per quarter skin of the whole body- i 18.00 reas per quarter estremity ~1

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4.000 reas per year whole body i i

5(N-18) reas total for lifetime whole body.

i c) If the dose history for the individual is complete, then  !

the administrative limits are

(07079)

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• 1.250 reas per quarter whole body -

7.000 reas per quarter skin of the whole body 18.00 reas per quarter estremities

• • 4.000 reas per year 5(N-18) ress total for lifetime-

• The quarterly administrative limit say. be increased to  !

2.500 ress with the Director Nuclear Plant Operations i y

approval, provided the annual dose does not exceed 5.000 l l

reas and-the total lifetime dose does not exceed 5(N-18) reas. (See ESP-314 and NPP-314.) (07437) I

• • The 4.000 reas annual limit may be increased to 5.000

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L reas by direction of the Director, Nuclear Plant Opera-tions.

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Rev. 00 Pave 5

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1 ENCLOSURE 4 RESOLUTION OF FACILITY COMMENTS ,

Facility Cossent Question #17 }

Conment not accepted. . The facility procedure exempts motor protection interlocks from bypassino to start an RCP. In addition, the bypass itself t does not remove motor protection interlocks. The licensee should review the procedure to ensure that it is consistent with their operational i, philosophy.

. 1 Facility Conment Question ill Comment accepted. Answer key modified to delete the question.

Facility Comment Question #25. -

Connent not accepted. This question is supported by NUREG-1122. Knowledge and Abilities Cataloc for PWRs. , ,

Facility Conment Question f36.

Comment accepted. Answer key modified as recommended.

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