ML20205B145

Comments on 860610 Licensing Exams for Senior Reactor Operator & Reactor Operator Candidates

ML20205B145
Person / Time
Site:	Saint Lucie
Issue date:	06/13/1986
From:	Sager D FLORIDA POWER & LIGHT CO.
To:	Monroe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20205B097	List: ML20205B093 ML20205B121 ML20205B145
References
NUDOCS 8608110533
Download: ML20205B145 (16)

Text

_

POST oF F ICE BOX 128, FT. PIERCE, FLORIDA 33454 Training Ltr. Bk. #86-80 FLOHIDA POWER & LIGHT COMPANY

' ENCLOSURE 3 June 13, 1986 Ef>

c_

p, p -~

Mr. J. Monroe, Acting Chief h., ..j h Nuclear Regulatory Comission AG i-Operator Licensing Branch  ?$ 2 Q Suite 3100 c) : N in 101 Marietta Street  %

g Atlanta, Georgia 30303

SUBJECT:

Comments on St. Lucie Licensing Examinations of June 10, 1986

Dear Mr. Monroe,

Comment #1 ,

Question 1.15 asks for two reasons for Hot Leg Injection. St. Lucie materials provide one reason. Reference St. Lucie SD 24, page 34.

. Recommendation #1 Change answer key to give full credit for the answer, prevents boric acid precipitation; or accept any reasonable second reason.

Comment #2 Question 1.19 - No realistic conditions are given to support scenario, therefore making the question ambiguous and confusing.

I r Recommendation #2 l

l Delete the question.

Comment #3 Question 2.02/6.01 - no comment

(

! Recommendation #3 l

l Change answer key. Correct answer is (b) since the limitorque will automatically reset (attachment 1).

l 8608110533 860730 ADOCK 05000335 PDR V PDR PEOPLE. . SERVING PEOPLE

4 Page Two Ltr. Bk. 86-80 June 13, 1986 Comment #4 Question 2.04/6.06 - Part (a) is wrong since I-MV-02-2 is only interlocked with RCP's A2 and B1. Part (c) is no longer applicable due to PCM 028-284 (Attachment 2). Reference St. Lucie SD 8, page 18 and Figure 18.

Recommendation #4 Delete the question Comment #5 Question 2.19 - no comment Recommendation #5 Change answer to read, hydraulic accumulators (N2 ), vice H2 accumulators.

Reference St. Lucie SD 112, page 18.

Comment #6 Question 2.20/6.20 - Refers to 120 VAC Vital Instrument power. St. Lucie has both 120 VAC Vital power and 120 VAC Instrument power. Reference St.

Lucie SD 145, Figure 4.

Recommendation #6 Accept the answer key for 120 VAC Vital or the following for 120 VAC Instrument a) MCC - Battery Charger -. DC Bus + Inverter -.120 VAC Panel b) MCC -+ Maintenance Transformer -+ 120 VAC Panel Comment #7

~

Question 3.05 part (c) - states, shutdown CEA cannot be withdrawn. . . , when in fact it cannot be inserted. Reference St. Lucie SD 5, page 28.

Recommendation #7 Delete part (c)

Comment #8 Question 3.09 part (a) - the question requires a color. The correct answer l to part (a) is the light is off, as stated in the answer key.

I Recommendation #8 Delete part (a)

, l Page Three Ltr. Bk. 86-80 June 13, 1986 Coment #9 Question 3.11 - question asks for five inputs and St. Lucie only uses four (attachment 4).

Recommendation #9 Change key to delete pressurizer pressure.

Comment #10 Question 3.12/6.14 part (b) - no coment Recommendation #10 Change answer key to reflect Tech. Spec. Amendment #3 (attachment 3).

Comment #11 Question 4.02 - no comment Recommendation #11 Change answer key to accept either (c) or (e) as correct since the "B" RCO goes to the Turbine operating level and then proceeds to the Turbine Switchgear room which houses the 6.9 KV Switchgear (RCP's and Feedwater Pumps). Reference St. Lucie EP 0030141.

Comment #12 Question 4.11/7.09 - Memorizing the diesel generator load block component's does not apply to EK 3.01. EK 3 is knowledge of the basis or reasons for

... [ order and time to sequence]. Reference EPE-056, EK 3.01.

1 Recommendation #12 Accept any 4 of 8 loads from the key as correct for full credit.

Comment #13 Question 4.19 - no comment Recommendation #13 Answer key (5), Control Center Log, and answer key (6), RCO log, are the same thing. Change answer key to accept either as correct.

I

Page Four Ltr. Bk. 86-80 June 13, 1986 Comment #14 Question 5.07 - no comment Recommendation #14 Change answer key to accept either the U-1 or U-2 L.S.S.S. basis as correct.

~

Comment #15 .

Question 5.09 - part (b), question does not provide enough information to determine whether dilution or boration will be required which in turn could yield either higher or lower as correct answers; part (c), this part is irrelevant since St. Lucie does not use curve data for calculational purposes and two values are needed to determine the reactivity change and part (c) only provide one.

Recommendation #15 Delete parts (b) and (c)

Comment #16 Question 5.11 - no comment Recommendation #16 Change answer key to accept (b) as correct. Reference St. Lucie Unit 1 Tech Spec. 3.1.1.1.

Comment #17 Question 5.14 - no comment Recommendation #17 Change answer key to accept either ASI or reactor power as correct.

Reference St. Lucie Unit 1 Tech. Spec. 3.2.5.

Comment #18 Question 6.05 - not valid since St. Lucie does not use this machine (Attachment 5).

Recommendation #18 Delete the question.

l l

s r

Page Five Ltr. Bk. 86-80 June 13, 1986 Coment #19 Question 7.02 - no coment Recomendation #19 Change answer key to accept either (a) or (b) as correct since the ANPS goes to both places and (a) is physically located in (b). Reference St. Lucie EP 0030141. .

Coment #20 ,

Question 7.03 - no coment Recomendation #20 Change answer key (b) to both vice Unit 2 (attachment .

Coment #21 Question 7.17 - no coment Recommendation #21 Change answer key part (b) to accept forced circulation is the preferred mode of heat removal as a correct answer.

Coment #22 Question 7.18 - no coment Recomendation #22 Change answer key part (b) to accept trolley indexed as one correct answer (attachment 7).

Coment #23 l Question 8.08 - no coment Recomendation #23 Change answer key on parts (c) and (d) to accept either St. Lucie Unit 1 or Unit 2 L.S.S.S. basis or any reasonable accident because there is no design accident identified for St. Lucie.

l l

1 -

Page Six Ltr. Bk. 86-80 June 13, 1986 Comment #24 Question 8.14 - no comment Recommendation #24 Change answer key part (a) to accept any three from the key for full credit since St. Lucie does not normally differentiate between badge and key card.

~

Comment #25 Question 8.18 - This question seems to lock importa'nce as evidenced by the answer key. Also, the machine is interlocked from fast to slow. Reference St. Lucie Refueling Equipment Handbook.

Recomme.1dation #25 Delete the question.

a MRA

./ag4r S

ant Manager St. Lucie Plant I

i

6.1, .

l (j . PCM 028-284 REACTOR COOLANT PUNP SEAL INJECTION SYSTEM N- INTRODUCTION f .

a 2. o 4 M ,u w 2 I

-[ W This PCM provides the design for the addition of an RCP Seal Injection System as an energency back-up cooling system. This system is intended to prevent damage to the seals in the event of a total loss of'CCW to the RCP Seals

. heat exchanger or when one or more RCPs are idle during alternate pump combination run.,

The Reactor Coolant Pumps (RCPs) are provided with mechanical seals on the pump shaft. When operating at reactor coolant temperature these seals require cooling in order to prevent. damage to the seals and to prolong seal life. Currently the only means of cooling the RCP Seals is by the Component Cooling Water System (CCW) to the seal heat exchanger and the RCP cover heat barrier. The pump manufacturer has established maximum limit of 10 minutes operating time without seal cooling water. Operation of the RCP beyond this limitation requires inspection of the seals for any damage.

3b. .

. ==J A problem developed during Post Core Load Hot Functional Testing where D the RCP seals were overheating when a pump was idle during the O alternate pump combination runs. This incident required inspection of g RCP seals for any degeneration / damage. -

l This PCM implements a backup cooling water system for the RCP seals q which is intended to eliminate the need for inspection and/or prevent i damage to the seals in the event of a total loss of CCW to the RCP g seals heat exchanger or when one or more RCPs are idle during Q alternate pump combination runs.

2 This design utilizes some of the existing sections, installed as part of the temporary system, particularly the hard piped sections at each Pump.

SYSTEM DESCRIPTION l The Reactor Coolant Pump (RCP) Seal Injection is designed as an emergency back-up to the normal cooling system, i.e. Component Cooling ip Water (CCW) to the RCP seal heat exchanger. In lieu of using a heat l l '- exchanger and heat sink fluid, this system will inject cooling water l directly into the RCP seals via the lower seal cavity vent pipe. The design is essentially the same as that for St Lucie Unit 1.,

The RCP Seal Injection System is sized for a flow of 6 to 8 gym to each of the pumps. A motor operated valve (V2598) with a bypass valve (V2705) is provided in the charging line upstream of the regenerative heat exchanger. The bypass valve (V2705) will be throttled and locked in position to ensure sufficient back pressure to give a seal injection flow of 6 - 8 gym to each RCP and also to provide enough cooling water for the regenerative heat exchanger when V2598 is fully closed. Another motor operated valve (V2185) is provided. in the seal injection line.

Local flow gauges are provided in each line near the pump. This will enable positioning of the individual pump throttle valves to achieve flow balancing of the system prior to plant startup and will assure proper distribution of the seal injection flow to the four RCPs.

FOR INFORMATION ONLY a

'N

t. .

SYSTEM DESCRIPTION (cont'd) Q (, [b Operation of the seal injection system will require manual initiation from the Control Ecom. When operation of this system is needed, actor operated valve V2185 on the seal injection system connection to the charging line has to be opened.

,# - ~

g Seal injection system must be initiated as soon as possible, within

&- 1 1/2 - 2 minutes, following loss of CCW to avoid thermal shock to the seals.

.[,

In order to assure adequate flow through the regenerative heat

.; exchanger, at least two charging pumps have to be in operation

. whenever this system is used. Therefore, when only one pump is in operation it will be necessary to start a accond one.

.I S.j The system will operate in two different modes depending on the status

.j of both RCPs 2A2 and 251. Since the charging lines are connected to the BC system at the discharge of these two RCPs, the pressure h

. '4 available.in the charging line for seal injection (Delta P between RCP Q suction and charging line) will be greater when the RCPs are in

> operation than when they are down. For this reasoa less throttling in the charging line (or none) is required when the RCPs are operating.

j O The throttling on the cb.arging line will be automatic since valve

?j E V2598 vill close whenever valve V2185 is open and either one or both

}j O RCPs 2A2 and 231 are not operating. The valve, V2598, will remain p open when either one of these signals are not present. An interlock

,f! between V2596 and V2185 and the two RCPs ' ensure this.

) Q: Both valves, V2598 and V2185 are powered from the essential section of C MCC-235 which loads automatically onto the diesel generator power on

..l M=. loss of off-site power, and therefore allows the operator to operate q

G E

~

the valve remotely from the Control . Room. Diesel Generator loading is

., ,.l insignicant by this addition.

.- < QC k This modification has no effect on the DC system. The power and control for both valves is supplied by the 480 VAC MCC 2B5.

I

,I Indicating lights are provided in the Control Room to monitor the open

,) and closed position of the motor operated valves. The valve, V2185, J vill be operated from the RTGB in the Control Room. Both valves,

,' V2185 and V2598 positions are indicated in the Control Room.

3 Valves have been provided for isolation of the system for maintenance "f - purposes and to isolate the system from the RCP seal cavity vent to a1 avoid interference of this system with the present RCP starting

'y procedure. .

DESIGN BASES

,q In addition to the St Lucie Design Criteria Manual the following y additional design inputs are applicable to this PCM:

Other system design parameters are as follows:

a. Seal water injection flow per RCP = 6 to 8 gpm

. b. Pressure at the RCP seal vent connection = 50 psi above RCP suction pressure

,M c. Approximate temperature of injection fluid = 1250F gj -

d. Allowable injection fluid temperature range = 1250F to 1350F bq'LJ

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TABit 3.3-4

,._ ENGINEERED SAFETY FEAlURES ACTUATION SYSTEM INSTRUMENTATION TRIP VALUES E

g ALLOWABLE

! , filflCl OHAt UNIT TRIP SETPolNT VALUES h 1. SAIElY INJECTION (SIAS)

d. Manual (Trip Buttons) Not Applicable Not Applicable le. Containment Pressure - liigh 5 3 5 psig 5 3.6 psig

c. Pressurizer Pressure - Low > 1736 psia 3 1728 psia D

r1 .

O .l. Automatic Actuationi Logic Not Applicable Not Applicable ~

g. CONIAINHENT SPRAY (CSAS) h m 4. Manual (Trip Buttons) Not Applicable Not Applicable

" O g 2 1. Containment Pressure -- liigh-High 5 5.40 psto 5 5 50 ps19 l

! m E "T1 l '

3:p t. Automatic Actuation Logic Not Applicable Not Applicable O C ==4 W h

2 CONIAlHHENT ISOLATION (CIAS) -

a. Hasissal CIAS (Irip Buttons) Not Applicable Not Applicable o h. o y" g Safety Injection (SIAS)

Not Applicable Not Applicable z F

4 w -< t. Containment Pressure - liigh 5 3.5 psig 5 3 6 psig l a ,, .b

& Containment Railiationi - liigli i

! 2

<l.

$ 10 R/hr i 10 R/hr 6 .~t-P

?, Automatic Actuationi logia.

2 c.

Not Applicable g Not Applicable 2 3 h

4. HAlti SIEAM LINE 1501 Al10N  %

g===

i g 4. Harissal (T:ip Bisttons) Not Applicable Hot Applicable M (\

le. steasii Geiierator Pressure - 1ow e 600 psia 3 567 psia t- Co itainment Pressure - liigh 5 3.5 psig 1 3.6 psig l

.l. Automatic Actinationi Logic Not Applicable -

Not Appilcable

va

~

REACTOR REGULATING SYSTEM l

O g NE ACTOR PROGRAM unit CALCulATOa RR8 SELECTOR swiTCa g

AU O esi 8 5 T THOT

'l LOOP'A'

% TCOt D N

lE i

1. 3:= 'l

~

h TAwG CALC

_ SET CALC.

T Q

l ,

m =

C THOT

RECOROER C

OOP'S* WG4REF Qg T

f F iCOL D ^'"""*'*

j M Tun sNE PRESSURE TREF Q l

0"LO RATE D l STAGE ' Or p

l RECORDER CHANGE 1

i EC CEA I

i ._

STATUS

+ RATE

__________________3 ES O I

_j C.A.F E

.uCL,E AR CPOWE.R.m CO,, ROL A,.

CeA 1

'  : eOwER i .

l l l  ! ftEACTOR COe6 TROL g i UNIT CALCULATOR e

L________________J' FIGURE 6

I CtGkIM(d Paga 45 cf 52 ST. LUCIE UNIT 1 I OPERATT" m ="= L 2^I h*0 M EIf , @rRRb(ttVisION17 w GN

• APPENDIX D CEA TRANSFERS OVER SFP RACKS AND TRANSFER OF FLCEA PLUGS OVER THE CORE

~.

See NOTES Below == ,

The CEA transfers will be performed in the SFP, prior to the reload '

sequence. An FPL Operator will operate the spent fuel machine. CE personnel will operate all other tools associated with the CEA transfers per CE provided instructions. The sequence of transfer and applicable CEA serial numbers and SEP location coordinates are covered by Appendix A, " Initial Fuel Transfer Sequence." ,

The part length CEA plugs will be transferred in a similar manner. An FPL

. Operator will operate the refueling machine and one ton hoist. CE personnel will operate all other tools associated with these transfers. Appendix A covers sequencing, serial numbers, and core location coordinates.

NOTE The sequence of transfer and applicable CEA serial numbers and spent fuel location coordinates were completed with FPL Material Transfer Reports in accordance with AP 0010433 previous to the Cycle 7 reload. These transfers were accomplished over the

. Spent Fuel Pool.

NOTE The one ton auxiliary hoist shall be configured with a load call when handling CEA's or their plugs. Pneumatic tools should be operationally checked prior to use. In addition, manipulation of these pneumatic devices should be performed away from the core region whenever possible.

Extreme caution shall be maintained to ensure that only CEA's or their plugs are hoisted through visual observation and load cell verifications. Upon loss of visual contact with core equipment being moved, such movement shall be immediately stopped.

FOR NFORMATION ONC'

ST. LUCIE UNIT 1 qg w 0FF-NORMAL OPERATING PROCEDURE NO. 1-0250030 REVISION 4 EMERGENCY BORATION 7

0

.0 1NSTRocttons:

?0R N0MEON Om i 5.1 IMMEDIATE AUTOMATIC ACTIONS:

1. None 5.2 IMMEDIATE OPERATOR ACTIONS:

s

1. Place Mode Selector Switch in the MANUAL or BORATE position.

2. Verify V-2525 (Boron Load Control Valve) is closed.

3. Start either 1A or 1B Boric Acid Pump.

4. Close V-2510 and V-2511 (Rccire valves).

5. Open V-2514 (Zmergency borate valve).

6. If V-2514 fails to open, open either V-2508 or V-2509 (Gravity Feed Valves) and close V-2501 (VCT outlet).

NOTE If VCT level is > 5%, V-2501 will not remain closed in the AUTO position unless switch is held to CLOSED.

( '

5.3 Subsequent Actions:

1. If emergency boration is initiated due to violation of Power Dependent Insertion Limit, monitor Tavg, Tref, and reactor power while positioning the CEAs above the power dependent insertion limit such that Tavg is maintained + 2 F of Tref.

2. For other reactivity changes in Section 4.0, observe Tavg, Tref, reactor power, and CEA position as boron is added until the reactivity excursion is under control.

3. Af ter the boration, close V-2514, then return the switch to AUTO.

4. Stop the BAM Pr.mp, and return the switch to AUTO.

5. Open V-2510 and V-2511 (Recire. Valves).

6. If gravity feed was used, open V-2501 and close V-2508 or V-2509, whichever was used.

7. Return Mode Selector Switch to the desired code of operation.

8. Operation with V-2525 may be resumed if necessary.

/R4

~

Pcg3 3 cf 4 V ST. LUCIE UNIT 2 8 0FF-NORMAL PROCEDURE NO. 2-0250030, REVISION 6 EMERGENCY BORATION ,

5.o I*STaUCTIo S:

70R INFORMATION ONLY 5.1 IMMEDIATE AUTOMATIC ACTIONS:

None 5.2 IMMEDIATE OPERATOR ACTIONS:

CAUTION PRIOR TO INITIATING EMERGENCY BORATION, VERIFY THAT RCP SEAL INJECTION, IF IN USE, IS SECURED. /R6

1. Place Mode Selector Switch in the MANUAL or BORATE position.

2. Verify V-2525 (Boron Load Control Valve) is closed.

3. Start either 2A or 2B Boric Acid Pump.

4. Close V-2650 and V-2651 (Recire Valves).

5. Open V-2514 (Emergency Borate Valve).

6. If V-2514 fails to open, open either V-2508 or V-2509 (Gravity

( Feed Valves) and close V-2501 (VCT Outlet).

NOIE If VCT level is > 5%, v-2501 will not remain closed in the AUTO position unless switch is held to CLOSED.

5.3 SUBSEQUEKr ACTIONS:

1. If emergency boration is initiated due to violation of Power Dependent Insertion Limit, monitor Tavg, Tref, and reactor power while positioning the CEAs above the power dependent insertion limit such that Tavg is maintained + 2*F of Tref.

2. For other reactivity changes in Section 4.0, observe Tavg, Tref, reactor power, and CEA position as boron is added until the reactivity excustion is under control.

3. After the bo ration, close V-2514, then return the switch to AUTO. ,

4. Stop the BAM Pump and return the switch to AUTO.

5. Open V-2650 and V-2651 (Recire Valves).

( 6. If gravity feed was used, open V-2501 and close V-2508 and V-2509, whichever was used.

7. Return Mode Selector Switch to the desired mode of operation.

l 8. Operation with V-2525 may be resumed if necessary.

[

l i il All digital readouts are the same type featuring 5 digit i j jf f.I positioning with plus or minus numbering. ] j' l il

2. Cams and Limit Switches ,

Certain zones of the refueling floor are restricted to

> 0 i

refueling machine activities. To set up boundaries and modes  ;

g ,

O of operations in these zones , cams and limit switches are .'* 4 i

E i O provided to assure correct operation for the zone of operation. I ~i g- The hoist motion utilizes cams and limit switches arranged in O the hoist programmer which will be explained in detail in La ,

E another section. U LL Bridge and trolley motion use'five limit switch cam config-urations and perform the following functions:

LS-T1- allows bridge fast speed when trolley is indexed on T1 cam. The Tl cam lines up the refuel mast to the tilt machine.

I LS-TCEAZ- inhibits trolley left movement toward'upender when CEA Change Machine is not home or upender not vertical.

Also, prevents CEA Machine traverse when trolley is in CEA Change Machine zone, i LS-TCC- allows trolley fast' speed for trolley movement within ,

core area where mast is free from striking the core  :

support barrel.  !

T.9-RTM Z- inhibits bridge reverse travel when CEA Change Machine f is not in home position or upender is not vertical.

Also prevents CEA Change Machine from traverse when bridge is in CEA Change Machine Zone.

LS-BCC- allows bridge fast speed within core area when mast is clear of core support barrel.

FOR INFORMATION DE I-23 l- . ._

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