ML20235T749

Forwards Util Comments Re Exam Rept 50-261/OL-87-01 on 870811-14.Comments Made by Listed Instructors from Plant Training Unit

ML20235T749
Person / Time
Site:	Robinson
Issue date:	08/14/1987
From:	Morgan R CAROLINA POWER & LIGHT CO.
To:	Munro J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20235T651	List: ML20235T648 ML20235T689 ML20235T749
References
NO-87R179, NUDOCS 8710130198
Download: ML20235T749 (22)

Text

- _ - _ _ .-

ENCLOSURE 3 CP&L l Carolina Power & Light Company l

l H. B. ROBINSON SEG PLANT j POST OFFICE B0X-790 1 HARTSVILLE, SOUTH CAROLINA 29550

]

August 14, 1987 File: NTS-4208(F) Serial: NO-87R179 )

i Mr. John Munro, Acting Chief i Operator Licensing Section J U. S. Nuclear Regulatory Commission, Region II 1 Suite 2900 101 Marietta Street, N.W.

Atlanta, Georgia 30323

SUBJECT:

Reactor Operator Written Examinations

Dear Mr. Munro:

On August 11, 1987, Mr. C. A. Casto and Mr. M. E. Ernstes of the USNRC administered written reactor operator examinations at H. B. Robinson. Enclosed, please find coninents for the examination.

Instructors from the H. B. Robinson Training Unit reviewed the examinations for I comments. They included: )

i R. S. Allen i A. McGilvray D. A. Heal D. K. Seagle V. L. Smith If you have any questions, please contact me or Mr. C. A. Bethea.

1 Very truly yours, I

1. 7 W B710130198 07 g y R. E. Morgan PDR ADOCK O PDR General Manager l V H. B. Robinson SEG Plant RSA:eaw Enclosures (2)

. . _ _ _ _ _ __ _ _ _ _ _ _ _ _ . - _ _ ._-______-_______a

7

.1- w ,

Enclosure 1 To Serial: NO-87R179 L

NRC EXAMINATION COMENTS )

H. B. ROBINSON R0 CLASS 87-1 EXAMINATION DATE - AUGUST 11, 1987  ;

i

1. Section 2 Question '2.01, Part b Recomend change answer' from "the holdup tank"' to "the VCT"..

Reference:

Plant Drawing #5379-685, Sheet 1, Note 16 I Question 2.14. Part b Recomend accepting any given pressure between 600 - 700 psig. Minimum 600 .

psig and maximum 700 psig. q

Reference:

SD-002, Page 23 Section 4.6, Minimum of Pressure 600 psig SD-002, Page 20, Section 3.6, SI Accumulator Relief 700 #

Question 2.15 Recomend change LCV-1150 to LCV-115B (typo on answer key). Also accept valve number CVC-358 (manual bypass for 1158).

Reference:

A0P-002, Page 4, Section 3.1.1 Question 2.16 Recomend accepting minimum flow as answer. " Blocked for-30 seconds after-starting" is a condition of the trip signal and should not be required as part of answer.

Reference:

SD-027, Page 14 and PLS-013, Page 1. Section 1.4 Question 2.20 Recomend also accept "no automatic actions". Question could be interpreted l based on current plant conditions, which has the valve selected to the plant vent.

j-

Reference:

Caution Tag Log, Tag #561 l

l 1 of 3 l

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._.m.____ _ _.__.- _ m -

-m -

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2. Section 3 Question 3.14 Recomend also accept the 4160 room and the D/S generator engine enclosure L since that is where the remote dedicated shutdown control panel and engine control panel are located. The question asked for location and not the name of the panel.

l

Reference:

OP-602, Pages 24 and 28 Question 3.15 Recommend also accept for answer:

S-signal or SI signal and t' P-signal or manual spray actuation (R-11 and R M is 0.K.)

Reference:

Logic Drawing #CP-300-5379-2759, Sheet 8 of 18 " Safeguard Actuation Signals" Question 3.16 Recomend acceptable answer be changed to " heats incoming coolant (0.5) to l saturation pressure (0.5)". This answer is taught in our R0 Program and the NRC reference (Westinghouse PWR System Manual) is not available at the Facility.

Reference:

RCS-H0-1, Session 5, Page 4 Question 3.17

{

Recommend delete "a three-way solenoid valve" from required answer. The I question asks how the trip open feature is accomplished, not the physical '

components used. ,

Question 3.18 Recommend change "SR reactor tip" to "deenergize source range high voltage". This is automatic but would have no setpoint. P-10 blocks the source range voltage from being reinstated.

Reference:

Logic Drawing #CP-300-5379-2754 " Nuclear Instruction Trip Signals 3 and Manual Trip" l

2 of 3 1 1

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Question 3.19 Recomend changing answer to "RHR system relief valve, opens at 600 psig".

The relief valve is the overpressure protective device downstream of the RHR pumps. The RCS/RHR system interlock only applies when initially pressurizing the system. The RHR system does not isolate on high RCS pressure. )

l

Reference:

SD-003, Page 8 System Drawing #5379-1484 (RHR System)  ;

Question 3.22, Part a i

From plant operating experience recomend changing answer to " level decreases due to the feed flow decrease on lower steam flow input resulting in a p7 ant i trip". i

Reference:

H. B. Robinson LER #85-017 j

, 3. Section 4 I

Question 4.13 Recomend changing answer to " containment pressure greater than 4 psig".

EPP-001 does not define adverse containment conditions. Question asks for  !

two conditions, therefore, candidates may have given two responses when only I l one condition exist. Recomend giving full credit if response of CV pressure l greater than 4 psig is given l I

Reference:

OMM-022, Page 10 Question 4.15 l

Recomend accepting either 4160V switchgear room or fire protection building as acceptable answers. The candidates attended operator requalification training and received information on the procedure change.

Reference:

A0P-004, Page 3, Revision 0 and Revision 1 i l

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( 3.0 INSTRUMENTATION AND CONTROLS (Continued)

CONTROLLER NO. WINDOW NAME WINDOW NO.

FIC-658 SI PHP COOLING WTR LO FLOW APP-002-37 ,

i Breakers CONT SRY PMP A/B MOTOR APP-002-41 OVERLOAD l i PT-929/PT-931 ACCUM TK C HI/LO PRESS APP-002-44 Breakers lSI PMPS MOTOR OVRLOAD/ TRIP APP-002-45 i

PC-951B, 953B, i CONTAINMENT HI OR HI-HI APP-003-36 955B, 951A, 953A, PRESS ]

950, 952, 954, 955A TS-A2 SAFETY INJ PUMP AREA TEMP APP-004-24 l HI 4

3.6 Relief Valve Setpoints .

VALVE NO. LOCATION SETPOINT SI-857A & B Boron Injection He.ader 1750 psig 1 52 psig SI-858A, B, C Safety Injection 700psigi21psigi(

Accumulator A, B, & C SI-859 High Head Safety Injection 1750 psig 1 52 psig Test Line SI-871 Containment Spray Pump 200 psig 1 6 psig Suction l I

SI-872 Spray Additive Tank 270 psig i 8 psig 3.7 Instrument setpoints l

INSTRUMENT NO. FUNCTION SETPOINT 1

PCV-937 Accumulator Nitrogen Supply 675 psig 110 psi a Regulator

• Accumulator Level High Alarm 78%f+0, -2)% l Low Alarm 64%(+2, -0)% 1

\

SD-002 Rev. 4 Pace 20 of la

>- . RGFERGWE FO P~ 2 I4 b g

4.0 SYSTEM AND COMPONENT DESIGN (Continued) 4.4 Containment Spray Pumps Manufacturer Worthington Corp.

Number 2 Model WT Type Horizontal centrifugal Design pressure 300 psig Design temperature 200*F Design flow rate 970 gpm*

Design head 470 ft.

Material Austenitic stainless steel

• Includes 10% additional flow for sodium hydroxide spray 4.5 Boron Injection Tank Number 1 Type Vertical Volume, tank 900 gal.

Design pressure 1750 psig Design temperature 300*F i Fluid Borated Water Material Austenitic stainless steel l

4.6 Safety Injection Accumulators Number 3 Type Vertical Volume, tank 1200 ft 3 fluid 775 ft 3 )

Design pressure 700 psig Design temperature 300*F  ;

Nominal operating pressure 660 psig Minimum operating pressure 600 psig K j Nominal operation temperature 120*F Fluid Borated water Material Carbon steel, austenitic stainless l steel lined i

l SD-002 Rev. 4 Page 23 of 34 l

1 EMERGENCY BORATION geretracs FoR .

O 2,15

( 3.0 OPERATOR ACTIONS 3.1 Inunediate Actions

. 3.1.1 Align the preferred available path to deliver Boric Acid to the Charging Pump Suction.

1. Open FCV-113A and 1138

% 2. Open LCV-115B or CVC-358 and close LCV-115C I

3. Open FCV-113A and 1148

4. Open MOV-350 NOTE I Do not use MOV-350 if the plant is to be' maintained at power unless none of options 1, 2, or 3 above is available. MOV-350 may be used freely if the intent is to shut down the reactor or maintain it i shut down.

p 3.1.2 Start a Boric Acid Transfer Pump if Option 1, 3, or 4 above is j

-4 used.

3.1.3 If a Boric Acid Pump is,being used, verify Boric Acid flow to the -

Charging Pump Suction.

3.1.4 Verify charging flow to the Reactor Coolant System.  ;

l 3.2 Subsequent Actions 3.2.1 Start an additional charging pump to decrease the delivery time of Boric Acid to the RCS. If pressurizer level is not decreasing in an uncontrolled menner, open an additional letdown orifice. '

3.2.2 If necessary, transfer rod control to manual and position rods to re-establish normal Tave in conjunction with the injection of boric acid.

3.2.3 continue boration as long as required to restore safe reactor conditions. '

3.2.4 If VCT level decreases to lo-lo level setpoint (12.4 in.), verify LCV-1158 opens and LCV-115C eleses.

1. When VCT level is restored, verify LCV-115C opens and LCV-1158 3 closes.

A0P-002 Rev, 2. Page 4 of 7

J e g Reveaue s:og 2.I6 -

h 2.0 COMPONENT DESCRIPTION (Continued)

The Main Feedwater Regulating Valves rely on motor operated block valves if needed to isolate them from the Main Feedwater Pump discharge. These valves are controlled from the RTCB and supplied power from: V2-6A for "A" Steam Generator from MCC-10, V2-6B for "B" Steam Generator from MCC-9, and V2-6C for "C" S/G from MCC-9.

2.7 Feedwater/ Condensate Recirculation During periods of cold shutdown a feedwater recirculating line can be utilized to reduce corrosion product buildup in the Feedwater System Condensate System by opening locked gate valve FW-232, globe valve FW-238 and a spectacle blind flange. The recirculating piping runs from the outlet side of the high pressure Feedwater Heaters 6A and B to the main condenser "B" vie main steam dump line 12-MS-4SB.

3.0 INSTRUMENTS AND CONTROLS i

3.1 Main Feedwater Pumps The control switches and indicating lights for the Main Feedwater Pumps are located on the RTGB. The following requirements must be met before a pump will start A Condensate Pump running, sufficient suction, and lube oil pressure.

A feedwater pump will trip from the following:

Electrical overload Undervoltage on its bus

$ Minimum flow - blocked for 30 secs. after starting Loss of condensate pump Low lube oil pressure Low suction pressure Safeguards actuation (SI signal)

Hi steam generator level SD-027 Rev. 8 Page 14 of 33

, ? ,* , ,.

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* PAGE TITLE REV, PROC. iVO. '

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__ O p Co& san aM h&am hstem J %D I kmwe M 2*

1.0 PRECAUTIONS AND LIMITATIONS 1.1 Limits of Condensate Level in Hotwell i -

In order to provide a minimum static head above condensate pumps and in order not to reduce condenset deaerating

space above the condensate level, changes are limited by pumping condensate to storage tank or allowing condensate to drain back by gravity to 2 in. above normal water level

\ and 10 in. below normal water level. When level reaches either limit, an alarm (LSL-1416 or LSH-1416) will be l

l annunciated.

( 1.2 Loss of Condenser Vacuum Alarm When a loss of vacuum is sensed in either condenser, pressure switch (PSH-1336 or 1337) will start an alarm and signal a

either one or two of the vacuum pumps.

1.3 Exhaust Hood Spray I

During low load, excessive temperature increase at LP turbine base will open control valves (TCV-1447 A and B typical) to let in condensate for turbine exhaust hood spray and thus lower the temperature.

1.4 Feedwater Pump Trip Any " low" condition of the following will trip the feedwater pumps:

1 - Low pump suction pressure- (PSL-1497-1,1458-1)

I

$ 2 - l'ow feedwater flow (FS-1444-D,1445-D) 3 - Low lube oil pressure (PSL-1991-A,-B-1)

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ATTACHMENT 9.1 Paga 2 of 9

.., DEDICATED SHUTDOWN DIESEL CENERATOR CHECKLIST z M4160V.SWITCHCEARROOM (Continued) N p Align the following on DS Control Panelt 3.N ;i l

SWITCH ID SWITCH DESCRIPTION POSITION INITIALS I

Parallel /DS Bus Only Selector BUS DS ONLY' Switch )

SS-C Synchroscope Selector Switch OFF SS-T Synchroscope Selector Switch OFF Voltage Adjust Rheostat OFF D/C Covernor Switch NEUTRAL SI/UV Bypass Switch NORMAL Align the following on Power Panel 51 Power Supply to MCC-24

.' i CLOSED Power Supply to Fuel Oil Transfer OPEN p.unp (Unless Transferring

(. Fuel 011) i

'l Power Supply to Uninterruptable Power Supply (UPS) j  !

CLOSED I i

Power Supply to Breathing Air CLOSED Station  !

125V DC Power Supply "A" CLOSED (Also to DSDC Auto and Manual i Voltage Control, and Tachometer) 1 SPARE OPEN i Align the following on UPS Panel:

UPS Charger ON Switch ON UPS Inverter ON Switch ON  ;

UPS Inverter Output Switch ON UPS 48V Battery Interrupt Switch  ;

(Knife Switch on Side of Inverter) CLOSED OP-602 Rev. 7 Page 24 of 31 i

i d

• 9 ATTACHMENT 9.1 Pass 6 of 9 .

DEDICATED SHUTDOWN DIESEL CENERATOR CHECKLIST' RgF64,6MC6 f~*4

' I DEDICATED SHUTDOWN DIESEL CENERATOR ENCLOSURE (Continued)

BREAKER NO. BREAKER DESCRIPTION POSITION INITIALS Lube Oil Circulating Pump Power Supply j Breaker CLOSED Lube Oil Circulating Pump Power Light ON Lube Oil Circulating Pump Control ON Switch. l Radiator Fan Power Supply Breaker CLOSED Radiator Fan Control Switch AUTO Inunersion Heater Power Supply Breaker CLOSED Battery Charger Power Supply Breaker CLOSED Lighting / Distribution Transformer .

Power Supply Breaker CLOSED Align the following on Lighting / Distribution Panelt MAIN Power Supply to Lighting / Distribution CLOSED k .. Panel 9 Fuel Oil Control Panel CLOSER 11 Duplex Receptacles CLOSED 12 Cenerator Control Panel CLOSED 13 Interior Lights CLOSED 14 Exterior Lights CLOSED 15 Cenerator Strip Heater CLOSED Align the following on renerator Control Panel:

Voltage Control NEUTRAL Governor Control 0FF Voltage Regulator Manual Control FULLY CCW Voltage Regulator Manual Control AUTO l

C OP-602 8tev. 7 Page 28 of 31

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. 6. The PZR heat up and cooldown rates are based on excessive stresses to the PZR Vessel.

7. The requirement for normal water level in the PZR precludes criticality while the PZR is solid, which could cause excessive pressure transients.

II. Operations A. Normal Operation l

l 1. Insurge of RCS coolant

a. Reduces volume of steam bubble

b. Temperature and pressure of steam increases

c. Steam is now superheated - some condensation occurs at

/, walls and surface

d. Pressure increase causes sprJ valves to open

e. Cools steam bubble and decreases pressure

f. Level increase energizes backup heaters >if level increase is large enough

[ g. Heats incoming coolant to saturation pressure.

2. Outsurge of RCS coolant

a. Increases volume of steam bubble

b. Water flashes to steam - limiting pressure decrease i

f Session 5 Page 4 of 6

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3.0 INSTRUMENTATION AND CONTROL: (Continued) k6f6A 3.19 3.4 Residual Heat Removal Instrumentation Setpoints-3.4.1 The following is a list of instrumentation that supply RTGB alarms.

Their setpoint may be found in the annunciator procedures.

WINDOW NAME CONTROLLER NO. WINDOW NO.-

RHR HT. EX. LO FLOW FC-605A APP-001-7.

FC-638- APP-001-15 RHR PMP'A COOLING WTR LO FLOW .

RHR PMP B COOLING WTR LO FLOW FC-637 APP-001-23' RHR PUMP A DISCHARGE HI PRESS PC-600 APP-001-31 RHR PUMP B DISCHARGE HI PRESS PC-601 ,

APP-001-39 RHR PMPS MOTOR OVERLOAD / TRIP 74-22A & APP-001-47'74-26B 3.4.2 The following is a list of instruments, their functions, and their i setpoints asso lated with the Residual Heat Removal System:

l Instrument No. Function .

Setpoint:

PIC-600 RHR pump discharge pressure. 560 psig 215 psi High Alarm SIS valve interlock 210 psig 110 psi i l

FICA-605 RER Flow low alarm 3000'gpa 2200 gpm FIA-637 RHR pump cooling water 7 gym 20.5 gpm l FIA-638 Flow low alarm PC-403 RCS valve interlock 465 psig +0, -10 psi 3.4.3 Relief Valve Setpoints Valve No. Location' Setpoin_t k RHR-706 RRR Discharge Line 600 psig 218' psi U '

l SU-003 Rev. 2 Page 8 of 14 l

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on August 22, 1985, the Plant tripped from 100% power due to a steam flow greater than fe::d . flow (SF>FF) mismatch coincident with low steam generator (S/C) level. The trip was caused by performing the steps of a procedure out of sequence which resulted in isolcting a steam pressure transmitter prior to transferring steam pressure control to a redundant instrument. The steam pressure transmitter provides a compensating signal to the steam flow instrumentation. The loss of the steam pressure signal caused the staca generator level control system to match actual feedwater flow to the false low I staam flow signal by closing "B" Feedwater Regulating Valve. This resulted in the 1

SF>FF coincident with a low S/G level reactor trip. x Corrcctive action is to provide

• improved procedural guidance for work on l instrumentation that could result in a Plant trip.

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\ 5.0 PROCEDURE (Continued)

Brackets are used to indicate values that- ehould be used if adverse

{ containment conditions are present. Adverse containment conditiows exist when containment pressure is greater than 4 psig. ,

l i

Example: Verify RCS Subcooling - GREATER THAN 25'F [45'F]

{

I 5.1.2 Foldouts Several E0Ps require the use of a FOLDOUT. The applicable FOLDOUT is intended to be available (visible) when the E0P is being j performed. The FOLDOUT page contains several pieces of information or' actions which are applicable at any step in the E0P being used.

The most important of these actions are procedure transitions which alilow immediate response to new symptoms as they appear. The l placement of these transitions on the FOLDOUT allows prompt response to the appearance of subsequent symptoms. The contents of each

( FOLDOUT specify actions which must be taken when the symptoms associated with that action ar recognized.

5.1.3 Supplements The EPP Supplements are used to provide information too lengthy to include on a PATH, EPP or FRP. Specific uses are described in the following paragraphs.

In PATH 1, the Operator is expected to be able to verify proper SI, Phase A, Containment Ventilation Isolation, etc., valve alignments from the Safeguards Status Panel (pink & blue lights). If he is I

unable to verify proper alignment from this panel, he can then refer i I to Supplement "A". Supplement "A" contains a list of all valves and their required position which actuate on a Safety Injection actuation. Using Supplement "A" and other available indications the Operator can verify proper valve alignment independent from the

• Safeguards Status Panel. I

(

j OMM-022 Rev. O Page 10 of 25

.. . CONTROL ROOM IIRCCESSIBILITY

-s , ,

MEFf.AEA>CE 1.0 SYMPImS FoK 1.1 Sacke or toxic gas in the control room.

Y.l$

1.2 Control room area radiation alarm.

1.3 Bonb threat or other acts of sabotage.

2.0 AUTOMATIC ACTIONS 2.1 None Applicable l

1 3.0 OPEPATOR ACTIONS 3.1 Imediate Actions 3.1.1 All on shift Operators should report to the 4160 switchgear room and await

( $ direction from the Shift Foreman.

l 3.2 Subseauent ActiQns l

EZS 1

Keys are maintained in a sealed cabinet to the right of doorway in the fire equipnent building. Copies of this procedure are located at the 4160 VAC Mimic Bus Panel, Secondary Cbntrol Panel and the Charging Pep Boom Control Panel.

I 1

l 3.2.1 STATION Operators at local control stations as directed by the Shift Foreman AfD OBTAIN two-way portable radios and keys for Secondary Control Panel and DS NIS System.

- 1. Charging Pep Room.

k l 2. Secondary Control Panel Turbine AOP-004 Rev. O Pace *4 of 10  ;

1

l

, a l

AN

( 1.0 SYMPTOMS 1.1 Smoke or toxic gas in the control room. k6f64dNC6 FoA 1.2 Control room area radiation alarm.  %/5 l

1.3 Bomb threat or other acts of sabotage.

i 2.0 AUTOMATIC ACTIONS l 1

1 2.1 None Applicable 1

3.0 OPERATOR ACTIONS 3.1 Immediate Actions 3.1.1 All available operators should report to the Fire Equipment Building

[ and await direction f rom the Shif t Foreman. l i

• • • * *** ********** * **** * ; :. ;. ;. :. ;. ;. ; *** * **** + + * **** ** :. ;. ;. ;. :. ;. ; :. ; :. *+**** ** ****** ** ** * * * **

CAUTION i

l IF AT ANY TIME DURING THE PERFORMANCE OF THIS PROCEDURE CONTROL OF THE I PLANT CANNOT BE MAINTAINED DUE TO FIRE DAMAGE, THEN C0 TO DSP-002.

\ i l

3.2 Subsequent Actions NOTE Keys are maintained in a sealed cabinet to the right of doorway in the l Fire Equipment Building. Copies of this procedure are located at the 1 Fire Equipment Building, Secondary Control Panel and the Charging Pump l Room Control Panel.

I 3.2.1 STATION Operators at local control stations as directed by the Shif t l

l Foreman g OBTAIN two-way portable radios and keys for Secondary Control Panel.

l \ 1. Charging Pump Room.

2. Secondary Control Panel Turbine Building Mezzanine.

AOP-004 Rev. 1 Page 3 of 10

_ _ _ _ _ _ _ _ _ _ - .